ML18039A761
| ML18039A761 | |
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|---|---|
| Site: | Browns Ferry  |
| Issue date: | 12/31/1998 |
| From: | TENNESSEE VALLEY AUTHORITY |
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| NUDOCS 9905040208 | |
| Download: ML18039A761 (146) | |
Text
Annual Radiological Environmental Operating Report Browns Ferry Nuclear Plant 1998 0
9'705040208 990427 PDR ADOCK 05000259 R
ANNUALRADIOLOGICALENVIRONMENTALOPERATING REPORT BROWNS FERRY NUCLEARPLANT 1998 TENNESSEE VALLEYAUTHORITY ENVIRONMENTALRADIOLOGICALMONITORINGANDINSTRUMENTATION
TABLEOF CONTENTS Table ofContents List ofTables lv List ofFigures Executive Summary.
Introduction..
Naturally Occurring and Background Radioactivity.
Electric Power Production..
2 2
4 Site/Plant Description.
Radiological Environmental Monitoring Program....
Direct Radiation Monitoring.
Measurement Techniques.
Results t
Atmospheric Monitoring.
Sample Collection and Analysis Results 10 10 11 14 14 15 Terrestrial Monitoring.
Sample Collection and Analysis Results 17 17 18 Liquid Pathway Monitoring..
Sample Collection and Analysis..
Results 20 20 22 Assessment and Evaluation.
Results Conclusions 25 26 27 References 28
Appendix ARadiological Environmental Monitoring Program and
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Sampling Locations...........
34 Appendix B 1998 Program Modifications....
45
'ppendix C Program Deviations.
48 Appendix D Analytical Procedures..
51 Appendix E Nominal Lower Limits ofDetection (LLD).
Appendix F Quality Assurance/Quality Control Program.
54 60 Appendix G Land Use Survey...
66 Appendix H Data Tables and Figures.
72
0
LIST OF TABLES Table 1
Comparison ofProgram Lower LimitsofDetection with Regulatory Limits for Maximum Annual Average Effluent Concentrations Released to Unrestricted Areas and Reporting Levels...........
29 Table 2 Results Rom the Intercomparison of Environmental Dosimeters 30 Table 3 Maximum Dose Due to Radioactive Effluent Releases.........................
31
LIST OF FIGURES Figure I Tennessee Valley Region.
32 Figure 2 Environmental Exposure Pathways ofMan Due to Releases ofRadioactive Materials to the Atmosphere and Lake.
33
EXECUTIVE
SUMMARY
This report describes the radiological environmental monitoring program conducted by TVAin the vicinityofthe Browns Ferry Nuclear Plant (BFN) in 1998. The program includes the collection ofsamples from the environment and the determination ofthe concentrations of radioactive materials in the samples.
Samples are taken &om stations in the general area ofth' plant and &om 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 &om 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 result ofatmospheric nuclear weapons fallout.
Small amounts ofCo-60, Cs-134, Cs-137, and Sr-90 were measured in a small number of samples collected during 1998. The level ofactivity measured in these samples would result in no measurable increase over background in the dose to the general public.
INTRODUCTION This report describes and summarizes results ofradioactivity measurements made in the vicinity ofBFN 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 effects on public heath and safety. This report satisfies the annual reporting requirements ofBFN Technical Specification 5.6.2 and Offsite Dose Calculation Manual (ODCM) Administrative Control 5.1.
In addition, estimates ofthe maximum potential doses to the surrounding population are made
&om radioactivity measured both in plant effluents and in environmental samples.
The data presented in this report include results Rom the prescribed program and information to help correlate the significance ofresults measured by this monitoring program to the levels of environmental radiation resulting from naturally occurring radioactive materials.
Naturall Occurrin and Back ound Radioactivit Most 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 of potassium (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 soft tissue ofthe body. Naturally occurring radioactive materials have always been in our environment.
Other examples of naturally occurring radioactive materials are beryllium (Be)-7, bismuth (Bi)-212, 214, lead (Pb)-
212,214, thallium (Tl)-208, actinium (Ac)-228, uranium (U)-238, 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 in the form ofcosmic ray radiation from outer space.
We are all exposed to this natural radiation 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day.
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 of radiation source.
The followinginformation is primarily adapted from References 2 and 3.
U.S. GENERAL POPULATIONAVERAGEDOSE EQUIVALENTESTIMATES Source Millirem/YearPer Person Natural background dose equivalent Cosmic Cosmogenic Terrestrial In the body Radon-222 Total t
Release ofradioactive material in natural gas, mining, ore processing, etc.
27 1
28 39 200 295 Medical (effective dose equivalent)
Nuclear weapons fallout Nuclear energy Consumer products 53 less than 1
0.28 0.03 Total 355 (approximately)
As can be seen from the table, the 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 ofradiation 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 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 ofplants 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.
The pathways through which radioactivity is released are monitored. Liquid and gaseous effluent monitors record the radiation levels for each release.
These monitors also provide alarm mechanisms to prompt termination ofany release above limits.
Releases are monitored at the onsite points ofrelease and through the 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 ofthese effluents. The dose to a member ofthe general public from radioactive materials released to unrestricted areas, as 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 vicinity ofa nuclear power plant, established in the Environmental Dose Standard of40 CFR 190, are as follows:
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 Browns 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 of Decatur, 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. Only 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 cityofDecatur. The largest city in the area with approximately 160,000 people is Huntsville, Alabama, located about 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 &om the site.
The Tennessee River is also a popular sport fishing area.
BFN consists ofthree boiling water reactors. Unit 1 achieved criticalityon August 17, 1973, and began commercial operation on August 1, 1974. Unit 2 began commercial operation on March 1, 1975. However, a fire in the cable trays on March 22, 1975, forced the shutdown ofboth reactors.
Units 1 and 2 resumed operation and Unit 3 began testing in August 1976. Unit 3 began commercial operation in March 1977.
Allthree units were out ofservice from March 1985 to May 1991. Unit 2 was restarted May 24, t
1991 and Unit 3 restarted on November 19, 1995. Unit 1 remains in a non operating status.
RADIOLOGICALENVIRONMENTALMONITORINGPROGRAM Most 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 efficiently monitor these pathways.
Sample types are chosen so that the potential for detection of radioactivity 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 pathway consists ofdirect radiation and inhalation by humans.
In the terrestrial pathway, radioactive materials may be deposited on the ground or on plants and subsequently be ingested by animals and/or humans.
Human exposure through the liquid pathway may result from drinking water, eating fish, or by direct exposure at the shoreline.
The types 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 Rom a critical pathway analysis based on weather patterns, dose projections, population distribution, and land use. Terrestrial sampling stations were selected after reviewing such things as the locations of dairy animals and gardens in conjunction with the air pathway analysis. Liquid pathway stations were selected based on dose projections, water use information, and availability 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 Modifications made to the program in 1998 are described in Appendix B and exceptions to the sampling 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 ofradioactive 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 t
trending analyses, ofwhether the operation ofBFN is impacting the environment and thus the surrounding population.
The determination ofimpact during the operating phase also considers the presence ofcontrol stations that have been established in the monitoring program. Results ofenvironmental samples taken at control stations (far &om the plant) are compared with those Rom 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 and analysis methods used to determine the radionuclide content ofsamples collected in the environment are very sensitive to small amounts ofradioactivity. The sensitivity ofthe measurement process is defined in terms ofthe lower limitofdetection (LLD).
Adescription ofthe nominal LLDs for the Radioanalytical Laboratory is presented in Appendix 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 participated in the EPA Interlaboratory Comparison Program for 1998. In addition, samples split with the EPA National Air'and 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 Appendix F.
0
DIRECT RADIATIONMONITORING Direct radiation levels are measured at a number ofstations around the plant site. These measurements include contributions from cosmic radiation, radioactivity in the ground, fallout
&om 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 from the plant, contributions from the plant may be difficultto distinguish.
Radiation levels measured in the area around the BFN site in 1998 were consistent with levels
&om 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 trapped 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 ofradiation 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 lithiumborate 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.
The TLDs are placed approximately 1 meter above the ground, with two or more TLDs at each monitoring location. Monitoring locations for TLDs are located in each ofthe sixteen compass sectors surrounding the site. One monitoring point is located in each sector near the site boundary and a second monitoring point is located at a distance ofapproximately five miles in each sector. Nine additional locations are distributed through the sectors out to a distance of approximately 32 miles. The TLDs are exchanged every 3 months and the accumulated exposure on the detectors is read with a Panasonic Model UD-710A automatic reader interfaced with a Hewlett Packard Model 9000 computer system.
Since the calcium sulfate phosphor is much more sensitive than the lithiumborate, the measured exposure is taken as the median ofthe results obtained Rom the calcium sulfate phosphors in all detectors from the monitoring location. 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 t
for environmental applications ofTLDs.
Since 1974, TVAhas participated in the 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 <br />0.608 hours <br />0.00362 weeks <br />8.33295e-4 months <br />). The monitoring locations are grouped according to the distance from the plant. The first group consists ofall locations 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 of I
all locations more than 6 miles from the plant. Past data have shown that the results from all monitoring points greater than 2 miles from the plant are essentially the same.
Therefore, for
~
l
purposes ofthis report, all locations 2 miles or less from the plant are identified as "onsite" stations and all others are considered "offsite." Prior to 1976, direct radiation measurements in the environment were made with dosimeters that were not as precise at lower exposures.
Consequently, the environmental radiation levels reported in the preoperational phase ofthe BFN 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 from the TLDs deployed around BFN in 1998 are summarized in Table H-1. The results &om all measurements at individual locations 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 1998 Onsite Stations Offsite Stations 66 57 The data in Table H-l indicate that the average quarterly radiation levels at the BFN onsite locations are approximately 2.3 mR/quarter higher than levels at the offsite locations. This difference is consistent with levels measured forpreoperation and construction phases ofTVA nuclear 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 conclusions are supported by the fact that similar differences between onsite and offsite locations were measured in the vicinityofthe WBN site during the construction and preoperational phase.
Figure H-l compares plots ofthe environmental gamma radiation levels from the onsite or site boundary locations with those from the offsite locations over the period from 1976 through 1998.
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 locations are higher than the levels at offsite stations.
Allresults reported in 1998 are consistent with direct radiation levels identified at locations 1
which are not influenced by the operation ofBFN. There is no indication that BFN activities increased the background direct radiation levels normally observed in the areas surrounding the plant.
ATMOSPHERIC MONITORING The atmospheric monitoring network is divided into three groups identified as local, perimeter, and remote. In the current program, five local air monitoring stations are located on or adjacent to the plant site in the general 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-6 and 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 of radionuclides based on preoperational meteorological data. Three perimeter air monitoring stations are located in communities out to about 13 miles from the plant, and two monitors used as controls are located out to 32 miles. The monitoring program and the locations ofmonitoring stations are identified in the tables and figures ofAppendix A.
Results from the analysis ofsamples in the atmospheric pathway are presented in Tables H-3 and l
H-4. Radioactivity levels identified in this reporting period are consistent with background radioactivity levels. 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 (cfm) 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. The sampling system is housed in a metal building. The filteris contained in a sampling head mounted on the outside ofthe monitor building. The filteris replaced weekly. 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.
4
Gaseous radioiodine is collected using a commercially available cartridge containing TEDA-impregnated charcoal.
This system is designed to collect iodine in both the elemental form and as organic compounds.
The cartridge is located in the same sampling head as the air particulate filterand 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 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 &om the container every 4 weeks. Any excess water is discarded.
Rainwater samples are held to be analyzed only ifthe air particulate samples indicate the presence ofelevated activity levels or if fallout is expected.
For example, rainwater samples were analyzed during the period offallout followingthe accident at Chernobyl in 1986. No rainwater samples from the vicinityofBFN were analyzed in 1998.
Results The results from the analysis ofair particulate samples are summarized in Table H-3. Gross beta activity in 1998 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 1968-1998 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 from the Chernobyl accident can also be seen in 1986.
These patterns are consistent with data &om monitoring programs conducted by TVAat other nuclear power plant sites during construction and preoperational stages.
Only naturally occurring radionuclides radioactive materials were identified by the monthly gamma spectral analysis ofthe air particulate samples.
No fission or activation products were found at levels greater than the LLDs. As shown in Table H-4, iodine-131 was not detected in any ofthe charcoal cartridge samples collected in 1998.
TERRESTRIAL MONITORING Terrestrial monitoring is accomplished by collecting samples ofenvironmental media that may transport radioactive material &om the atmosphere to humans.
For example, radioactive material may be deposited on a vegetable garden and be ingested along with the vegetables or itmay be deposited on pasture grass where dairy cattle are grazing. When the cow ingests the radioactive material, some ofitmay be transferred to the milk and consumed by humans who drink the milk.
Therefore, samples ofmilk, vegetation, soil, and food crops are'collected and analyzed to determine the potential impacts from exposure to this pathway. The results from the analysis of these samples are shown in Tables H-5 through H-13.
A 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 milk samples.
No other milk-producing animals have been t
identified within 5 miles ofthe plant. The results ofthe 1998 land use survey are presented in Appendix G.
Sam le Collection and Anal sis Milksamples are collected every 2 weeks &om two dairies identified as indicator locations and
&om 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 performed on each sample and Sr-89,90 analysis is performed every 4 weeks.
Samples ofvegetation are collected every 4 weeks for I-131 analysis.
The vegetation samples are collected from one farm which previously produced milk and from one control dairy farm.
The samples are collected by cutting or breaking enough vegetation to provide between 100 and 200 grams ofsample.
Care is taken not to include any soil with the vegetation.
The sample is placed in a container with 1650 ml of0.5 N NaOH for transport back to the laboratory. A second sample ofbetween 750 and 1000 grams is also collected from each location. After drying and grinding, this sample is analyzed by gamma spectroscopy.
Soil samples are collected annually from the air monitoring locations. The samples are collected with either a "cookie cutter" or an auger type sampler.
AAer drying and grinding, the sample is analyzed by gamma spectroscopy.
When the gamma analysis is complete, the sample is ashed and analyzed for Sr-89,90.
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 ofchanges in the local vegetable gardens.
In 1998 samples ofcabbage, corn, green beans, potatoes, and tomatoes were collected Rom local vegetable gardens.
In addition, samples ofapples were also obtained from the area.
The edible portion ofeach sample is analyzed by Results The results from the analysis ofmilksamples are presented in Table H-S. 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 two samples.
The average Sr-90 concentration measured in the samples was approximately 2.02 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 1). 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.
The results for Strontium-89 analysis were less than the LLDof3.5 pCi/liter. By far the predominant isotope reported in milksamples was the naturally occurring K-40. An average of approximately 1350 pCi/literofK-40 was identified in all milksamples.
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 0.8 pCi/g in a sample &om one ofthe control stations.
This concentration is consistent with levels previously reported Rom 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 t
decreasing as a result ofthe cessation ofweapons testing in the atmosphere, the 30-year half-life ofCs-137 and transport through 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.
LI UIDPATHWAYMONITORING Potential exposures from the liquid pathway can occur Rom drinking water, and ingestion offish, and &om direct radiation exposure to radioactive materials deposited in the river sediment.
The liquid pathway monitoring program conducted during 1998 included the collection ofsamples of surface (river/reservoir) water, groundwater, drinking water supplies, fish, Asiatic clams (not consumed by humans), bottom sediment, and shoreline sediment.
Samples from the reservoir are
.collected both upstream and downstream &om the plant.
Results &om the analysis ofaquatic samples are presented in Tables H-14 through H-20.
Radioactivity levels in water, fish, clams, and shoreline sediment were consistent with background and/or fallout produced levels previously reported.
The presence ofCo-60, Cs-134 and Cs-137 was identified in samples ofbottom sediment.
Sam le Collection and Anal sis systems lrom 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. Aquarterly composite is analyzed for tritium.
At other selected locations, grab samples are collected &om drinking water systems which use the Tennessee River as their source.
These samples are analyzed every 4 weeks by gamma spectroscopy and for gross beta activity. Aquarterly composite sample &om 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. Aprogram modification initiated in late 1997 and completed in January 1998 uses water sampled from the intake ofthe Decatur City Water Plant as the control location sample for surface and drinking water.
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 Samples 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.
During 1998 a program modification was implemented for sampling 'ofsediment and clams. The sampling ofbottom sediment was replaced by sampling ofshoreline sediment during the second sampling period ofthe year and the sampling ofclams was deleted after the Spring sampling period. The sampling ofshoreline sediment &om areas ofrecreational use was evaluated as a better method ofmonitoring the potential exposure pathway to the public than the sampling of bottom sediment.
The sampling ofclams was deleted from the program since there is no human consumption ofthe Asiatic Clams &om the Tennessee River and no exposure pathway to man.
The samples ofbottom sediment were collected from selected Tennessee River Mile(TRM) locations using a dredging apparatus or Scuba divers. The samples were dried and ground and analyzed by gamma spectroscopy.
Afterthis analysis was complete, the samples were ashed and analyzed for Sr-89,90.
Shoreline sediment was collected from two downstream recreational use areas and one upstream location. The samples were collected at the normal water level shoreline and analyzed by gamma spectroscopy.
The samples ofAsiatic clams were collected &om one location below the plant and one location above the plant. The clams were collected in the dredging or diving process with the sediment.
Enough clams were collected to produce approximately 50 grams ofwet flesh. The flesh was t
separated from the shells, and the dried flesh samples were 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 with previously reported levels. A trend plot ofthe gross beta activity in surface water samples from 1968 through 1998 is presented in Figure H-6. A summary table ofthe results for this reporting period is shown in Table H-14.
For drinking water (public water), gross beta activity averaged 2.8 pCi/liter at the downstream stations and 2.7 pCi/liter at control stations.
The results are shown in Table H-15 and a trend plot ofthe gross beta activity &om 1968 to the present is presented in Figure H-7.
e No fission 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 samples ofboth game and commercial fish. The highest concentration of0.12 pCi/g was measured in a game fish sample &om the indicator reservoir. A concentration of0.05 pCi/g was measured in a sample fiom the control location sample.
These concentrations are consistent with data from previous monitoring years.
The only other isotopes found in fish were naturally occurring. Concentrations ofK-40 ranged from 10.1 pCi/g to 16.9 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 likely the results offallout or other upstream effluents rather than activities at BFN.
Radionuclides ofthe types produced by nuclear power plant operations were identified in bottom sediment samples.
The materials identified were Cs-137, Cs-134, and Co-60. The average levels ofCs-137 were 0.68 pCi/g in downstream samples and 0.34 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 of the Cs-137 concentrations in sediment since 1968. The Co-60 concentrations in downstream samples averaged 0.09 pCi/g. Cobalt-60 was not identified in samples &om the upstream sampling point during 1998. Figure H-l1 presents a graph ofthe Co-60 concentrations measured in sediment since 1968. Samples Rom the downstream sampling points contained Cs-134 at an average concentration of0.05 pCi/g. There was not Cs-134 detected in the sample &om the upstream location. A realistic assessment ofthe impact to the general public from these radioisotopes produces a negligible dose equivalent.
Results Rom the analysis ofsediment samples are shown in Table H-19.
The data reported in Table H-19 for Sr-90 analyses indicates one result above the nominal LLD value of0.4 pCi/g. The referenced result was below the actual LLDfor the specific analysis and does not represent a positive identification ofSr-90 in the sample ofbottom sediment.
The analysis specific LLDwas 0.57 pCi/g. The elevated LLDfor this analysis was the result ofa lower than normal chemical yield for the strontium analysis.
Only naturally occurring radionuclides were identified by the gamma spectral analyses of samples ofshoreline sediment.
The results &om the analysis ofshoreline sediment are provided in Table H-20.
The gamma spectroscopy analyses ofthe samples ofAsiatic clams collected during the Spring sampling period identified only the naturally occurring Bi-214 and Pb-214. The results from the analysis ofclam samples are presented in Table H-21.
ASSESSMENT ANDEVALUATION Potential 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 living in the vicinityofa 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 significantly lower.
The area around the plant is analyzed to determine the pathways through which the public may receive an exposure.
As indicated in Figure 2, the two major ways by which radioactivity is introduced into the environment are through liquid and gaseous effluents.
For liquid effluents, the public can be exposed to radiation from three sources:
drinking water
&om the 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 &om the radioactivity in the air, direct radiation &om 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 ofthe effluents in the atmosphere.
Again, as many ofthe parameters as possible are based on actual site specific data.
Results The estimated doses to the maximum exposed individual due to radioactivity released Rom BFN in 1998 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. With the implementation ofthe process for zero liquid release during 1998, the maximum calculated dose equivalent &om measured liquid effluents as noted in Table 3 were insignificant. The maximum organ dose equivalent from gaseous effluents was 0.30 mrem/year which represents 2.0 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.
t As stated earlier in the report, the estimated increase in radiation dose equivalent to the general public resulting &om the operation ofBFN is negligible when compared to the dose from natural background radiation. The results Rom each environmental sample are compared with the concentrations from the corresponding control stations and appropriate preoperational and background data to determine influences from the plant. During this report period, Co-60, Cs-134 and Cs-137 were identified in aquatic media. The distribution ofCs-137 in sediment and fish is consistent with fallout levels identified in samples both upstream and downstream from the plant during the preoperational phase ofthe monitoring program.
Since there is no direct exposure pathway to humans, the Co-60 and Cs-134 identified in sediment samples would produce no measurable increase in the dose to the general public. No increases ofradioactivity have been seen in water samples.
Dose estimates were made from concentrations ofradioactivity found in samples of environmental media. Media evaluated include, but were not limited to, air, milk, food products, drinking water, fish, soil, and shoreline sediment.
Inhalation, ingestion and direct doses estimated for persons at the indicator locations were essentially identical to those determined for persons at control stations. More than 99 percent ofthose 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 &om 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 from 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 offallout or natural background radiation. Any activity which may be present as a result ofplant operations does not represent a significant contribution to the exposure ofMembers of the Public.
REFERENCES
- 1. MerrilEisenbud, Environmental Radioactivit 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 &om 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 LeveP Concentrations in Water Ci/Liter Lower limit ofDetection'ffluent Concentration'eporting Level Lower limit ofDetection~
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 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 3,000 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 0.01 0.015 0.01 Note:
1 pCi ~ 3.7 x10'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.
l
0 Table 2 Results from the Intercomparison ofEnvironmental Dosimeters Year TVAResults mrem Average, all Respondents mrem Calculated Exposure (See Note I) mrem
% Difference TVA:
Calculated
% Difference Respondents:
Calculated Field Dosimeters 74 77 79 81 82 84 86a 86b 93a 93b 96a 96b 15.0 30.4 13.8 31.8 43.2 73.0 33.2 9.4 24.4 27.6 16.9 17.6 16.3 31.5 16.0 30.2 45.0 75.1 28.9 10.1 26.4 26.4 18.9 18.9 16.3 34.9 14.1 30.0 43.5 75.8 29.7 10.4 27.0 27.0 19.0 19.0
-8.0
-12.9
-2.1 6.0
-0.7
-3.7 11.8
-9.6
-9.6 2.2
-11.1
-7.4 0.0
-9.7 13.5 0.7 3.4
-0.9
-2.7
-2.9
-2.2
-2.2
-0.5
-0.5 Low Irradiated Dosimeters 74 27.9 79 12.1 86 18.2 93a 24.9 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
'.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 179.0 82b 136.0 84a 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
-4.0
-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 1998 mrem/year T~e Dose From LiquidEffluents 1998 Dose NRC Limit Percent of NRC Limit Total Body Any Organ 9.5E-IO 6.6E-09 10
<0.01
<0.01 Doses From Gaseous Effluents
~Te Noble Gas (Gamma)
Noble Gas (Beta)
Any Organ 1998 Dose 1.5E-3 2.1E-3 3.0E-1 NRC Limit 10 20 15 Percent of NRC Limit 0.02 0.01 2.0 Total Cumulative Dose
~Te Total Body or Any Other Organ Tllyrold 1998 Dose 7.4E-2 3.0E-1 EPA Limit 25 75 Percent of EPA Limit 0.3 0.4 LOUISVLLE PAOUCAHI M
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Figure 2
ENVIRONMENTALEXPOSURE PATHWAYS OF MAN DUE TO RELEASES OF RADIOACTIVEMATERIAL TO THE ATMOSPHERE AND LAKE.
Diluted By Atmosphere Airborne Releases Ptume Exposure liquid Releases Diluted By Lake Animals (Milk,Meat)
Consumed By Animals Consumed By Man Shoreline Exposure Drinking Water Fish Vegetation Uptake From Soil 0
0
APPENDIXA RADIOLOGICALENVIRONMENTALMONITORINGPROGRAM AND SAMPLINGLOCATIONS Table A-I BROWNS FERRY NUCLEARPLANT RADIOLOGICALENVIRONMENTALMONITORINGPROGRAM>
Exposure Pathway
~and/or Sam ie Number ofSamples and Locationsb Sampling and Collection Fre uenc Type and Frequency
~a/Anal sis
- 1. AIRBORNE
- a. Particulates
- b. Radioiodine
- c. Rainwater 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-1 and RM-6).
Three samples from locations in communities approximately 10 miles from the plant (PM-1, PM-2, and PM-3).
Same locations as air particulates.
'ame locations as air particulates.
Continuous sampler operation with sample collection as required by dust loading but at least once per 7 days.
Continuous sampler operation with charcoal canister collection at least once per 7 days.
Composite sample at least once per 31 days.
Analyze for gross beta radioactivity greater than or equal to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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.
I-131 by gamma scan on each sample.
Analyzed for gamma nuclides only if radioactivity in other media indicates the presence ofincreased levels of fallout
Table A-1 BROWNS FERRY NUCLEARPLANT RADIOLOGICALENVIRONMENTALMONITORINGPROGRAM*
Exposure Pathway
~antSor Sam le Number ofSamples and Locationsb Sampling and Collection Fre uenc Type and Frequency
~ofAnal sls
- d. Soil Samples from same locations as air particulates.
Once every year.
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 9 additional locations ofspecial interest.
- 2. WATERBORNE
- a. Surface Water
- b. Drinking water One sample upstream (TRM 306.0).
One sample immediately downstream ofdischarge (TRM 293.5).
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'.
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 tritiumat least once per 92 days.
Gross beta and gamma scan on 4-week composite.
Composite for tritiumanalysis at least once per 92 days.
Table A-1 BROWNS FERRY NUCLEARPLANT RADIOLOGICALENVIRONMENTALMONITORING PROGRAM'xposure Pathway
~anti/or Sam le
- c. Drinking Water (Continued)
- d. Ground water Number ofSamples and Locationsb Four additional samples ofpotable surface water downstream from the plant (TRM 282.6, TRM 274.9, TRM 259.8 and TRM 259.6).
One sample at a control location~
(TRM 306).
One sample adjacent to the plant (WellNo. 6).
Sampling and Collection Fre uenc Grab sample taken from water supply at a facilityusing water from the public supply being monitored.
Sample collected at least once per 31 days.
Collected by automatic sequential-type sampler with composite sample taken at least once per 31 days'.
Collected by automatic sequential-type sampler with composite sample taken at least once per 31 days.
Type and Frequency
~ofAnal sis Gross beta and gamma scan on 4-week composite.
Composite for tritiumanalysis at least once per 92 days.
Same as downstream location.
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 for tritiumanalysis at least once per 92 days.
- e. ShorelineSediment One sample upstream from a recreational area (TRM 305).
At least once per 184 days.
Gamma scan ofeach sample.
Table A-1 BROWNS FERRY NUCLEARPLANT RADIOLOGICALENVIRONMENTALMONITORING PROGRAM'xposure Pathway
~antf/or Sam le Number ofSamples and Locationsb Sampling and Collection Fre uenc Type and Frequency
~ofAnal sls
- e. Shoreline Sediment (Continued)
One sample from each ofat least two downstream locations with recreational use (TRM 293 and 279.5).
Atleast once per 184 days.
Gamma scan ofeach sample.
- 4. INGESTION
- a. Milk At least 2 samples from dairy farms in Atleast 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.
Gamma scan and I-131 on each sample.
Sr-89 and Sr-90 at least once per 31 days.
- b. Fish Atleast one sample from control location (Farm Be and/or R).
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.
Table A-1 BROWNS FERRY NUCLEARPLANT RADIOLOGICALENVIRONMENTALMONITORINGPROGRAM*
Exposure Pathway
~and/or Sam le Number ofSamples and Locationsb Sampling and Collection Fre uenc Type and Frequency
~ofAnal ala
- d. Fruits and Vegetables Samples offood crops such as greens, corn, green beans, tomatoes, and potatoes grown at private gardens and/or farms in the immediate vicinity ofthe plant.
At least once per year at time of harvest.
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 but not providing a milksample (Farm T).
Once per 31 days.
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 1998.
- b. Sample locations, sector and distance from plant, are described in Table A-2 and A-3 and shown in Figures A-l,A-2, and A-3.
- c. Composite samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
- d. The sample location at the Decatur City Water Plant serves as a control sample forboth surface water and drinking water.
e Table A-2 BROWNS FERRY NUCLEARPLANT RADIOLOGICALENVIRONMENTALMONITORINGPROGRAM SAMPLINGLOCATIONS Map Location Numbera I
2 3
4 5
6 7
8 9
10 11 12 13 19 22 23 24 25 26 28 34 36 70 71 72 73 74 Sector NW NE SSE W
W E
N NNE ENE NNW SSW NNW N
(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 Farm Bc Farm T TRM 259.8 TRM 286.5 TRM305 TRM293 TRM 279.5 Wheeler Reservoir Guntersville Reservoir Approximate Distance
~iles 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 11.4d 12.0d 34.4d 19.1d 05d 28.8 3.2 34.2d 7.5d 11.0d I.od 14.5d Indicator (I) or Control C I
I I
I C
C I
I I
I I
I I
C I
I C
I I
I C
I I
I C
I I
I C
Samples Collectedb 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
F CF M
S V
- 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 ~ Tcnncssee River Mile.
- d. Miles from plant discharge at (TRM 294).
Charcoal filter(Iodine)
~ Milk
~ Soil Vegetation PW ~ Public drinking water SS
~ Shoreline sediment W
~ Well water Table A-3 BROWNS FERRY NUCLEARPLANT THERMOLUMINESCENTDOSIMETER (TLD)LOCATIONS Map Location NumbeR I
2 10 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 5G 57 58 59 60 61 62 G3 G4 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-l S-2 SSW-I SSW-2 SW-I SW-2 SW-3 WSW-I WSW-2 WSW-3 W-I W-2 WA 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
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 7.5 31.3 24.2 1.0 0.9 0.9 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
~Offside 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.
See Figures A-l,A-2, and A-3.
- b. TLDs designated "onsitc" are those located 2 miles or less from the plant.
TLDS designated "offsitc"arc those located morc than 2 miles from the plant.
4
Figure A-1 Radiological Environmental Monitoring Locations Within 1 mile of Plant 326.2 7
~ 8 33.75 NE 303.75 WNW 28m 56.25 41'9 ENE 281.26 78.76 44 258.75 WSW
~
~l BROWNS FERRY 4g NucLEAR PLANT 6p 48 46 101.25 236.25 123.75 SW 213.75 SSW 191.26 S
168.75 146.25 SSE Scale Mile SE
Figure A-2 Radiological Environmental Monitoring Locations Between 1 and 5 miles from the Plant
$2$.2$
NNW
$$4.2$
N 23 I
lead NW NE 42
$ $.2$
WNW 85 er
~ 8
~ 10 2$ I.2 38, 84
~82 BI 4
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. I 9
47 WSW ree re 61 I22.2$
66 SE 2 IS.T$
14$>$
SSW I~ Idd IM.TS
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0 SCALE 0$
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Figure A-3 Radiological Environmental Monitoring Locations More than 5 miles from the Plant 34S 7d 11.2S 328.2d 33.75 HW AW EHCESDRO RIILASKI HE 303.7S TAV TTEVILLE 8.25 34 281.26 FLOREHC L
~ 2 SCLE HOAL AT S
0 43 46 TSVILL 258.76 57 3
18 DECA IHISS LLVILLE WS
<<Wn
~ AL 328.2 HALEVVI LE ARAB 123.76 SE 213.76 SSW 181.2d s
188.76 148.25 SCALE MILES
APPENDIX B 1998 PROGRAM MODIFICATIONS
APPENDIXB Radiolo ical Environmental Monitorin Pro am Modifications Modifications were made in the sampling ofsediment and invertebrates (Asiatic Clams) during 1998. A change in the BFN monitoring program implemented for the Fall sampling period eliminated the collection ofclams and replaced the collection ofbottom sediment with the collection ofshoreline sediment.
These modifications were made based on the guidance provided in NUREG-1302, "Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls forBoiling Water Reactors."
The change in sediment sampling was implemented to provide for the monitoring ofthe direct exposure pathway &om radionuclides that may be deposited in the sediment.
Sampling ofshoreline sediment &om recreational use areas willprovide a better assessment ofthis potential exposure pathway.
Since there is no human consumption ofthe Asiatic Clams &om the Tennessee River, it was concluded that sampling ofthese clams for monitoring ofthe ingestion pathway was not necessary.
Table B-1 provides a detail summary ofthe 1998 modifications.
Table B-I Radiolo ical Environmental Monitorin Pro ram Modifications Date Station Location Remarks 11/98 TRM 305 Decatur Riverwalk Added location for the collection ofshoreline Marina sediment.
11/98 TRM 293 Mallard Creek Recreational area Added location for the collection ofshoreline sediment.
11/98 TRM 279.5 Joe Wheeler State Park Day Use Area Added location for the collection ofshoreline sediment.
12/98 TRM 293.7 0.3 miles downstream Deleted station and collection ofbottom sediment.
12/98 TRM 288.8 5.2 miles downstream Deleted station and collection ofbottom sediment.
12/98 12/98 12/98 TRM 297.0 Control Indicator Upstream Downstream Deleted the collection ofclams.
Deleted the collection ofclams.
3.0 miles upstream Deleted station and collection ofbottom sediment.
Appendix C, Pro am Deviations During 1998, seven samples were not collected as scheduled due to equipment problems or sample unavailability. Details ofthe missed samples are provided below and in Table C-l.
Atotal offour air particulate filterand charcoal cartridge samples were not collected from sampling location LM-3 due to equipment problems.
Samples were not available Rom this location on July 27, 1998 or August 3, 1998 due to problems with the sampling pump. Repairs were made to the sampling pump and the pump operated correctly for the next four weeks.
Additional problems with the sampling system resulted in missed samples again on September 8, 1998 and September 14, 1998. Repairs were made and the sampling system operated normally for the remainder ofthe year.
t The continuous surface water sample scheduled for collection on January 20, 1998 &om the control location at TRM 306 was not available due to the relocation ofthe sampling equipment from the TRM 305. This sample also serves as the control for public water sampling.
Grab samples were taken weekly at the location during the relocation ofthe equipment.
The analysis ofthese grab samples identified only the normal natural background levels.
The milksample scheduled for collection from the Richardson Dairy farm on February 23, 1998 was not available. This location is one oftwo control locations for milksampling. A sample was collected on February 23, 1998 &om the other dairy farm used as a control location.
The continuous well water sample scheduled for collection on December 21, 1998 &om Well /f6 was not collected due to problems with the sampling pump. The electrical power for the pump was not available.
Table C-1 Radiolo ical Environmental Monitorin Pro ram Deviations Date Station Location Remarks 01/20/98 TRM 306 12.0 miles upstream Continuous surface water sample was not available. The sampling equipment was out ofservice due to relocation ofthe sampling point from TRM 305. Relocation was completed and the samples were collected as scheduled for the remainder ofthe year.
02/23/98 Farm R I
07/27/98 LM-3 12.5 miles SW 0.9 miles ENE Milkwas not available at the farm. A sample was collected as scheduled from the other control location dairy farm.
Airparticulate filterand charcoal cartridge samples not collected due to equipment problems.
Repairs initiated.
08/03/98 LM-3 0.9 miles ENE Sampling equipment stillout ofservice.
Repairs were completed and samples collected as scheduled for the next sampling period.
09/08/98 LM-3 0.9 miles ENE Airparticulate filterand charcoal cartridge samples not collected due to equipment problems.
Repairs initiated.
09/14/98 LM-3 0.9 miles ENE Sampling equipment stillout ofservice.
Repairs were completed and samples collected as scheduled for the next sampling period.
12/21/98 Well //6 On site The continuous well water sample was not collected due to sampling pump power supply problems.
Power was restored to the sampling system.
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.
Normal counting times are 50 minutes. Water samples are prepared by evaporating 500 ml of samples to near dryness, transferring to a stainless steel planchet and completing the evaporation process. 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.
With the beta-gamma coincidence counting system, background counts are virtuallyeliminated and extremely low levels ofdetection can be obtained.
After a radiochemical separation, samples analyzed for Sr-89,90 are counted on a low background beta counting system.
The sample is counted a second time after a 7-day ingrowth period. Prom 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.
0
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 high resolution spectroscopy system germanium detector.
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 LimitsofDetection Sensitive radiation detection devices can produce a signal even when no radioactivity is present in a sample being analyzed.
This signal may come 6'om 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 Rom 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 reading, 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
&om 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 from 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 fallbelow the average machine background and halfthe 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.
Anumber 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 nominal LLDs have not been established, and LLDofzero is assumed in determining ifa measured activity is 4
TABLEE-1 Nominal LLDValues A. Radiochemical Procedures Gross Beta Tritium iodine-131 Strontium-89 Strontium-90 AirFilters
~Ci/m'.002 Water
~Ci/L 1.9 300 0.4 5.0 2.0 Milk
~Ci/L 0.4 3.5 2.0 Wet Vegetation
~C//K wet 6.0 31.0 12.0 Sediment and Soil
~Ci/ ~~
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 Tl-208 Ra-224 Ra-226 Ac-228 Air Particulates
~C//m3
.005
.01
.02
.005
.005
.02
.005
.005
.005
.005
.005
.005
.005
.OQ5
.04
.015
.01
.005
.02
.005
.005
.005
.02
.002
.01 Charcoal Filter ttCi/m3
.02
.07 0.15 0.03 0.02 0.12 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 pCi/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
~Ci/
dD/
.07
.15
.30
.20
.03
.15
.03
.03
.05
.25
.03
.03
.05
.03
.40
.30
.20
.08
.25
.04
.50
.10
.25
.03
.10 Wet Vegetation kCCi/k wet 35 115 200 60 25 190 30 25 45 30 20 20 45 20 400 130 50 40 200 40 80 55 250 30 70 Soil and Sediment p~Ci/ ~d
.10
.20
.35
.25
.03
.20
.03
.03
.05
.04
.03
.03
.05
.03 75
.30
.20
.05
.25
.10
.15
.15
.45
.06
.75
.15
.25 Fish
~Ci/ d~
.Q7
.15
.30
.20
.03
.15
.03
.03
.05
.25
.03
.Q3
.05
.03
.40
.30
.20
.08
.25
.04
.50
.10
.25
.03
.10 Clam Flesh
~Ci/
dry
.35
.85 2.4 1.7
.25 1.25
.14
.15
.45
.25
.25
.20
.40
.20 3.50 2.4 1.4
.45 1.9
.30
.10
.50 2.0
.25
.75 Foods Tomatoes Potatoes, etc.
~Cilk wet 20 60 95 20 25 90 10 10 45 10 10 10 45 10 250 50 25 25 90 40 8Q 40 130 30 50
Table E-2 Maximum Values for the Lower LimitsofDetection (LLD)
Specified by the BFN Offsite Dose Calculation Manual A~ssl sis gross beta Water pCi/L Airborne Particulate or Gases
~C//m' x10'ish
~Ci/k wet Milk
~C//L N.A.
Food Products p~Ci/k wet Sediment
~Ci/k, dry N.A.
H-3 2000'.A.
N.A.
Mn-54 15 N.A.
130 N.A.
N.A.
Fe-59 30 N.A.
260 N.A.
N.A.
Co-58,60 Zn-65 15 30 N.A.
N.A.
130 260 N.A.
N.A.
N.A.
N.A.
Zr-95 30 N.A.
N.A.
N.A.
N.A.
N.A.
Nb-95 I-131 Cs-134 Cs-137 15 lb 15 18 N.A.
7x 10' x10'x10'.A.
N.A.
130 150 N.A.
15 18 N.A.
60 60 80 N.A.
N.A.
150 180 Ba-140 s
La-140 60 15 N.A.
N.A.
N.A.
60 15 N.A.
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/lite'r for I-131.
Appendix F uali Assurance/
uali 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. There are two primary tests which are performed on all devices. In the first type, the device is operated without a sample on the detector to determine the background count rate. The background counts are usually low values and are due to machine noise, cosmic rays, or trace amounts 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 Rom either test fall outside the expected range, the device is inspected for malfunction or contamination. It is not placed into ser vice 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 t
device 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 Rom 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 staff can split a sample into two portions.
Such 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 staffmember 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 has immediate knowledge ofthe quality ofthe measurement process. Aportion 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.
At present, 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 t
best 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 1998, 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 another 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.
A. Radiochemical Analysis ofWater (pCi/L)
Gross Beta Strontium-89 EPA Value TVA EPA Value Date
(+3 ~si ma A~v.
(+3 ~si ma Strontium-90 TVA EPA Value TVA
~Av.
(+3~si ma
~Av Tritium Iodine-131 TVA EPA Value TVA A~v.
(+3 ~si ma
~Av EPA Value
(+3~si ma 4+9 8
8+9 01/98 02/98 03/98 04/98 07/98 08/98 09/98 10/98 11/98 10 32+9 30 105+18 2155+602 2199 6+9 21+9 8
21 18+9 7+9 18 8
16 13+9 17996+3118 17900 6+3 19+9 8+9 19 4+9 B. Gamma-Spectral Analysis ofWater (pCi/L)
~Av.
(+3~si ma
~Av Barium-133 Cobalt-60 EPA Value TVA EPA Value Date
(+3~si ma
~Av
(+3~si ma Cesium-134 Cesium-137 TVA EPA Value TVA
~Av.
(+3~si ma
~Av EPA Value
(+3~si ma 04/98 06/98
. 10/98 11/98 50+9 12+9 21+9 38+9 51 13 22 41 22+9 31+9 6+9 105+9 21 30 7
94 10+9 10 35+9 35 50+9 51 111+10 108 41 40+9 104+17 131+23 104 56+10 55 132 Table F-I RESULTS OBTAINEDIN INTERLABORATORYCOMPARISON PROGRAM
Appendix G Land Use Surve A land use survey was conducted to identify the nearest milk animal, the nearest residence, and the nearest garden ofgreater than 500 square feet producing fresh leafy vegetables in each of 16 meteorological sectors within a distance of5 miles from the plant. The land use survey also identified the location ofall milkanimals and gardens ofgreater than 500 square feet producing fresh leafy vegetables within a distance of3 miles Gom the plant.
The land use survey was conducted between April 1 and October 1 using appropriate techniques such as door-to-door survey, mail survey, telephone survey, aerial survey, or information from local agricultural authorities or other reliable sources.
In order to identify the locations around BFN which have the greatest relative potential for l
impact by the plant, radiation doses were projected for individuals livingnear BFN. These projections used the data obtained in the survey and historical meteorological data. The calculations also assumed that releases were equivalent to the design basis source terms. The dose projections are relative in nature and do not reflect actual exposures to individuals living near BFN. Calculated doses to individuals based on measured effluents from the plant were well below applicable dose limits (see Assessment and Evaluation Section and Table 3).
Dose projections &om air submersion were calculated for the nearest resident in each sector and dose projections from drinking milkor eating foods produced near the plant were calculated for the areas with milkproducing animals and gardens, respectively.
Airsubmersion doses were calculated for the nearest resident in each sector, the resulting values were similar to those calculated for 1997. Any changes &om the 1997 results were small and
were due to differences in the distance values used for the nearest resident.
These differences occurred from 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 1998. Gardens were identified in two sectors in 1998 that did not contain a garden in 1997.
For milkingestion, projected annual doses were calculated for the same two locations reported in 1997. These were the only two locations where milkproducing animals were identified.
Samples are collected &om both ofthese farms. There were no changes in relative projected doses calculated for these two locations compared to the results &om 1997 survey.
Tables G-1, G-2, and G-3 show the comparative calculated doses for 1997 and 1998.
Table G-1 BROWNS FERRY NUCLEARPLANT Relative Projected Annual AirSubmersion Dose to the Nearest Resident WithinFive Miles ofPlant mrem/year Sector N
NNE NE ENE E
SSW SW WSW 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 0.19 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 1998 Surve Annual Dose 0.45 0.14 0.12 0.17 0.33 0.22 0.15 0.18 0.10 0.08 0.19 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
SSW SW WSW 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
a 1.10 Annual Dose 8.11 1.18 1.27 2.24 1.75 2.28 2.68 0.60 1.27 10.10 1998 Surve Approximate Distance Miles 1.24 3.10 2.67 2.68 2.70 1.56 a
a 2.78 2.59 2.77 2.84 1.85 a
a 1.10 Annual Dose 8.11 1.18 1.27 1.33 1.75 4.08 2.28 2.68 1.15 0.56 1.15 10.10 Number of Gardens Within
~3milee 1993 2
1 1
1 1
1 0
0 1
1 1
1 1
0 0
5 note a Garden not found within 5 miles.
I Table G-3 BROWNS FERRY NUCLEARPLANT Relative Projected Annual Dose to Receptor Thyroid from Ingestion ofMilk mrem/year Location Sector Approximate Distance Feeding Factor Consumer Age *
{M~iles'997 1998 1997 1998 Annual Dose 1997 1998 s/m'arm Bn Farm B N
4.9 0.38 0.38 A
A 0.029 0.029 6.8 0.01 0.01 A
A 0.005 0.005 1.28E-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.
A = Adult, age 17+ years
APPENDIXH DATATABLES ANDFIGURES
Table H-1 Average External Gamma Radiation Levels at Various Distances from BROWNS FERRY Nuclear Plant for Each Quarter -1998 mR / Quarter (a)
Distance Miles 1st qtr 0-1 16.1 a 0.9 1 - 2 14.4 2 1.3 2 - 4 13.4 2 1.0
> 6 13.4 2 0.8 2nd qtr 16.8 2 1.0 15.4 2 1.5 14.2 k 1.0 14.1 k 1.4 14.0 2 0.8 3rd qtr 18.0 R 0.9 16.2 2 1.5 15.2 k 1.4 15.3 2 1.7 15.5 2 1.2 Average External Gamma Radiation Levels (b) 4th qtr 16.4 2 1.1 14.9 R 1.2 13.8 R 0.9 14.0 R 1.4 14.1 f0.6 per annum mR/yr 67 61 57 56 57
- Average, 0 - 2 miles 15.6 t 1.2 (onsite) 16.4 k 1.3 17.5 R 1.3 16.0 k 1.3 66
- Average,
>2miles 13.211.1 (offsite) 14.1 2 1.2 15.3 2 1.5 14.0 2 1.1 57 (a)
Field periods normalized to one standard quarter (2190 hours0.0253 days <br />0.608 hours <br />0.00362 weeks <br />8.33295e-4 months <br />)
(b)
Average of the individual measurements in the set s 1 standard deviation of the set TABLE H-2 DIRECT RADIATIONLEVELS Individual Stations at Browns Ferry Nuclear Plant Environmental Radiation Levels Map Location Hua~
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 61 62 85 91 90 110 112 130 135 163 165 185 182 TLD Station Direction, Hua~
daarcaa Approx
- Distance, 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 39K 17.2 12.6 15.4 16.6 12.3 17.1 14.9 14.0 16.1 13.8 16.5 14.0 14.6 14.3 13.7 15.5 9.5 13.8 14.3 14.0 12.0 mR I q 2nd Qtr Apr-Jun 18.2 13.3 16.2 note 1 13.5 17.2 15.9 14.7 17.4 note 1
17.6 14.7 14.6 15.0 14.1 15.9 10.1 14.7 15.1 15.0 12.9 uarter 3rd Qtr Jul - Sep 19.2 14.4
. 18.1 18.3 15.4 18.1 18.3 15.3 18.2 18.1 19.0 16.4 15.7 16.2 15.9 16.8 10.9 15.1 15.5 15.8 13.8 4th Qtr Oct-Dec 17.3 13.0 16.5 16.9 13.7 17.6 16.1 14.5 16.4 14.6 17.5 14.6 14.6 14.3 13.8 14.7 9.8 14.4 14.6 14.4 12.7 Annual Exposure mHhcar 71.9 53.3 66.2 69.1 54.9 70.0 65.2 58.5 68.1 62.0 70.6 59.7 59.5 59.8 57.5 62.9 40.3 58.0 59.5 59.2 51.4 note 1
Sum of available quarterly data normalized to 1 year for the annual exposure value
TABLE H -2 continued DIRECT RADIATIONLEVELS Individual Stations at Browns Ferry Nuclear Plant Environmental Radiation Levels Map Location Humbler.
53 54 55 56 57 58 59 60 61 62 5
63 64 65 66 67 1
68 10 69 TLD Station Hua~
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 Direction, RQERR 203 199 228 219 224 244 251 257 275 268 275 265 291 293 326 321 310 331 331 339 Approx
- Distance, miha 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 2995 12.2 13.3 12.9 13.4 12.3 12.3 13.8 12.5 14.3 12.3 12.8 13.1 13.2 13.2 15.2 14.0 13.7 15.8 16.0 13.5 mR/
2nd Qtr Apr-Jun 12.8 14.5 13.5 14.3 13.0 13.2 15.9 13.2 15.4 13.7 13.0 14.8 14.4 14.1 15.7 15.1 13.8 16.8 17.2 14.8 quarter 3rd Qtr Jul - Sep 19K 12.8 15.2 14.4 14.8 note 1
14.0 15.5 14.7 16.1 14.6 13.8 16.2 15.3 15.5 17.3 17.4 14.5 18.0 18.2 16.8 4th Qtr Oct-Dec 1996 12.5 14.3 13.7 14.2 13.2 12.9 14.9 13.3 14.5 13.3 13.3 14.8 14.1 14.4 15.3 15.1 13.9 16.2 16.5 15.0 Annual Exposure mBhesr 50.3 57.3 54.5 56.7 51.3 52.4 60.1 53.7 60.3 53.9 52.9 58.9 57.0 57.2 63.5 61.6 55.9 66.8 67.9 60.1 note 1
Sum of available quarterly data normalized to 1 year for the annual exposure value
TENNESSEE VALLEY AUTHORITY ENVIRONMEHTAL RADIOLOGICAL HONITORING AND INSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IH AIR FILTER PCI/H3 - 0.037 BQ/M3 NAME OF FACILITY: BROWS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIMESTONE ALABAMA DOCKET NO.:
50-259,260,296 REPORTING PERIOD:
1998 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)
RAHGE DISTANCE AND DIRECTION RANGE SEE NOTE 1
SEE NOTE 2 SEE NOTE 2 COHTROL LOCATIONS HEAN (F)
RANGE SEE NOTE 2 NUHBER OF NONROUTINE REPORTED MEASUREHEN'fS GROSS BETA 2.00E-03 2.13E-02( 464/ 464) PH-2 BF ATHENS AL 6.56E 4.47E-02 10.9 MILES NE 2.26E-02(
52/
52) 2.13E-02(
104/ 104) 9.78E 4.09E-02 8.01E 4.63E-02 GAMMA SCAN (GELI) 143 BE-7 BI-214 PB-214 2.00E-02 5.00E-03 5.00E-03 1 '5E-01( 117/ 117) PH-2 BF ATHENS AL 4.66E 1.50E-01 10.9 MILES NE 1.19E-02(
68/ 117) LM-78F LAKEVIEW 5.00E 3.09E-02 2.1 MILES WEST 1.29E-02(
58/ 117)
LM4 BF TRAILER P 5 ~ OOE 3.35E-02 1.7 MILES NN'W 1.10E-01(
13/
13) 5.84E 1.50E-01 1.42E-02(
5/
13) 1.02E 2'0E-02 1.48E-02(
8/
13) 5 'OE 3.02E-02 1.04E-01(
26/.26) 4.39E 1 '8E-01 9.77E-03(
12/
26) 5.60E 2.26E-02 8.45E-03(
13/
26) 5.00E 2.22E-02 NOTE:
1 ~
NOMINAL LOWER LIHIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1 ~
NOTE:
2.
MEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY'RACTION OF DETECTABLE HEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATED IH PARENTHESES (F).
TENNESSEE VALLEY AUTHORITY ENVIRONMENTAL RADIOLOGICAL MONITORING AHD INSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN CHARCOAL FILTER PCI/M3 - 0.037 BQ/M3 NAME OF FACILITY: BRDWNS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIMESTONE ALABAMA DOCKET HO.:
50-259,260,296 REPORTIHG PERIOD: 1998 TYPE AHD TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT ALL OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN DETECT IOH MEAN (F)
NAME MEAN (F)
(LLD)
RANGE DISTANCE AHD DIRECl'IOH RANGE SEE HOTE 1
SEE NOTE 2 SEE NOTE 2 CONTROL LOCATIONS MEAN (F)
RANGE SEE NOTE 2 NUMBER OF NOHROUT INE REPORTED MEASUREMENTS GAMMA SCAN (GELI) 568 81-214 K-40 PB-214 5 'OE-02 3.00E-01 7.00E-02 6.80E-02(
21/ 464) 5.07E 1.78E-01 3.38E-01(
24/ 464) 3.01E 4.12E-01 9.08E-02(
10/ 464) 7.28E 1.51E-01 PM-3 BF DECATUR AL 8.2 MILES SSE LM3 BF NORTHEAST 1.0 MILE EHE PM-3 BF DECATUR AL 8.2 MILES SSE 1.15E-01(
5.14E 3.71E-01(
3 '2E 1 ~ 51E-01(
1.51E 2/
52) 1.78E-01 2/
48) 3.90E-01 1/
52) 1.51E-01 6.68E-02(
4/ 104) 5.26E 9.09E-02 3.54E-01(
5/ 104) 3.13E 4 ~ 11E-01 1.10E-01(
1/ 104) 1.10E 1.10E-01 I-131 SEE NOTE 3.
NOTE:
1 ~
HOMINAL LOWER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1.
NOTE:
2.
MEAN AHD RANGE BASED UPON DETECTABLE MEASUREMENTS OHLY.
FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)-
NOTE:
3.
THE ANALYSIS OF CHARCOAL FILTERS WAS PERFORMED BY GAMMA SPECTROSCOPY.
NO l-131 WAS DETECTED.
THE LLD FOR I-131 BY GAMMA SPECTROSCOPY WAS 0.03 pCi/cubic meter.
TEHHESSEE VALLEY AUTHORITY ENVIROHMENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IH MILK PCI/L - 0.037 BQ/L HAHE OF FACILITY: BROWNS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIMESTONE ALABAMA DOCKET NO.:
50-259,260,296 REPORTIHG PERIOD: 1998 TYPE AHD 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 RAHGE SEE NOTE 1
SEE NOTE 2 SEE NOTE 2 CONTROL LOCATIONS MEAN (F)
RANGE SEE NOTE 2 NUMBER OF NOHROUTIHE REPORTED MEASUREMENTS IOD IN E-131 2.00E+01 52 VALUES < LLD SHITH/BENNETT FARM 5.0 MILES H 1.00E+02 1.35E+03(
52/
- 52) SHITH/BENNETT FARM 1.24E+03-1.49E+03 5.0 MILES N K-40 SR 89 51 3.50E+00 25 VALUES < LLD SR 90 51 103 4.00E-01 52 VALUES < LLD GAMMA SCAN (GELI) 103 BI-214 51 VALUES < LLD 26 VALUES < LLD 2.04E+01(
1/
51) 2.04E+01-2.04E+01 1.37E+03(
26/
26) 1.33E+03(
51/
51) 1.26E+03-1.49E+03
'1.18E+03-1.48E+03 26 VALUES < LLD 2.DOE+00 2.02E+00(
2/
25)
SMITH/BEHNETT FARM 2.02E+00(
2/
12) 26 VALUES < LLD 2.01E+00-2'3E+00 5.0 MILES H 2.01E+00-2.03E+00 NOTE:
1.
NOMINAL LOWER LIMIT OF DETECTION (LLD) AS DESCRIBED IH TABLE E-1.
NOTE:
2.
MEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY.
FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IH PARENTHESES (F).
TENNESSEE VALLEY AUTHORITY ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUHENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN VEGETATION PCI/KG - 0.037 BQ/KG (WET WEIGHT)
NAHE OF FACILITY: BROWNS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIMESTONE ALABAMA DOCKET NO.:
50-259,260,296 REPORTING PERIOD: 1998 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIHIT ALL OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN DETECTION MEAN (F)
NAHE MEAN (F)
(LLD)
RANGE DISTANCE AND DIRECTION RANGE SEE NOTE 1
SEE NOTE 2 SEE NOTE 2 CONTROL LOCATIONS HEAN (F)
RANGE SEE NOTE 2 NUMBER OF NONROUtINE REPORTED MEASUREHEHTS IODINE-131 23 6.DOE+00 '1 VALUES < LLD 12 VALUES < LLD GAMHA SCAN (GELI) 26 BE-7 BI-214 K-40 PB-214 2.DOE+02 5.50E+01 4.DOE+02 B.DOE+01 1.26E+03(
10/
13)
TERRY FARH 4.28E+02-2.99E+03 3.2 HILES WN'W 7.70E+01(
2/
13)
TERRY FARH 7.47E+01-7.92E+01 3.2 HILES WNW 4.93E+03(
13/
13)
TERRY FARH 2.26E+03-7.01E+03 3.2 MILES WNW 13 VALUES < LLD TERRY FARM 3.2 HILES WNW 1 '6E+03(
10/
13) 4 '8E+02-2.99E+03 7.70E+01(
2/
13) 7.47E+01-7.92E+01 4.93E+03(
13/
13) 2.26E+03-7.01E+03 13 VALUES < LLD 1.07E+03(
13/
13) 2.02E+02-3.06E+03 2.45E+02(
5/
13) 6.41E>01-9.00E+02 5.80E+03(
13/
13) 2.70E+03-7.70E+03 1.30E+02(
1/
13) 1.30E+02-1.30E+02 NOTE:
1.
NOHINAL LOWER LIHIT OF DETECtION (LLD) AS DESCRIBED IN TABLE E-1.
NOTE:
2.
HEAN AND RANGE BASED UPON DE'tECTABLE MEASUREHENTS ONLY.
FRACTION OF DETECTABLE HEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).
0 TENNESSEE VALLEY AUTHORITY ENVIRONHENTAL RADIOLOGICAL HONITORING AND INSTRUHENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN SOIL PCI/GH - 0.037 BQ/G (DRY WEIGHT)
NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIHESTONE ALABAHA DOCKET NO.:
50-259,260,296 REPORTING PERIOD:
1998 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORHED LOWER LIHIT OF DETECTION (LLD)
SEE NOTE 1
ALL INDICATOR LOCATIONS LOCATION 'WITH HIGHEST ANNUAL HEAN MEAN (F)
NAME MEAN (F)
RANGE DISTANCE AND DIRECTION RANGE SEE NOTE 2 SEE NOTE 2 CONTROL LOCATIONS HEAN (F)
RANGE SEE NOTE 2 NUMBER OF NONROUTINE REPORTED HEASUREHENTS I
I GAMMA SCAN (GELI) 11 AC-228 2.50E-01 4.50E-01 1.50E-01 3.00E-02 7.50E-01 1 ~ OOE-01 1.50E-01 7.50E-01 1.50E-01 6.00E-02 1.13E+00(
6.31E 1.22E+00(
7.42E 8.97E-01(
5.78E 2.51E-01(
1.28E 5.34E+00(
2.31E+00-1.14E+00(
6.60E 9.96E-01(
6.67E 'l.32E+00(
1.01E+00-8.97E-01(
5.78E 3.60E-01(
2.08E BI-212 BI-214 CS-137 K-40 PB-212 PB-214 RA-224 RA-226 TL-208 SR 89 SR 90 11 1.60E+00 9 VALUES 11 4.00E-01 9 VALUES 9/
9) 1.40E+00 9/
9) 1.48E+00 9/
9) 1.16E<00 8/
9) 4 ~ 11E-01 9/
9) 7.54E+00 9/
9) 1.42E+00 9/
9) 1.26E+00 7/
9) 1.60E+00 9/
9) 1.16E+00 9/
9) 4.35E-01
< LLD
< LLD PH-3 BF DECATUR AL 8.2 MILES SSE LM4 BF TRAILER P 1.7 HILES NNW LH4 BF TRAILER P 1.7 HILES NNW LH-6BF BAKER BOTTOH 3'
HILES SSW LH2 BF NORTH 0.9 HILE NNE LH1 BF HORTNWEST
'I.O MILE N LH4 BF TRAILER P 1.7 HILES NN'W LM4 BF TRAILER P 1.7 HILES NNW LH4 BF TRAILER P 1.7 HILES NNW PH-3 BF DECATUR AL 8.2 HILES SSE 1.40E+00(
1 ~ 40E+00-1.48E+00(
1.48E+00-1.16E+00(
1.16E+00-4.11E-01(
4 ~ 11E 7.54E+00(
7.54E+00-1.42E+00(
1.42E+00-1.26E+00(
1 ~ 26E+00-1.60E+00(
1.60E+00-1.16E+00(
1.16E+00-4.35E-01(
4.35E 1/
1) 1.40E+00 1/
1) 1.48E+00 1/
1) 1.16E+00 1/
1) 4.11E-01 1/
1) 7.54E+00 1/
1) 1.42E+00 1/
I) 1.26E+00 1/
1) 1.60E<00 1/
1) 1.16E+00 1/
1) 4.35E-01 8.49E-01(
6.61E 8.47E-01(
7.17E 7-56E-01(
7.31E 5.42E-01(
2.51E 4.22E+00(
3.93E+00-9.00E-01(
7.25E 8.30E-01(
8.03E 1.11E+00(
1.11E+00-7.56E-01(
7.31E 2.80E-01(
2.22E 2/
2) 1.04E+00 2/
2) 9.77E-01 2/
2) 7.81E-01 2/
2) 8.33E-O'I 2/
2) 4.50E+00 2/
2) 1.08E+00 2/
2) 8.57E-01 1/
2) 1.11E+00 2/
2) 7.81E-01 2/
2) 3.37E-01 2 VALUES < LLD 2 VALUES < LLD NOTE:
1.
NOMINAL LOWER LIHIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1.
NOTE:
2.
HEAN AND RANGE BASED UPON DETECTABLE MEASUREHENTS ONLY-FRACTION OF DETECTABLE HEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).
TEHHESSEE VALLEY AUTHORITY ENVIRONHENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN APPLES PCI/KG - 0.037 BQ/KG (WET WT)
NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIMESTONE ALABAMA DOCKET NO.:
50-259,260,296 REPORTING PERIOD:
1998 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT ALL OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN DETECTION HEAN (F)
NAHE HEAN (F)
(LLD)
RAHGE DISTANCE AHD DIRECTION RANGE SEE NOTE 1
SEE NOTE 2 SEE NOTE 2 CONTROL LOCATIONS HEAN (F)
RANGE SEE NOTE 2 NUHBER OF NONROUT INE REPORTED MEASUREMENTS GAMMA SCAN (GELI) 2 K-40 2.50E+02 9.52E+02(
1/
1)
BFNP Paradise Shores 9.52E+02(
1/
1) 8.49E+02(
1/
1) 9.52E+02-9.52E+02 1.5 Miles NNW 9.52E+02-9.52E+02 8.49E+02-8.49E+02 NOTE:
1.
NOHINAL LOWER LIHIT OF DETECTION (LLD) AS DESCRIBED IH TABLE E-1 ~
NOTE:
2.
HEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY-FRACTION OF DETECTABLE MEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).
TENNESSEE VALLEY AUTHORITY ENVIRONHENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATION MESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN CABBAGE PCI/KG - 0.037 BQ/KG (llET IIT)
HAME OF FACILITY: BRSINS FERRY NUCLEAR PLANT LOCATIOH OF FACILITY: LIMESTONE ALABAMA DOCKET NO.:
50-259,260,296 REPORTING PERIOD:
1998 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LelER LIMIT ALI.
OF INDICATOR LOCATIONS LOCATION HITH 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 NONROUTINE REPORTED MEASUREMENTS GAMMA SCAN (GELI)
K-40 2
2.50E+02 1.76E+03(
1/
- 1) 3 MILES SSM 1.76E+03-1.76E+03 1.76E+03(
1/
1) 2.03E+03(
1/
1) 1.76E+03-1.76E+03 2.03E+03-2.03E+03 NOTE:
1.
NOMINAL LOMER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABI.E E-1.
NOTE:
2.
MEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY.
FRACTION OF DETECTABLE MEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) ~
TENNESSEE VALLEY AUTHORITY ENVIRONHENTAL RADIOLOGICAL HONITORING AND INSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN CORN PCI/KG - 0.037 BQ/KG (WET WT)
NAHE OF-FACILITY: BROWNS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIMESTONE ALABAMA DOCKET NO.:
50-259,260,296 REPORTING PERIOD: 1998 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIHIT ALL OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN DETECTION MEAN (F)
NAME MEAN (F)
(LLD)
RANGE DISTANCE AND DIRECTION RANGE SEE NOTE
'I SEE NOTE 2 SEE NOTE 2 CONTROL LOCATIONS MEAN (F)
RANGE SEE NOTE 2 NUMBER OF NONROUTINE REPORTED MEASUREMENTS GAMMA SCAN (GELI) 2 K-40 2.50E+02 1.69E+03(
1/
1)
BFNP Paradise Shores 1.69E+03(
1/
1) 1.96E+03(
1/
1) 1.69E+03-1.69E+03 1.5 Miles NNW 1.69E+03-1.69E>03 1.96E+03-1.96E>03 NOTE:
1.
HOMINAL LOWER LIHIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-l.
NOTE:
2.
MEAN AND RANGE BASED UPON DETECTABLE MEASUREHENTS ONLY.
FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).
TEHNESSEE VALLEY AUTHORITY ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IH GREEN BEAHS PCI/KG - 0.037 BQ/KG (IIET MT)
NAME OF FACILITY: BROWS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIMESTONE ALABAMA DOCKET NO.:
50-259,260,296 REPORTING PERIOD:
1998 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LONER LIMIT ALL OF IHDICATOR LOCATIOHS.
LOCATION IIITH HIGHEST AHNUAL MEAN DETECTION MEAN (F)
NAME MEAN (F)
(LLD)
RANGE DISTANCE AND DIRECTION RANGE SEE NOTE 1
SEE NOTE 2 SEE NOTE 2 CONTROL LOCATIONS MEAN (F)
RANGE SEE NOTE 2 NUMBER OF NOHROUTINE REPORTED MEASUREMENTS GAMMA SCAN (GELI) 2 K-40 2.50E+02 3.05E+03(
1/
- 1) BFNP Paradise Shores 3.05E+03(
1/
1) 1.84E>03(
1/
1) 3.05E+03-3.05E+03 1.5 Miles NNM 3.05E+03-3.05E+03 1.84E+03-1.84E+03 NOTE:
1.
HOMINAL LQIER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1.
NOTE:
2.
MEAN AHD RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY.
FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) ~
TENNESSEE VALLEY AUTHORITY ENVIRONHEHTAL RADIOLOGICAL HONITORING AND INSTRUHENTATION llESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN POTATOES PCI/KG - 0.037 BQ/KG (llET MT)
NAHE OF FACILITY: BRONNS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIHESTONE ALABAMA DOCKET HO.:
50-259,260,296 REPORTIHG PERIOD: 1998 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORHED LONER LIHIT ALL OF INDICATOR LOCATIONS LOCATION MITH HIGHEST ANNUAL HEAN DETECTION MEAN (F)
NAHE MEAN (F)
(LLD)
RANGE DISTANCE AND DIRECTION RANGE SEE NOTE 1
SEE NOTE 2 SEE NOTE 2 CONTROL LOCATIONS HEAN (F)
RANGE SEE NOTE 2 NUHBER OF NONROUTINE REPORTED MEASUREHENTS GAMMA SCAN (GELI)
K-40 2
2.50E+02 2.86E+03(
1/
- 1) 3.0 MILES NNE 2.86E+03-2.86E+03 3.0 MILES NNE 2.86E+03(
1/
1) 3.12E+03(
1/
1) 2-86E+03-2.86E+03 3.12E+03-3.12E+03 NOTE:
1.
NOMINAL LONER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1 ~
NOTE:
2.
MEAN AND RANGE BASED UPON DETECTABLE HEASUREMENTS ONLY.
FRACTION OF DETECTABLE MEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).
TENNESSEE VALLEY AUTHORITY ENVIRONMENTAL RADIOLOGICAL MONITORING AHD INSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IH 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 REPORTIHG PERIOD:
1998 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT ALL OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN DETECTIOH MEAN (F)
NAME MEAN (F)
(LLD)
RANGE DISTANCE AND DIRECTION RANGE SEE NOTE 1
SEE NOTE 2 SEE NOTE 2 CONTROL LOCATIOHS MEAN (F)
RANGE SEE NOTE 2 NUMBER OF HOHROUT IHE REPORTED MEASUREMENTS GAMMA SCAN (GELI)
K-40 2.50E+02 1.85E+03(
1/
- 1) BFHP Paradise Shores 1.85E>03(
1/
1) 1.86E+03(
1/
1) 1.85E+03-1.85E+03 1.5 Miles NNW 1.85E+03-1.85E+03 1.86E+03-1.86E+03 NOTE:
1.
HOMINAL LOWER LIMIT OF DETECTION (LLD) AS DESCRIBED IH TABLE E-1.
NOTE:
2.
MEAN AND 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 WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN SURFACE MATER(Total)
PCI/L - 0.037 BQ/L NAHE OF FACILITY: BROWNS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIHESTONE ALABAMA DOCKET NO.:
50-259,260,296 REPORTING PERIOD: 1998 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT 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 NUHBER OF NONROUTINE REPORTED MEASUREHENTS GROSS BETA I
25 1.90E+00 2.76E+00(
12/
13)
TRH 293.5 2.07E+00- 3.35E+00 2.76E+00(
12/
13) 2.74E+00(
12/
12) 2.07E+00- 3.35E+00 1.95E+00- 3.57E+00 GAMMA SCAN (GELI) 25 BI-214 TR IT IUH 2.DOE+01 2.85E+01(
1/
13)
TRH 293.5 2.85E+01-2.85E+01 3.DOE+02 4 VALUES < LLD 2.85E+01(
1/
13) 3.75E+01(
1/
12) 2.85E+01-2.85E+01 3.75E+01-3.75E+01 4 VALUES < LLD NOTE:
NOTE:
2.
MEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS OHL'Y.
FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).
TENNESSEE VALLEY AUTHORITY ENVIRONHENTAL RADIOLOGICAL MONITORIHG AND INSTRUHEHTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN PUBLIC WATER(Total)
PCI/L - 0.037 BQ/L NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIMESTONE ALABAHA DOCKET NO.:
50-259,260,296 REPORTING PERIOD: 1998 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIHIT ALL OF INDICATOR LOCATIONS LOCATION WITH NIGHEST ANNUAL HEAN DETECTION HEAR (F)
NAME HEAN (F)
(LLD)
RANGE DISTANCE AHD DIRECTION RANGE SEE NOTE 1
SEE NOTE 2 SEE NOTE 2 CONTROL LOCATIONS HEAN (F)
RANGE SEE NOTE 2 NUHBER OF NONROUTINE REPORTED HEASUREMENTS GROSS BETA 1.90E+00 2.82E+00(
56/
65)
W HOR-E LAWR WAT ATH 2.99E+00(
12/
13) 2.74E+00(
12/
12) 1.92E+00-4 '2E+00 TRH 286.5 2.11E+00- 3.71E+00 1.95E+00-3 ~ 57E+00 GAMMA SCAN (GELI) 77 BI -214 PB-214 TRITIUH 2.DOE+01 2.DOE+01 1.12E+02(
2/
65)
FLORENCE, AL 2.12E+01-2.02E+02 TRM 259.8 2.09E+02(
1/
65)
1/
13) 3.75E+01(
1/
12) 2'2E+02-2.02E+02 3.75E+Ol-3.75E+01 2.09E+02(
1/
13) 12 VALUES < LLD 2.09E+02-2.09E+02 3.DOE+02 20 VALUES < LLD 4 VALUES < LLD NOTE:
1.
NOMINAL LOWER LIHIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-'I.
NOTE:
2.
HEAN AND RANGE BASED UPON DETECTABLE HEASUREHENTS ONLY.
FRACTION OF DETECTABLE MEASUREMEHTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) ~
TENNESSEE VALLEY AUTHORITY ENVIRONHENTAL RADIOLOGICAL HONITORING AND INSTRUHENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN WELL WATER(TotaI)
PCI/L - 0.037 BO/L NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIHESTONE ALABAHA DOCKET NO.:
50-259,260,296 REPORTING PERIOD: 1998 TYPE AND TOTAL NUHBER OF ANALYSIS PERFORMED LOWER LIMIT ALL OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN DETECTION MEAN (F)
NAME MEAN (F)
(LLD)
RANGE DISTANCE AND DIRECTION RANGE SEE NOTE 1
SEE NOTE 2 SEE NOTE 2 CONTROL LOCATIONS HEAN (F)
RANGE SEE NOTE 2 NUHBER OF NONROUT INE REPORTED HEASUREHENTS Ico I
GAHHA SCAN (GELI) 25 BI-214 PB-214 TRIT IUH 2.00E+01 2.24E+01(
2/
12)
BFN WELL 45 2.21E+01-2.27E+01 0.02 HILES W 2.00E+01 2.26E+01(
1/
12)
BFN WELL 06 2.26E+01-2.26E+01 0.02 HILES W 3.DOE+02 4 VALUES ( LLD 2.24E+01(
2/
'l2) 3.11E+02(
12/
13) 2.21E+01-2.27E+01 1.67E+02-4.30E+02 2.26E+01(
1/
12) 3.13E+02(
12/
13) 2.26E+01-2.26E+01 1.69E+02-4.36E+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 HEASUREMENTS ONLY.
FRACTION OF DETECTABLE HEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).
TENNESSEE VALLEY AUTHORITY EHVIRONHENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IH CQSERCIAL FISH PCI/GH - 0.037 BQ/G (DRY WEIGHT)
NAHE OF FACILITY: BROWNS FERRY NUCLEAR PLANT LOCATION OF FACILITYI LIHESTOHE ALABAMA DOCKET NO.:
50-259,260,296 REPORTING PERICOI 1998 TYPE AND TOTAL NUHBER OF ANALYSIS PERFORHED 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 NOTE 2 CONTROL LOCATIONS HEAN (F)
RANGE SEE NOTE 2 NUMBER OF NONROUTINE REPORTED HEASUREHEHI'S GAHMA SCAN (GELI) 4 Bl-214 CS-'137 K-40 1.00E-01 3.00E-02 4.00E-01 3.36E-01(
1/
- 2) WHEELER RES 3.36E 3.36E-01 TRH 275-349 3.56E-02(
1/
- 2) WHEELER RES 3.56E 3.56E-02 TRH 275-349 1.27E+01(
2/
1/
2) 3.36E 3.36E-01 3.56E-02(
1/
2) 3.56E 3.56E-02 1.27E+01(
2/
2) 1.01E+01-1.54E+01 1.40E-01(
1/
2) 1.40E 1.40E-01 2 VALUES ( LLD 1.21E+01(
2/
2) 1.10E+01-1.32E+01 NOTE:
1.
NOHINAL LOWER LIHIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1.
NOTE:
2.
MEAN AND RANGE BASED UPON DETECTABLE HEASUREHENTS ONLY'RACTION OF DETECTABLE HEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).
TENNESSEE VALLEY AUTHORITY ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IH GAME FISH PCI/GM - 0.037 BQ/G (DRY WEIGHT)
NAME OF FACILITY: BROWHS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIMESTOHE ALABAMA DOCKET HO.:
50-259,260,296 REPORTING PERIOD: 1998 TYPE AND TOTAL NUHBER OF ANALYSIS PERFORHED LOWER LIMIT ALL OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN DETECTION MEAN (F)
NAME HEAN (F)
(LLD)
RANGE DISTANCE AND DIRECTION RANGE SEE NOTE 1
SEE NOTE 2 SEE NOTE 2 CONTROL LOCATIONS MEAN (F)
RANGE SEE NOTE 2 NUMBER OF HOHROUTIHE REPORTED MEASUREMENTS GAMMA SCAN (GELI) 4 Bl-214 CS-137 K-40 1.00E-01 3.00E-02 4 ~ OOE-01 1.63E-01(
1/
2/
2/
1.63E 7.47E-02(
3.41E 1.56E+01(
1 ~ 52E+01-1/
2) 1.63E-01 2/
2) 1.15E-01 2/
2) 1.60E+01 1.77E-O'I(
1/
2) 1.77E 1.77E-01 4.54E-02(
1/
2) 4.54E 4.54E-02 1.6BE+01(
2/
2) 1.68E+01-1.69E+01 NOTE:
1.
NOMINAL LOWER LIMIT OF DETECTIOH (LLD) AS DESCRIBED IN TABLE E-1.
NOTE:
2.
MEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY.
FRACTION OF DETECTABLE MEASUREHEHTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) ~
0 TENNESSEE VALLE AUTHORITY ENVIRONHENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATION IIESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN SEDIMENT PCI/GM - 0.037 BQ/G (DRY MEIGHT)
NAHE OF FACILITY: BROWS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIHESTONE ALABAMA DOCKET NO.:
50 259g260g296 REPORTING PERIOD: 1998 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED GAMMA SCAN (GELI)
LOWER LIMIT ALL OF INDICATOR LOCATIONS LOCATION MITH HIGHEST ANNUAL MEAN DETECTION MEAN (F)
NAHE MEAN (F)
(LLD)
RANGE DISTANCE AND DIRECTION RANGE SEE NOTE 1
SEE NOTE 2 SEE NOTE 2 CONTROL LOCATIONS HEAN (F)
RANGE
'EE NOTE 2 NUHBER OF NONROUTINE REPORTED HEASUREHENTS AC-228 BE-7 BI-212 81-214 C0.60 CS-134 CS-137 K-40 PB-212 PB-214 RA-224 RA-226 TL-208 SR 89 2.50E-01 2.50E-01 4.50E-01 1.50E-01 3.00E-02 3.00E.02 3.00E-02 7.50E-01 1 ~ OOE-01 1 '0E-01 7.50E-01 1.50E-01 6.00E-02 2.00E+00(
1 ~ 54E+00-1.62E+00(
9.40E 2.18E+00(
1.47E+00-1.59E+00(
1.03E+00-8.56E-02(
8.26E 5 '0E-02(
4.61E 6.79E-01(
5.69E 1.95E+01(
1.35E+01-2.14E+00(
1.49E+00-1.73E+00(
1.07E+00-2.30E+00(
1.61E+00-1.59E+00(
1.03E+00-6.58E-01(
4.59E 2/
2) 2.47E+00 2/
2) 2.30E+00 2/
2) 2.89E+00 2/
2) 2.14E+00 2/
2) 8.86E-02 2/
2) 5.79E-02 2/
2) 7.89E-01 2/
2) 2.56E+01 2/
2) 2.78E+00 2/
2) 2.39E+00 2/
2) 2.98E+00 2/
2) 2 ~ 14E+00 2/
2) 8.58E-01 TRM 293.7 BFN DISCHARGE TRH 288.78 TRH 293.7 BFN DISCHARGE TRH 293.7 BFN DISCHARGE TRH 293.7 BFN DISCHARGE TRH 293.7 BFN DISCHARGE TRH 293.7 BFN DISCHARGE TRH 293.7 BFN DISCHARGE TRM 293.7 BFN DISCHARGE TRH 293.7 BFN DISCHARGE TRM 293.7 BFN DISCHARGE TRH 293.7 BFN DISCHARGE TRM 293.7 BFN DISCHARGE 2.47E+00(
2.47E+00-2.30E+00(
2.30E+00-2.89E+00(
2.89E+00-2.14E+00(
2.14E+00-8.86E-02(
8.86E 5.79E-02(
5.79E 7.89E-01(
7.89E 2.56E+01(
2.56E+01-2.78E+00(
2.78E+00-2.39E+00(
2.39E+00-2.98E+00(
2.98E+00-2.14E+00(
2.14E+00-8.58E-01(
8.58E 1/
1) 2.47E+00 1/
1) 2.30E+00 1/
1) 2.89E+00 1/
1) 2.14E+00 1/
1) 8.86E-02 1/
1) 5.79E-02 1/
1) 7.89E-01 1/
1) 2.56E+01 1/
1) 2.78E+00 1/
1) 2.39E+00 1/
1) 2.98E+00 1/
1) 2.14E+00 1/
1) 8.58E-01 1 '5E+00(
1.25E+00-4.53E-01(
4.53E 1.39E+00(
1.39E+00-9.26E-01(
9.26E 1 VALUES 1/
1) 1.25E+00 1/
1) 4.53E-01 1/
1) 1.39E+00 1/
1) 9.26E-01
< LLD 3.36E-01(
3.36E 1.34E+01(
1.34E+01-1.29E+00(
1.29E+00-1.03E+00(
1.03E+00-1.29E+00(
1.29E+00-9.26E-01(
9.26E 3.93E-01(
3.93E 1/
1) 3.36E-01 1/
1) 1.34E+01 1/
1) 1.29E+00 1/
1) 1.03E+00 1/
1) 1.29E+00 1/
1) 9.26E-01 1/
1) 3.93E-01 1
VALUES < LLD SR 90 1.60E+00 4.00E-01 2 VALUES < LLD 4.08E-01(
1/
2)
TRH 293.7 4.08E 4.08E-01 BFN DISCHARGE 1 VALUES < LLD 4.08E-01(
1/
1) 1 VALUES < LLD 4.08E 4.08E-01 NOTE:
1 ~ NOMINAL LOWER LIHIT OF DETECTION (LLD) AS DESCRIBED IN TABLE NOTE:
2.
HEAN AND RANGE BASED UPON DETECTABLE MEASUREHENTS ONLY.
FRACTION OF DETECTABLE HEASUREMENTS AT SPECIFIED
" LOCATIONS IS INDICATED IN PARENTHESES (F) ~
TENNESSEE VALLEY AUtHORITY EHVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUHENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN SHORELINE SEDIMENT PCI/GH - 0.037 BQ/G (DRY WEIGHT)
NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIMESTONE ALABAMA DOCKET NO.:
50-259,260,296 REPORTING PERIOD:
1998 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT ALL OF INDICATOR LOCATIONS LOCATION WITH HIGKEST ANNUAL MEAN DETECTION MEAN (F)
NAME MEAN (F)
(LLD)
RANGE DISTANCE AND DIRECTION RANGE SEE NOTE 1
SEE NOTE 2 SEE NOTE 2 CONTROL LOCATIONS MEAN (F)
RANGE SEE NOTE 2 NUHBER OF NONROUTIHE REPORTED MEASUREMENTS GAMMA SCAN (GELI) 3 AC-228 BI-214 K-40 PB-212 PB-214 RA-226 TL-208 2.50E-01 1.50E-01 7.50E-01 1.00E-01 1.50E-01 1.50E-01 6.00E-02 2.78E-01(
2.78E 2.22E-01(
1.75E 2 VALUES 1/
2) 2.78E-01 2/
2) 2.70E-01
< LLD 2.07E-01(
2/
2) 1.63E 2.51E-01 2.37E-01(
2/
2) 1.70E 3.03E-01 2.22E-01(
2/
2) 1.75E 2.70E-01 7.61E-02(
1/
2) 7.61E 7.61E-02 JOE WHEELER ST PARK TRM 279.5 JOE WHEELER ST PARK TRH 279.5 MALLARD CREEK REC AR TRH 293.0 JOE
'WHEELER ST PARK TRH 279.5 JOE WHEELER ST PARK TRH 279.5 JOE WHEELER ST PARK TRH 279.5 JOE WHEELER ST PARK TRH 279.5 2.78E-01(
1/
'I) 2.78E 2.78E-01 2.70E-01(
1/
1) 2.70E 2.70E-01 1 VALUES < LLD 2.51E-01(
1/
1) 2.51E 2.51E.01 3.03E-01(
1/
1) 3.03E 3.03E-01 2.70E-01(
1/
1) 2.70E 2.70E"01 7.61E-02(
1/
1) 7.61E 7.61E-02 1
VALUES < LLD 1.66E-01(
1/
1) 1.66E 1.66E-01 1 '2E+00(
1/
1) 1.52E+00-1.52E+00 2.08E-01(
1/
1) 2.08E 2.08E-01 2.08E-01(
1/
1) 2.08E 2.08E-01 1.66E-01(
1/
1) 1.66E 1.66E-01 1 VALUES < LLD NOTE:
1 ~
NOMINAL LOWER LIHIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1.
NOTE:
2.
MEAN AND RANGE BASED UPON DETECTABLE MEASUREHENTS ONLY.
FRACTION OF DETECI'ABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).
TENNESSEE VALLEY AUTHORITY ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUMEHTATION 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: LIHESTONE ALABAMA DOCKET NO.:
50-259,260,296 REPORTING PERIOD:
1998 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT ALL OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL HEAN DETECTION MEAN (F)
NAME HEAN (F)
(LLD)
RANGE DISTANCE AND DIRECTION RANGE SEE NOTE 1
SEE NOTE 2 SEE NOTE 2 CONTROL LOCATIONS MEAN (F)
RANGE SEE NOTE 2 NUMBER OF NONROUTINE REPORTED MEASUREMEN'TS GAMMA SCAN (GELI) 2 BI-2'14 PB-214 5.00E-01 1.00E-01 1.57E+00(
1/
1)
DOWNSTREAM LOCATION 1.57E+00(
1/
1) 3.75E+00(
1/
1) 1 ~ 57E+00-1.57E+00 DOWNSTREAM 1.57E+00-1.57E+00 3.75E+00- 3.75E+00 1.83E+00(
1/
1)
DOWNSTREAM LOCATION 1.83E+00(
1/
1) 3.79E+00(
1/
1) 1.83E+00-1.83E+00 DOWNSTREAM 1.83E+00-1.83E+00 3.79E+00- 3.79E+00 NOTE:
1.
NOMINAL LOWER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1 ~
NOTE:
2.
MEAN AND RANGE BASED UPON DETECTABLE MEASUREHENTS ONLY.
FRACTION OF DETECTABLE MEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).
Direct Radiation Levels Browns Ferry Nuclear Plant 25 20 CO 15 E
10 1975 1980 1985 Calendar Year 1990 1995 2000
~ On-Site m Off-Site
Direct Radiation Levels by Thermoluminescence Dosimetry Watts Bar Nuclear Plant 25 Initial WBNP operation in January, 1996 20 M
E 15
~ on-site (within 2 miles)
~ off-site (more than 2 miles) 10 1990 1991 1992 1993 1994 1995 Calendar Year 1996 1997 1998 1999 2000
0.25 Annual Average Gross Beta Activity in AirFilters - BFNP 0.20 Initial plant operaton in August, 1973 0.15 O
> 010 O
I I
I I
I I
I I
'7 Preoperational Average 0.05 0.00 1965 1970 1975 1980 1985 1990 W-OW 1995 2000 Calendar Year e
indicator~
Control
20 Annual Average Sr-90 Activity in Milk-BFNP 15 O~
10 O
initial plant operation in August, 1973 Preoperational A~rage Nominal LLD 1965 1970 1975 1980 19S5 1990 1995 2000 Calendar Year
~ hdicator~ Control
Annual Average Cs-137 Activity in Soil - BFNP E
2 Q)
O CL initial plant operation in August, 1973 I
I Q
I I
I I
I I
I I
1 I
I Preoperational Average 1965 1970 1975 1980 1985 1990 1995 2000 Calendar Year
~ indicator~ control
Annual Average Gross Beta Activity in Surface Water - BFNP c) 4 O
CL
- Preoperational Awrage 2
I Initial Plant I
Operation in August, 1973 I
Note: no gross beta measurements were made in 1978 1965 1970 1975 1980 1985 1990 1995 2000 Calendar Year
~ dow nstream~ upstream
Annual Average Gross Beta Activity in Drinking Water - BFNP 4
O Initial plant operation in August, 1973, I
I I
I I
I I
Preoperational Amrage Q
2 1965 1970 1975 1980 1985 Calendar Year
~ dow nstream o
upstream 1990 1995
0.5 Annual Average Cs-137 Activityin Fish Flesh Game Fish - BFNP initial piant operation in August, 1973 0.4 E
0.3 O
SL 0.2 Preoperational Average 0.1 0.0 1965 1970 1975 1980 1985 Calendar Year
~ dow nstream o
upstream 1990 1995
0.25 0.20 E
0.15 0
0.10 0.05 Annual Average Cs-137 Activityin Fish Flesh Commercial Fish - BFNP initial plant operation in August, 1973 Preoperational Aerage 0.00 0
OW OW O-O-1965 1970 1975 1980 1985 1990 1995 2000 Catendar Year
~ dow nstream ~
upstream
Annual Average Cs-137 Activity in Sediment - BFNP Initial plant operation in August, 1973 E
CQ 3
O CL 2
Preoperational Average 1965 1970 1975 1980 1985 1990 1995 2000 Calendar Year
~ dawnstream o
upstream
0.8 Annual Average Co%0 Activity in Sediment - BFNP 0.6 E
CO Oa 0.4 02 Initial plant operation in August, 1973 Preoperational Aerage 0.0 1965 1970 1975 1990 1995 1980 1985 Calendar Year
~ ~ dow nstream ~
upstream 2000