Text

Annual Radiological Environ Operating Rept for Browns Ferry Nuclear Plant Units 1 & 2 for 970101-1231
	ML18039A322
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Site:	Browns Ferry
Issue date:	12/31/1997
From:	; TENNESSEE VALLEY AUTHORITY
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Annual Radiological Environmental Operating Report Browns Ferry Nuclear Plant 1997 9'804240350 980420 PDR ADQCK 05000259 PDR

TABLEOF CONTENTS able ofContents List ofTables lv List ofFigures.

Executive Summary.

Introduction.

Naturally Occurring and Background Radioactivity.

Electric Power Production..

2 2

5 Site/Plant Description.

Radiological Environmental Monitoring Program......

Direct Radiation Monitoring.

Measurement Techniques.........

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Results............

tmospheric Monitoring.

Sample Collection and Analysis...

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Results 11 11 12 15

'15 16 Terrestrial Monitoring.........

Sample Collection and Analysis Results........... ~............

18 18 19 Aquatic Monitoring....

Sample Collection and Analysis Results......... ~.............

21 21 23 Assessment and Evaluation.

Resul'ts

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Conclusions 25 26 27 References.

28 Appendix ARadiological Environmental Monitoring Program and Sampling Locations....

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ppendix B 1997 Program Modifications.

34 45 Appendix C Program Deviations.....

48 Appendix D Analytical Procedures. ~.........

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51 Appendix E Nominal Lower Limits ofDetection (LLD).

54 Appendix F Quality Assurance/Quality Control Program.

60 Appendix G Land Use Survey.

66 Appendix H Data Tables and Figures..

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LIST OF TABLES le 1 Comparison ofProgram'Lower Limits ofDetection with Regulatory Limits for Maximum Annual Average Effluent Concentrations Released to Unrestricted Areas and Reporting Levels.'.......,....

29

'able'2 Results &om the Intercomparison of Environmental Dosimeters..............

30 Table 3 Maximum Dose Due to Radioactive Effluent Releases 31'

LIST OF FIGURES

. gure 1

Tennessee Valley Region.

32 Figure 2 Environmental Exposure Pathways ofMan Due to Releases ofRadioactive Materials to the Atmosphere and Lake.

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EXECUTIVE

SUMMARY

is report describes the radiological environmental monitoring program conducted by TVAin the vicinityofthe Browns Ferry Nuclear Plant (BFN) in 1997. The program includes the collection of samples Rom the environment and the determination ofthe concentrations ofradioactive materials in the samples.

Samples are taken from stations in the general area ofthe plant and Rom areas not influenced by plant operations.

Station locations are selected after careful consideration ofthe weather patterns and projected radiation doses to the various areas around the plant. Monitoring includes the sampling ofair, water, milk, foods, vegetation, soil, fish, sediment, and the measurement ofdirect radiation levels. Results from stations near the plant are compared with concentrations &om control stations and with preoperational measurements to determine potential impacts ofplant operations.

The vast majority ofthe exposures calculated from environmental samples were contributed by naturally occurring radioactive materials or from materials commonly found in the environment as a ult ofatmospheric nuclear weapons fallout.

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

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INTRODUCTION This report describes and summarizes results ofradioactivity measurements made in the vicinityof BFN and laboratory analyses ofsamples collected in the area.

The measurements are made to comply with the requirements of 10 CFR 50, Appendix A, Criterion 64 and 10 CFR 50, Appendix I,

- Sections IV.B.2, IV.B.3 and IV.C and to determine potential eFects on public heath and safety.

This report satisfies the annual reporting requirements ofBFN Technical Specification 6.9.1.5 and Oft'site Dose Calculation Manual (ODCM) Administrative Control 5.1. In addition, estimates ofthe maximum potential doses to the surrounding population are made from radioactivity measured both in plant eBluents and in environmental samples.

The data presented in this report include results from the prescribed program and other useful or interesting information for individuals who do not work with this material routinely.

Naturall Occurrin and Back round Radioactivit st materials in our world today contain trace amounts ofnaturally occurring radioactivity.

Approximately 0.01 percent ofall potassium is radioactive potassium-40.

Potassium-40 (K-40),

with a half-lifeof 1.3 billionyears, is one ofthe major types ofradioactive materials found naturally in our environment.

An individual weighing 150 pounds contains about 140 grams ofpotassium (Reference 1). This is equivalent to approximately 100,000 pCi ofK-40 which delivers a dose of 15 to 20 mrem per year to the bone and so& tissue ofthe body. Naturally occurring radioactive materials have always been in our environment.

Other examples ofnaturally occurring radioactive materials are beryllium (Be)-7, bismuth (Bi)-212, 214, lead (Pb)-212,214, thallium (Tl)-208, actinium (Ac)-228, uranium (U)-238, uranium-235, thorium (Th)-234, radium (Ra)-226, radon (Rn)-222, carbon (C)-14, and hydrogen (H)-3 (generally called tritium). These naturally occurring radioactive materials are in the soil, our food, our drinking water, and our bodies.

The radiation from these materials makes up a part ofthe low-level natural background radiation. The remainder ofthe 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 Rom radiation Rom ter space (part ofnatural background radiation) is about 27 mrem/year.

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

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

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

&om the food we eat which contains naturally occurring radioactive materials &om the soil. An example ofthis is K-40 as described above.

Even building materials affect the natural background radiation levels in the environment. Livingor working in a building which is largely made of earthen material, such as concrete or brick, willgenerally result in a higher natural background radiation level than would exist ifthe same structure were made ofwood. This is due to the naturally occurring radioisotopes in the concrete or brick, such as trace amounts ofuranium, radium, thorium, etc.

Because the city ofDenver, Colorado, is over 5000 feet in altitude and the soil and rocks there contain more radioactive material than the U.S. average, the people ofDenver receive around 350 mrem/year total natural background radiation dose equivalent compared to about 295 mrem/year for-the national average.

People in some locations ofthe world receive over 1000 mrem/year natural background radiation dose equivalent, primarily because ofthe greater quantity ofradioactive materials in the soil and rocks in those locations.

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

It is possible to get an idea ofthe relative hazard ofdifferent types ofradiation sources by evaluating the amount ofradiation the U.S. population receives from each general type ofradiation source.

The followinginformation is primarily adapted from References 2 and 3.

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U.S. GENERAL POPULATIONAVERAGEDOSE EQUIVALENTESTIMATES urce Millirem/YearPer Person Natural background dose equivalent Cosmic Cosmo genic Terrestrial In the body Radon-222 Total 27 1

28 39 200 295 Release ofradioactive material in natural gas, mining, ore processing, etc.

Medical (effective dose equivalent)

Nuclear weapons fallout Nuclear energy Consumer products 53 less than 1

0.28 0.03 Total 355 (approximately) can be seen from the table, natural background radiation dose equivalent to the U.S. population normally exceeds that from nuclear plants by several hundred times. This indicates that nuclear plant operations normally result in a population radiation dose equivalent which is insignificant compared to that which results from natural background radiation. It should be noted that the use of radiation and radioactive materials for medical uses has resulted in a similar effective dose equivalent to the U.S. population as that caused by natural background cosmic and terrestrial radiation.

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

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average annual effective dose equivalent from radon in the United States is approximately 200 em/year.

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

Electric Power Production Nuclear power plants are similar in many respects to conventional coal burning (or other fossil fuel) electrical generating plants. The basic process behind electrical power production in both types of plants is that fuel is used to heat water to produce steam which provides the force to turn turbines and generators.

However, nuclear plants include many complex systems to control the nuclear fission process and to safeguard against the possibility ofreactor malfunction, which could lead to the release ofradioactive materials. Very small amounts ofthese fission and activation products are released into the plant systems.

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

Allpaths through which radioactivity is released are monitored. Liquid and gaseous effluent nitors record the radiation levels for each release.

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

Releases are monitored at the onsite points ofrelease and through an environmental monitoring program which measures the environmental radiation in outlying areas around the plant In this way, not only is the release ofradioactive 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 ofradiation or radioactive materials.

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

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The dose to a member ofthe general public from radioactive materials released to unrestricted areas, given in NRC guidelines and in the ODCM, is limited as follows:

Li uid Effluents Total body Any organ

<3 mrem/year

<10 mrem/year Gaseous Effluents 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 vicinityof clear power plant, established in the Environmental Dose Standard of40 CFR 190, are as ollows:

Total body Thyroid Any other organ

<25 mrem/year

<75 mrem/year

<25 mrem/year Appendix B to 10 CFR 20 presents the regulatory limits for the annual average concentrations ofradioactive materials released in gaseous and liquid effluents at the boundary of the unrestricted area.

Table 1 ofthis report compares the nominal lower limits ofdetection for the BFN monitoring program with the regulatory limits for maximum annual average effluent concentrations released to unrestricted areas and levels requiring special reports to the NRC. The data presented in this report indicate compliance with the regulations.

SITE/PLANTDESCRIPTION owns Ferry Nuclear Plant (BFN) is located on the north shore ofWheeler Reservoir at Tennessee River Mile294 in Limestone County in north Alabama (Figure 1). Wheeler Reservoir averages 1 to 1-1/2 miles in width in the vicinityofthe plant. The site, containing approximately 840 acres, is approximately 10 miles southwest ofAthens, Alabama, and 10 miles northwest ofDecatur, Alabama. The dominant character ofland use is small, scattered villages and homes in an agricultural area. A number ofrelatively large farming operations occupy much ofthe land on the north side ofthe 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 ofthe plant.

Approximately 2500 people live within a 5-mile radius ofthe plant. The town ofAthens has a population ofabout 17,000, while approximately 49,000 people live in the city ofDecatur. The largest city in the area with approximately 160,000 people is Huntsville, Alabama, located about 24 O

miles east ofthe site.

Area recreation facilities are developed along the Tennessee River. The nearest facilities are public use areas located 2 to 3 miles from the site. The city ofDecatur 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 ofthree boiling water reactors; each unit is rated at 1098 megawatts (electrical). Unit 1 achieved criticalityon August 17, 1973, and began commercial operation on August 1, 1974.

C Unit 2 began commercial operation on March 1, 1975. However, a fire in the cable trays on March 22, 1975, forced the shutdown ofboth reactors.

Units 1 and 2 resumed operation and Unit 3 began testing in August 1976. Unit 3 began commercial operation in March 1977.

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

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RADIOLOGICALENVIRONMENTALMONITORINGPROGRAM ost ofthe radiation and radioactivity generated in a nuclear power reactor is contained within the reactor itselfor one ofthe other plant systems.

Plant effluent monitors are designed to detect the small amounts released to the environment.

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

The monitoring program is designed to check the pathways between the plant and the people in the immediate vicinityand to most efficientlymonitor these pathways.

Sample types are chosen so that the potential for detection ofradioactivity in the environment willbe maximized. The radiological environmental monitoring program is outlined in Appendix A.

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

air and water (see Figure 2). The air pathway can be separated into two components:

the direct (airborne) pathway and the indirect (ground or terrestrial) pathway. The direct airborne athway consists ofdirect radiation and inhalation by humans.

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

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

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

A number offactors 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 ofdairy animals and gardens in conjunction with the air pathway analysis. Liquid pathway stations were selected based on dose projections,'water use information, and availability ofmedia such as fish and sediment.

Table A-2 (Appendix A, Table 2: This method ofnotation is used for all tables and figures given in the appendices.) lists the sampling stations and the types ofsamples collected &om each.

Modifications made to the program in 1997 are described in Appendix B and exceptions to the pling and analysis schedule are presented in Appendix C.

To determine the amount ofradioactivity in the environment prior to the operation ofBFN, a preoperational radiological environmental monitoring program was initiated in 1968 and operated until the plant began operation in 1973. Measurements ofthe 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 ofthe overall program. During the 1950s, 60s, and 70s, atmospheric nuclear weapons testing released radioactive material to the environment causing fluctuations in background radiation levels. This radioactive material is the same type as that produced in the BFN reactors.

Preoperational knowledge ofpre-existing radionuclide patterns in the environment permits a determination, through comparison and trending analyses, ofwhether the operation ofBFN is impacting the environment and thus the surrounding ulation.

The determination ofimpact during the operating phase also considers the presence ofcontrol stations that have been established in the environment.

Results ofenvironmental samples taken at control stations (far from the plant) are compared with those from indicator stations (near the plant) to establish the extent ofBFN influence.

Allsamples are analyzed by the Radioanalytical Laboratory ofTVA's Environmental Radiological Monitoring and Instrumentation group located at the Western Area Radiological Laboratory (WARL)in Muscle Shoals, Alabama. Allanalyses are conducted in accordance with written and approved procedures and are based on accepted methods. A summary ofthe analysis techniques and methodology is presented in Appendix D. Data tables summarizing the sample analysis results are presented. in Appendix H.

The radiation detection devices used to determine the radionuclide content ofsamples collected in

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

The Radioanalytical Laboratory employs a comprehensive quality assurance/quality control program to monitor laboratory performance throughout the year. The program is intended to detect any problems in the measurement process as soon as possible so they can be corrected.

This program includes equipment checks to ensure that the radiation detection instruments are working properly and the analysis ofquality control samples which are included alongside routine environmental samples.

The laboratory participates in the EPA Interlaboratory Comparison Program. In addition, samples split with the EPA National Airand Radiation Environmental Laboratory and the State ofAlabama provide an independent verification ofthe overall performance ofthe laboratory. A complete description ofthe quality control program is presented in A pendix F.

DIRECT RADIATIONMONITORING rect radiation levels are measured at a number ofstations 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 ofplant operations.

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

Radiation levels measured in the area around the BFN site in 1997 were consistent with levels from previous years and with levels measured at other locations in the region.

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

When heated (thermo-), the electrons are released, producing a pulse oflight (-luminescence).

The intensity ofthe 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 ofTLDs.

From 1968 through 1989, TVAused a Victoreen dosimeter consisting ofa manganese activated calcium fluoride (Ca,F:Mn) TLDmaterial encased in a glass bulb. In 1989, TVAbegan the process ofchanging &om the Victoreen dosimeter to the Panasonic Model UD-814 dosimeter, and completely changed to the Panasonic dosimeter in 1990. This dosimeter contains four elements consisting ofone 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. ofthe detector to low energy radiation.

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The TLDs are placed approximately 1 meter above the ground, with two or more TLDs at each tion. Sixteen stations are located around the plant near the site boundary, one station in each of sixteen compass sectors.

Dosimeters are also placed at the perimeter and remote air monitoring sites and at 19 additional stations out to approximately 32 miles from the site. The TLDs are exchanged every 3 months and the accumulated exposure on the detectors is read with a Panasonic Model UD-710A automatic reader interfaced with a Hewlett Packard Model 9000 computer system.

Nine ofthe 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 lithiumborate, the measured exposure is taken as the median ofthe results obtained from the calcium sulfate phosphors in all detectors from the monitoring station. The values are corrected for gamma response, system variations, and transit exposure, with individual gamma response calibrations for each element.

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

Since 1974, TVAhas participated in nine ofthe eleven intercomparisons ofenvironmental dosimeters conducted by the U.S. Department ofEnergy and other interested parties.

The results, shown in Table 2, demonstrate that direct radiation levels determined by TVAare generally within ten percent ofthe calculated or known values.

Results Allresults 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 ofall stations within 1 mile ofthe 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 fiAhgroup is made up ofall stations more than 6 miles from the plant. Past data have shown that the results from all stations greater than 2 miles

&om the plant are essentially the same.

Therefore, for purposes ofthis report, all stations 2 miles or lessIfrom the plant are identified as "onsite" stations and all others are considered "offsite."

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

'I re not as precise at lower exposures.

Consequently, the environmental radiation levels reported the preoperational phase ofthe monitoring program exceed current measurements ofbackground 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 TVAWatts Bar Nuclear Plant (WBN) construction phase and preoperational radiological environmental monitoring program are referenced.

The quarterly gamma radiation levels determined &om the TLDs deployed around BFN in 1997 are summarized in Table H-1. The results from all measurements at individual stations are presented in Table H-2. The exposures are measured in milliroentgens. For purposes ofthis report, one milliroentgen (mR), one millirem (mrem), and one millirad are assumed to be numerically equivalent.

The rounded average annual'exposures are shown below.

Annual Average Direct Radiation Levels mR/Year BFN 1997 Onsite Stations Offsite Stations 55 The data in Table H-l indicate that the average quarterly radiation levels at the BFN onsite stations are approximately 2.5 mR/quarter higher than levels at the offsite stations. This difference is t

consistent with levels measured for preoperation and construction phases ofTVAnuclear plant sites where the average radiation levels on site were generally 2-6 mR/quarter higher than the levels offsite. The causes ofthese differences have not been isolated; however, it is postulated that the differences are probably attributable to combinations ofinfluences such as natural variations in environmental radiation levels, earth-moving activities onsite, and the mass ofconcrete employed in the construction ofthe plant. Other undetermined influences may also play a part. These

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

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

Figure H-2 depicts the environmental gamma radiation levels measured during the construction and preoperational phase ofthe WBN site. Note that the data follow a similar pattern to the BFN data and that, as discussed above, the levels reported at onsite stations are higher than the levels at offsite stations.

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

ATMOSPHERIC MONITORING e atmospheric monitoring network is'divided into three groups identified as local, perimeter, and remote. In the current program, five local air monitoring stations are located on or adjacent to the plant site in the general direction ofgreatest wind frequency.

Three ofthese stations (LM-1,LM-2, and LM-3)are located on the plant side ofthe Tennessee River and two stations (LM-6and LM-7) are located immediately across the river from the plant site. One additional station (station LM-4)is located at the point ofmaximum predicted offsite concentration ofradionuclides 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 ofmonitoring stations are identified in the tables and figures ofAppendix A. The remote stations are used as control or baseline stations.

Results Rom the analysis ofsamples in the atmospheric pathway are presented in Tables H-3 and H-

4. Radioactivity levels identified in this reporting period are consistent with background and onuclides produced as a result offallout from previous nuclear weapons tests.

There is no indication ofan increase in atmospheric radioactivity as a result ofBFN.

Sam le Collection and Anal sis Airparticulates are collected by continuously sampling air at a flowrate ofapproximately 2 cubic feet per minute (cfin) through a 2-inch glass fiber filter. The sampling system consists ofa pump, a magnehelic gauge for measuring the drop in pressure across the system, and a dry gas meter. This allows an accurate determination ofthe volume ofair passing through the filter. This system is housed in a building approximately 2 feet by 3 feet by 4 feet. The filteris contained in a sampling head mounted on the outside ofthe monitor building. The filteris replaced every 7 days. Each filteris analyzed for gross beta activity about 3 days after collection to allow time for the radon daughters to decay. Every 4 weeks, composites ofthe filters from each location are analyzed by gamma spectroscopy.

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

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

The cartridge is located in the same sampling head as the air particulate filter and is downstream ofthe particulate filter. The cartridge is changed at the same time as the particulate filterand samples the same volume ofair. 'Each cartridge is analyzed for I-131 by a complete gamma spectroscopy analysis.

Rainwater is sampled by use ofa collection tray attached to the monitor building. The collection tray is protected &om debris by a screen cover. As water drains from the tray, it is collected in one oftwo 5-gallon jugs inside the monitor building. A 1-gallon sample is removed from the container every 4 weeks. Any excess water is discarded.

Samples are held to be analyzed only ifthe air particulate samples indicate the presence ofelevated activity levels or iffallout is expected.

For example, rainwater samples were analyzed during the period offallout following the accident at Chernobyl in 1986. No rainwater samples from the vicinityofBFN were analyzed in 1997.

ults The results from the analysis ofair particulate samples are summarized in Table H-3. Gross beta activity in 1997 was consistent with levels reported in 'previous years.

The average level at indicator stations was 0.021 pCi/m'hile the average at control stations was also 0.021 pCi/m'. The annual averages ofthe gross beta activity in air particulate filters at these stations for the years 1968-1997 are presented in Figure H-3. Increased levels due to fallout &om atmospheric nuclear weapons testing are evident, especially in 1969, 1970, 1971, 1977, 1978, and 1981. Evidence ofa small increase resulting Rom the Chernobyl accident can also be seen in 1986. These patterns are consistent with data from monitoring programs conducted by TVAat other nuclear power plant sites during construction and preoperational stages.

Only natural radioactive materials were identified by the monthly gamma spectral analysis ofthe air rticulate samples.

No fission or activation products were found at levels greater than the LLDs.

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

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

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

For example, radioactive material may be deposited on a vegetable garden and be ingested along with the vegetables or it may be deposited on pasture grass where dairy cattle are grazing. When the cow ingests the radioactive material, some ofitmay be transferred to the milkand consumed by humans who drink the milk.

Therefore, samples ofmilk, vegetation, soil, and food crops are collected and analyzed to determine the potential impacts &om exposure to this pathway. The results from the analysis ofthese samples are shown in Tables H-5 through H-13.

land use survey is conducted annually to locate milkproducing animals and gardens within a 5-mile radius ofthe plant. Only one dairy farm is located in this area.

One additional dairy farm has been identified within 7 miles ofthe plant. These two dairies are considered indicator stations and routinely provide milksamples.

No other milk-producing animals have been identified within 5 es ofthe plant. The results ofthe 1997 land use survey are presented in Appendix G.

Sam le Collection andAnal sis Milksamples are purchased every 2 weeks from two dairies identified as indicator locations and from at least one oftwo control farms. These samples are placed on ice for transport to the radioanalytical laboratory. A specific analysis for I-131 and a gamma spectral analysis are II performed on each sample and Sr-89,90 analysis is performed every' weeks.

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

The samples are collected &om one farm which previously produced milkand &om one control dairy farm. The samples are collected by cutting or breaking enough vegetation to provide between 100 and 200 grams of sample.

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

The sample is placed in a

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container with 1650 ml of0.5 N NaOH for transport back to the radioanalytical laboratory. A ond sample ofbetween 750 and 1000 grams is also collected from each location. After drying d grinding, this sample is analyzed by gamma spectroscopy.

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

Soil samples are collected annually from the air monitoring locations. The samples are collected with either a "cookie cutter" or an auger type sampler.

AAerdrying and grinding, the sample is analyzed by gamma spectroscopy.

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

Samples representative offood crops raised in the area near the plant are obtained from individual gardens, corner markets, or cooperatives.

Types offoods may vary from year to year as a result of changes in the local vegetable gardens.

In 1997 samples ofcabbage, corn, green beans, potatoes, and tomatoes were collected from local vegetable gardens.

In addition, samples ofapples were also obtained &om the area.

The edible portion ofeach sample is analyzed by gamma spectroscopy.

Results The results from the analysis ofmilksamples are presented in Table H-5. No radioactivity which could be attributed to BFN was identified. All1-131 results were less than the established nominal LLDof0.4 pCi/liter. Strontium-90 was identified in a total offour samples.

The average Sr-90 concentration measured in samples from both indicator and control locations was approximately 2.1 pCi/liter. These levels are less than concentrations measured in samples collected prior to plant operation and are consistent with concentrations expected in milk as a result offallout from atmospheric nuclear weapons tests (Reference I). Figure H-4 displays the average Sr-90 concentrations measured in milksince 1968. The concentrations have steadily decreased as a result

,ofthe 28-year half-lifeofSr-90 and the washout and transport ofthe element through the soil over the period.

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The results for Strontium-89 analysis were less than the LLDof3.5 pCi/liter. By far the dominant isotope reported in milksamples was the naturally occurring K-40. An average of proximately 1350 pCi/literofK-40 was identified in all milk samples.

Similar results were found for vegetation samples as reported in Table H-6. AllI-131 values were less than nominal LLD. Gamma spectroscopy analysis identified only naturally occurring radionuclides.

The largest concentrations identified were for the isotopes K-40 and Be-7.

The only fission or activation product identified in soil samples was Cs-137. The maximum concentration was approximately 0.6 pCi/g in a sample from one ofthe control stations.

This concentration is consistent with levels previously reported from fallout. Allother radionuclides reported were naturally occurring isotopes.

The results ofthe analysis ofsoil samples are reported in Table H-7. Aplot ofthe annual average Cs-137 concentrations in soil is presented in Figure H-5.

Like the levels ofSr-90 in milk, concentrations ofCs-137 in soil are steadily decreasing as a result ofthe cessation ofweapons testing in the atmosphere, the 30-year half-lifeofCs-137 and transport ugh the environment.

Only naturally'occurring radioactivity was identified in food crops. The predominant natural radionuclide detected in samples offood crops was K-40. As noted earlier, K-40 is one ofthe major radionuclides found naturally in the environment and is the predominant radioactive component in normal foods and human tissue. Analysis ofthese samples indicated no contribution from plant activities. The results are reported in Tables H-8 through H-13.

A UATICMONITORING tential exposures from the liquid pathway can occur from drinking water, ingestion offish and invertebrates, or &om direct radiation exposure to radioactive materials deposited in the river sediment.

The aquatic monitoring program includes the collection ofsamples ofsurface (river/reservoir) water, groundwater, drinking water supplies, fish, Asiatic clams (not consumed by humans), and bottom sediment.

Samples Rom the reservoir are collected both upstream and downstream &om the plant.

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

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

The presence ofCo-60, Zn-65, Cs-134 and Cs-137 was identified in samples ofbottom sediment and Zn-65 was identified in one sample ofclams collected &om downstream monitoring location.

le Collection and Anal sis Samples ofsurface water are collected &om the Tennessee River using automatic sampling systems from one downstream station and one upstream station. A timer turns on the system at least once every two hours. The line is flushed and a sample collected into a collection container. A 1-gallon sample is removed &om the container every 4 weeks and the remaining water in the jug is discarded.

The 4 week composite sample is analyzed by gamma spectroscopy and for gross beta activity. A quarterly composite sample is analyzed for tritium.

Samples are also collected by an automatic sampling system at the first downstream drinking water intake. These samples are collected in the same manner as the surface water samples.

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

A quarterly composite is analyzed for tritium.

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

These samples are analyzed every 4 weeks by gamma ectroscopy and for gross beta activity. Aquarterly composite sample from each station is analyzed for tritium. The sample collected at the first downstream public water supply is sampled by the automatic system directly from the river at the intake structure.

Since the sample at this point is raw water, not water processed through the water treatment plant, the control sample should also be unprocessed water. Therefore, the upstream surface water sample is also considered as a control sample for drinking water. During the last month of 1997, a program modification was initiated to relocate the upstream sampling point used as surface water and drinking water control to the intake k

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

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

Water is also collected

&om a private well in an area unaffected by BFN. Samples &om the wells are collected every 4 weeks and analyzed by gamma spectroscopy.

A quarterly composite sample is analyzed for tritium.

ples ofcommercial and game fish species are collected semiannually from each oftwo reservoirs:

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

The samples are collected using a combination ofnetting techniques and electrofishing. To sample edible portions ofthe fish, the fish are filleted. After drying and grinding, the samples are analyzed by gamma spectroscopy.

Bottom sediment is collected semiannually from selected Tennessee River Mile(TRM) locations using a dredging apparatus or Scuba divers. The samples are dried and ground and analyzed by gamma spectroscopy.

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

f

~

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

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

Enough ams are collected to produce approximately 50 grams ofwet flesh. The flesh is separated &om the shells, and the dried flesh samples are analyzed by gamma spectroscopy.

Results Allradioactivity in surface water samples was below the detection limits except the gross beta activity and naturally occurring isotopes.

These results are consistent withpreviously reported levels. A trend plot ofthe gross beta activity in surface water samples from 1968 through 1997 is presented in Figure H-6. A summary table ofthe results for this reporting period is shown in Table H-14.

For drinking water, average gross beta activity was 2.9 pCi/liter at the downstream stations and control stations.

The results are shown in Table H-15 and a trend plot ofthe gross beta activity O

from 1968 to the present is presented in Figure H-7.

No concentrations offission or activation products were detected in groundwater samples.

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

Results from the analysis ofgroundwater samples are presented in Table H-16.

Cesium-137 was identified in two fish samples (game fish). A concentration of0.06 pCi/g was measured &om one indicator location sample while the concentration in the control location sample was 0.05 pCi/g. These concentrations are consistent with data &om previous monitoring years.

The only other isotopes found in fish were naturally occurring. Concentrations ofK-40 ranged from 7.1 pCi/g to 14.8 pCi/g. The results are summarized in Tables H-17 and H-18. Plots ofthe annual average Cs-137 concentrations. in fish are presented in Figures H-8 and H-9. Since the concentrations downstream are essentially equivalent to the upstream levels, the Cs-137 activity is most likelythe results offallout or other upstream effluents rather than. activities at BFN.

Radionuclides ofthe types produced by nuclear power plant operations were identified in sediment mples. The materials identified were Cs-137, Cs-134, Zn-65 and Co-60. The average levels of

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

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

This relationship is graphically represented in Figure H-10 which presents a plot ofthe Cs-137 concentrations in sediment since 1968.

Cobalt-60 concentrations in downstream samples averaged 0.08 pCi/g. Cobalt-60 was measured in one sample from the upstream sampling point. The concentration measured from this sample was 0.03 pCi/g. The maximum concentration measured in downstream samples was 0.12 pCi/g. Figure H-11 presents a graph ofthe Co-60 concentrations measured in sediment since 1968.

One sediment sample from the downstream sampling point closest to the plant discharge contained measurable I

levels ofZn-65 and Cs-134.

The Zn-65 concentration was 0.07 pCi/g and the Cs-134 concentration was 0.06 pCi/g. Arealistic assessment ofthe impact to the general public from these radioisotopes roduces a negligible dose equivalent.

Results Rom the analysis ofsediment samples are shown in le H-19.

Zinc-65 was measured at a concentration of0.78 pCi/g in one sample ofclam flesh collected at the downstream sampling point. There is no human consumption ofthe Asiatic clams sampled in BFN program, therefore, the presence ofZn;65 in the sample does not present an exposure potential to humans.

The results for the analysis ofclam flesh samples are presented in Table H-20.

~

ASSESSMENT ANDEVALUATION tential doses to the public are estimated &om measured effluents using computer models.

These models were developed by TVAand are based on methodology provided by the NRC in Regulatory Guide 1.109 for determining the potential dose to individuals and populations livingin the vicinity ofa nuclear power plant; The doses calculated are a representation ofthe dose to a "maximum exposed individual." Some ofthe factors used in these calculations'(such as ingestion rates) are maximum expected values which willtend 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.

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

drinking water fr'om Tennessee river, eating fish caught in the Tennessee River, and direct exposure to radioactive material due to activities on the banks ofthe 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 ofthe material in the river. Whenever possible, data used in the dose calculation are based on specific conditions for the BFN area.

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

direct radiation Rom the radioactivity in the air, direct radiation from radioactivity deposited on the ground, inhalation ofradioactivity in the air, ingestion ofvegetation which contains radioactivity deposited

&om the atmosphere, and ingestion ofmilk&om animals which consumed vegetation containing deposited radioactivity. The concentrations ofradioactivity in the air and the soil are estimated by computer models which use the actual meteorological conditions to determine the distribution

fthe effluents in the atmosphere.

Again, as many ofthe parameters as possible are based on actual e specific data.

Results The estimated doses to the maximum exposed individual due to radioactivity released from BFN in 1997 are presented in Table 3. These estimates were made using the concentrations ofthe liquids and gases measured at the effluent monitoring points. Also shown are the ODCM limits for these doses and a comparison between the calculated dose and the corresponding limit. The maximum calculated whole body dose equivalent from measured liquid effluents as presented in Table 3 is 0.25 mrem/year, or 8.4 percent ofthe limit. The maximum organ dose equivalent Rom gaseous effluents is 0.11 mrem/year.

This represents 0.7 percent ofthe NRC limit. A more complete description ofthe effluents released from BFN and the corresponding doses projected from these effluents can be found in the BFN Annual Radioactive Effluent Release Reports.

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

The results from each environmental sample are compared with the concentrations from the corresponding control stations and appropriate preoperational and background data to determine influences Rom the plant. During this report period, Co-60, Zn-65, Cs-134 and Cs-137 were seen in aquatic media. The distribution ofCs-137 in sediment and fish is consistent with fallout levels identified in samples both upstream and downstream &om the plant during the preoperational phase ofthe monitoring program.

Since there is no direct exposure pathway to humans, the Co-60, Zn-65 and Cs-134 identified in sediment samples and the Zn-65 in the one clam sample downstream &om the plant would produce no measurable increase in the dose to the general public. No increases of radioactivity have been seen in water samples.

ose estimates were made from concentrations ofradioactivity found in samples ofenvironmental dia. Media evaluated include, but are not limited to, air, milk, food products, drinking water, fish d soil. Inhalation, ingestion and direct doses estimated for persons at the indicator locations were essentially identical to those determined forpersons at control stations.

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

Concentrations ofSr-90 and Cs-137 are consistent with levels measured in TVA'spreoperational radiological environmental monitoring programs.

Conclusions It is concluded &om the above analysis ofthe environmental sampling results and from the trend plots presented in Appendix H that the exposure to members ofthe general public which may have been attributable to BFN is negligible. The radioactivity reported herein is primarily the results of fallout or natural background radiation. Any activity which may be present as a result ofplant o erations does not represent a significant contribution to the exposure ofMembers ofthe Public.

REFERENCES MerrilEisenbud, Environmental Radioactivi Academic Press, Inc., New York, NY, 1987.

2.

National Council on Radiation Protection and Measurements, Report No. 93, "Ionizing Radiation Exposure ofthe Population ofthe United States," September 1987.

3.

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

Table 1

COMPARISON OF PROGRAM LOWER LIMITSOF DETECTION WITHTHE REGULATORYLIMITSFOR MAXIMUMANNUALAVERAGEEFFLUENT CONCENTRATIONS RELEASED TO UNRESTRICTED AREAS ANDREPORTING LEVELS Effluent Concentration'eporting Level~

Concentrations in Water Ci/Liter Lower limit ofDetection~

Effluent Concentration'eporting Level~

Lower limit ofDetection3 Concentrations in Air Ci/Cubic Meter H-3 Cr-51 Mn-54 Co-58 Co-60 Zn-65 Sr-89 Sr-90

,Nb-95 Zr-95 O

Ru-103 Ru-106 I-131 Cs-134 Cs-137 Ce-144 Ba-140 La-140 1,000,000 500,000 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

~

200 200 300 45 5

5 5

10 5

2 5

10 5

40 0.4

,5 5

30 25 10 100,000 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 0.0011 0.0004 0.005 0.005 0.005 0.02 0.03 0.005 0.005 0.011 0.015 0.01 Note: lpCi=3.7xl0'Bq.

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

1 Source:

Table 2 ofAppendix B to 10 CFR 20.1001-20.2401 2 Source: BFN Offsite Dose Calculation Manual, Table 2.3-2 3 Source:

Table E-1 ofthis report.

~

Table 2 Results from the Intercomparison ofEnvironmental Dosimeters'ear Field Dosimeters 74 77 79 81 82 84 SGa 86b 93a 93b 96a 96b TVAResults mrem 15.0 30.4 13.8 31.8 43.2

'73.0 33.2 9.4 24.4 27.6 16.9 17.6 Average, all Respondents

'rem 16.3 31.5 16.0 30.2 45.0 75.1 28.9 10.1 26.4 26.4 18.9 18.9 Calculated Exposure (See Note I) mrem 16.3 34.9 14.1 30.0 43.5 75.8 29.7 10.4 27.0 27.0 19.0 19.0 o/o Difference TVA:

Calculated

-8.0

-12.9

-2.1 6.0

-0.7

-3.7 11.8

-9.6

-9.6 2.2

-10.9

-7.4

'/o Difference Respondents:

Calculated 0.0

-9.7 13.5 0.7 3.4

-0.9

-2.7

-2.9

-2.2

-0.5

-0.5 Low Irradiated Dosimeters 74 27.9 79 12.1 86 18.2 93a'4.9 93b 27.8 28.5 12.1 16.2 25.0 25.0 30.0 12.2 17.2 25.9 25.9

-7.0

-0.8 5.8

-3.9 7.3

-5.0

-0.8

-5.8

-3.5

-3.5 High Irradiated Dosimeters 77 99.4 79 46.1 81a 84.1 81b 102.0 82a '79.0 82b 136.0 S4a 85.6 84b 76.8 93a 67.8 93b 80.2 96a 60.7 96b 59.4 86.2 43.9 75.8 90.7 191.0 149.0 77.9 73.0 69.8 69.8 55.2 55.2 91.7 45.8 75.2 88.4 202.0 158.0 79.9 75.0 72.7 72.7 58.1 58.1 8.4 0.7 11.8 15.4

-11.4

-13.9 7.1 2.4

-6.7 10.3 4.5 2.2

-6.0

-4.1 0.8 2.6

-5.4

-5.7

-2.5

-2.7 4.0 C.O

-5.0

-5.0 Notes:

1. The calculated exposure is the "known" exposure determined by the testing agency.

Table 3 Maximum Dose Due to Radioactive Effluent Releases Browns Ferry Nuclear Plant 1997 mrem/year Dose From LiquidEffluents T~e Total Body Any Organ 1997 Dose 2.5E-1 3.7E-1 NRC Limit 10 Percent of NRC Limit 8.4 3.7 Doses From Gaseous EfHuents

~Te 1997 Dose NRC Limit Percent of NRC Limit Noble Gas (Gamma)

Noble Gas (Beta)

Any Organ 1.2E-3 1.9E-3 1.1E-1 10 20 15 0.01 0.01 0.7 Total Cumulative Dose

~Te 1997 Dose EPA Limit Percent of EPA Limit Total Body or Any Other Organ Thyroid 6.9E-1 4.1E-1 25 75 2.8

~

LOOSW.E TENNESSEE VALLEY REGION i (TVA NUCLEAR PLANT SITES)

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Figure 2

ENVIRONMENTALEXPOSURE PATHWAYS OF MAN DUE TO RELEASES OF RADIOACTIVEMATERIAL TO THE ATMOSPHERE AND LAKE.

~

~P..q.

Diluted By Atmosphere Airborne Releases Plume Exposure Liquid Releases Diluted By Lake Animals (Milk,Meat)

Consumed By Animals Consumed By Man Shoreline Exposure Drinking Water Fish Vegetation Uptake From Soil

~

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APPENDIXA RADIOLOGICALENVIRONMENTALMONITORINGPROGRAM AND SAMPLINGLOCATIONS Table A-I BROWNS FERRY NUCLEARPLANT RADIOLOGICALENVIRONMENTALMONITORINGPROGRAMa 0

Exposure Pathway

~and/or Sam ie Number ofSamples and Locations~

Sampling and Collection Fre uenc Type and Frequency

~ofAnal sis

1. AIRBORNE

a. Particulates Six samples from locations (in different sectors) at or near the site boundary (LM-I,LM-2,LM-3,LMA, LM-6, and LM-7).

Two samples from control locations greater than 10 miles from the plant (RM-I and RM-6).

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

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

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 followingfilterchange.

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

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

b. Radioiodine 5ame locations as air particulates.

Continuous sampler operation with charcoal canister collection at least once per 7 days.

I-131 by gamma scan on each sample.

c. Rainwater Same locations as air particulates.

Composite sample at least once per 31 days.

Analyzed for gamma nuclides only if radioactivity in other media indicates the presence ofincreased levels of fallout

Table A-1 BROWNS FERRY NUCLEARPLANT RADIOLOGICALENVIRONMENTALMONITORINGPROGRAM*

8 Exposure Pathway

~and/or Sam

/e

d. Soil Number ofSamples and Locationsb Samples from same locations as air particulates.

Sampling and Collection Fre uenc Once every year..

Type and Frequency

~ofAnal sis Gamma scan, Sr-89, Sr-90 once per year.

e. Direct Two or more dosimeters placed at locations (in different sectors) at or near the site boundary in each ofthe 16 sectors.

At least once per 92 days.

Gamma dose once per 92 days.

Two or more dosimeters placed at stations located approximately 5 miles from the plant in each ofthe 16 sectors.

At least once per 92 days.

Gamma dose once per 92 days.

Two or more dosimeters in at least 8 additional locations ofspecial interest.

2. WATERBORNE

a. Surface Water One sample upstream (TRM 306.0).

One sample immediately downstream ofdischarge (TRM 293.5).

Collected by automatic sequential-type sampler with composite sample taken at least once per 31 days'.

Gross beta and gamma scan on 4-week composite.

Composite for tritium at least once per 92 days.

b. Drinking water One sample at the first potable surface water supply downstream from the plant (TRM 286.5).

Collected by automatic sequential-type sampler with composite sample taken at least once per 31 days'.

Gross beta and gamma scan on 4-week composite.

Composite for tritium analysis at least once per 92 days.

Table A-1 BROWNS FERRY NUCLEARPLANT RADIOLOGICALENVIRONMENTALMONITORINGPROGRAM*

0 Exposure Pathway

~and/or Sam le Number ofSamples and Locationsb Sampling and Collection Fre uenc Type and Frequency

~ofAnal sis

c. DrinkingWater (Continued)

Four additional samples ofpotable surface water downstream from the plant (TRM282.6, TRM 274.9, TRM 259.8 and TRM 259.6)

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

Composite for tritiumanalysis at least once per 92 days; One sample at a control location4 (TRM 306).

Collected by automatic sequential-type sampler with composite sample-taken at least once per 31 days'.

Same as downstream location.

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

Collected by automatic sequential-type sampler with composite sample taken at least once per 31 days.

Gamma scan on each composite.

Composite for tritiumanalysis at least once per 92 days.

One sample at a control location up gradient from the plant (Farm Bn)

Grab sample taken at least once per 31 days.

Gamma scan on each sample.

Composite fortritiumanalysis at least once per 92 days.

3. AQUATIC

a. Sediment One sample upstream from discharge At least once per 184 days.

point (TRM 297.0)

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

Table A-1 BROWNS FERRY NUCLEARPLANT RADIOLOGICALENVIRONMENTALMONITORINGPROGRAM*

0 Exposure Pathway

~and/or Sam le Number ofSamples and Locations~

Sampling and Collection Fre uenc Type and Frequency

~ofAnal aia

a. Sediment (Continued)

One sample in immediate downstream area ofdischarge point (TRM 293.7)

One additional sample downstream from the plant (TRM 288.8)

4. INGESTION I

co I

a. Milk Atleast 2 samples from dairy farms in At least once per 15 days when the immediate vicinityofthe plant animals are on pasture; at least once (Farms B and Bn).

per 31 days at other times.

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

Gamma scan and I-131 on each sample.

Sr-89 and Sr-90 at least once per 31 days.

b. Fish Two samples representing commercial and game species in Guntersville Reservoir above the plant.

At least once per 184 days.

Gamma scan at least once per 184 days on edible portions.

Two samples representing commercial and game species in Wheeler Reservoir near the plant.

c. Clams One sample downstream from the discharge.

At least once per 184 days:

Gamma scan on flesh only.

One sample upstream from the plant.

(No permanent stations established; depends on location ofclams)

Table A-1 BROWNS FERRY NUCLEARPLANT RADIOLOGICALENVIRONMENTALMONITORINGPROGRAM*

0 Exposure Pathway

~and/or Sam le

d. Fruits and Vegetables Number ofSamples and Locationsb Sampling and Collection Fre uenc Samples offood crops such as greens, At least once per year at time of corn, green beans, tomatoes, and harvest.

potatoes grown at private gardens and/or farms in the immediate vicinity ofthe plant.

Type and Frequency

~of Ana1 sis Gamma scan on edible portion.

e. Vegetation One sample ofeach ofthe same foods grown at greater than 10 miles distance from the plant.

Samples from farms producing milk Once per 31 days.

but not providing a milksample (Farm T).

I-131, gamma scan once per 31 days.

Control samples from one control dairy (Farm R).

a. The sampling program outlined in this table is that which was in effect at the end of 1997.

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

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

d. The sample location at the Decatur City Water Plant serves as a control sample for both surface water and drinking water.

Table A-2 BROWNS FERRY NUCLEARPLANT RADIOLOGICALENVIRONMENTALMONITORINGPROGRAM SAMPLINGLOCATIONS Map Location Numbera I

2 3

4 5

6 7

8 9

10ll 12 13 19 22 23 24 25 26 28 31 37 70 71 Sector NW NE SSE W

W E

N NNE ENE

NNW, SSW NNW N

SW NW NW WNW 275-349)

(TRM 349424)

Station PM-I PM-2 PM-3 LM-7 RM-I RM-6 LM-1 LM-2 LM-3 LM4 LM-6 Farm B Farm Bn Farm R Well No.6 TRMc 282.6 TRM 306.0 TRM 259.6 TRM 274.9 TRM 293.5 TRM 293.7 TRM 288.8 Farm Be Farm T TRM 297.0 TRM 259.8 TRM 286.5 Wheeler Reservoir (TRM Guntersville Reservoir Approximate Distance

~ilbs 13.8 10.9 7.5 2.1 31.3 24.2 1.0 0.9 0.9 1.7 3.0 6.8 5.0 12.5 0.02

>>.4d 12.0d 34 4d 19 ld 0.5d 03d 5.2d 28.8 3.2 3.0 34 2d 75d Indicator (I) or Control C I

I I

I C

C I

I I

C I

I C

I I

I C

I I

I C

Samples Collcctedb 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 AP,CF,R,S AP,CF,R,S M

M,W M,V W

PW PW, SW PW PW SW SD SD M

V SD PW PW F,CL F

CF ~ Charcoal filter(Iodine)

M ~ Milk S

~ Soil V

~ Vegetation

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

b. Sample codes:

AP ~ Airparticulate filter F

~ Fish R

~ Rainwater SW Surface Water

c. TRM ~ Tennessee River Mile.

d. Miles from plant discharge at (TRM 294).

CL ~ Clams PW ~ Public drinking water SD

~ Sediment W

Well water Table A-3 BROWNS FERRY NUCLEARPLANT THERMOLUMINESCENTDOSIMETER (TLD)LOCATIONS Map Location Numbera I

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 68 69 Station NW-3 NE-3 SSE-2 W-3 E-3 N-I NNE-I ENE-I NNW-2 N-2 NNE-2 NNE-3 NE-I NE-2 ENE-2 E-I E-2 ESE-I ESE-2 SE-I SE-2 SSE-I S-I S-2 SSW-I SSW-2 SW-I SW-2 SW-3 WSW-I WSW-2 WSW-3 W-I W-2 W-4 WNW-I WNW-2 NW-I NW-2 NNW-I NNW-3 Sector NW NE SSE W

E N

NNE ENE NNW N

NNE NNE NE NE ENE' E

ESE ESE SE SE SSE S

S SSW SSW SW SW SW WSW WSW WSW W

W W

WNW WNW NW NW NNW NNW 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 1.0 5.2 Onsite (On)b or

~Offsile 0 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, Off On Off Off Off Off Off Off On Off

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

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

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

Figure A-1 Radiological Environmental Monitoring Locations Within 1 Mile of Plant 348.75 1 1.25 NNE 68

'7

~ 8 33.75 NE 303.75 WNW 28'9~

41 9

56.25 ENE 0

258.75 WSW

~OO 3>

/

~i BROWNS FERRY

+g NUCLEAR PLANT 8@

48 ri.

~44 46 78.75 101.25 ESE 236.25 1 23.75 SW 213.75 SSW 146.25 SSE 19125 S

168 75 Scale Mile Figure A-2 Radiological Environmental Monitoring Locations From 1 to 5 Miles from the Plant 325.25 NNW 355.75

~ 8 13 11.25 NNE 33.75 NW 303.75 55.25 WNW 85 Pg+~

/P

~

8

~ 10

.ENE 251.2 38,84 75.7$

2$5.7$

~ 62 81 4

0 SROWNS FE Y

IAICLEARPLANT 55

~

0 47

~101,25 WSW PS. 37+

44,

/P ESE 235.2d 63 51 123.75 SW 68 SE 213.'Td SSW 64 52 145.25 SCALE 101.2$

3 155.75 0.5 1

0.5 2

LSLES

~

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

ON SE 83

~ 2 LMT 8

SOLE HOAL 9

7 57 3

AT ENS 43 45 NTSVILL 78.75 101.25 2S8.75 O CATUA IIUSS LLVILLE OUWWesvAL Esf 328.2 HALEVVI LE AIIAS 123.76 CULLMAN SE 213.7 191.25 5

188.76 55E 146.25 SCALE 0

MlLES APPENDIXB 1997 PROGRAM MODIFICATIONS APPENDIXB Environmental Radiolo ical Monitorin Pro am Modifications Only two modifications were made in the BFN monitoring program in 1997. The fish sampling was modified to add an alternative species for both game and commercial fish. Historically crappie have been collected as representing game fish and smallmouth buffalo have been collected as the commercial species.

During some sampling periods it has been difficultto find an adequate number offish for a sample.

To address this problem, largemouth bass was added as an alternative game fish and channel catfish was added as an alternative commercial species.

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

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

~

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

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

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

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

~

r

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

As noted in the program modifications discussed in Appendix B, the automatic surface water sampler located at TRM 305 was relocated to TRM 306 during the last month ofthe 1997. The sampler was removed from TRM 305 during the last monthly sampling period ofthe year. The sample available in the sampler was collected and analyzed.

The results were consistent with the data from the other samples collected from this location during the year and are included in the data used for this report. In addition, grab sampling was performed weekly at the TRM 306 until the automatic sampler was returned to service.

Each weekly grab sample was analyzed for gross beta and gamma isotopic. The results were consistent with the normal data from the control location. Since a sample was available from TRM 305 for part ofthe sampling period and the additional weekly grab sampling was performed during the period ofrelocation ofthe sampler, no samples are considered to be missing &om this location for,1997.

Table C-1 lists the missed milksample. Allother samples were collected as scheduled.

~

Table C-1 Environmental Radiolo ical Monitorin Pro ram Deviations Date Station Location Remarks 10f06/97 Farm R I

12.5 miles SW Milkwas not available from the Richardson Dairy. Samples were collected from the other control dairy.

J

Appendix D Anal ical Procedures Analyses ofenvironmental samples are performed by the radioanalytical laboratory located at the Western Area Radiological Laboratory facilityin Muscle Shoals. Allanalysis procedures are based on accepted methods. A summary ofthe analysis techniques and methodology follows.

The gross beta measurements are made with an automatic low background counting system.'ormal counting times are 50 minutes. Water samples are prepared by evaporating 500 ml of samples to near dryness, transferring to a stainless steel planchet and completing the evaporation process. Airparticulate filters are counted directly in a shallow planchet.

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

The normal count time is 50 minutes.

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

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

The sample is counted a second time after a 7-day ingrowth period. From the two counts the Sr-89 and Sr-90 concentrations can be determined.

Water samples are analyzed for tritium content by first distilling a portion ofthe 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. Allgamma counts are obtained with germanium type detectors interfaced with a computer based multichannel analyzer system.

Spectral data reduction is performed by the computer program HYPERMET.

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

Allofthe necessary efficiency values, weight-efficiency curves, and geometry tables are established and maintained on each detector and counting system. A series ofdaily and periodic quality control checks are performed to monitor counting instrumentation.

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

Appendix E Nominal Lower Limits ofDetection Sensitive radiation detection devices can produce a signal even when no radioactivity is present in a sample being analyzed.

This signal may come from trace amounts ofradioactivity in the components ofthe device, &om cosmic rays, from naturally occurring radon gas, or from electronic noise. The signal registered when no activity is present in the sample is called the background.

The point at which the signal is determined to represent radioactivity in the sample is called the critical level. This point is based on statistical analysis ofthe background readings from any particular device. However, any sample measured over and over in the same device willgive different readings, some higher than others.

The sample should have a well-defined average eading, but any individual reading willvary &om that average.

In order to determine the activity present in a sample that willproduce a reading above the critical level, additional statistical analysis ofthe background readings is required.

The hypothetical activity calculated from this analysis is called the lower limitofdetection (LLD). A listing oftypical LLDvalues that a laboratory publishes is a guide to the sensitivity ofthe analytical measurements performed by the laboratory.

Every time an activity is calculated from a sample, the background must be subtracted &om the sample signal. For the very low levels encountered in environmental monitoring, the sample signals are oAen very close to the background.

The measuring equipment is being used at the limitofits capability. For a sample with no measurable activity, which oAen happens, about half the time its signal should fall below the average machine background and half the time it should be above the background. Ifa signal above the background is present, the calculated activity is compared to the calculated LLDto determine ifthere is really activity present or ifthe number is and artifact ofthe way radioactivity is measured.

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

The most likelyvalues for these factors have been evaluated for the various analyses performed in the environmental monitoring program. The nominal LLDs calculated from these values, in accordance with the methodology prescribed in the ODCM, are presented=in Table E-l.

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

The nominal LLDs are also presented in the data tables. For analyses for which LLDs have not been established, and LLDofzero is assumed in determining ifa measured activity is greater than the LLD.

TABLEE-1 Nominal LLDValues A. Radiochemical Procedures AirFilters

~Ci/m'ater

~Ci/L Milk

~Ci/L Fish

~Ci/ ~ d+

Wet Vegetation

~C//K we/

Sediment and Soil

~Ci/~ d+

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

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

Ce-141 Ce-144

'Cr-51 1-131, RU-103 Ru-106 Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Mn-54 Zn-65 Co-60 K-40 Ba-140 La-140 Fe-59 Be-7 Pb-212 Pb-214 Bi-214 Bi-212 TI-208 Ra-224 Ra-226 Ac-228 Air Particulates

~Ci/m3

.005

.01

.02

.005

.Q2

.005

.04

.015

.01

.005

.02

.005

.02

.002

.01 Charcoal Filter itCi/nD

.02

.07 0.15 0.03 0.02 Q.12 0.02 0.02 0.03 0.02 0.02 0.02 0.03 0.02 0.30.

0.07 0.04 0.04 0.15 0.03 0.07 0.05 0.20 0.02 0.07 Water and Milk 1ICi/L 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 Vegetation and Grain 1ICi/g dry

.07

.15

.30

.20

.03

.15

.03

.05

.25

.03

.05

.03

.40

.30

.20

.08

.25

.04

.50

.10

.25

'.03

.10 Wet Vegetation

~Ci/k wet 35 115 200 60 25 190 30 25 45 30 2Q 20 45 20 400 130 50 40 200 40 80 55 250 30 70 Soil and Sediment

~Ci/

dry

.10

.20

.35

.25

.03

.20

.03

'.03

.05

.04

.Q3

.03

.05

.03

.75

.30

.20

.05

.25

.10

.15

.45

.06

.75

.15

.25 Fish

'Ci/

~~dry

.07

.15

.30

.20

.03

.15

.03

.05

.25

.03

.05

.03

.40

.30

.20

.08

.25

.04

.50

.10

.25

.03

.10 Clam Flesh i/ r~Q

.35

.85 2.4 1.7

.25 1.25

.14

.15

.45

.25

.20

.40

.20 3.50 2.4 1.4

.45 1.9

.30

.10

.50 2.0

.25

.75 Foods Tomatoes Potatoes, etc.

~Ci/k wet 20 60 95 20 25 90 10 10 45 10 10 10 45 10 250 50 25 25 90 40 80 40 30 130 50

e

Table E-2 Maximum Values for the Lower LimitsofDetection (LLD)

Specified by the BFN Offsite Dose Calculation Manual

~Anet eie Rater pCi/L Airborne Particulate or Gases

~C//mt Fish Milk

~Cilk wet

~Ci/L Food Products

~Ci/k ~~ wet Sediment

~Ci/k dry gross beta H-3 2000' x10~

e N.A.

N.A.

Mn-54 Fe-59

'o-58,60 Zn-65 15 30 15 30 N.A.

N.A.

130 260 130 260 N.A.

N.A.

Zr-95 30 N.A.

N.A.

Nb-95 I-131 Cs-134 Cs-137 Ba-140 La-140 15 lb 15 18 60 15 N.A.

7x10' x10'x102 N.A.

N.A.

130 150'.A.

N.A.

15 18 60 15 N.A.

60 60 80 N.A.

N.A.

150 180 N.A.

N.A.

a.

Ifno drinking water pathway exists, a value of3000 pCi/liter may be used.

b.

LLDfor analysis ofdrinking water and surface water samples shall be performed by gamma spectroscopy at approximately 15 pCi/liter. Iflevels greater than 15 pCi/liter are identified in surface water samples downstream from the plant, or in the event ofan unanticipated release ofI-131, drinking water samples willbe analyzed at an LLDof 1.0 pCi/liter for I-131.

~

Appendix F ualit Assurance/

ualit Control Pro am A thorough quality assurance program is employed by the laboratory to ensure that the environmental monitoring data are reliable. This program includes the use ofwritten, approved procedures in performing the work, a complete training and retraining system, internal self assessments ofprogram performance, audits by various external organizations, and a laboratory quality control program.

The quality control program employed by the radioanalytical laboratory is designed to ensure that the sampling and analysis process is working as intended.

The program includes equipment checks and the analysis ofquality control samples along with routine samples.

Radiation detection devices can be tested in a number ofways. Three are two primary tests which are performed on all devices, In the first type, the device is operated without a sample on he detector to determine the background count rate. The background counts are usually low.

values and are due to machine noise, cosmic rays, or trace amounts ofradioactivity in the materials used to construct the detector.

Charts ofbackground 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 ofradioactivity present.

The number ofcounts registered &om such a radioactive standard should be very reproducible.

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

When counts from either test fall outside the expected range, the device is inspected for malfunction or contamination. It is not placed into service until it is operating properly.

In addition to these two general checks, other quality control checks are performed on the variety ofdetectors used in the laboratory. The exact nature ofthese checks depends on the type of vice and the method it uses to detect radiation or store the information obtained.

Quality control samples ofa variety oftypes are used by the laboratory to verify the performance ofdifferent portions ofthe 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 ofthe type being measured.

Such samples are analyzed to determine whether there is any contamination of equipment or commercial laboratory chemicals, cross-contamination in the chemical process, or interference &om isotopes other than the one being measured.

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

For example, ifthe routine program calls for four milk samples every week, on a random basis each farm might provide an additional sample several times a year. These duplicate samples are analyzed along with the other routine samples.

The duplicate samples provide information about the variabilityofradioactive content in the various sample media.

Ifenough sample is available for a particular analysis, the laboratory analyst can split a sample into two portions.'uch a sample can provide information about the variabilityofthe analytical process since two identical portions ofmaterial are analyzed side by side.

Analytical knowns are another category ofquality control sample. Aknown amount of radioactivity is added to a sample medium by the quality control staff or by the person performing the analyses.

The staff member performing the analyses knows the radioactive content ofthe sample.

Whenever possible, the analytical knowns contain the same amount of radioactivity each time they are run. In this way, the lab staff ha immediate knowledge ofthe quality ofthe measurement pro'cess. A portion ofthese samples are also blanks.

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

The person performing the analysis does not know that the sample contains radioactivity. Since the bulk ofthe ordinary workload ofthe environmental laboratory contains no measurable activity or only naturally occurring radioisotopes, blind spikes can be used to test the detection capability ofthe laboratory or to test the data review process. Ifan analysis routinely generates numerous zeroes for a particular isotope, the presence ofthe isotope is brought to the attention ofthe laboratory supervisor in the review process.

Blind spikes test this process.

Furthermore, the activity can be put into such samples at the extreme limitofdetection (near the LLD)to determine whether or not the laboratory can find any unusual radioactivity whatsoever.

Atpresent, 5 percent ofthe laboratory workload is in the category ofinternal cross-checks.

These samples have a known amount ofradioactivity added and are presented to the person performing the analysis labeled as cross-check samples.

This means that the quality control staff knows the radioactive content or "right answer" but the lab staff does not. Such samples test the est performance ofthe laboratory by determining ifthe lab can find the "right answer." These samples provide information about the accuracy ofthe measurement process.

Further information is available about the variabilityofthe process ifmultiple analyses are requested on the same sample. Like blind spikes or analytical knowns, these samples can also be spiked with low levels ofactivity to test detection limits.

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

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

They provide an independent check ofthe entire measurement process that cannot be easily provided by the laboratory itself. That is, unlike internal cross-checks, EPA cross-checks test the calibration ofthe laboratory detection devices since different radioactive standards produced by individuals outside TVAare used in the cross-checks.

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

These reports indicate how well the laboratory is doing compared to others across the nation. Like internal cross-checks, the EPA cross-checks provide information to the laboratory about the precision and accuracy ofthe radioanalytical work it does.

The results ofTVA'sparticipation in the EPA Interlaboratory Comparison Program are presented in Table F-1. For 1997, all EPA cross-check sample concentrations measured by TVA's laboratory were within+ 3-sigma ofthe EPA reported values.

TVAsplits certain environmental samples with laboratories operated by the States ofAlabama and Tennessee and the EPA National Airand Radiation Environmental Laboratory in Montgomery, Alabama. When radioactivity has been present in the environment in measurable quantities, such as followingatmospheric nuclear weapons testing, followingthe Chernobyl incident, or as naturally occurring radionuclides, the split samples have provided TVAwith yet other level ofinformation about laboratory performance.

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

Allthe quality control data are routinely collected, examined, and reported to laboratory supervisory personnel.

The data are checked for trends, problem areas, or other indications that a portion ofthe 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 ofradioactivity far below the levels which could be harmful to humans.

Gross Beta Strontium-89 EPA Value TVA EPA Value TVA Date

(+3~si ma

~Av

(+3~si ma

~Av.

Strontium-90 Tritium Iodine-131 TVA EPA Value

TVA,

~Av.

(+3~si ma,

~Av.

EPA Value TVA

(+3~si ma

~Av EPA Value

(+3~si ma 15+9 17 01/97 02/97 03/97 04/97 07/97 08/97 09/97 10/97 10/97 86+16 75 7900+1368 7770 24+9 44+9 25 43 13+9 16+9 12 17 16 15+9 11010+1907 11106 10+10 10 49+9 36+9 22+9 33 24 B. Gamma-Spectral Analysis ofWater (pCi/L)

Cobalt-60 Zinc-65 TVA EPA Value TVA EPA Value TVA

~Av

(+3 s~ima

~Av.

(+3 ~si ma

~Av Barium-133 Cesium-134 Cesium-137 TVA EPA Value TVA

~Av.

(+3~si ma

~Av EPA Value

(+3~si ma EPA Value

(+3~si ma Date 21+9 18+9 10+9 27+9 21 21 10 27 04/97 06/97 1Q/97 11/97 31+9 22+9 41+9 10+9 29 20 39 10 22+9 2Q 49+9 48 34+9 33

.74+9 74 100+17 75+16 25 25+9 99 99+17 95 74 Table F-I RESULTS OBTAINEDIN INTERLABORATORYCOMPARISON PROGRAM A. Radiochemical Analysis ofWater (pCi/L)

Appendix G Land Use Surve A land use survey is conducted annually to identify the nearest milk animal, the nearest residence, and the nearest garden ofgreater than 500 square feet producing &esh leafy vegetables in each of 16 meteorological sectors within a distance of5 miles from the plant. The land use survey also identifies the location ofall milkanimals and gardens ofgreater than 500 square feet producing fresh leafy vegetables within a distance of3 miles from the plant.

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

t In order to identify the locations around BFN which have the greatest relative potential for a

'mpact by the plant, radiation doses are projected for individuals livingnear BFN. These projections use the data obtained in the survey and historical meteorological data. They also assume that releases are equivalent to the design basis source terms. The calculated doses are relative in nature and do not reflect actual exposures to individuals livingnear BFN. Calculated doses to individuals based on measured effluents from the plant are well below applicable dose limits (see Assessment and Evaluation Section and Table 3).

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

Airsubmersion doses were calculated for the nearest resident in each sector, the resulting values were similar to those calculated for 1996. Any changes from the 1996 results were small and were due to differences in the distance values used for the nearest resident.

These differences occurred &om either slight changes in the distance value entered for the location or an actual change in the location. Doses calculated for ingestion ofhome-grown foods changed in some sectors, reflecting shifts in the location ofthe nearest garden.

The changes were small and did not significantly impact the doses calculated for 1997.

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

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

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

Table G-1 BROWNS FERRY NUCLEARPLANT Relative Projected Annual AirSubmersion Dose to the Nearest Resident Within Five Miles ofPlant mrem/year Sector N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW Approximate Distance Miles 1.24 1.58 2.54 1.52 1.00 1.15 a

4.60 2.78 2.59 2.76 2.47 1.57 3.39 2.09 1.02

'1996 Surve Annual Dose 0.45 0.14 0.12 0.17 0.33 0.22 0.08 0.15 0.18 0.10 0.08 0.18 0.10 0.30 0.76 Approximate Distance Miles 1.24 1.61 2.54 1.52 1.00 1.15 a

a 2.78 2.59 2.76 2.47 1.57 3.39 2.09 1.02 1997 Surve Annual Dose 0.45 0.14 0.12 0.17 0.33 0.22 0.15 0.18 0.10 0.08 0.18 0.10 0.30 0.76 note a None identified in this sector:

Table G-2 BROWNS FERRY NUCLEARPLANT Relative Projected Annual Dose to Child's Bone from Ingestion ofHome-Grown Foods mrem/year Sector

.N NNE NE ENE E

ESE SE SSE S

SSW SW WSW 1996 Surve Approximate Distance Miles 1.24 2.57 2.67 2.63 2.41 a

a 4.60 2.78 2.59 a

2.67 1.69 a

2.09 1.03 Annual Dose 8.11 1.52 1.27 1.37 2.05 0.88 2.28 2.68 0.60 1.27 4.93 10.70 1997 Surve Approximate Distance Miles 1.24 3.10 2.67 1.85 2.70 a

a a

2.78 2.59 a

2.67 1.69 a

1.10 Annual Dose 8.11 1.18 1.27 2.24 1.75 2.28 2.68 0.60 1.27 4.93 10.10 Number of Gardens Within

~3miiee 1997 2

1 1

0 0

0 1

2 0

2 1

0 0

6 note a Garden not found within 5 miles.

Table G-3 BROWNS FERRY NUCLEARPLANT Relative Projected Annual Dose to Receptor Thyroid from Ingestion ofMilk mrem/year Location Farm Bn Farm B Sector N

Approximate Distance fMMiles

'.9 6.8 Feeding Factor 1996 1997 0.38 0.38 0.33 0.01 Consumer Age

1996 1997 Annual Dose 1996 1997 A

A 0.016 0.005 I

A 0.224 0.029 s/m'.28E-08 1.32E-08 NOTE: The feeding factor is an estimate ofthe percentage ofthe time the animals are feeding from pasture.

A feeding factor of0.01 is used in the dose calculation when the estimated feeding factor is 0.

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

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

Distance Miles 1st qtr 0-1 16.5 2 1.1 1-2 14.811.4 2 - 4 13.6 k 1.2, 4 - 6 13.8 2 1.4

> 6 13.9 2 1.0 2nd qtr 16.4 2 1.0 14.3 2 1.5 13.1 k 1.2 13.3 2 1.3 14.0 R 0.7 3rd qtr 17.5 2 0.9 15.2 k'1.5 14.2 k 1.1 14.2 0 1.4 14.5 2 0.9 Average External Gamma Radiation Levels (b) 4th qtr 16.5 R 1.0 14.5 2 1.3 13.7 2 1.1 13.7 k 1.4 14.2 2 1.5 yearly mR/yr 67 59 55 55 56

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

Average,

>2miles 13.8a1.2 (offsite) 13.5 2 1.2 14.3 0 1.2 13.8 2 1.4 55 (a)

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

(b)

Average of the individual measurements in the set a 1 standard deviation of the set

TABLE H-2 DIRECT RADIATIONLEVELS Individual Stations Environmental Radiation Levels 7

38 8

39 40 41 42 2

9 43 44 45 6

46 47 48 49 50 3

51 52 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-2 348 1

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

135 163 37 165 185 182 21 Map TLD Location Station (1) NRC Direction, Number Number Station No

~de race Approx

Distance, miles 1.0 5.0

.9

.7 5.2

.8 5.0 10.9

.9 6.2

.8 5.2 24.2 9

3.0

.5 5.4 5.1 7.5 3.1 4.8 1st Qtr Jan-Mar 1997 18.0 (2) 15.7 16.7 13.7 16.9 15.5 14.7 17.1 14.7 17.4 14.6 14.6 14.4 14.2 15.6 10.1 14.3 14.8 13.8 12.5 mR I 2nd Qtr Apr-Jun 1997 17.9 12.1 16.1 16.3 12.8 17.5 15.1 14.3 16.5 14.7 16.3 14.0 14.6 14.5 13.2 15.7 9.8 14.2 14.8 13.7 12.4 quarter 3rd Qtr Jul - Sep 1997 18.7 13.2 17.0 (2) 13.9 17.9 16.4 15.0 17.9 15.1 18.1 (2) 15.2 15.8 14.7 16.5 10.8 15.1 15.3 14.8 13.2 4th Qtr Oct-Dec 1997 17.8 12.7 15.5 16.9 13.5 17.0 15.7 14.2 16.9 18.0 17.9 14.7 14.5 15.0 14.5 15.8 9.9 14.2 14.3 14.1 12.5 Annual Exposure

~mRI ear 72A 50.7 64.3 66.5 53.9 69.3 62.7 58.2 68.4 62.5 69.7 57.7 58.9 59.7 56.6 63.6 40.6 57.8 59.2 56.4 50.6 (1)

Locations with TVAand NRC stations co-located (2)

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

TABLE H -2 (continued)

DIRECT RADIATIONLEVELS Individual Stations Environmental Radiation Levels 53 54 55 56 57 58 59 60 61 62 5

63 64 65 66 67 1

68 10 69 SSW-1 SSW-2 SW-1 SW-2 SW-3 WSW-1 WSW-2 WSW-3 W-1 W-2 W-3 WP WNW-1 WNW-2 NW-1 NW-2 NW-3 NNW-1 NNW-2 NNW-3 15 13 12 10 203 199 228 219 224 244 251 257 275 268 275 265 291 293 326 321 310 331 331 339 Map TLD Location Station (1) NRC Direction, Number Number Station No

~de race Approx

Distance, miles 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 1st Qtr Jan-Mar 1997 12.0 13.7

- 13.1 13.6 12.3 12.2 14.4 12.6 14.7 13.1 12.6 14.8 14.0 14.2 15.6 15.6 13.7 17.1 16.5 15.0 mR/

2nd Qtr Apr-Jun 1997 11.5 13.3 12.7 13.6 14.3 11.9 14.1 13.0 14.0 12.5 12.8 13.7 13.6 13.2 14.9 14.7 13.5 16.8 16.3 14.5 quarter 3rd Qtr Jul - Sep 1997 12.7 14.4 13.8 14.4 13.5 13.3 15.1 12.7 14.7 13.3 13.7 15.3 13.9 14.4 16.1 15.7 14.3 17.8 17.2 15.4 4th Qtr Oct-Dec 1997 12.1 13.9 12.9 13.7 13.1 12.3 13.8 12.9 14.6 13.1 12.8 14.5 13.9 13.6 15.1 15.1 13.6 16.1 16.1 15.2 Annual.

Exposure

~mRI ear 48.3 55.3 52.5 55.3 53.2 49.7 57.4 51.2 58.0 52.0 51.9 58.3 55.4 55.4 61.7 61.1 55.1 67.8 66.1 60.1 (1)

(2)

Locations with fVAand NRC stations co-located Sum of availabIe quarterly data normalized to 1 year for the annual exposure value

85 TENNESSEE VALLEY AUTHORITY ENVIRONHENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN AIR FILTER PCI/H3 - 0.037 BQ/M3 NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIMESTONE ALABAMA DOCKET NO.:

50-259,260(296 REPORTING PERIOD: 1997 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 DIRECI'ION RANGE SEE NOTE 1

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

RANGE SEE NOTE 2 NUMBER OF NONROUTINE REPORTED MEASUREHENTS GROSS BETA 572 2.00E-03 2.06E-02( 468/ 468) PM-2 BF ATHEHS AL 7.59E 3.91E-02 10.9 MILES NE 2.14E-02(

52/

52) 2.10E-02(

104/ 104) 8.43E 3.91E-02 8.25E 3.80E-02 GAMMA SCAN (GELI) 143 BE-7 BI-214 PB-214 2.00E-02 5.00E-03 5.00E-03 1 ~ 11E-01(

117/ 117)

PM-3 BF DECATUR AL 6.94E 1.68E-01 8.2 MILES SSE 1.18E-02(

95/ 117)

PM-1 ROGERSVILLE AL 5.00E 3.50E-02 13.8 HILES NW 1 ~ 10E-02(

94/ 117) PH-1 ROGERSVILLE AL 5.00E 3.37E-02 13.8 MILES NW 1 ~ 15E-01(

13/

13) 1.11E-01(

26/

26) 7.83E 1.51E.01 7.03E 1.58E-01 1.37E-02(

9/

13) 1.13E-02(

18/

26) 5.20E 2.41E-02 5.90E 2.32E-02 1.28E-02(

9/

13) 1.19E-02(

17/

26) 5.20E.03-2.33E-02 6.10E 2.33E-02 NOTE:

1.

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

NOTE:

2.

MEAN AND RANGE BASED UPOH DETECTABLE MEASUREMENTS ONLY.

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

TENNESSEE VALLEY AUTHORITY ENVIRONHENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATION WESTERN AREA RAD10LOGICAL LABORATORY RADIOACTIVITY IN CHARCOAL FILTER PCI/H3 - 0.037 BQ/M3 NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIMESTONE ALABAHA DOCKET NO.:

50-259,260,296 REPORTING PERIOD:

1997 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIHI7 ALL OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL HEAN DETECTION MEAN (F)

NAHE 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 GAMMA SCAN (GELI) 572 BI-214 K-40 PB-214 5.00E-02 3.00E-01 7.00E-02 6.22E-02(

23/ 468)

LM4 BF TRAILER P 5.00E 8.88E-02 1.7 HILES NNW 3.57E-01(

34/ 468)

LM.6BF BAKER BOTTOM 3.01E 5.34E-01 3.0 HILES SSW 8.80E-02(

11/ 468)

LM4 BF TRAILER P 7.42E 1.14E-01 1.7 MILES,NN'W 8.88E-02(

8.88E 3.97E-01(

3.70E 1. 14E-01(

1:14E 1/

52) 7.63E-02(

5/ 104) 8.88E.02 5.08E 1.45E-01 2/

52) 3.48E-01(

5/ 104) 4.24E-01 3.05E 4.40E-01 1/

52) 9.88E-02(

3/ 104) 1.14E-01 7.07E 1.51E-01 NOTE:

1.

NOMINAL LOWER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-l.

NOTE:

2.

MEAN AND RANGE BASED UPON DETECTABLE HEASUREMENTS ONLY.

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

NOTE:

3.

THE ANALYSIS OF CHARCOAL FILTERS WAS PERFORMED BY GAMMA SPECTROSCOPY.

NO I-131 WAS DETECTED.

THE LLD FOR I-131 BY GAMMA SPECTROSCOPY

'WAS 0.03 pCi/m 3.

TENNESSEE VALLEY AUTHORITY ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN HILK PCI/L - 0.037 BO/L NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANI'OCATION OF FACILITY: LIHESTONE ALABAMA DOCKET NO.:

50-259,260,296 REPORTING PERIOD: 1997 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIHIT ALL OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN DETECTION HEAN (F)

NAHE MEAN (F)

(LLD)

RANGE DISTANCE AND DIRECTION RANGE SEE NOTE 1

SEE NOTE 2 SEE NDTE 2 CONTROL LOCATIONS MEAH (F)

RANGE SEE NOTE 2 NUHBER OF NONROUT INE REPORTED HEASUREMENTS IODINE-131 103 4.00E-01 52 VALUES < LLD 51 VALUES < LLD GAMMA SCAN (GELI) 103 AC-228 Bl-214 K-40 PB-214 SR 89 52 2.00E+01 52 VALUES < LLD

2.00E+01 2.87E+01(

4/

52) 2.02E+01-3.91E+01 1.DOE+02 1.34E+03(

52/

52) 1.19E+03-1.64E+03 2.DOE+01 2.44E+01(

2/

52) 2.14E+01-2.74E+01 SHITH/BENNETT FARH 5.0 MILES N SHITH/BENNETT FARH 5.0 MILES H SMITH/BENNETT FARH 5.0 MILES N SMITH/BENNETT FARM 5 ~ 0 MILES N 26 VALUES < LLD 3.67E+01(

2/

26) 3.43E+01-3.91E+01 1 '5E+03(

26/

26) 1.19E+03-1.64E+03 2.44E+01(

2/

26) 2.14E+01-2.74E+01 2.01E+Ol (

2.01E+01-2.54E+01(

2.18E+01.

1.35E+03(

1 ~ 19Ei03-2.58E+01(

2.58E+01-1/

51) 2 ~ 01E+01 8/

51) 3.2ZE+01 51/

51) 1.50E+03 1/

5'I) 2.58E+01 SR 90 52 3.50E+00 26 VALUES < LLD 26 VALUES < LLD 2.DOE+00 2.12E+00(

2/

26) SHITH/BENNETT FARH 2.12E+00(

2/

13) 2.15E+00(

2/

26) 2.06E+00-2.17E+00 5.0 MILES N 2.06E+00-2.17E+00 2.11E+00-2.19E+00 NOTE:

1 ~ NOHINAL LOWER LIHIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1.

NOTE:

2.

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

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

NAME OF FACILITY: BR(W FERRY NUCLEAR PLANT LOCATIOH OF FACILITY-LIMESTONE ALABAMA DOCKET NO.:

50-259,260,296 REPORTING PERIOD:

1997 TYPE AND TOTAL NUMBER OF AHALYSIS PERFORMED LOVER LIHIT ALL OF INDICATOR LOCATIONS LOCATION NTH HIGHESI'NNUAL MEAN DETECTION HEAN (F)

NAME MEAN (F)

(LLD)

RANGE DISTANCE AND DIRECTION RANGE SEE NOTE

'I SEE NOTE 2 SEE NOTE 2 CONTROI.

LOCATIONS MEAN (F)

RAHGE SEE NOTE 2 NUMBER OF NONROUTINE REPORTED HEASUREMENTS IODINE-131 2.DOE+02 5 '0E+01 1.51E+03(

13/

13)

TERRY FARM 2.44E+02-6.35E+03 3.2 MILES NNQ 1.50E+02(

4/

13)

TERRY FARM 6.31E+01-2.85EtOZ 3.2 MILES llNM 5.47E+03(

13/

13)

TERRY FARM 3.74E+03-6.66E+03 3.2 MILES NNM 1 '0E+02(

1/

13)

TERRY FARM 1.10E+02-1.10E402 3.2 MILES NNM 1.33E+02(

3/

13)

TERRY FARH 1.03E>02-1.48E+02 3.2 MILES HNH 3.74E+01(

1/

13)

TERRY FARM 3.74E+01-3.74EtOI 3.2 MILES HNW BI-214 4.DOE+02 4 'OE+01 8.DOE+01 3.DOE+0'I K-40 PB-2'I2 PB-214 TL-208 26 6.DOE+00 13 VALUES < LLD GAMMA SCAN (GELI) 26 BE-7 1.51E+03(

2.44E+02-1 ~ 50E+02(

6.31E401-5.47E+03(

3.74Ei03-1.10E+02('.10E+02-1.33E+02(

1.03E+02-3.74E+01(

3.74E+01-13/

13) 6.35E003 4/

13) 2.85E+02 13/

13) 6.66E+03 1/

13) 1.10E+02 3/

13) 1.48E+02 1/

13) 3.74E+01'3 VALUES < LLD 1.51E+03(

3.45E+02-8.55E+01(

5.87E<01-6.46E+03(

3.58E+03-

" 13 VALUES 13/

13) 4.60E+03 5/

13) 1.24E+02 13/

13) 7.82E+03

< LLD 1.01E+02(

3/

13) 8.13E+01-1.14E+02 13 VALUES < LLD NOTE:

1.

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

NOTE:

2.

MEAN AND RANGE BASED UPON DETECTABI.E MEASUREMENTS ONLY.

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

W

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

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

50-259,260,296 REPORTING PERIOD:

1997 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIHIT OF DETECTION (LLD)

SEE NOTE '1 ALL INDICATOR LOCATIONS LOCATIOH WITH HIGHEST ANNUAL HEAN HEAN (F)

NAHE MEAN (F)

RANGE DISTANCE AND DIRECTION RANGE SEE NOTE 2 SEE NOTE 2 CONTROL LOCATIONS MEAN (F)

RANGE SEE NOTE 2 NUMBER OF NONROUTINE REPORTED MEASUREMENTS GAHHA SCAN (GELI)

'l1 AC-228 BI-212 BI-214 CS-137 K-40 PB-212 PB-214 RA-224 RA-226 TL-208 SR 89 2.50E-01 4.50E-01 1.50E-01 3.00E-02 7.50E-01 1.00E-01 1.50E-01 7.50E-01 1.50E-01 6.00E-02 1 ~ 10E+00(

5.40E-01.

1. OBE+00(

5.77E-01.

8.19E-01(

5.23E 2.48E-01(

4.81E 4.63E+00(

1.87E+00-1.01E+00(

4.93E-01 9.20E-01(

5.74E 1.20E+00(

9.43E 8.19E 01(

5.23E 3 '2E-01(

1.58E 9/

9) 1.33E+00 9/

9) 1 '4E+00 9/

9) 9.66E-01 9/

9) 4.52E-01 9/

9) 6.82E+00 9/

9) 1.24E+00 9/

9) 1 '2E+00 8/

9) 1.49E+00 9/

9) 9.66E-01 9/

9) 3.95E-01 PH-3 BF DECATUR AL 8.2 MILES SSE LM2 BF NORTH 0.9 MILE NNE LH2 BF NORTH 0.9 MILE NNE LH.6BF BAKER BOT'TOM 3.0 HILES SSW LM1 BF NORTHWEST 1.0 HILE N PM-3 BF DECATUR AL 8.2 HILES SSE LH2 BF NORTH 0.9 HILE NNE LM2 BF NORTH 0.9 HILE NNE LH2 BF NORTH 0.9 HILE NNE PH-3 BF DECATUR AL 8.2 MILES SSE 1.33E+00(

1.33E+00-1.34E+00(

1.34E+00-9.66E-01(

9.66E 4.52E-01(

4.52E 6.82E+00(

6.82E+00-1.24E+00(

1.24E+00-

1. 12E+00(

1.12E+00-1.49E+00(

1.49E+00-9.66E-01(

9.66E 3.95E-01(

3.95E 1/

1) 1 '3E+00 1/

'I) 1.34E+00 1/

1) 9.66E-01 1/

1) 4.52E-01 1I 1) 6.82E+00 1/

I) 1.24E+00 1/

1) 1 '2E+00 1/

1) 1.49E+00 1/

1) 9.66E-01 1I 1) 3.95E.01 6.91E-01(

2/

2) 5.56E 8.25E-01 8.38E-01(

2/

2) 6.07E 1.07E+00 7.35E-01(

2/

2) 6.30E 8.39E-01 3.96E-01(

2/

2) 1.74E 6 17E 0'I 3.82E+00(

2/

2) 3.28E+00-4.37E+00 7.03E-01(

2/

2) 5.97E 8.09E-01 8.53E-01(

2/

2) 7.38E 9.69E-01 2 VALUES < LLD 7.35E-01(

2/

2) 6.30E 8.39E-01 2.31E-01(

2/

2) 1.88E 2.73E-01 SR 90 1.60E+00 9 VALUES < LLD 2 VALUES < LLD 4.00E-01 9 VALUES < LLD 2 VALUES < LLD NOTE:

1.

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

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

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

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

50-259,260,296 REPORTING PERIOD: 1997 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 DISTAHCE AND. DIRECTION RANGE SEE NOTE 1

SEE NOTE 2 SEE NO'IE 2 CONTROL LOCATIONS HEAN (F)

RANGE SEE NOTE 2 NUMBER OF NONROUTINE REPORTED MEASUREHEN'IS GAMMA SCAN (GELI) 2 BI-214 K-40 4.DOE+01 6.57E+01(

1/

1)

BF AREA 6.57E+01-6.57E+01 2.50E+02 1 ~ 02E+03(

1/

1) BF AREA 1.02E+03-1.02E+03 6.57E+01(

1/

1) 1 VALUES < LLD 6.57E+01-6.57E+01 1.02E+03(

1/

1) 9.58E+02(

1/

1) 1.02E+03-1.02E+03 9.58E+02-9.5BE+02 NOTE:

1.

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

,NOTE:

2.

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

~

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

NAME OF FACILITY: BRSIHS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIMESTONE ALABAMA DOCKEI'O.:

50-259,260,296 REPORTIHG PERIOD: 1997 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT ALL OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN DETECTION MEAN (F)

NAME MEAH (F)

(LLD)

RANGE DISTAHCE AND DIRECI'ION RANGE SEE NOTE 1

SEE NOTE 2 SEE NOTE 2 CON'IROL LOCATIONS MEAN (F)

RANGE SEE NOTE 2 NUMBER OF NONROUT IHE REPORTED MEASUREHENTS GAMMA SCAN (GELI) 2 K-40 2.50E+02 1.58E+03(

1/

1) BF AREA 1.58E+03-1.58E+03 1.58E+03(

1/

1) 2.36E+03(

1/

1) 1.58E+03-1-58E+03 2.36E+03-2.36E+03 NOTE:

1.

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

NOTE:

2.

MEAN AHD RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY.

FRAG'IION OF DETECTABLE MEASUREMEHTS AT SPECIFIED LOCATIOHS IS INDICATED IH PAREHTHESES (F).

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

NAHE OF FACILITY: BRSSS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIMESTONE ALABAMA DOCKET NO.:

50-259,260,296 REPORTING PERIOD:

1997 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORHED LONER LIHIT AI.L OF INDICATOR LOCATIONS LOCATION HITH NIGHEST 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 NUMBER OF NONROUT INE REPORTED MEASUREHENTS GAMMA SCAN (GELI) 2 81-214 K-40 4.DOE+0'I 1 VAl.UES < LLD BF AREA 2.50E+02 2.18E+03(

1/

1) BF AREA 2.18E+03-2.18E+03 1 VALUES < LLD 4.30E+01(

1/

'I) 4.30E+01.

4.30E+01 2.18E+03(

1/

1) 2.77E+03(

1/

1) 2.18E+03-2. 18E+03 2.77E+03-2.77E+03 NOTE:

1.

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

NOTE:

2 ~

MEAN AND RANGE BASED UPON DETECTABLE MEASUREHENTS ONLY.

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

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

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

50-259,260,296 REPORTING PERIOD:

1997'YPE AND TOTAL HUHBER OF ANALYSIS PERFORHED LOWER LIHIT ALL OF INDICATOR LOCATIONS

.LOCATION WITH HIGHEST ANNUAL MEAN DETECTION MEAN (F)

NAHE 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 NUHBER OF NONROUT INE REPORTED MEASUREMENTS GAMMA SCAN (GELI) 2 BI-214-K-40 4.DOE+01 5.57E+01(

1/

1)

BF AREA 5.57E+01-5.57E+01 2.50E+02 2.37E+03(

1/

1) BF AREA 2.37E+03-2.37E+03 5.57E+01(

1/

1) 1 VALUES < LLD 5.57E+D1-5.57E+01 2.37E+03(

1/

1) 2.38E+03(

1/

1) 2.37E+03-2.37E+03 2.3BE+03-2.3BE+03 NOTE:

1.

NOHINAL LOWER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1.

NOTE:

2 ~

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

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

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

50.259,260,296 REPORTING PERIOD:

1997 TYPE AND TOTAL NUHBER OF ANALYSIS PERFORHEO LOWER LIMIT ALL OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL HEAN 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 HEASUREMENTS Ico I

GAMMA SCAN (GELI)

BI-214 K-40 4.00E+01 2'0E+02 6.33E+01(

1/

1)

BFNP Paradise Shores 6.33E+01(

1/

1) 1 VALUES < LLD 6.33E+01-6.33E+01 1.5 Hi les NNW 6.33E+0'I-6.33E+01 4 '0E+03(

1/

1) BFHP Paradise Shores 4.10E+03(

1/

1) 3.88E+03(

1/

1) 4.10E+03-4.10E+03 1.5 Miles.NNW 4.10E+03-4.10E+03 3.88E+03-3.88E+03 NOTE:

1 ~

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

NOTE:

2 ~

MEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY.

FRACTION OF DETECTABLE MEASUREHENTS AT SPECIFIED LOCATIONS IS INDICAI'ED IN PARENTHESES (F).

TENNESSEE ALLEY AUTHORITY EHVIROHMENTAL RADIOI.OGICAL MOHITORING AHD IHSTRUMENTATIOH WESTERN AREA RADIOLOGICAL LABORATORY 0

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

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

50-259,260,296 REPORTING PERIOD:

1997 TYPE AND TOTAL NUMBER OF AHALYSIS PERFORMED LOWER LIMIT ALL OF INDICATOR LOCATIONS LOCATION WITH HIGHEST AHNUAL MEAN DETECTIOH MEAN (F)

NAME MEAN (F)

(LI.D)

RANGE DISTANCE AHD DIRECTION RANGE SEE NOTE 1

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

RANGE SEE HO'IE 2 NUMBER OF HONROUTIHE REPORTED MEASUREMEHTS GAMMA SCAN (GELI) 2 K-40 2.50E+02 2.15E+03(

1/

1) BF AREA 2.15E+03-2.15E+03 2 ~ 15E+03(

1/

1) 2.54E+03(

1/

1) 2.15E+03-2.15E+03 2.54E+03-2.54E+03 NOTE:

1 ~ HOMINAL LOWER LIMIT OF DETECTION (LI.D) AS DESCRIBED IH TABLE E 1.

NOTE:

2.

MEAN AHD RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY.

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

TENNESSEE VALLEY AUTHORITY ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATION MES'IERN AREA RADIOLOGICAL LABORATORY 0

RADIOACTIVITY IN SURFACE llATER(Total)

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

50-259,260,296 REPORTING PERIOD: 1997 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LONER LIMIT ALL OF INDICATOR LOCATIONS LOCATION MITN 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 HEAN (F)

RANGE SEE NOTE 2 NUMBER OF NONROUT I HE REPORTED MEASUREHENTS GROSS BETA 26 1.90E+00 3.21E+00(

12/

13)

TRH 293.5 2.16E+00- 4.55E+00 3.21E+00(

12/

13) 2.75E+00(

11/

13) 2.16E+00-4.55E+00 2.04E+00-3.71E+00 Ioo I

PB-214 TRITIUM 2.DOE+01 GAMMA SCAN (GELI) 26 Bl-214 2.DOE+01 2.43E+01(

1/

13)

TRM 293.5 2.43E+01-2.43E+01 3.02E+01(

1/

13)

TRH 293.5 3.02E+01-3.02E+01 2.43E+01(

1/

13) 2.73E+01(

6/

13) 2.43E+01-2.43E+01 2.22E+01-3.37E+01 3.02E+01(

1/

13) 0.19E+01(

1/

13) 3.02E+O'I-3.02E+01 2.19E+01-2:19E+01 8

3.DOE+02 4 VALUES < LLD 4 VALUES < LLD NOTE:

1.

NOMINAL LONER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1.

NO'IE:

2.

MEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY.

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

TENNESSEE VALLEY AUTHORITY ENVIRONMENTAL RADIOLOGICAL MONITORING AND IHSTRUHENTATION WESTERN AREA RADIOLOGICAL LABORATORY 0

RADIOACTIVITY IN PUBLIC WATER(Total)

PCI/L - 0.037 BQ/L

/

NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIHES'IONE ALABAMA DOCKET NO.:

50-259,260,296 REPORTING PERIOD: 1997 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIHIT ALL OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL HEAN DETECTION HEAN (F)

NAME HEAN (F)

(LLO)

RANGE DISTANCE AND DIRECTION RANGE SEE NOTE 1

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

RANGE SEE NOTE 2 NUMBER OF NONROUT INE REPORTED MEASUREMENTS GROSS BETA 91 1.90E+00 2.94E+00(

56/

65)

W MOR-E LAIR WAT ATH 3.12E+00(

11/

13) 2.88E+00(

23/

26) 1.91E+00-5.56E<00 TRH 286.5 2.19E+00-4 '3E+00 1.94E+00-4.98E+00 GAMMA SCAN (GELI) oo 91 I

BI-214 PB-214 TRITIUM 28 2.DOE+01 2.DOE+01 3.22E+01(

8/

65)

W MOR-E LAWR WAT ATH 4.98E+01(

1/

13) 2.84E+01(

9/

26) 2.28E+01-4.98E+01 TRM 286.5 4.98E401 4.98E+01 2.01E+01-4.36E+01 2.65E+01(

4/

65)

W HOR-E LAWR WAT ATH 3.50E+01(

1/

13) 2.99E+01(

3/

26) 2.15E+01-3.50E+01 TRH 286.5 3.50E+01-3.50f+01 2.19E+01-4.21E+01 3.DOE+02 20 VALUES < LLD 8 VALUES < LLD NOTE:

1.

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

NOTE:

2.

MEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY.

FRACTIDN OF DETECTABLE HEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) ~

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

PCI/L - 0.037 BQ/L NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIMESTONE Al.ABAMA DOCKET <<O.:

50-259,260,296 REPORTING PERIOD: 1997 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 DIRECT ION RANGE SEE NOTE 1

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

RANGE SEE NOTE 2 NUHBER OF NONROUI'INE REPORTED HEASUREHENTS GAHHA SCAN (GELI) 26 BI-214 PB-214 TRITIUM 2.DOE+01 2.65E+01(

3/

13)

BFN WELL ¹6 2.12E+0'I-3.03E+01 0.02 HILES W 2.DOE+01 2.36E+01(

1/

13) BFN WELL ¹6 2.36E+01-2.36E+01 0.02 HILES W 3.DOE+02 4 VALUES < LLD 2.65E+01(

3/

13) 3.08E+02(

13/

13) 2.12E+01-3.03E+01 2.10E+02-4.06E+02 2.36E+01(

1/

13) 3.13E+02(

13/

13) 2.36E+01-2.36E+01 2.12E+02-4.28E+02 4 VALUES < LLD NOTE:

1.

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

NOTE:

2.

HEAN AND RANGE BASED UPON DETECTABLE HEASUREHEN'IS ONLY.

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

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

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

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

50-259,260,296 REPORTING PERIOD: 1997 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT ALL OF INDICATOR LOCATIONS LOCATION WITH HIGHEST AHHUAL MEAN DETECTION MEAN (F)

NAME MEAN (F)

(LLD)

RANGE DISTANCE AND DIRECTION RAHGE SEE NOTE 1

" SEE NOTE 2 SEE HOTE 2 CONTROL LOCATIOHS MEAN (F)

RANGE SEE NOTE 2 NUMBER OF NONROUTINE REPORTED MEASUREMENTS GAMMA SCAN (GELI) 4 BI-214 cs-137 K-40 1.00E-01 3.00E-02 4.00E-01 2 VALUES < LLD WHEELER RES TRM 275-349 6.19E-02(

1/

2)

WHEELER RES 6.19E-02.

6.19E-02 TRM 275-349 1.41E+01(

2/

2) WHEELER RES 1.40E+01-1.41E+01 TRH 275-349 2 VALUES < LLD 6.19E-02(

1/

2) 6.19E 6.19E-02 1.41E+01(

2/

2) 1.40E+01-1.41E+01 1 ~ 19E-O'I(

1/

2) 1.19E-01.

1.19E-D'1 4.70E-02(

1/

2) 4.70E 4.70E-02 1.48E+01(

2/

2) 1.41E+01-1.55E+01 NOTE:

1.

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

HOTE:

2.

MEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY.

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

TENNESSEE LLEY AUTHORITY ENVIRONHENTAL RADIOLOGICAL MONITORING AND INSTRUHENTATION MESTERN AREA RADIOLOGICAL LABORATORY DOCKET NO.:

50.259,260,296 REPORTIHG PERIOD: 1997 RADIOACTIVITY IH COMMERCIAL FISH (SMALLMOUTH BUFFALO OF CHANNEL CATFISH FLESH)

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

NAME OF FACILITY: BROWS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIHESTONE ALABAMA TYPE AND TOTAL NUHBER OF ANALYSIS PERFORHED LOWER LIMIT ALL OF INDICATOR LOCATIONS LOCATION MITH HIGHEST ANNUAL MEAN DETECTIOH MEAN (F)

NAME HEAN (F)

(LLD)

RANGE D IS'TANCE AND DIRECTION RANGE SEE NOTE 1

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

RANGE SEE NOTE 2 NUMBER OF NONRGUTINE REPORTED HEASUREMENTS GAHHA SCAN (GELI)

BI-214 K-40 1.00E-01 1.86E-01(

2/

2) WHEELER RES

'1.68E 2.04E-01 TRH 275-349 4-OOE 01 8.02E+00(

2/

2) MHEELER RES 7.14E+00-8.90E+00 TRM 275-349 1.86E-01(

2/

2) 1.30E-01(

1/

2) 1.68E 2.04E.01 1.30'E 1.30E-01 8.02E+00(

2/

2) 1.19E+01(

2/

2) 7.14E+00-8.90E+00 9.59E+00-1.42E+Ol NOTE:

1.

NOMIHAL L(S LIMIT OF DETECTIOH (LLD) AS DESCRIBED IN TABLE E-1.

HOTE:

2 ~

MEAN AND RANGE BASED UPON DETECTABLE HEASUREHENTS ONLY.

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

TENNESSE~EY AUTHORITY ENVIRONHENTAL RADIOLOG~<ONITORING AND INSTRUHENTATION MESTERN AREA RADIOLOGICAL LABORATORY HAHE OF LOCATION OF TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED GAHMA SCAN (GELI)

RADIOACTIVITY IN SEDIHENT PCI/GH - 0.037 BQ/G (DRY HEIGHT)

FACILITY: BRSINS FERRY NUCLEAR PLANT DOCKET NO.:

50-259,260,296 FACILITY: LIHESTONE ALABAMA REPORTING PERIOD:

1997 LONER LIHIT ALL CONTROL OF INDICATOR LOCATIONS LOCATION llITH HIGHEST ANNUAL HEAN LOCATIONS DETECTION MEAN (F)

NAHE MEAN (F)

MEAN (F)

(LLD)

RANGE DISTANCE AND DIRECTION RANGE RANGE SEE NOTE 1

SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 NUHBER OF NONROUTINE REPORTED HEASUREHENTS AC-228 BE-7 81-212 81-214 C0.60 CS-134 CS-137 K-40 PB-212 PB-214 RA-224 RA-226 TL-208 ZH-65 SR 89 2.50E-01 2.50E-01 4.50E-01 1.50E-01 3.00E-02 3.00E-02 3.00E-02 7.50E-01 1.00E-01 1.50E-01 7.50E-01 1.50E-01 6.00E-02 5.00E-02 1.24E+00(

8.61E 4.48E-01(

2.66E 1.25E+00(

8.43E 8.89E-01(

7.03E 8.28E-02(

5.90E 6.00E-02(

6.00E 4.04E-01(

1.37E 1.22E+01(

1.06E+0'I-1.21E+00(

7.92E 9.93E-01(

7.41E 1.41E+00(

1.38E+00-8.89E-01(

7.03E 3.94E-01(

2.83E 6.63E-02(

6.63E 4/

4) 1.40E+00 3/

4) 6.89E-01 4/

4) 1.48E+00 4/

4) 1.08E+00 3/

4) 1.16E-01 1/

4) 6.00E-02 4/

4) 5.62E-01 4/

4) 1.39E+01 4/

4) 1.40E+00 4/

4) 1.21E+00 2/

4) 1.45E+00 4/

4) 1.08E+00 4/

4) 4.45E-01 1/

4) 6.63E-02 TRM 293.7 BFH DISCHARGE TRH 293.7 BFN DISCHARGE TRH 293.7 BFN DISCHARGE TRH 293.7 BFN DISCHARGE TRH 288.78 TRM 293.7 BFN DISCHARGE TRH 293.7 BFN DISCMARGE TRH 288.78 TRH 293.7 BFN DISCHARGE TRM 293.7 BFN DISCHARGE TRM 293.7 BFN DISCHARGE TRM 293.7 BFN DISCHARGE TRH 293.7 BFN DISCHARGE TRH 293.7 BFN DISCHARGE

'I.35E+00(

1.31E+00-4.77E-01(

2.66E 1.34E+00(

1.28E+00-9.65E-01(

8.45E 1 ~ 16E-01(

1.16E 6.00E-02(

6.00E 4.58E-01(

4.'14E 1.29E+01(

1.19E+01-1.34E+00(

1.28E+00-1.09E+00(

9.66E 1.45E+00(

1.45E+00-9.65E-01(

8.45E 4.38E-01(

4.31E 6.63E-02(

6.63E 2/

2) 1.40E+00 2/

2) 6.89E-01 2/

2) 1.40E+00 2/

2) 1.08E+00 1/

2) 1.16E-01 1/

2) 6.00E-02 2/

2) 5.02E-01 2/

2) 1.39E+01 2/

2) 1.40E+00 2/

2) 1.21E+00 1/

2) 1.45E+00 2/

2) 1.08E+00 2/

2) 4.45E-01 1/

2) 6.63E-02 1 '9E+00(

9.91E 4.02E-01(

3.94E 1.09E+00(

9.08E 8.00E-01(

7.34E 3.02E-02(

3.02E 2 VALUES 2.05E-01(

1.08E 9.76E+00(

7.96E+00-1.11E+00(

9.87E 8.43E-01(

7.83E 1.34E+00(

1.15E+00-8.00E-01(

7.34E 3.49E-01(

3.03E 2 VALUES 2/

2) 1.20E+00 2/

2) 4.10E-01 2/

2) 1.28E+00 2/

2) 8.65E-01

'I/

2) 3.02E-02

< LLD 2/

2) 3.03E-01 2/

2) 1 ~ 16E+01 2/

2) 1.23E+00 2/

2) 9.04E-O'I 2/

2) 1.52E+00 2/

2) 8.65E-01 2/

2) 3.95E-01

< LLD SR 90 1.60E+00 4 VALUES < LLD 2 VALUES < LLD 4.00E.01 4 VALUES < LLD 2 VALUES < LLD NOTE:

1.

NOHINAL LSIER LIHIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1.

NOTE:

2 ~

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

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

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

50-259,260,296 REPORTING PERIOD: l997 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 LOCATIOHS MEAN (F)

RANGE SEE NOTE 2 NUMBER OF HONROUTIHE REPORTED MEASUREMENTS GAMMA SCAN (GELI) 4 BI -214 PB-214 ZN-65 5.00E-01 1.00E-01 4.00E-01 2.43E+00$

2/

2)

DOWNSTREAM LOCATION 1.12E+00- 3.75E+00 DOWNSTREAM 2.24E+00(

2/

2)

DOWNSTREAM LOCATION 9.47E 3.54E+00 DOWHSTREAM 7.84E-01(

1/

2)

DOWNSTREAM LOCATION 7.84E 7.84E-01 DOWNSTREAM 2.43E+00(

1.12E+00-2.24E+00(

9.47E-Oi" 7.84E-01(

7.84E 2/

2) 3.75E+00 2/

2) 3.54E+00 1/

2) 7.84E-01 5 52E+00(

2/

2) 1.87E+00- 9.17E+00 5.40E+00(

2/

2) 1.81E+00-8.98E+00

2. VALUES < LLD NOTE:

1.

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

NOTE:

2.

MEAN AND RANGE BASED UPON DETECTABLE MEASUREMEHTS ONLY.

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

Direct Radiation Levels Browns Ferry Nuclear Plant 20 0

15 E

10 1975 1980 1985 Calendar Year 1990 1995 2000

~On-Site ~OffZite

Direct Radiation levels by Thermoluminescence Dosimetry Watts Bar Nuclear Plant 25 m

20 Q

~

15 E

~on-site (within 2 miles)

~off-site (more than 2 miles)

Initial WBNP operation in

January, 1996 10 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 Calendar Year

0.25 Annual Average Gross Beta Activity in AirFilters - BFNP 0.20 Initial plant operaton in August, 1973 0.15 O

0.10 0.05 0.00 I

I I

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

~ Indicator 8

Control

20 Annual Average Sr-90 Activity in Mitk-BFNP 15 O~

10 0

Initial plant operation in August, 1973 Preoperational Average 1965 1970 1975 1980 1985 1990 1995 2000 Calendar Year

~ Indicator o

Control

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

L 2

D)

OQ.

1 0

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

~ Indicator ~

Control

Annual Average Gross Beta Activity in Surface Water - BFNP o

4 OtL Preoperational Average I

Initial Plant Operation in

August, i973,'

I I

Note: no gross beta measurements were made in 1978 1965 1970 1975 1980 1985 1990 1995 2000 Calendar Year

~ Indicator o

Control

Annual Average Gross Beta Activity in Drinking Water -BFNP I

CD CD I

4 O

Q.

Initial plant operation in August, 1973 I

I I

I Preoperational Aerage 1965 1970 1975 1980 1985 1990 1995 2000 Calendar Year

~ Indicator o

Control

0.5 Annual Average Cs-137 Activity Crappie or Largemouth Bass - BFNP initial plant operation in August, 1973 0.4 E

0.3 OQ.

0.2 I

IQ I

I I

Preoperational Aerage 0.1 0.0 1965 1970 1975 1980 1985 1990 1995 2000 Calendar Year

~ Dow nstream o

Upstream

0.25 0.20 E

tlat 0.15 O

0.10 0+

0.05 Annual Average Cs-137 Activityin Fish Smallmouth Buffalo or Channel Catfish Flesh-BFNP Initial plant operation in August, 1973 Preoperational Average 0.00 1965 1970 1975 1980 1985 0- 0-0-0-~-

1990 1995 2000 Calendar Year

~ Dow nstream ~ Upstream

0

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

C$

Ul 3

OQ.

Preoperational Average 0

-0%-0~A)~~

1965 1970 1975 1980 1985 1990 1995 2000 Calendar Year

~ Dow nstream ~

Upstream

v

0.8 Annual Average Co-60 Activity in Sediment - BFNP 0.6 E

Oa 0.4 0.2 Initial plant operation in August, 1973 I

I I

I Preoperational Average 0.0 1965 1970 CD- 0-.~.

1975 1980 1985 1990 1995

'~ O~ o o s 2000 Calendar Year

~ Dow nstream ~

Upstream

r

ML18039A322

Text

SUMMARY

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