ML18037A857
| ML18037A857 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 12/31/1993 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML18037A855 | List: |
| References | |
| NUDOCS 9405040174 | |
| Download: ML18037A857 (189) | |
Text
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ANNUAL RAOIOLOGICAL ENVIRONMENTAL OPERATING REPORT BRONNS FERRY NUCLEAR PLANT 1993 TENNESSEE VALLEY AUTHORITY OPERATIONS SERVICES TECHNICAL PROGRAMS April 1994
TABLE OF CONTENTS Table of Contents List of Tables ii 1v List of Figures Executive Summary Introduction Naturally Occurring and Background Radioactivi Electric Power Production ty
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5 Site/Plant Description Environmental Radiological Monitoring Program Oirect Radiation Monitoring Measurement Techniques Results 8
10 14 14 16 Atmospheric Monitoring Sample Collection and Analysis Results 19 19 21 Terrestrial Monitoring Sample Collection and Analysis Results 22 22 24 Aquatic Monitoring Sample Collection and Analysis Results 26 26 28 Assessment and Evaluation Results Conclusions References
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Appendix A
Environmental Radiolog Sampling Locations ical Monit Appendix B
1993 Program Modifications ing Progr and 31 32 34 35 40 53
C
e Appendix C
Program Deviations.
Appendix 0
Analytical Procedures Appendix E
Nominal Lower Limits of Detection (LLD)
Appendix F
Quality Assurance/Quality Control Program Appendix G
Land Use Survey Appendix H
Data Tables 56 62 68 77 83 111
(
LIST OF TASLES Table 1
Comparison of Maximum Annual Average Effluent Concentrations Released to Unrestricted Areas Hith Reporting Levels and Lower Limits of Detection 36 Table 2
Maximum Dose Due to Radioactive Effluent Releases 37
LIST OF FIGURES Figure 1
Tennessee Valley Region 38 Figure 2
Environmental Exposure Pathways of Man Due to Releases of Radioactive Material to the Atmosphere and Lake 39
EXECUTIVE
SUMMARY
This report describes the environmental radiological monitoring program conducted by TVA in the vicinity of Browns Ferry Nuclear Plant (BFN) in 1993.
The program includes the collection of samples from the environment and the determination of the concentrations of radioactive materials in the samples.
Samples are taken from stations in the general area of the plant and from areas not influenced by plant operations.
Station locations are selected after careful consideration of the weather patterns and projected radiation doses to the various areas around the plant.
Material sampled includes air, water, milk, foods, vegetation, soil, fish, sediment, and direct radiation levels.
Results from stations I
near the plant are compared with concentrations from control stations and with preoperational measurements to determine potential impacts of plant operations.
The vast majority of the exposures calculated from environmental samples were contributed by naturally occurring radioactive materials or from materials commonly found in the environment as a result of atmospheric nuclear weapons fallout.
Small amounts of Co-60, Cs-134 and Zn-65 were found in sediment samples downstream from the plant.
This activity in stream sediment would result in no measurable increase over background in the dose to the general public.
INTRODUCTION This report describes and summarizes a large volume of data, the results of thousands of measurements and laboratory analyses.
The measurements are made to comply with the requirements of 10 CFR 20, Appendix A, Criterion 64 and 10 CFR 20, Appendix I, Section IV.B, and to determine potential effects on public health and safety.
This report satisfies the annual reporting requirements of BFN Technical Specification 6.9.1.5.
In addition, estimates of the maximum potential doses to the surrounding population are made from radioactivity measured both in plant effluents and in environmental samples.
Some of the data presented are prescribed by specific requirements while other data are included which may be useful or interesting to individuals who do not work with this material routinely.
Naturall Occurrin and Back round Radioactivit Most materials in our world contain trace amounts of naturally occurring radioactivity.
Approximately 0.01 percent of all potassium is radioactive potassium-40.
Potassium-40 (K-40), with a half-life of 1.3 billion years, is one of the major types of radioactive materials found naturally in our environment.
An individual weighing 150 pou'nds contains about 140 grams of potassium (Reference 1).
This is equivalent to approximately 100,000 pCi of K-40 which delivers a dose of 15 to 20 mrem per year to the bone and soft tissue of the body.
Naturally occurring radioactive materials have always been in our environment.
Other examples of naturally occurring radioactive materials are beryllium (Be)-7, bismuth (Bi)-212 and 214, lead (Pb)-212 and 214, thallium (Tl)-208, actinium (Ac)-228, uranium (U)-238, uranium-235,
thorium (Th)-234, radium (Ra)-226, radon (Rn)-222, carbon (C)-14, and hydrogen (H)-3 (generally called tritium).
These naturally occurring radioactive materials are in the soil, our food, our drinking water, and our bodies.
The radiation from these materials makes up a part of the low-level natural background radiation.
The remainder of the natural background radiation comes from outer space.
He 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.
The average dose equivalent at sea level resulting from radiation from outer space (part of natural background radiation) is about 27 mrem/year.
This essentially doubles with each 6600-foot increase in altitude in the lower atmosphere.
Another part of natural background radiation comes from naturally occurring radioactive materials in the soil and rocks.
Because the quantity of naturally occurring radioactive material varies according to geographical
- location, the part of the natural background radiation coming from this radioactive material also depends upon the geographical location.
Most of the remainder of the natural background radiation comes from the radioactive materials within each individual's body.
Ne absorb these materials from the food we eat which contains naturally occurring radioactive materials from the soil.
An example of this is K-40 as described above.
Even building materials affect the natural background radiation levels in the environment.
Living or working in a building which is largely made of earthen material, such as concrete or brick, will generally result in a higher natural background radiation level than would exist if the same structure were made of wood.
This is due to the naturally occurring radioisotopes in the concrete or brick, such as trace amounts of uranium, radium, thorium, etc.
e Because the city of Denver,
- Colorado, is over 5000 feet in altitude and the soil and rocks there contain more radioactive material than the U.S, average, the people of Denver receive around 350 mrem/year total natural background radiation dose equivalent compared to about 295 mrem/year for the national average.
People in some locations of the world receive over 1000 mrem/year natural background radiation dose equivalent, primarily because of the greater quantity of radioactive materials in the soil and rocks in those locations.
Scientists have never been able to show that these levels of radiation have caused physical harm to anyone.
It is possible to get an idea of the relative hazard of different types of radiation sources by evaluating the amount of radiation the UPS. population t
receives from each general type of radiation source.
The information below is primarily adapted from References 2 and 3.
U.S.
GENERAL POPULATION AVERAGE DOSE EQUIVALENT ESTIMATES Source Mi1 1 irem/Year Per Person Natural background dose equivalent Cosmic Cosmogenic Terrestrial In the body Radon Total 27 1
28 39 200 295 Release of'adioactive material in natural
- gas, mining, ore processing, etc.
Medical (effective dose equivalent)
Nuclear weapons fal lout Nuclear energy Consumer products Total 53 less than 1
0.28 0.03 355 (approximately)
Y>>
t As can be seen from the table on the preceeding
- page, natural background radiation dose equivalent to the UPS. population normally exceeds that from nuclear plants by several hundred times.
This indicates that nuclear plant operations normally result in a population radiation dose equivalent which is insignificant compared to that which results from natural background radiation.
It should be noted that the use of radiation and radioactive materials for medical uses has resulted in a similar effective dose equivalent to the U.S. population as that caused by natural background cosmic and terrestrial radiation.
Significant discussion recently has centered around exposures from radon.
Radon is an inert gas given off as a result of the decay of naturally occurring radium-226 in soil.
Nhen dispersed in the atmosphere, radon concentrations are relatively low.
- However, when the gas is trapped in closed spaces, it can build up until concentrations become signi'ficant.
The National Council of Radiation Protection and Measurements (Reference 2) has estimated that the average annual effective dose equivalent from radon in the United States is approximately 200 mrem/year.
This estimated dose is approximately twice the average dose equivalent from all other natural background sources.
Electric Power Production Nuclear power plants are similar in many respects to conventional coal burning (or other fossil fuel) electrical generating plants.
The basic process behind electrical power production in both types of plants is that fuel is used to heat water to produce steam which provides the force to turn turbines and t
generators.
However, nuclear plants include many complex systems to control
the nuclear fission process and to safeguard against the possibility of reactor malfunction, which could lead to the release of radioactive materials.
Very small amounts of these fission and activation products are released into the plant systems.
This radioactive material can be transported throughout plant systems and some of it released to the environment.
A11 paths through which radioactivity is released are monitored.
Liquid and gaseous effluent monitors record the radiation levels for each release.
These monitors also provi e
a arm
'd 1
m mechanisms to prompt termination of any release above limits.
Releases are monitored at the onsite points of release and through an environmenta moni or ng p
1
't i
rogram which measures the environmental radiation in outlying areas aroun e
p an d th plant.
In this way, not only is the release of radioactive materia s
rom e
1 f th plant tightly controlled, but measurements are made in surrounding areas to verify that the population is not being exposed to significant levels of radiation or radioactive materials.
The BFN OOCM, which is required by the plant Technical Specifications, prescribes imi s
or e r 1't f th elease of radioactive effluents, as well as limits for doses to the general public from the release of these effluents.
The dose to a member o
e gener f th ral public from radioactive materials released to unrestricted
- areas, as given in NRC guidelines and 'n the ODCM, is limited as follows:
E
Li uid Effluents Total body Any organ Gaseous Effluents
<3 mrem/year
<10 mrem/year Noble gases:
Gamma radiation Beta radiation Particulates:
<10 mrad/year
<20 mrad/year Any organ
<15 mrem/year The Environmental Protection Agency (EPA) limits for the total dose to the public in the vicinity of a nuclear power plant, established in the Environmental Oose Standard of 40 CFR 190, are as follows:
Total body Thyroid Any other organ 25 mrem/year 75 mrem/year 25 mrem/year radioactive materials released to unrestricted
- areas, and the revised regulation, 10 CFR 20.1302(b)
(implemented by TVA on January 1,
1994) presents annual average limits for the concentrations of radioactive materials released in gaseous and liquid effluents at the boundary of the unrestricted areas.
Table 1 of this report presents the annual average concentration limits for the principal radionuclides associated with nuclear power plant effluents.
This table also presents (1) the concentrations of radioactive materials in the environment which would require a special report to the NRC and (2) the detection limits for the listed radionuclides.
It should be noted that the levels of radioactive materials measured in the environment are typically t
below or only slightly above the lower limit of detection.
The data presented in this report indicate compliance with both versions of the regulation.
p i1
SITE/PLANT DESCRIPTION Browns Ferry Nuclear Plant (BFN) is located on the north shore of Wheeler Reservoir at Tennessee River Mile 294 in Limestone County in north Alabama.
Wheeler Reservoir averages 1 to 1-1/2 miles in width in the vicinity of the plant.
The site, containing approximately 840 acres, is approximately 10 miles southwest of Athens,
- Alabama, and 10 miles northwest of the center of
- Decatur, Alabama (Figure 1).
The dominant character of land use is small, scattered villages and homes in an agricultural area.
A number of relatively large farming operations occupy much of the land on the north side of the river immediately surrounding the plant.
The principal crop grown in the area is cotton.
At least two dairy farms are located within a 10-mile radius Approximately 2500 people live within a 5-mile radius of the plant.
The town of Athens has a population of about 15,000, while approximately 45,000 people live in the city of Decatur.
The largest city in the area with approximately 145,000 people is Huntsville, Alabama, located about 24 miles east of the site.
Area recreation facilities are being developed along the Tennessee River.
The nearest facilities are two county parks located about 8 miles west-northwest of the site and a commercial boat dock across the river from the site.
The city of Decatur has developed a large municipal recreation
- area, Point Mallard Park, approximately 15 miles upstream from the site.
The Tennessee River is also a popular sport fishing area.
BFN consists of three boiling water reactors; each unit is rated at 1098 megawatts (electrical).
Unit 1 achieved criticality on August 17,
- 1973, and began commercial operation on August 1,
1974.
Unit 2 began commercial operation on March 1, 1975.
- However, a fire in the cable trays on March 22, 1975, forced the shutdown of both reactors.
Units 1
and 2 resumed operation and Unit 3 began testing in August 1976.
Unit 3 began commercial operation in March 1977.
All three units were taken out of service in March 1985.
Unit 2 was restarted May 24, 1991.
ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM The unique environmental concern associated with a nuclear power plant is its production of radioactive materials and radiation.
The vast majority of this radiation and radioactivity is contained withi n the reactor itself or one of the other plant systems designed to keep the material in the plant.
The retention of the materials in each level of control is achieved by system engineering,
- design, construction, and operation.
Environmental monitoring is a final verification that the systems are performing as planned.
The monitoring program is designed to check the pathways between the plant and the people in the immediate vicinity and to most efficiently monitor these pathways.
Sample types are chosen so that the potential for detection of radioactivity in the environment will be maximized.
The environmental radiological monitoring program is outlined in Appendix A.
There are two primary pathways by which radioactivity can move through the environment to humans:
air and water (see Figure 2).
The air pathway can be separated into two components:
the direct (airborne) pathway and the indirect (ground or terrestrial) pathway.
The direct airborne pathway consists of direct radiation and inhalation by humans.
In the terrestrial
- pathway, radioactive materials may be deposited on the ground or on plants and subsequently be ingested by animals and/or humans.
Human exposure through the liquid pathway may result from drinking water, eating fish, or by direct exposure at the shoreline.
The types of samples collected in this program are designed to monitor these pathways.
e A number of factors were considered in determining the locations for collecting environmental samples.
The locations for the atmospheric monitoring stations were determined from a critical pathway analysis based on weather patterns, dose projections, population distribution, and land use.
Terrestrial sampling stations were selected after reviewing such things as the locations of dairy animals and gardens in conjunction with the air pathway analysis.
Liquid pathway stations were selected based on dose projections, water use information, and availability of media such as fish and sediment.
Table A-2 (Appendix A, Table 2:
This identification system is used for all tables and figures given in the appendices.)
lists the sampling stations and the types of samples collected from each.
Modifications made to the program in 1993 are described in Appendix 8 and exceptions to the sampling and analysis schedule are presented in Appendix C.
To determine the amount of radioactivity in the environment prior to the operation of BFN, a preoperational environmental radiological monitoring program was initiated in 1968 and operated until the plant began operation in 1973 'easurements of the same types of radioactive materials that are measured currently were assessed during the preoperational phase to establish normal background levels for various radionuclides in the environment.
The preoperational monitoring program is a very important part of the overall program.
During the
- 1950s, 60s, and 70s, atmospheric nuclear weapons testing 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 of preexisting radionuclide patterns in the environment permits a determination, through "t
comparison and trending analyses, of whether the operation of BFN is impacting the environment and thus the surrounding populations The determination of impact during the operating phase also considers the presence of control stations that have been established in the environment.
Results of environmental samples taken at control stations (far from the plant) are compared with those from indicator stations (near the plant) to establish the extent of BFN influence.
All samples are analyzed by the Radioanalytical Laboratory of TVA's Environmental Radiological Monitoring and Instrumentation Department located at the Hestern Area Radiological Laboratory (HARL) in Muscle Shoals, Alabama.
All analyses are conducted in accordance with written and approved procedures t
and are based on accepted methods.
A summary of the analysis techniques and methodology is presented in Appendix D.
Data tables summarizing the sample analysis results are presented in Appendix H.
The sophisticated radiation detection devices used to determine the radionuclide content of samples collected in the environment are generally quite sensitive to small amounts of radioactivity.
In the field of radiation measurement, the sensitivity of the measurement process is discussed in terms of the lower limit of detection (LLD).
A description of the nominal LLDs for the Radioanalytical Laboratory is presented in Appendix E.
The Radioanalytical Laboratory employs a comprehensive quality assurance/
quality control program to monitor laboratory performance throughout the year.
The program s
n en i
i tended to detect any problems in the measurement process as soon as poss e
so ibl so they can be corrected.
This program includes equipment chec s
o ensure h
k t ure that the complex radiation detection devices are working proper y an e
1 d th analysis of special samples which are included alongside routine environmental samples.
The laboratory participates in the EPA Interlaboratory Comparison Program.
In additio s
p p
n am les s lit with the EPA and the State of Alabama provide an independent verification of the overall performance o
e f th laboratory.
A complete description of the program is presented in Appendix F, DIRECT RADIATION MONITORING Direct radiation levels are measured at a number of stations around the plant site.
These measurements include contributions from cosmic radiation, radioactivity in the ground, fallout from atmospheric nuclear weapons tests conducted in the past, and radioactivity that may be present as a result of plant opera ions.
ecau B cause of the relative large variations in background radiation as compared to the small levels from the plant, contributions from the plant may be difficult to distinguish, Radiation levels measured in the area around the BFN site in 1993 were consistent with levels from previous years and with levels measured at other locations in the region.
Measurement Techni ues Direct radiation measurements are made with thermoluminescent dosimeters (TLDs).
When certain materials are exposed to ionizing radiation, many of the electrons which become displaced are trapped in the crystalline structure of the material.
They remain trapped for long periods of time as long as the material is no ea e
t h t d.
When heated (thermo-),
the electrons are released, producing a pu se o
ig 1
f 1't (-luminescence).
The intensity of the light pulse is proportiona o
e amou
- 1. t th amount of radiation to which the material was exposed.
Materials which display these characteristics are used in the manufacture of TLDs.
From 1968 through
TLD material encased in a glass bulb.
In 1989, TYA began the process of changing from the Victoreen dosimeter to the Panasonic Model UD-814 dosimeter, and completely changed to the Panasonic dosimeter in 1990.
This dosimeter contains four elements consisting of one lithium borate and three calcium sulfate phosphors.
The calcium sulfate phosphors are shielded by approximately 1000 mg/cm'lastic and lead to compensate for the over-response of the detector to low energy radiation.
The TLOs are placed approximately 1 meter above the ground, with three TLDs at each station.
Sixteen stations are located around the plant near the site
- boundary, one station in each of the sixteen compass sectors.
Oosimeters are also placed at the perimeter and remote air monitoring sites and at 19 additional stations out to approximately 32 miles from the site.
The TLOs are exchanged every 3 months and the accumulated exposure on the detectors is read with a Panasoni c Model UD-710A automatic reader interfaced with a Hewlett Packard Model 9000 computer system.
Nine of the locations also have TLD devices processed by the NRC.
The results from the NRC measurements are reported in NUREG 0837.
Since the calcium sulfate phosphor is much more sensitive that the lithium
- borate, the measured exposure is taken as the median of the results obtained from the nine calcium sulfate phosphors in three detectors.
The values are corrected for gamma response, system variations, and transit exposure, with individual gamma response calibrations for each element.
The system meets or exceeds the performance specifications outlined in Regulatory Guide 4.13 for environmental applications of TLOs.
Results All results are normalized to a standard quarter (91.25 days or 2190 hours0.0253 days <br />0.608 hours <br />0.00362 weeks <br />8.33295e-4 months <br />).
The stations are grouped according to the distance from the plant.
The first group consists of all stations within 1 mile of'he plant.
The second group lies between 1
and 2 miles, the third group between 2 and 4 miles, the fourth between 4 and 6 miles, and the fifth group is made up of all stations more than 6 miles from the plant.
Past data have shown that the results from all stations greater than 2 miles from the plant are essentially the same.
Therefore, for purposes of this report, all stations 2 miles or less from the plant are identified as "onsite" stations and all others are considered "offsite."
1 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 of the monitoring program exceed current measurements of background radiation levels.
for this reason, data collected prior to 1976 are not included in this report.
For comparison
- purposes, direct radiation measurements made in the Natts Bar Nuclear Plant (HBN) environmental radiological monitoring program are referenced.
The NBN is a non-operating plant under construction near Spring City, Tennessee.
The quarterly gamma radiation levels determined from the TLDs deployed around BFN in 1993 are given in Table H-1.
The exposures are measured in milliroentgens and reported in mi llirem per standard quarter.
For purposes of this report, one milliroentgen and one millirem (mrem) are assumed to be equivalent.
The rounded average annual exposures are shown below.
Annual Average Direct Radiation Levels mrem/ ear BFN WBN Onsite Stations Offsite Stations 64 56 64 57 The data in Table H-1 indicate that the average quarterly radiation levels at the BFN onsite stations are approximately 2 mrem/quarter higher than levels at the offsite stations.
This difference is also noted at the stations at HBN and other nonoperating nuclear power plant construction sites where the average levels onsite are generally 2-6 mrem/quarter higher than levels offsite.
The causes of these differences have not been isolated; however, it is postulated that the differences are probably attributable to combinations t
of influences such as natural variations in environmental radiation levels, earth-moving activities onsite, and the mass of concrete employed in the construction of the plant.
Other undetermined influences may also play a
part.
These conclusions are supported by the fact that similar differences between onsi te and offsi te stations were measured in the vicinity of the HBN construction site.
Figure H-1 compares plots of the environmental gamma radiation levels from the onsi te or site boundary stations wi th those from the offsi te stations over the period from 1976 through 1993.
To reduce the seasonal variations present in the data sets, a 4-quarter moving average was constructed for each data set.
Figure H-2 presents a trend plot of the direct radiation levels as defined by the moving averages.
The data follow the same general trend as the raw data, but the curves are much smoother.
Figures H-3 and H-4 depict the environmental
gamma radiation levels measured during the construction of TVA's NBN to the present.
Note that the data follow a similar pattern to the BFN data and
- that, as discussed
- above, the levels reported at onsite stations are similarly higher than the levels at offsite stations.
All results reported in 1993 are consistent with direct radiation levels identified at locations which are not influenced by the operation of BFN.
There is no indication that BFN activities increase the background radiation levels normally observed in the areas surrounding the plant.
ATMOSPHERIC MONITORING The atmospheric monitoring network is divided into three groups identified as local, perimeter, and remote.
In the current program, five local air monitoring stations are located on or adjacent to the plant site in the general directions of greatest wind frequency.
One additional station is located at the point of maximum predicted offsite concentration of radionuclides based on preoperational meteorological data.
Three perimeter air monitoring stations are located in communities out to about 13 miles from the plant, and two remote air monitors are located out to 32 miles.
The monitoring program and the locations of monitoring stations are identified in the tables and figures of Appendix A.
The remote stations are used as control Results from the analysis of samples in the atmospheric pathway are presented in Tables H-2 and H-3.
Radioactivity levels identified in this reporting period are consistent with background and radionuclides produced as a result of fallout from previous nuclear weapons tests.
There is no indication of an increase in atmospheric radioactivity as a result of BFN.
Sam le Collection and Anal sis Air particulates are collected by continuously sampling air at a flow rate of approximately 2 cubic feet per minute (cfm) through a 2-inch Hollingsworth and Vose LB5211 glass fiber filter.
The sampling system consists of a pump, a
magnehelic gauge for measuring the drop in pressure across the system, and a
dry gas meter.
This allows an accurate determination of the volume of air passing through the filter.
This system is housed in a building approximately 2 feet by 3 feet by 4 feet.
The filter is contained in a sampling head mounted on the outside of the monitor building.
The filter is replaced every 7 days.
Each filter is analyzed for gross beta activity about 3 days after collection to allow time for the radon daughters to decay.
Every 4 weeks composites of the filters from each location are analyzed by gamma spectroscopy.
On March 27,
- 1989, two moni tors, one local and one remote, were equipped with a second sampler.
The filters from these samplers are analyzed weekly for gross alpha and composited quarterly for analysis of transuranic isotopes and for Sr-89,90.
t Gaseous radioiodine is collected using a commercially available cartridge containing TEDA-impregnated charcoal.
This system is designed to collect iodine in both the elemental form and as organic compounds.
The cartridge is located in the same sampling head as the air particulate filter and is downstream of the particulate filter.
The cartridge is changed at the same time as the particulate filter and samples the same volume of air.
Each cartridge is analyzed for I-131 by a complete gamma spectroscopy analysis.
Rainwater is collected by use of a collection tray attached to the monitor building.
The collection tray is protected from debris by a screen cover.
As water drains from the tray, it is collected in one of two 5-gallon jugs inside the monitor building.
A 1-gallon sample is removed from the container every 4
weeks.
Any excess water is discarded.
Samples are held to be analyzed only if the air particulate samples indicate the presence of elevated activity
levels or if fallout is expected.
For example, rainwater samples were analyzed during the period of fallout following the accident at Chernobyl in 1986.
Results The results from the analysis of air particulate samples are summarized in Table H-2.
Gross beta activity in 1993 was consistent with levels reported in previous years.
The average level at both indicator and control stations was I
0.020 pCi/m'.
The annual averages of the gross beta activity in air particulate filters at these stations for the years 1968-1993 are presented in Figure H-5.
Increased levels due to fallout from atmospheric nuclear weapons testing are evident, especially in 1969,
- 1970, 1971,
- 1977, 1978, and 1981.
t Evidence of a small increase resulting from the Chernobyl accident can also be seen in 1986.
These patterns are consistent with data from monitoring programs conducted by TVA at nonoperating nuclear power plant construction sites.
Only natural radioactive materials were identified by the monthly gamma spectral analysis of the air particulate samples.
No fission or activation products or transuranic isotopes were found at levels greater than the LLDs.
As shown in Table H-3, iodine-131 was not detected in any of the charcoal canister samples collected in 1993.
Since no plant-related air activity was detected, no rainwater samples from the vicinity of BFN were analyzed during this reporting period.
TERRESTRIAL MONITORING Terrestrial monitoring is accomplished by collecting samples of environmental media that may transport radioactive material from the atmosphere to humans.
For example, radioactive material may be deposited on a vegetable garden and be ingested along with the vegetables or it may be deposited on pasture grass where dairy cattle are grazing.
Hhen the cow ingests the radioactive
- material, some of it may be transferred to the milk and consumed by humans who drink the milk.
Therefore, samples of milk, vegetation, soil, and food crops are collected and analyzed to determine the potential impacts from exposure to this pathway.
The results from the analysis of these samples are shown in Tables H-4 through H-ll.
t A land use survey is conducted annually to locate milk producing animals and gardens within a 5-mile radius of the plant.
Only one dairy farm is located in this area;
- however, one additional dairy farm has been identified within 7 miles of the plant.
These two dairies are considered indicator stations and routinely provide milk samples No other milk-producing animals have been identified within 3 miles of the plant.
The results of the 1993 land use survey are presented in Appendix G.
Sam le Collection and Anal sis Milk samples are purchased every 2 weeks from two dairies within 7 miles of the plant and from at least one of two control farms.
These samples are placed on ice for transport to the radioanalytical laboratory.
A specific and Sr-89,90 analysis is performed every 4 weeks.
Samples of vegetation are collected every 4 weeks for I-131 analysis.
The samples are collected from one farm which previously produced milk and from one control dairy farm.
The samples are collected by cutting or breaking enough vegetation to provide between 100 and 200 grams of sample.
Care is taken not to include any soil with the vegetation.
The sample is placed in a container with 1650 ml of 0.5 N
NaOH for transport back to the radioanalytical laboratory.
A second sample of between 750 and 1000 grams is also collected from each location.
After drying and grinding, this sample is analyzed by gamma spectroscopy.
Once each quarter, the sample is ashed after the gamma analysis is completed and analyzed for Sr-89,90.
Soil samples are collected annually from the air monitoring locations.
The t
samples are collected with either a "cookie cutter" or an auger type sampler.
After drying and grinding, the sample is analyzed by gamma spectroscopy.
Nhen the gamma analysis is complete, the sample is ashed and analyzed for Sr-89,90.
Analyses for transuranic isotopes are also performed on samples from the two monitoring stations with the second air samplers.
Samples representative of food crops raised in the area near the plant are obtained from individual gardens, corner mar'kets, or cooperatives.
Types of, foods may vary from year to year as a result of changes in the local vegetable
- gardens, In 1993 samples of cabbage, corn, potatoes, and tomatoes were collected from local vegetable gardens.
In addition, samples of apples were also obtained from the area.
The edible portion of each sample is analyzed by gamma spectroscopy.
Resul ts The results from the analysis of milk samples are presented in Table H-4.
No radioactivity which could be attributed to BFN was identified.
All I-131 results were less than the established nominal LLD of 0.2 pCi/liter.
Strontium-90 was found in less than half of the samples.
These levels are consistent with concentrations measured in samples collected prior to plant operation and with concentrations reported in milk as a result of fallout from atmospheric nuclear weapons tests (Reference 1).
Figure H-6 displays the average Sr-90 concentrations measured in milk since 1968.
The concentrations have steadily decreased as a result of the 28-year half-life of Sr-90 and the washout and transport of the element through the soil over the period.
The average Sr-90 concentration reported from indicator locations was 2.6 pCi/liter; the concentration from control stations was also approximately 2.6 pCi/liter.
By far the predominant isotope reported in milk samples was the naturally occurring K-40.
An average of approximately 1300 pCi/liter of K-40 was identified in all milk samples.
Similar results were reported for vegetation samples (Table H-5).
All I-131 and Cs-137 values were less than the nominal LLD.
Strontium-90 was not identified in any samples.
Again, the largest concentrations identified were for the naturally occurring isotopes K-40 and Be-7.
The only fission or activation products identified in soil samples was Cs-137.
The maximum concentration was approximately 0.7 pCi/g.
These concentrations are consistent with levels previously reported from fallout.
l All other radionuclides reported were naturally occurring isotopes (Table H-6).
A plot of the annual average Cs-137 concentrations in soil is presented in Figure H-7.
Like the levels of Sr-90 in milk, concentrations of Cs-137 in soil are steadily decreasing as a,.result of the cessation of weapons testing in the atmosphere, the 30-year half-life of Cs-137 and transport through the environment.
Analyses for transuranic isotopes (Am-241; Pu-238; Pu-239,240; Cm-242; and Cm-244) in soil have been performed since 1989.
The results have generally agreed with the concentrations reported by the Electric Power Research Institute (EPRI) in Reference 4.
The EPRI report concludes that essentially I
all of the radionuclides in soils from around the nuclear power plants participating in the study (including BFN) were of fallout origin and that the variations in concentrations were a function of soil texture, soil t
permeability, and/or disturbances of the soil surface.
The concentrations measured in 1993 are included in Table H-6.
Only naturally occurring radioactivity was identified in food crops.
As noted
- earlier, K-40 is one of the major radionuclides found naturally in the environment and is the predominant radioactive component in normal foods and human tissue.
Analysis of these samples indicated no contribution from plant activities.
The results are reported in Tables H-7 through H-ll.
A VATIC MONITORING Potential exposures from the liquid pathway can occur from drinking water, ingestion of fish and clams, or from direct radiation exposure to radioactive materials deposited in the river sediment.
The aquatic monitoring program includes the collection of samples of surface (river/reservoir) water, groundwater, drinking water supplies, fish, Asiatic clams, and bottom sediment.
Samples from the reservoir are collected both upstream and downstream from the plant.
Results from the analysis of aquatic samples are presented in Tables H-12 through H-19.
Radioactivity levels in water, fish and clams were consistent with background and/or fallout levels previously reported.
The presence of Co-60, Cs-134, Cs-137 and Zn-65 was identified in sediment samples;
- however, the projected exposure to the public from this medium is significantly less than 0.1 mrem/year.
Sam le Collection and Anal sis Samples of surface water are collected from the Tennessee River using automatic sampling pumps from two downstream'tations and one upstream station.
A timer turns on the pump approximately once every hour.
The line is flushed and a sample collected into a collection container.
A 1-gallon sample is removed from the container every 4 weeks and the remaining water in the jug is discarded.
The 4-week composite sample is analyzed by gamma spectroscopy and for gross beta activity.
A quarterly composite sample is analyzed for Sr-89,90 and tritium.
Samples are also collected by an automatic sampling pump at the first downstream drinking water intake.
These samples are collected in the same manner as the surface water samples.
These monthly samples are analyzed by gamma spectroscopy and for gross beta activity.
At other selected locations, grab samples are collected from drinking water systems which use the Tennessee River as their source.
These samples are analyzed every 4 weeks by gamma spectroscopy and for gross beta activity.
A quarterly composite sample from each station is analyzed for Sr-89,90 and tritium.
The sample collected by the automatic pumping device is taken directly from the river at the intake structure.
Since the sample at this point is raw water, not water processed through the water treatment plant, the control sample should also be unprocessed water.
Therefore, the upstream surface water sample is also considered as a control sample for drinking water.
A groundwater well onsite is equipped with an automatic water sampler;
- however, permanent power to this well was not available for the whole year in 1993.
Temporary power has been made available to the sampler so that grab samples could be taken each month.
Permanent power was restored in October and automatic sampling resumed at that time.
Hater is also collected from a private well in an area unaffected by BFN.
Samples from the wells are collected every 4 weeks and analyzed by gamma spectroscopy.
A quarterly composite sample is analyzed for Sr-89,90 and tritium.
Samples of commercial and game fish species are collected semiannually from each of two reservoirs:
the reservoir on which the plant is located (Hheeler t
Reservoir) and the upstream reservoir (Guntersville Reservoir).
The samples are collected using a combination of netting techniques and electrofishing.
Most of the fish are filleted, but one group is processed whole for analysis.
After drying and grinding, the samples are analyzed by gamma spectroscopy.
Bottom sediment is collected semiannually from selected Tennessee River Mile (TRM) locations using a dredging apparatus or divers.
The samples are dried and ground and analyzed by gamma spectroscopy.
After this analysis is
- complete, the samples are ashed and analyzed for Sr-89,90.
Samples of Asiatic clams are collected from one location below the plant and one location above the plant.
The clams are usually collected in the dredging or diving process with the sediment.
Enough clams are collected to produce approximately 50 grams of wet flesh.
The flesh is separated from the shells, and the dried flesh samples are analyzed by gamma spectroscopy.
Sufficient to find.
Results All radioactivity in surface water samples was below the LLD except the gross beta activity and naturally occurring isotopes.
Tritium was reported in one sample at a concentration of approximately 1:5 times the lower limit of detection.
These results are consistent with previously reported levels.
A trend plot of the gross beta activity in surface water samples from 1968 through 1993 is presented in Figure H-8.
A summary table of the results for this reporting period is shown in Table H-12.
For drinking water, average gross beta activity was 2.3 pCi/liter at the downstream stations and 2.3 pCi/liter at the control stations.
The results are shown in Table H-13 and a trend plot of the gross beta activity in drinking water from 1968 to the present is presented in Figure H-9.
Concentrations of fission and activation products in groundwater samples were all below the LLDs.
Only naturally occurring radon decay products (Bi-214 and Pb-214) were identified in these samples.
Results from the analysis of groundwater samples are presented in Table H-14.
Cesium-137 was identified in three fish samples.
The downstream sample had a
concentration of 0.09 pCi/g while the concentration in the upstream samples averaged 0.08 pCi/g.
The only other radioisotopes found in fish were 17.2 pCi/g.
The results are summarized in Tables H-15, H-16, and H-17.
Plots of the annual average Cs-137 concentrations in fish are presented in Figures H-10, H-ll, and H-12.
Since the concentrations downstream are essentially equivalent to the upstream levels, the Cs-137 activity is probably a result of fallout or other upstream effluents rather than activities at BFN.
Radionuclides of the types produced by nuclear power plant operations were identified in sediment samples.
The materials identified were Cs-137, Co-60, Cs-134 and ln-65.
The average levels of Cs-137 were 0.58 pCi/g in downstream samples and 0.12 pCi/g upstream.
The Cs-137 concentrations at downstream stations has historically been higher than concentrations upstream.
This of the Cs-137 concentrations in sediment since 1968.
Cobalt-60 concentrations in downstream samples averaged 0.15 pCi/g, while concentrations in upstream samples were below the lower limit of detection.
The maximum concentration downstream was 0.54 pCi/g.
Figure H-14 presents a
graph of the Co-60 concentrations measured in sediment since 1968.
Cesium-134 concentrations in upstream samples were all below the LLD.
Levels in two downstream samples averaged 0.02 pCi/g, with a maximum of 0.02 pCi/g.
The remaining samples showed no Cs-134 activity.
linc-65 was identified at one downstream station at a concentration of 0.06 pCi/g.
A realistic assessment of the impact to the general public from these radioisotopes produces a negligible dose equivalent.
Results from the analysis of sediment samples are shown in Table H-18.
t Only naturally occurring radioisotopes were identified in clam flesh samples.
The results are presented in Table H-19.
ASSESSMENT AND EVALUATION Potential doses to the public are estimated from measured effluents using computer models.
These models were developed by TVA and are based on methodology provided by the NRC in Regulatory Guide 1.109 for determining the potential dose to individuals and populations living in the vicinity of a nuclear power plant.
The doses calculated are a representation of the dose to a "maximally exposed individual."
Some of the factors used in these calculations (such as ingestion rates) are maximum expected values which will tend to overestimate the dose to this "hypothetical" person.
In reality, the expected dose to actual individuals is lower.
The area around the plant is analyzed to determine the pathways through which the public may receive an exposure.
As indicated in Figure 2, the two major ways by which radioactivity is introduced into the environment are through liquid and gaseous effluents.
For liquid effluents, the public can be exposed to radiation from three sources:
drinking water from the Tennessee river, eating fish caught in the Tennessee
- River, and direct exposure to radioactive material due to activities on the banks of the river (recreational activities).
Data used to determine these doses are based on guidance given by the NRC for maximum ingestion
- rates, exposure
- times, and distribution of the material in the river.
Nhenever possible, data used in the dose calculation are based on specific conditions for the BFN area.
For gaseous effluents, the public can be exposed to radiation from several sources:
direct radiation rom e r i
f th radioactivity in the air, direct radiation from radioactivity deposited on the ground, inhalation of radioactivity in the air, ingestion of vegeta on w ic t ti h ch contains radioactivity deposited from the atmosphere, and nges on o d
i ti of, milk or meat from animals which consumed vegetation con a
n ng ep t i i d
osited radioactivity.
The concentrations of radioactivity in the air an h
the soil are estimated by computer models which use the actual meteorological conditions to determine the distribution of the effluents in the atmosphere.
- Again, as many of the parameters as possible are based on actual site-specific data.
Results The estimated doses o
e ma t
th aximally exposed individual due to radioactivity released from 8 in a
FN 1993 re presented in Table 2.
These estimates were made using the concentrations o
e q
f th li uids and gases measured at the effluent monitoring points.
so s
own t
Al shown are the ODCM limits for these doses and a
comparison between the calculated dose and the corresponding limit.
The maximum calculated whole o y ose eq 1
b d
d equivalent from measured liquid effluents as presented in Tab e
s 2 i 0
12 mrem/year, or 4.0 percent of the limit.
The maximum organ dose equ va en r
i 1
t from gaseous effluents is 0.036 mrem/year.
This th ODCM limit.
A more complete description of the represents 0.24 percent of e
effluents released from an BFN d the corresponding doses projected from these effluents can be foun in e
d 'h BFN Radioactive Effluent Release Reports.
As stated earlier in t e repor th t
the estimated increase in radiation dose
equivalent to the general public resulting from the operation of BFN is undetectably small when compared to the dose from natural background radiation.
The results from each environmental sample are compared with the concentrations from the corresponding control stations and appropriate preoperational and background data to determine influences from the plant.
During this report period, Co-60, Cs-134, Cs-137, and Zn-65 were seen in aquatic media.
The distribution of Cs-137 in sediment is similar to fallout levels identified in samples both upstream and downstream from the plant during the preoperational phase of the monitoring program.
Co-60, Cs-134 and Zn-65 were identified in sediment samples downstream from the plant in concentrations which would produce no measurable increase in the dose to the t
general public.
No increases of radioactivity have been seen in water samples.
Dose estimates were made from concentrations of radioactivity found in samples of environmental media.
Media evaluated
- include, but are not limited to, air, milk, food products, drinking water, and fish.
Inhalation and ingestion doses estimated for persons at the indicator locations were essentially identical to those determined for persons at control stations.
More than 95 percent of those doses were contributed by the naturally occurring radionuclide K-40 and by Sr-90 and Cs-137, which are long-lived radioisotopes found in fallout from nuclear weapons testing.
Concentrations of Sr-90 and Cs-137 are consistent with levels measured in TVA's preoperational environmental radiological monitoring programs.
Conclusions It is concluded from the above analysis of the environmental sampling results and from the trend plots presented in Appendix H that the exposure to members of the general public which may have been attributable to BFN is negligible.
The radioactivity reported herein is primarily the result of fallout or natural background radiation.
Any activity which may be present as a result of plant operations does not represent a significant contribution to the exposure of members of the public.
REFERENCES 1.
Merri 1 Ei senbud, Environmental Radioacti vit
, Academic Press, Inc.,
New York, NY, 1987.
2.
National Council on Radiation Protection and Measurements, Report No.
93, "Ionizing Radiation Exposure of the Population of the United States,"
September 1987.
3.
United States Nuclear Regulatory Commission, Regulatory Guide 8.29, "Instruction Concerning Risks From Occupational Radiation Exposure," July 1981.
4.
Electric Power Research Institute,,Report No.
EPRI EA-2045, Project
- 1059, "Transuranium and Other Long-Lived Radionuclides in the Terrestrial Environs of Nuclear Power Plants,"
September 1981.
Table 1
D T A
FF NT T
A E
TRA N
Effluent Reporting Lower Limit
~fhb~~IB'ffluent
~Zu~r~m'eporting 1
r Lower Limit H-3 Cr-51 Hn-54 Co-58 Co-60 Zn-65 Sr-89 Sr-90 Nb-95 Zr-95 Ru-103 Ru-106 I-131 Cs-134 Cs-137 Ce-144 Ba-140 La-140 1,000,000 500,000 30,000 20,000 30,000 5,000 8,000 500 30,000 20,000 30,000 3,000 1,000 900 1,000 3,000 8 F 000 9,000 20,000 1,000 1,000 300 300 400 400 2
30 50 200 200 250 45 5
5 5
10 3
1.4 5
10 5
40 1
5 5
33 25 8
100,000 30,000 1,000 1.000 50 400 1,000 6
2,000 400 900 20 200 200 200 40 2,000 2,000 0.9 10 20 0.02 0.005 0.005 0.005 0.005 0.0006 0.0003 0.005 0.005 0.005 0.02 0.02 0.005 0.005 0.01 0.01 0.005 Note:
1 pCi
= 3.7 x 10
~ Bq.
Note:
For those reporting levels that are blank, no value is given in the reference.
1 Source:
Table 2 of Appendix B to 10 CFR 20.1001-20.2401 2
Source:
BFN Offsi te Dose Calculation Hanual, Table 2.3-3 3
Source:
Table E-1 of this report
Table 2
Maximum Dose due to Radioactive Effluent Releases Brogans Ferry Nuclear Plant 1993 mrem/year Li uid Effluents 1YY)e Total Body Any Organ 1993 Dose 0.12 0.16 NRC Limit 10 Percent of NRC Limit 4.0 1.6 EPA Limit 25 25 Percent of EPA Limit 0
~ 5 0.6 Gaseous Effluents
~Te Noble Gas (Gamma)
Noble Gas (Beta)
Any Organ 1993 Dose 0.003 0.002 0.036 NRC Limit 10 20 15 Percent of NRC Limit
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APPENDIX A ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM AND SAMPLING LOCATIONS 40
Table A-1 BROWNS FERRY NUCLEAR PLANT Environmental Radiological Honitoring Program'xposure Pathway n
r m
Number of Samples and Sampling and 1
r Type and Frequency AIRBORNE Par t icul a tes Radioiodine Rainwater S ix sampl es from 1 oc at i on s (in different sectors) at or near boundary site (LH-l, LH-2 LH-3, LH-4, LH-6. and LH-7)
Two samples from control locations greater than 10 miles from the plant (RH-1 and RH-6)
Three samples from locations in communities approximately 10 miles from the plant PH-l, PH-2, and PH-3)
Same locations as air particulates Same location as air particulate 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 Particulate sampler.
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 /> following filter change.
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 every 7 days Analyzed for gaama nuclides only if radioactivity in other media indicates the presence of increased levels of fallout
Table A-1 BROWNS FERRY NUCLEAR PLANT Environmental Radiological Honi toring Program'xposure Pathway n
m Soil Direct Number of Samples and Samples from same locations as air particulates Two or more dosimeters placed at locations (in different sectors) at or near the site boundary in ea=h of the 16 sectors Two or more dosimeters placed at stations located approximately 5 miles from the plant in each of the 16 sectors Sampling and 1
i F
n Once every year At least once per 92 days At least once per 92 days Type and Frequency f
1 Gamma scan, Sr-89, Sr-90 once per year Galena dose once per 92 days Gamma dose once per 92 days WATERBORNE Surface Water Drinking Water Two or more dosimeters in at least 8 additional locations of special interest One sample upstream (TRH 305.0)
One sample immediately down-stream of discharge (TRH 293.5)
One sample downstream from plant (TRH 285.2)
One sample at the first potable surface water supply downstream from the plant (TRH 282.6)
Collected by automatic sequential-type sampler with composite sample taken at least once per 7
days'ollected by automatic sequential-type sampler with composite sample taken at least once per 31 days Gross beta and gamma scan on 4-week composite.
Composite for Sr-89, Sr-90 'nd tritium at least once per 92 days Gross beta and gamma scan on 4-week composite.
Composite for Sr-89, Sr-90, and tritium at least once per 92 days
Table A-1 BROWNS FERRY NUCLEAR PLANT Environmental Radiological Honitoring Program'xposure Pathway n
r m
1 Drinking Water (Continued)
Number of Samples and Three additional samples of potable surface water down-stream from the plant (TRH 274.9, TRH 259.5 and TRH 259.8)
Sampling and ll Fr r
Grab sample taken at least once per 31 days Type and Frequency f Anl Gross beta and gamma scan on each sample.
Composite for Sr-89, Sr-90, and tritium at least once per 92 days Ground Water A()VATIC Sediment One sample at a control location (TRH 306)
One additional sample at a control location (TRH 305)
One s amp 1 e adjacen t to the plant (Well No. 6)
One sample at a control
'iocation upgradient from the plant (Farm Bn)
Two samples upstream from discharge point (TRH 297.0 and 307.52)
One sample in immediate downstream area of discharge point (TRH 293.7)
Two additional samples downstream from the plant (TRH 288.78 and 277.98)
Collected by automatic sequentia')-type sampler with composite sample taken at least once per 7
days'ollected by automatic sequential-type sampler with composite sample taken at least once per 31 days Grab sample taken at least once per 3) days At least once per 184 days At least once per )84 days Gamma scan on each composite.
Composite for Sr-89, Sr-90, and tritium at least once per 92 days Gamma scan on each sample.
Composite for Sr-89, Sr-90, and tritium at least once per 92 days Gamma scan, Sr-89 and Sr-90 analyses Gamma scan, Sr-89 and Sr-90 analyses
Table A-1 BROWNS FERRY NUCLEAR PLANT Environmental Radiological Honitoring Program'xposure Pathway m
Number of Samples and Sampling and 11 i
Fr Type and Frequency f
n 1
i INGESTION Nilk At least 2 samples from dairy farms in the immediate vicinity of the plant (Farms B and Bn)
At least once per 15 days when animals are on pasture; at least once 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 Fish Cl ams At least one sample from control location (Farm Be and/or GL)
Three samples representing commercial and game species in Guntersville Reservoir above the plant Three samples representing commercial and game species in Wheeler Reservoir near the plant.
One sample downstream from the discharge One sample upstream from the plant (No permanent stations established; depends on location of clams)
At least once per 184 days At least once per 184 days Gamma scan at 'least once per 184 days on edible portions Gamma scan on flesh only
Table A-1 BROWNS FERRY NUCLEAR PLANT Environmental Radiological Monitoring Program'xposure Pathway Number of Samples and Sampling and 1
Type and Frequency Fruits and Vegetables Vegetation Samples of food crops such as corn, green beans,
- tomatoes, and potatoes grown at private gardens and/or farms in the immediate vicinity of the plant One sample of each of the same foods grown at greater than 10 miles distance from the plant Samples from farms producing milk but not providing a milk sample (Farm T)
Control samples.
from one control dairy (Farm GL)
At least once per year at time of harvest Once per 31 days Gamma scan on edible portion I-131, gamma scan once per 31 days a.
The sampling program outlined in this table is that which was in effect at the end of 1993.
b.
Sampling locations, sector and distance from plant, are described in Table A-2 and A-3 and shown in c.
Composite samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
d.
The surface water control sample shall be considered a control for the drinking water sample.
Table A-2 BROHNS FERRY NUCLEAR PLANT Environmental Radiological Monitoring Program Sampling Locations Map Location Number'tation Approximate Indicator (I)
Distance or Sector (miles)
Control (C)
Samples Collected' 2
5 6
7 8
9 10ll 12 13 18 22 23 24 25 26 27 28 29 30 31 32 33 34 36 37 70 PM-1 PM-2 PM-3 LM-7 RM-1 RM-6 LM-1 LM-2 LM-3 LM-4 LM-6 Farm B
Farm Bn Farm Gl Hell No.
6 TRM'82.6 TRM 306.0 TRM 259.6 TRM 274.9 TRM 285.2 TRM 293.5 TRM 305.0 TRM 307.52 TRM 293.7 TRM 288.78 TRM 277.98 Farm Be Farm T
TRM 297.0 TRM 259.8 NH NE SSE H
H E
N NNE ENE NNH SSH NNH N
HSH NH 13.8 10.9 8.2 2.1
- 31. 3 24.2 1.0 0.9 0.9 1.7 3.0 6.8 5.0 35.0 0.02 11.4'2.0'4.4 19.1'.8 0.5'1.0'3.52'.3'
'2 16.02'8.8 3.2 3.0 34.2 I
I I
I C
C I
I I
I I=
I C
I I
C I
I I
I Ce C
I I
I C
I C
I 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,H M,V H
PH PH PH PH SH SH SH SD SD SD SD M
V SD PH
Table A-2 BROHNS FERRY NUCLEAR PLANT Environmental Radiological Monitoring Program Sampling Locations (Continued)
Map Location Number'tation Approximate Indicator (I)
Distance or Sector (miles)
Control (C)
Samples Collected'heeler Reservoir'TRM 275-349)
Guntersvi lie Reservoir'RM (349-424)
F,CL a.
See figures A-l, A-2, and A-3.
b.
Sample Codes; AP = Air particulate filter CF = Charcoal filter (Iodine)
CL = Clams F
= Fish M = Milk PH = Public drinking water c.
Miles from plant discharge (TRM 294).
e.
Also used as a control for public water.
R
= Rainwater S
Soil SD
= Sediment SH = Surface water V
Vegetation W
= Hell water
Table A-3 BROWNS FERRY NUCLEAR PLANT Thermoluminescent Dosimeter (TLD) Locations Hap Location Number'0 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 Station NH-3 NE-3 SSE-2 H-3 E-3 N-1 NNE-1 ENE-1 NNW-2 N-2 NNE-2 NNE-3 NE-1 NE-2 ENE-2 E-1 E-2 ESE-1 ESE-2 SE-1 SE-2 SSE-1 S-l S-2 SSH-1 SSW-2 SH-1 SW-2 SH-3 WSW-1 WSH-2 WSW-3 H-1 H-2 W-4 WNH-1 HNH-2 NW-1 NW-2 Sector NH NE SSE W
NNE ENE NNH NNE NNE NE NE ENE E
S SSW SSW SH SH SH HSH HSH WSH H
H W
HNH HNll NW NH Approximate Distance (miles) 13.8 10.9 8.2 31.3 24.2 0.97 0.88 0.92 1;7 5.0 0.7 5.2 0.8 5.0 6.2 0.8 5.2 0.9 3.0 0.5 5.4 5.1 3.1 4 '
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 Onsite (On)'r Offsi te (Off)
Off Off Off Off Off On On On On Off On Off On Off Off On Off On Off On Off Off Off Off Off Off On Off Off Off Off Off On Off Off Off Off Off Off Table A-3 BROWNS FERRY NUCLEAR PLANT Thermoluminescent Dosimeter (TLD) Locations (Continued)
Map Location Number'8 69 Station NNH-1 NNH-3 Sector NNW NNH Approximate Distance (miles) 1.0 5.2 Onsite (On)'l Offsite (Off)
On Off a.
See figures A-l, A-2, and A-3.
b.
TLDs designated onsite are those located 2 miles or less from the plant.
TLDs designated offsite are those located more than 2 miles from the plant.
49
Figure A-1 Environmental Radiological Sampling Locations Within 1 Mile of Plant NW 326.2 348.75 1 1.25 NNE
'7
~ 8 33.75 NE 303.75 28'9 41' 56.25 ENE 78.75 258.75
/ I BROWNS FERRY NUCLEAR PLANT 48 IIIIIIIW
'44 o46 101.25 ESE 236.25 123.75 213.75 146.25 ssvr SSE 1 9 1.25 S
1 68.75 Scale Mile SE Figure A-2 Environmental Radiological Sampling Locations From 1 to 5 Miles From the Plant NNW 348.75 N
~ 6 13 11.25 NNE 328.25 33.75 NW NE 303.75 42 56.25 WNW 65 o
6
~ 10 ENE 36,64 78.75 W-
~62 61 BROWNS PER Y
NUCLEAR PLANT 258.75 WSW I
ss 47 37+
/g, a101.25 L'SE 236.25 53 51 12 '.75 SW 56 SE 213.75 SSW
~ 54 191.25 I
I 52 I
168.75 146.25 SSE SCALE 0
0.5 1
0.5 2
MILES
\\
FigU(B P-S ocat)ons Racho/og<cai Sarnp
> g Environrnenta]
a i bh'Aes From the Plant Greater Than 5
> e 848.75 11.25 826.25 38.75 AAREHGESVIIO PVLASIII 308.75 FA'(ETTA I.LE 56.25 FLOIIEHGE AT EHS 78.7 6
, 2 VSGLE SHOP L 48 45 VHTSTILLE 258.76 57 101.25 IIVSSE VILLE 18 GUN'ISASVII.Lg All 326.2 HALETVI I.E, 128.76 GVLLIPAH 218,75 191.25 168.75 146.25 SGAI,E
~
0 IO
'I IPIL'ES
APPENDIX 8 1993 PROGRAM HODIFICATIONS
APPENDIX B
Environmental Radiolo ical Monitorin Pro ram Modifications During 1993, only slight modifications were made in the environmental monitoring program.
The city of Florence,
- Alabama, began operation of a new water treatment plant, The plant takes water from the Tennessee River at Tennessee River Mile (TRM) 259.8.
Sampling of water from the plant was initiated in January, 1993.
The following table lists the changes in the monitoring program in 1993.
Table B-l Environmental Radiolo ical Monitorin Pro ram Modifications Oate 1/18/93 Station Location
APPENDIX C PROGRAM DEVIATIONS
0 Appendix C
Pro ram Deviations During 1993, a small number of samples were not collected.
Those occurrences resulted in deviations from the scheduled program but not from the minimum program required in the Offsite Dose Calculation Manual.
Table C-1 lists these occurrences.
A general description follows.
Permanent electrical power to the automatic well water sampler was out of service for a portion of the year.
During this time, temporary power permitted the collection of monthly grab samples from the well.
Permanent t
power was restored in October,
- 1993, and automatic sampling resumed at that time.
One public water sample was not collected because of the malfunction of the electrical switch.
The switch was replaced and the remaining samples collected as scheduled.
One air particulate sample was missed as a result of a broken sampling head.
The head was replaced during the same week and subsequent samples collected as scheduled.
One control milk sample was not collected because milk was not available from the farm on the sample date and one milk sample was spoiled and unsuitable for analysis'
)
4
Table C-1 Environmental Radiolo ical Honitorin Pro ram Deviations Date Station Location Remarks 1/22/93 5
Hell 6
12/21/93 Onsi te Permanent power to the automatic well sampler was out of service for a portion of the year.
Grab samples were taken monthly until
- October, 1993.
Permanent power was restored at that time and automatic sampling
- resumed, 3/22/93 t
7/26/93 9/27/93 11/29/93 Farm Gl Farm Bn Champion Paper Co.
PM-1 BF 35.0 miles WSW 5.0 miles N
11.4 miles downstream 10.9 miles NE One of two control stations.
No milk was available on the collection date.
Milk was collected from the other control station.
The sample was spoiled and unsuitable for analysis.
Public water sample not collected as a result of sampler malfunction in the electrical switch.
The switch was replaced and subsequent samples collected.
Air particulate filter was not collected as a result of a broken filter head.
The head was
'eplaced and subsequent samples collected.
APPENDIX D ANALYTICALPROCEDURES APPENDIX D Anal tical Procedures Analyses of environmental samples are performed by the radioanalytical laboratory located at the Hestern Area Radiological Laboratory facility in Muscle Shoals.
All analysis procedures are based on accepted methods.
A ill summary of the analysis techniques and methodology follows.
The gross beta measurements are made with an automatic low background counting system.
Normal counting times are 50 minutes.
Hater samples are prepared by evaporating 500 ml of samples to near dryness, transferring to a stainless steel planchet and completing the evaporation process.
For solid samples, a
specified amount of the sample is packed into a deep stainless steel planchet.
Air particulate filters are counted directly in a shallow planchet.
The specific analysis of I-131 in milk, water, or vegetation samples is performed by first isolating and purifying the iodine by radiochemical separation and then counting the final precipitate on a beta-gamma coincidence counting system.
The normal count time is 100 minutes.
Hith the beta-gamma coincidence counting
- system, background counts are virtually eliminated and extremely low levels of detection can be obtained.
After a radiochemical separation, samples analyzed for Sr-89,90 are counted on a low background beta counting system.
The sample is counted a second time after a 7-day ingrowth period.
From the two counts the Sr-89 and Sr-90 concentrations can be determined.
Hater samples are analyzed for tritium content by first distilling a portion of the sample and then counting by liquid scintillation.
A commercially available scintillation cocktail is used.
Gamma analyses are performed in various counting geometries depending on the sample type and volume.
All gamma counts are obtained with germanium type detectors interfaced with a computer based mutlichannel analyzer system.
Spectral data reduction is performed by the computer program HYPERMET.
The charcoal cartridges used to sample gaseous radioiodine were analyzed by gamma spectroscopy using a germanium detector system.
All of the necessary efficiency values, weight-efficiency curves, and geometry tables are established and maintained on each detector and counting system.
A series of daily and periodic quality control checks are performed to monitor counting instrumentation.
System logbooks and control charts are used to document the results of the quality control checks.
The analysis of transuranic isotopes in soil and air filters is performed by leaching the sample with acid and then separating the isotopes of interest from the acid leach by an ion exchange technique.
The ion exchange technique separates the samples into two fractions, one containing plutonium and the other containing both americium and curium.
The Pu fraction and the Am/Cm fractions are electroplated onto separate stainless steel
- discs, and counted for 1200 minutes on an alpha spectrometer employing a surface barrier detector.
APPENDIX E
NOMINAL LONER LIMITS OF DETECTION (LLD)
Appendix E
Nominal Lower Limits of Detection Sensitive radiation detection devices can give a signal or reading even when no radioactivity is present in a sample being analyzed.
This signal may come from trace amounts of radioactivi ty in the components of the device, from cosmic rays, from naturally occurring radon gas, or from electronic noise.
- Thus, there is always some sort of signal on these sensitive devices.
The signal registered when no activity is present in the sample is called the background.
The point at which the signal is determined to represent radioactivity in the sample is called the critical level.
This point is based on statistical analysis of the background readings from any particular device.
- However, any sample measured over and over in the same device will give different readings, some higher than others.
The sample should have a well-defined average
- reading, but any individual reading will vary from that average.
In order to determine the activity present in a sample that will produce a reading above the critical level, additional statistical a'nalysis of the background readings is required.
The hypothetical activity calculated from this analysis is called the lower limit of detection (LLD).
A listing of typical LLD values that a laboratory publishes is a guide to the sensitivity of the analytical measurements performed by the laboratory.
Every time an activity is calculated from a sample, the background must be subtracted from the sample signal.
For the very low levels encountered in
~(
environmental monitoring, the sample signals are often very close to the
~
~
background.
The measuring equipment is being used at the limit of its capability.
For a sample with no measurable activity, which often happens, about half the time its signal should fall below the average machine background and half the time it should be above the backgrounds If a signal above the background is present, the calculated activity is compared to the calculated LLD to determine if there is really activity present or if the number is an artifact of the way radioactivity is measured.
A number of factors influence the LLD, including sample size, count time, counting efficiency, chemical processes, radioactive decay factors, and interfering isotopes encountered in the sample.
The most likely values for t
these factors have been evaluated for the various analyses performed in the environmental monitoring program, The nominal LLDs calculated from these
- values, in accordance with the methodology prescribed in the ODCM, are presented in Table E-1.
The maximum values for the lower limits of detection specified in the ODCM are shown in Table E-2.
The LLDs are also presented in the data tables.
For analyses for which LLDs have not been established, an LLD of zero is assumed in determining if a measured activity is reported as greater than the LLD.
Table E-1 Nominal LLD Values A.
Radiochemical Procedures Air Filters LuQlm'3 Charcoal Filters
~m~g Water
~i~
Hi 1 k Ll Fish Flesh l<iL~uinl Sediment Whole Fish Food Crops and Soil Q)~i~w Gross Beta Tritium Iodine-131 Strontium-89 Strontium-90 0.002 0.0006 0.0003
.020'.7 250 1.0 3 '
1.4 0.2 2.5 2.0 0.3 0.04 0.7 0.09 1.0 0.3 Gross Beta Iodine-131 Strontium-89 Strontium-90 Wet Vegetation 4
140 60 Clam Flesh gJ)~
0.2 Heat
/~i 15
'he LLD for I-131 in charcoal filters analyzed by germanium spectroscopy is 0.03 pCi/m~.
Table E-1 Nominal LLD Values B.
Gamma Analyses (GeLi)
Air Particulates m'i Water and Milk UKLil Vegetation Wet Soil and
- Foods, Tomatoes Meat and and Grain Vegetation Sediment Fish Clam Flesh
- Potatoes, etc.
Poultry Ce-141 Ce-144 Cr-51 I-131 Ru-103 Ru-106 Cs-134 Cs-137 Z1-95 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 Pa-234m
.005
.01
.02
.005
.005
.02
.005
.005
.005
.005
.005
.005
.005
.005
.04
.01
.005
.005
.02
.005
.005
.005
.001
.014 10 33 45 10 5
40 5
5 10 5
5 5
10 5
150 25 8
5 45 20 20 20 53 7
25 700
.07
.25
.45
.09
.05
.48
.07
.06
.11
.06
.05
.05
.11
.07 1.00
.23
.11
.10
.50
.10
.20
.12
.40
.03
.10 28 100 180 36 20 190 28 24 44 24 20 20 44 28 400 92 44 40 200 40 80 48 40 26 80
.02
.06
.10
.02
.01
.09
.01
.01
.02
.01
.01
.01
.01
.01
.20
.05
.02
.01
.10
.02
.02
.04
.25
.02
.30
.05
~ 10 3.00
.07
.25
.45
.09
.05
.48
.07
.06
.11
.06
.05
.05
.11
.07 1.00
.23
.11
.10
.50
.10
.20
.12
.40
.03
.10
.15
.50
.94
.18
.11
.95
.11
.10
.19
.11
.10
.10
.21
.11 2.00
.47
.17
.13
.90
.25
.25
.25
.35 1.00 10 33 45 10 5
40 5
5 10 5
5 5
10 5
150 25 8
5 45 20 20 20 53 7
22 25 50 90 20 15 95 15 15 25 15 15 15 25 15 300 50 20 15 100 40 40 40 22
Table E-2 Maximum Values for the Lower Limits of Detection (LLD)
Specified by the BFN Offsite Dose Calculation Manual Hater A~nal sls gCi/L Airborne Particulate or Gases Fish Milk
~Cl/m'Cl/K wet ~Cl/t Food Products Sediment
~l
~d gross beta 4
1 x10~
N.A.
N.A.
N.A.
H-3 2000 N.A.
N.A.
N.A.
N.A.
Mn-54 15 N.A.
130 N.A.
N.A.
N.A.
Fe-59 30 N.A.
260 N.A.
N.A.
N.A.
Cs-134 Cs-137 Ba-140 La-140 15 18 60 15 Co-58,60 15 Zn-65 30 t
N.A.
N.A.
N.A.
7x10' x
10 '
x 10-z N.A.
N.A.
130 260 N.A.
N.A.
N.A.
130 150 N.A.
NBA.
N.A.
N.A.
N.A.
N.A.
15 18 60 15 N.A.
N.A.
N.A.
N.A.
60 60 80 N.A.
N.A.
N.A.
N.A.
N.A.
N.A.
N.A.
150 180 N.A.
N.A.
LLD for analysis of drinking water and surface water samples shall be performed by gamma spectroscopy at approximately 15 pCi/L. If levels greater than 15 pCi/L are identified in surface water samples downstream from the plant, or in the event of an unanticipated release of I-131, drinking water samples will be analyzed at an LLD of 1.0 pCi/L for I-131.
APPENDIX F QUALITY ASSURANCE/QUALITY CONTROL PROGRAM l
Appendix F
vali t Assurance/ ualit Control Pro ram A thorough quality assurance program is employed by the laboratory to ensure that the environmental monitoring data are reliable.
This program includes the use of written, approved procedures in performing the work, a
nonconformance and corrective action tracking system, systematic internal
- audits, a complete training and retraining system, audits by various external organizations, and a laboratory quality control program.
The quality control program employed by the radioanalytical laboratory is t
designed to ensure that the sampling and analysis process is working as intended.
The program includes equipment checks and the analysis of special samples along with routine samples.
Radiation detection devices are complex and can be tested in a number of ways.
There are two primary tests which are performed on all devices.
In the first type, the device is operated without a sample on the detector to determine the background count rate.
The ba'ckground counts are usually low values and are due to machine
- noise, cosmic rays, or trace amounts of radioactivity in the materials used to construct the detector.
Charts of background counts are kept and monitored to ensure that no unusually high or low values are encountered.
Itk
~
C
~
radioactivity present.
The number of counts registered from such a
radioactive standard should be very reproducible.
These reproducibility checks are also monitored to ensure that they 'are neither higher nor lower than expected.
When counts from either test fall outside the expected
- range, the device is inspected for malfunction or contamination.
It is not placed into service until it is operating properly.
In addition to these two general
- checks, other quality control checks are performed on the variety of detectors used in the laboratory.
The exact nature of these checks depends on the type of device and the method it uses to detect radiation or store the information obtained.
guality control samples of a variety of types are used by the laboratory to verify the performance of different portions of the analytical process.
These quality control samples may be blanks, replicate
- samples, blind samples, or cross-checks.
Blanks are samples which contain no measurable radioactivity or no activity of the type being measured.
Such samples are analyzed to determine whether there is any contamination of equipment or commercial laboratory chemicals, cross-contamination in the chemical
- process, or interference from isotopes other than the one being measured.
Duplicate samples are generated at random by the same computer program which schedules the collection of the routine samples.
For example, if the routine t
program calls for four milk samples every week, on a random basis each farm
might provide an additional sample several times a year.
These duplicate samples are analyzed along with the other routine samples.
They provide information about the variability of radioactive content in the various sample media.
If enough sample is available for a particular analysis, the laboratory analyst can split it into two portions.
Such a sample can provide information about the variability of the analytical process since two identical portions of material are analyzed side by side.
Analytical knowns are another category of quality control sample.
A known amount of radioactivity is added to a sample medium by the quality control staff or by the analysts themselves.
The analysts are told the radioactive content of the sample.
Whenever possible, the analytical knowns contain the same amount of radioactivity each time they are run.
In this way, the analysts have immediate knowledge of the quality of the measurement process.
A portion of these samples are also blanks.
Blind spikes are samples containing radioactivity which are introduced into the analysis process disguised as ordinary e'nvironmental samples.
The analyst does not know they contain radioactivity.
Since the bulk of the ordinary workload of the environmental laboratory contains no measurable activity or only naturally occurring radioisotopes, blind spikes can be used to test the detection capability of the laboratory or they can be used to test the data
particular isotope, the presence of the isotope is brought to the attention of the laboratory supervisor in the daily review process.
Blind spikes test this process since they contain radioactivity at levels high enough to be detected.
Furthermore, the activity can be put into such samples at the extreme limit of detection (near the LLD) to determine whether or not the laboratory can find any unusual radioactivity whatsoever.
At present, 5 percent of the laboratory workload is in the category of internal cross-checks.
These samples have a known amount of radioactivity added and are presented to the analysts labeled as cross-check samples.
This means that the quality control staff knows the radioactive content or "right answer" but the analysts do not.
They are aware they are being tested.
Such samples test the best performance of the laboratory by determining if the analysts can find the "right answer."
These samples provide information about the accuracy of the measurement process.
Further information is available about the variability of the process if multiple analyses are requested on the same sample.
Internal cross-checks can also tell if there is a difference in performance between two analysts.
Like blind spikes or analytical
- knowns, these samples can also be spiked with low levels of activity to test detection limits.
A series of cross-checks is produced by the EPA in Las Vegas.
These interlaboratory comparison samples or "EPA cross-checks" are considered to be the primary indicator of laboratory performance.
They provide an independent check of the entire measurement process that cannot be easily provided by the t
laboratory itself.
That is, unlike internal cross-checks, EPA cross-checks
test the calibration of the laboratory detection devices sine'e different radioactive standards produced by individuals outside TVA are used in the cross-checks.
The results of the analysis of these samples are reported back to EPA which then issues a report of all the results of all participants.
These reports are examined very closely by laboratory supervisory and quality control personnel.
They indicate how well the laboratory is doing compared to others across the nation.
Like internal cross-checks, the EPA cross-checks provide information to the laboratory about the precision and accuracy of the radioanalytical work it does.
The results of TVA's participation in the EPA Interlaboratory Comparison Program are presented in Table F-1.
For 1993, all but one EPA cross-check t
sample concentrations measured by TVA's laboratory were within ~ 3-sigma of the EPA reported values.
During this year EPA reduced the number of samples in the intercomparison by approximately 30 percent.
TVA splits certain environmental samples with laboratories operated by the States of Alabama and Tennessee and the EPA National Air and Radiation Environmental Laboratory in Montgomery, Alabama.
Nhen radioactivity has been present in the environment in measurable quantities, such as following atmospheric nuclear weapons testing, following the Chernobyl incident, or as naturally occurring radionuclides, the split samples have provided TVA with yet another level of information about laboratory performance.
These samples demonstrate performance on actual environmental sample matrices rather than on the constructed matrices used in cross-check programs.
All the quality control data are routinely collected,
- examined, and reported to laboratory supervisory personnel.
They are checked for trends, problem
- areas, or other indications that a portion of the analytical process needs correction or improvement.
The end result is a measurement process that provides reliable and verifiable data and is sensitive enough to measure the presence of radioactivity far below the levels which could be harmful to humans.
Table F-1 RESOLTS OBTAINEO IN INTERLABORATORY COMPARISON PROGRAM A.
Air Filter (pCi/Filter)
EPA Value TVA EPA Value TVA EPA Value TVA EPA Value TVA
~<~mQ
~v.
~~im~
~Av
~~iqmmm A~v.
Q~im~
~v 8/93 19 9 21 47 9 50 19 9 27 9=9 9
B.
Radiochemical Analysis of Water (pCi/L)
I 1/93 4/93'/93 7/93 10/93 10/93'1/93 EPA Value TVA
~~im~ ~v EPA Value
~iqmm TVA EPA Value TVA EPA Value TVA EPA Value TVA EPA Value TVA
~Av
~icCim
~Av
~<<LLBm~
~v.
Q~iqmm
~Av
~~qm~
+v 43 12 15= 9 40 17 44 9
45 15 9 41=9 34 9 15=9 14 34 32 10 9
29.9 25=9 10 9 8
29 9844=1704 25 8
7398=1281 9070 7493 117 21 104 20 3 19
Table F-1 RESULTS OBTAINED IN INTERLABORATORY COMPARISON PROGRAH (Continued)
C.
Gamma-Spectral Analysis of Water (pCi/L) ri m-1 EPA Value
~iqmm.
TVA EPA Value TVA EPA Value TVA
~v.
~~iqmmL ~v.
~~LLgm~
i
-1 EPA Value TVA EPA Value TVA EPA Value TVA
<<Ltgm~ ~.
QQ<LLg~m
~.
~~qmm 4/93'/93 10/93~
11/93 99 17 79 14 39 9 40 100 15 9 15 103=17 106 10=9 10 77 30=9 30 150=26 157 119=21 101 201=35 182 27=9 25 5=9 5
12=9 9
59 9 55 32 9 33 5.9 4
10 9 10 40 9 41 D.
Milk (pCi/L)
EPA Value TVA EPA Value TVA jgmm ~v.
~~iqmm
~v 9/93 30=9 20 25 9 22 EPA Value TVA EPA Value TVA EPA Value TVA
~irwin ~v. ~~im~ ~v. ~~~i~
~v 120=21 117 49=9 47 1679 146 1692 a.
Performance Evaluation Intercomparison Study.
b.
Units are milligrams of total potassium per liter rather than picocuries of K-40 per liter.
c.
The Grand Average of non-outlier participants indicates that the Performance Evaluation Standard had a negative bias for Sr-89.
If the Grand Average of 24.03 pCi/liter were used for the known, TVA's results would be -1.3 sigma from the known.
APPENDIX G LAND USE SORVEY Appendix G
Land Use Surve A land use survey is conducted annually to identify the location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 square feet producing fresh leafy vegetables in each of 16 meteorological sectors within a distance of 5 miles from the plant.
The land use survey also identifies the location of all milk animals and gardens of greater than 500 square feet producing fresh leafy vegetables within a distance of 3 miles from the plant.
The land use survey is appropriate techniques survey, aerial
- survey, other reliable sources.
conducted between April 1
and October 1 using such as door-to-door survey, mail survey, telephone or information from local agricultural authorities or In order to identify the locations around BFN which have the greatest relative potential for impact by the plant, radiation doses are projected for individuals living near BFN.
These projections use the data obtained in the survey and historical meteorological data.
They also assume that the plant is operating and that releases are equivalent to the design basis source terms.
The calculated doses are relative in nature and do not reflect actual exposures to individuals living near BFN.
Calculated doses to individuals based on measured effluents from the plant are well below applicable dose limits (see Assessment and Evaluation).
Doses from breathing air (air submersion) are calculated for the nearest resident in each sector, while doses from drinking milk or eating foods produced near t e
p an are c
th 1
t a e calculated for the areas with milk producing animals and gardens, respectively.
Air submersion doses were calculated for the same locations as in 1992, with the resulting va ues s
m ar o
1 i ilar to those calculated in 1992.
Doses calculated for ingestion of home-grown foods changed in some sectors, reflecting shifts in the location of the nearest garden.
The changes were only very slight and did not significantly impact the doses caluclated in 1993.
For milk ingestion, projected annual doses were almost identical to those calcualted in 1992.
Only two locations with milk producing animals were identified.
Samples are being taken from both of these farms.
Tables G-l, G-2, and s
ow G-3 h
the comparative calculated doses for 1992 and 1993.
Table G-1 BROWNS FERRY NUCLEAR PLANT Relative Projected Annual Air Submersion Dose to the Nearest Resident (Within 5 miles) mrem/year/reactor 1992 Surve Approximate Sector Distance (Miles)
Annual Dose 1993 Surve Annual Dose Approximate Distance (Miles)
~
ss~
NSH HNW NN NNH 2.08 1.61 2.34 1.42 2.37 1.33 5.03 4.26 2.82 2.60 3.15 2.56 1.51 2.84 2.27 0.95 0.19 0.09 0.13 0.09 0.09 0.06 0.07 0.08 0.11 0.14 0.12 0.07 0.10 0.12 0.22 0.38 2.08 1.61 2.56 1.42 2.56 1.33 5.03 4.26 2.82 2.60 3.15 2.56 1.51 2.84 2.27 0.95 0.15 0.08 0.10 0.10 0.08 0.07 0.06 0.06 0.10 0.12 0.07 0.05 0.11 0.09 0.18 0.42 Table G-2 BROHNS FERRY NUCLEAR PLANT Relative Projected Annual Dose to Child's Bone from Ingestion of Home-Grown Foods (Nearest Garden Hithin 5 Miles) mrem/year/reactor 1992 Surve Approximate Sector Distance (Miles) Annual Dose 1993 Surve Approximate Distance (Miles) Annual Dose Number of Gardens Hithin 3 Miles (1993)
NNE t
HSH HNH NH NNH 2.08 3.41 2.75 1.51 2.37 2.75 4.17 2.82 2.84 3.88 2.70 1.69 a
2.72 1.14 4.11 0.93 1.22 2.76 2.38 2.09 1.18 2.15 2.43 0.82 0,64 1.18 3.76 10.10 2.56 3.41 2.75 1.70 2.60 2.46 a
4.36 2.82 2.84 3.88 2.70 1.69 a
2.72 1.11 3.08 1.01 1.23 2.44 1.84 2.19 0.97 2.25 2.35 0.69 0.60 1.26 3.41 9.96 a.
Garden not identified in this sector.
Table G-3 BRONNS FERRY NUCLEAR PLANT Relative Projected Annual Dose to Receptor Thyroid from Ingestion of Milk mrem/year/reactor Location Sector Farm Bn' Farm B'NN Approximate Distance (Miles) 4.9 6.8 Annual Dose 1992 1993 0.008 0.008 0.02 0.015 X/Q s/m'.28 E -8 1.32 E -8 a.
Milk being sampled at these locations.
APPENDIX H
DATA TABLES Table H-1 DIRECT RADIATION LEVELS Average External Gamma Radiation Levels at Various Distances from Browns Ferry Nuclear Plant for Each Quarter 1993 mrem/Quarter'istance Miles 0-1 1-2 2-4 4-6 1
6
- Average, 0-2 miles 1st uarter 16.2 x 0.8 15.5 5 1.2 13.9 a 1.3 14.0 2 0.9 14.5 a 1.5 2nd var ter 16.7 a
1.1 15.6 a 1.6 14.1 a 1.4 14.2 a 1.2 13.9 R 0.9 3rd uarter 16.6 x 1.0 15.1 x 1.3 14.0 N 1.4 14.1 a 0.9 13.9 2 0.9 Avera e External Gamma Radiation Levels'th uarter 15.0 a 1.8 14.8 R 0.8 14.6 a 1.9 14.2 a 1.8 13.4 2 1.0 (onsite) 16.0 a 1.0 16.4 a 1.3 16.2 a 1.3 15.0 2 1.7
- Average,
)
2 miles (offsi te) l4.1
~ 1.2 14.1 a 1.1 14.0 2 1.0 14.0 x 1.7 a.
Data normalized to one quarter (2190 hours0.0253 days <br />0.608 hours <br />0.00362 weeks <br />8.33295e-4 months <br />).
b.
Averages of the individual measurements in the set
~
1 standard deviation of the set.
TENNESSEE VALLEY AUI'HORITY TECHNICAL PROGRAMS ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATIOH WESTERH AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IH AIR FILTER PCI/M3 - 0.037 BQ/M3 NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIMESTONE ALABAMA DOCKET NO.:
50-259,260,296 REPORTING PERIOD:
1993 TYPE AND TOTAL HUMBER OF ANALYSIS PERFORMED LOWER LIMIT ALL OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN DETECTIOH MEAN (F)
NAME'EAN (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 HOHROUTIHE REPORTED MEASUREMENTS GROSS ALPHA 104 GROSS BETA 571 7.00E-04 8.84E-04(
2/
- 52) LM-1 BF 7.37E 1.03E-03 1.0 MILES N 8.84E-04(
2/
52) 8.23E-04(
4/
52) 7.37E 1.03E-03 7.61E 8.59E-04 2.00E-03 2.02E-02( 467/ 467)
LM-6BF BAKER BOTTOM 2.07E-02(
52/
52) 2.02E-02(
104/ 104) 8.10E 3.64E-02 3.0 MILES SS'W 1.23E 3.45E-02 1.02E 3.28E-02 GAMMA SCAN (GELI) 143 BE-7 Bl-214 K-40 Pe-214 TL-208 SR 89 2.00E-02 5.00E-03 4.00E-02 5.00E-03 1.00E-03 9.26E-02(
116/ 117) 5.72E 1.45E-01 9.43E-03(
24/ 117) 5.00E 2.23E-02
- 1.44E-01(
1/ 117) 1.44E 1.44E-01 9.57E-03(
23/ 117) 5.00E 2.20E-02 3.05E-03(
2/ 117) 1.60E 4.50E-03 LM4 BF TRAILER P 1.7 MILES HNW LM4 BF TRAILER P 1.7 MILES HNW LM4 BF TRAILER P 1.7 MILES NN'W LM4 BF TRAILER P 1.7 MILES NHW PM 2 BF ATHENS AL 10.9 MILES HE 9.53E-02(
12/
13) 5.86E 1.33E-01 1.54E-02(
3/
13) 8.40E 2.23E-02 1.44E-01(
1/
13) 1.44E 1.44E-01 1.43E.02(
3/
13) 9.10E 2.20E-02 4.50E-03(
1/
13) 4'0E 4.50E-03 9.04E-02(
26/
26) 5.26E 1.28E-01 8.43E-03(
3/
26) 5.20E 1.41E-02 26 VALUES < LLD 7.45E-03(
4/
26) 5.10E 1.25E-02 26 VALUES < LLD SR 90 AM 241 CM 244 PU 239,240 PU 238 6.00E-04 4 VALUES < LLD 3.00E-04 4 VALUES < LLD 2.50E-05 4 VALUES < LLD 8
2.50E-05 4 VALUES < LLD 8
2'0E-05 4 VALUES < LLD 2.50E-05 4 VALUES < LLD 4 VALUES < LLD 4 VALUES < LLD 4 VALUES < LLD 4 VALUES < LLD 4 VALUES < LLD 4 VALUES < LI.D NOTE:
1.
HOMIHAL LOWER LIMIT OF DETECTIOH (LLD) AS DESCRIBED IN TABLE E-1 NOTE:
2.
MEAN AHD RANGE BASED UPON DETECTABLE MEASUREMENTS OHLY~
FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIOHS IS INDICATED IH PARENTHESES (F).
TENNESSEE VALLEY AUTKORITY TECKHICAL PROGRAMS ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSI'RUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN AIR FILTER PCI/H3 0.037 BO/H3 NAME OF FACILITY: BROWS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIMESTONE ALABAMA DOCKET NO.:
50-259,260,296 REPORTING PERIOD:
1993 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LEER LIMIT ALL OF INDICATOR LOCATIONS LOCATION IJITK KIGKEST ANNUAL HEAN DETECTION MEAN (F)
NAME HEAN (F)
(LLD)
RANGE DISI'ANCE AND DIRECTION RANGE SEE NOTE 1
SEE NOTE 2 SEE NOTE 2 CONTROL LOCATIONS MEAN (F)
RANGE SEE NOTE 2 NUMBER OF NONROUTINE REPORTED MEASUREMENTS CM 242 8
2.50E-05 4 VALUES < LLD 4 VALUES < LLD NOTE:
1.
NOMINAL LONER LIHIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-l NOTE:
2.
MEAN AND RANGE BASED UPON DETECTABLE HEASUREMENTS ONLY.
FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PAREHTKESES (F)-
TENNESSEE VALLEY AUTHORITY TECHNICAL PROGRAMS ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN CHARCOAL FILTER PCI/M3 - 0.037 BQ/M3 0
NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIMESTONE ALABAMA DOCKET NO.:
50 259,260,296 REPORTING PERIOD:
1993 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT ALL OF INDICATOR LOCATIONS LOCATION 'WITH HIGHEST ANNUAL MEAH 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 NINBER OF NONROUTINE REPORTED MEASUREMENTS GAMMA SCAH (GELI) 572 Bl-214 K-40 PB-212 PB-214 TL-208 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 2.07E-02(
59/ 468) 3.00E 7.01E-02 2.58E.01(
40/ 468) 1.55E 5.79E-01 5.60E.03(
32/ 468) 5.00E 2.76E-02 2.01E-02(
150/ 468) 7.00E 7.95E-02 1.00E 02(
1/ 468) 1.00E I ~ OOE 02 LM-7BF LAKEVIEW 2.1 MILES WEST LM2 BF NORTH 0.9 MILE NNE PM-1 ROGERSVII.LE AL
'I3.8 MILES NW PM-1 ROGERSVILLE AL 13.8 HILES NW PM-1 ROGERSVILLE AL 13.8 HILES NW 2.76E-02(
5/
52) 5.30E 5'0E-02 3.47E-01(
5/
52) 2.70E.01-5.79E-01 1.43E-02(
3/
52) 6.80E 2.76E-02 2.27E-02(
16/
52) 5.30E 3.81E-02 1.00E.02(
1/
52) 1.00E 'I.ODE-02 2.43E-02(
11/ 104) 3.60E.03-6.54E-02 2.20E-01(
1/ 104) 2.20E 2.20E-01 4.65E-03(
2/ 104) 4.10E 5.20E-03 2.64E-02(
28/ 104) 4.60E 6.86E-02 104 VALUES < LLD NOTE:
1 ~ NOMINAL LOWER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1 NOTE:
2.
MEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY.
FRACTION OF DETECTABLE MEASUREMEHTS AT SPECIFIED LOCATIONS IS IHDICATED IN PARENTHESES (F).
TENNESSEE VALLEY AUTHORITY TECHNICAL PROGRAMS ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN HILK PCI/L - 0.037 BQ/L NAME OF FACILITY: BROWHS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIMESTONE ALABAHA DOCKET NO.:
50-259,260,296 REPORTING PERIOD:
1993 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORHED LOWER LIMIT ALL OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAH DETECTION MEAN (F)
NAME MEAN (F)
(LLD)
RANGE DISTANCE AND DIRECTION RANGE SEE NOTE 1
SEE NOTE 2 SEE NOTE 2 CONTROL LOCATIONS MEAN (F)
RANGE SEE NOTE 2 NUMBER OF NONROUTINE REPORTED MEASUREMENTS IODINE-131 102 2.00E-01 51 VALUES < LLD 51 VALUES < LLD GAMMA SCAN (GELI) 102 81-214 K-40 PB-214 SR 89 51 2.DOE+01 1.50E+02 2.DOE+01 7.83E+01(
1/
- 51) SMITH/BENNETT FARM 7.83E+01-7.83E+01 5.0 MILES N 1.30E+03(
51/
51)
BROOKS FARM 6.8 MILE 9.62E+02-1.59E+03 S
NNW 7.18E+01(
1/
51)
SHITH/BEHNETT FARM 7.18E+01-7.18Et01 5.0 MILES N 7.83E+01(
1/
25) 7.83E+01-7.83E+01 1.31E+03(
26/
26) 1.22Et03-1.42E+03 7.18Et01(
1/
25) 7.18E+01-7.18E+01 2.18E+01(
1/
51) 2.18E+01-2.18E+01 1.34E+03(
51/
51) 1.15E+03-1.47E+03 51 VALUES < LLD SR 90 2.50E+00 25 VALUES < LLD 51 2.DOE+00 2.50E+00(
9/
- 25) SMITH/BENNETT FARH 2.61E<00(
6/
12) 2.60E+00(
2/
26) 2.07E+00- 3.20E+00 5.0 M!LES N 2.10E+00.
3.20E+00 2.51E+00-2.69E+00 NOTE:
1 ~
NOMINAL LOWER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1 NOTE:
2.
MEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY.
FRACTIOH OF DETECTABLE MEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) ~
TENNESSEE VALLEY AUTHORITY TECHNICAL PROGRAHS ENVIRONMENTAL RADIOLOGICAL NOHITORING AND INSTRUHEHTATION
'MESTERH AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN VEGETATION PCI/KG - 0.037 BQ/KG (MET WEIGH'I)
NAME OF FACILITY: BROWHS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LINESTONE ALABAMA DOCKET NO.:
50-259,260,296 REPORTING PERIOD:
1993 TYPE AHD TOTAL HUNBER OF ANALYSIS PERFORHED LOWER LIHIT ALL OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN DETECTION MEAN (F)
HAHE HEAH (F)
(LLD)
RANGE DISTANCE AND DIRECTION RANGE SEE NOTE 1
SEE NOTE 2 SEE HOLE 2 CONTROL LOCATIOHS MEAN (F)
RAHGE SEE NOTE 2 NUHBER OF NONROUTINE REPORTED MEASUREHEHTS IODINE-131 26 4.DOE+00 13 VALUES < LLD 13 VALUES < LLD GAHHA SCAN (GELI) 26 BE-7 BI -214 K-40 PB-212 PB-214 TL-208 SR 89 2.DOE+02 4.80E+01 4.DOE+02 4.DOE+01 8.DOE+01 2.60E+01
'1.98E+03(
12/
13)
TERRY FARN 3.50E+02-6.52E+03 3.2 HILES MNM 2.'ISE+02(
4/
13)
TERRY FARH 6.17E+01-2.77E+02 3.2 HILES MHM 5.44E+03(
13/
13)
TERRY FARH 3.22E+03-8.51E+03 3.2 NILES MHM 8.14E+01(
1/
13)
TERRY FARH 8.14E+01-8.14E+Ol 3.2 HILES MNM 2.20E+02(
3/
13)
TERRY FARN 1.52E+02-2.93E+02 3.2 HILES MNM 3.06E+01(
1/
'l3) TERRY FARH 3.06E+01-3.06E>01 3.2 HILES WHM 1.98E+03(
3 ~ 50E+02-2.15Ei02(
6.17E+01-5.44E+03(
3.22E+03-8.14E+01(
8.14E+01-2.20E+02(
1.52E+02-3.06E+01(
3.06E+01-12/
13) 6.52E+03 4/
13) 2.77E+02 13/
13) 8.51E+03 1/
13) 8.14E+01 3/
13) 2.93E+02 1/
13) 3.06Ei01 6.33E+02(
13/
13) 2.48E+02-
'1.23E+03 1.06E+02(
2/
13) 1.02E+02-1.10E+02 5.82E+03(
13/
13) 3.35E+03-1.23E+04 13 VALUES < LLD 9.24E+01(
2/
13) 8.64Et01-9.84E+01 13 VALUES < LLD SR 90 8
1.40E+02 4 VALUES < LLD 6.DOE+01 4 VALUES < LLD 4 VALUES < LLD 4 VALUES < LLD NOTE:
1.
NONINAL LOWER LIHIT OF DETECTION (LLD) AS DESCRIBED IH TABLE E-1 NOTE:
2.
NEAN AND RANGE BASED UPON DETECTABLE HEASUREHENTS ONLY.
FRACTION OF DETECTABLE NEASURENENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).
TENNESSEE VALLEY AUTHORITY TECHNICAL PROGRAMS ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATION NESTERN AREA RADIOLOGICAL I.ABORATORY RADIOACTIVITY IN SOIL PCI/GM - 0.037 BQ/G (DRY WEIGHT)
NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIMESTONE ALABAMA DOCKFT NO.:
50-259,260,296 REPORTING PERIOD:
1993 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORHED LONER LIMIT ALL OF INDICATOR LOCATIONS LOCATION MITH HIGHEST ANNUAL MEAN DETECTION MEAN (F)
NAME MEAN (F)
(LI.D)
RANGE DISTANCE AND DIRECTION RANGE SEE NOTE 1
SEE NOTE 2 SEE NOTE 2 CONTROL LOCATIONS MEAN (F)
RANGE SEE NOTE 2 NUMBER OF NONROUTI NE REPORTED MEASUREMENTS GROSS ALPHA 2
NOT ESTAB 4.88E+00(
1/
'I) LHl BF NORTNNEST 4.88E+00-4.88E+00 1.0 HILE N 4.88E+00(
1/
'I) 3.05E+00(
1/
1) 4.88E+00-4.88E+00 3.05E+00- 3.05E+00 GAMMA SCAN (GELI)ll AC-228 BE-7 81-212 81-214 CS-137 K-40 PB-212 PB-214 RA-224 RA-226 TL-208 SR 89 1.00E-01
'I.OOE.01 2.50E-01 4.00E-02 1.00E-02 2.00E-01 2.00E-02 2 ~ OOE-02 3.00E-01 5.00E-02 2.00E-02 1.18E+00(
6.07E.01-1.63E-01(
1.17E 1.27E+00(
6.87E 9.15E-01(
5.34E-OI-2.79E-01(
3.36E 5.20E+00(
2.60E+00-1.12E+00(
5.34E 9.76E-01(
6.01E 1.26E+00(
6.23E 9. 15E-01(
5.34E 3.94E-01(
1.93E 9/
9) 1.47E+00 2/
9) 2.09E-01 9/
9) 1.57E+00 9/
9) 1.15E+00 9/
9) 6.71E-O'I 9/
9) 8.19E+00 9/
9) 1.38E+00 9/
9) 1.21E+00 9/
9) 1.68E+00 9/
9) 1.15E+00 9/
9) 4.87E-01 LH-7BF LAKEVIEll 2.1 MILES NEST PM-1 ROGERSVILLE AL 13.8 MILES NH LH1 BF NORTKWEST 1.0 MILE N LM2 BF NORTH 0.9 HILE NNE PM-1 ROGERSVILLE AL 13.8 MILES NH LH1 BF NORTHWEST 1.0 HILE N LM4 BF TRAILER P 1.7 HILES NNN LM2 BF NORTH 0.9 HILE NNE PH-3 BF DECATUR AL 8.2 MILES SSE LM2 BF NORTH 0.9 HILE NNE LH-7BF LAKEVIEM 2.1 MILES NEST 1.4?E+00(
1/
1) 1.47E+00-1.47E+00 2.09E-01(
1/
1) 2.09E 2.09E-OI 1.57E+00(
1/
1) 1.57E+00-1.57E+00 1.15E+00(
1/
1) 1.15E+00-1.15E+00 6.71E-01(
1/
'I) 6.7'IE-01. 6.71E-01 8.19E+00(
1/
1) 8.19E+00 8.19E+00 1.38E+00(
1/
1) 1.38E+00.
1.38E+00 1.21E+00(
1/
1) 1.21E+00.
1.21E+00 1.68E+00{
1/
'I) 1.68E+00-1.68E+00 1.15E+00(
1/
1)
'l.15E+00-1.15E+00 4.87E-01(
1/
1) 4.87E 4.8?E-01 1.01E+00(
7.34E 7.49E-01(
7.31E.01-1.51E-01(
1.11E 3.97E+00(
3.39E+00-9.02E-01(
6.81E 8.34E-01(
8.01E 7.5?E-01(
7.57E 7.49E-O'I(
7.31E 3.04E-01(
2.42E 2/
2) 1.29E+00 2/
2) 7.67E.01 2/
2) 1.92E-01 2/
2) 4.54E+00 2/
2) 1.12E+00 2/
2) 8.67E-01 1/
2) 7.57E-01 2/
2) 7.67E-01 2/
2) 3.66E-01 9.69E-01(
2/
2) 7.09E-OI-1 '3E+00 2 VALUES < LLD SR 90 1.DOE+00 9 VALUES < LLD 3.00E.01 9 VALUES < LLD 2 VALUES < LLD 2 VALUES < LLD NOTE:
1.
NOMINAL LONER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1
~
NOTE:
2-MEAN AND RANGE BASED UPON DETECTABLE MEASUREHENTS ONLY FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).
TENNESSEE VALLEY AUTHORITY TECHNICAL PROGRAMS ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUMEN'IATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN SOIL PCI/GM - 0.037 BQ/G (DRY WEIGHT)
NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIMESTONE ALABAMA DOCKET NO.:
50.259,260,296 REPORT'ING PERIOD:
1993 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT ALL OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN DETECTION HEAN (F)
NAME MEAN (F)
(LLD)
RANGE DISTANCE AND DIRECTION RANGE SEE NOTE 1
SEE NOTE 2 SEE NOTE 2 CONTROL LOCATIONS MEAN (F)
RANGE SEE NOTE 2 NUMBER OF NONROUTINE REPORTED HEASUREMEN'IS AM 241 NOT ESTAB 1 VALUES < LLD LM1 BF NORTHWEST 1.0 MILE N 1 VALUES < LLD 1 VALUES < LLD PU 239,240 CH 244 CH 242 NOT ESTAB 1
VALUES < LLD LM'I BF NORTHWEST 1.0 HILE N NOT ESTAB 1 VALUES < LLD LH1 BF NORTHWEST 1.0 MILE N NOT ESTAB 1 VALUES < LLD LM1 BF NORTHWEST 1.0 HILE N NOT ESTAB 1 VALUES < LLD LM1 BF NORTHWEST 1.0 MILE H 1 VALUES < LLD 7.98E-04(
I/
1) 7.98E-D4-7.98E-04 1 VALUES < LLD 1 VALUES < LLD 1 VALUES < LLD 1 VALUES < LLD 1 VALUES < LLD 1 VALUES < LLD NOTE:
1.
NOMINAL LOWER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1.
NOTE:
2.
MEAN AND RANGE BASED UPOH DETECTABLE MEASUREMENTS ONLY-FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).
TEHNESSEE VALLEY AUTHORITY TECHNICAL PROGRAMS ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATION HESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IH APPLES PCI/KG - 0.037 BQ/KG (HET HT)
NAME OF FACILITY: BRONHS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIMESTONE ALABAMA DOCKET NO.:
50-259,260,296 REPORTIHG PERIOD:
1993 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LQIER LIMIT ALL OF INDICATOR LOCATIONS LOCATION illTM HIGHEST ANNUAL MEAN DETECTION MEAN (F)
NAME MEAN (F)
(LLD)
RANGE DISTANCE AND DIRECTION RANGE SEE NOTE 1
SEE NOTE 2 SEE NOTE 2 CONTROL LOCATIONS MEAN (F)
RANGE SEE HOTE 2 NUMBER OF NONROUT INE REPORTED MEASUREMENTS GAMMA SCAH (GELI) 2 K-40 1.50E+02 1.32E+03(
1/
- 1) 7 MILES HNQ 1.32E+03-1.32E+03 1.32E+03(
1/
1) 6.68E+02(
1/
1) 1.32E+03-1.32E+03 6.68E+02-6.68E+02 NOTE:
1.
HOMINAL LQ!ER LIMIT OF DETECTIOH (LLD) AS DESCRIBED IH TABLE E 1
~
NOTE:
2.
MEAN AND RAHGE BASED UPON DETECTABLE MEASUREMENTS ONLY-FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATEO IH PARENTHESES (F) ~
TENHESSEE VALLEY AUTHORITY TECHNICAL PROGRAMS ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUHENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN CABBAGE 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:
1993 TYPE AND TOTAL NUMBER OF ANAL'YSIS PERFORMED LOWER LIMIT ALL OF INDICATOR LOCATIONS LOCATION WITH H!GHEST 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 MEAH (F)
RANGE SEE HOTE 2 NUMBER OF NONROUTINE REPORTED MEASUREMENTS GAMMA SCAN (GELI) 2 K-40 1.50E+02 1.95E+03(
1/
- 1) 2 MILES NNW 1.95E+03-1.95E+03 1.95E+03(
1/
'I) 1.98E+03(
1/
1) 1.95Et03-1.95E+03 1.98E+03-1.98E+03 NOTE:
1.
NOMINAL LOWER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1 NOTE:
2.
HEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY.
FRACTION OF DETECTABLE HEASUREHEN'IS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).
TENNESSEE VALLEY AUTHORITY TECHHICAL PROGRAMS ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUMEHTATIOH WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IH CORN PCI/KG - 0.037 BQ/KG (WET WT)
HAME OF FACILITY: BROWHS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIMESTONE ALABAMA DOCKET HO.:
50-259,260,296 REPORTING PERIOD:
1993 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT ALL OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN DETECTION MEAN (F)
NAME MEAN (F)
(LLD)
RANGE DISTANCE AND DIRECTION RANGE SEE NOTE 1
SEE NOTE 2 SEE NOTE 2 CON'IROL LOCATIOHS MEAN (F)
RANGE SEE NOTE 2 NUMBER OF HOHROUI'N E REPORTED MEASUREMEH'TS GAMMA SCAN (GELI)
K-40 1.50E+02 1.75E+03(
1/
- 1) 7 MILES HHW 1.75E+03-1-75E+03 1.75E+03(
1/
1) 4.85E+03(
1/
1) 1.75E+03-1.75E+03 4.85E+03-4.85Et03 NOTE:
1 ~
NOMINAL LOWER LIMIT OF DETECT'IOH (LLD) AS DESCRIBED IH TABLE E-1 NOTE:
2.
MEAN AHD RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY-FRACTION OF DETECT'ABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IH PARENTHESES (F).
TENNESSEE VALLEY AUTHORITY TECHNICAL PROGRAMS ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUHENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN POTATOES PCI/KG - 0.037 BQ/KG (WET WT)
NAME OF FACILITY: BROWNS FERRY HUCLEAR PLANT LOCATION OF FACILITY: LIMESTONE ALABAMA DOCKET NO.:
50-259,260,296 REPORTING PERIOD:
1993 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT ALL OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN DETECTION MEAN (F)
NAME MEAN (F)
(LLD)
RANGE DISTANCE AND DIRECTION RANGE SEE NOTE 1
SEE NOTE 2 SEE NOTE 2 CONTROL LOCATIONS HEAN (F)
RANGE SEE NOTE 2 NUHBER OF NONROU'IINE REPORTED HEASUREHENTS GAMMA SCAN (GELI) 2 K-40 1.50E+02 3.70E+03(
1/
'I) 2 MILES NNW 3.70E+03-3.70E+03 3.70E+03(
1/
1) 7.31E+03(
1/
1) 3.TOE+03-3.70E+03 7.31E+03-7.31E+03 I
Ln I
NOTE:
1.
NOMINAL LOWER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1 NOTE 2
MEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY.
FRACTION OF DETECTABLE MEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) ~
TENNESSEE VALLE THORITY TECHNICAL PROGRAMS ENVIRONMENTAL RADIOLOGICAL HONITORING AND INSTRUHENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN TOMATOES PCI/KG - 0.037 BQ/KG (WET IF)
NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIMESTONE ALABAMA DOCKET NO.:
50-259,260,296 REPORTING PERIOD:
1993 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT ALL OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN DETECTION MEAN (F)
NAME MEAN (F)
(LLD)
RANGE DISTANCE AND DIRECTION RANGE SEE NOTE 1
SEE NOTE 2 SEE NOTE 2 CONTROL LOCATIONS MEAN (F)
RANGE SEE NOTE 2 NUMBER OF NONROUTINE REPORTED HEASUREMENTS GAMMA SCAN (GELI) 2 K-40 1.50E+02 2.47E+03(
1/
- 1) 2 MILES N 2.47E+03-2.47E+03 2.47E+03(
1/
1) 1.91E+03(
1/
1) 2.47E+03-2.47E+03 1.91Et03-1.91Et03 NOTE:
1.
NOMIHAL LOWER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1.
NOTE:
2.
MEAN AND RANGE BASED UPON DETECTABLE HEASUREMENTS OHLY.
FRACTION OF DETECTABLE HEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) ~
TEHHESSEE VALLEY AUTHORITY TECHNICAL PROGRAMS ENVIRONMENTAL RADIOLOGICAL MONITORING AHD INSTRUMEN'TATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IH SURFACE WATER(Total)
PCI/L - 0.037 BQ/L NAME OF FACILITY: BROWHS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIMESTONE ALABAMA DOCKET NO.:
50.259,260,296 REPORTING PERIOD:
1993 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT ALL OF INDICATOR LOCATIONS LOCATION WITH HIGHEST AHHUAL 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 NDNROUTINE REPORTED MEASUREMENTS GROSS BETA 39 1.70E+00 2.55E+00(
20/
26)
TRM 285.2 1.91E+00-5.37E+00 2.83E+00(
9/
13) 2.32E+00(
11/
13) 1.91E+00-5.37E+00 1.86E+00-2.74E+00 GAMMA SCAN (GELI) 39 BI-214 SR 89 12 SR 90 12 TR ITIUM 12 2.DOE+01 2.98E+01(
2/
26)
TRM 293.5 2.77E+01-3 ~ 19E+01 3.DOE+00 8 VALUES < I.LD 1.40E+00 8 VALUES < LLD 2.50E+02 3.61E+02(
1/
8)
TRM 285.2 3.61Et02-3.61E+02 3.19E+01(
1/
13) 13 VALUES < LLD 3.19E+01-3.19E+01 4 VALUES < LLD 4 VALUES < LLD 3.61E+02(
1/
4) 4 VALUES < LLD 3.61E+02-3.61E+02 NOTE:
1.
HOMINAL LOWER LIMIT OF DETECTIOH (LLD) AS DESCRIBED IN TABLE E-1
~
NOTE:
2.
MEAN AND RANGE BASED UPON DETECTABLE MEASUREMEHTS OHLY.
FRACTION OF DETECTABLE MEASUREMEHTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).
TENNESSEE VALLEY THORITY TECHNICAL PROGRAMS ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATION 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 ALABAMA DOCKET NO.:
50.259,260,296 REPORTIHG PERIOD:
1993 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT ALL OF INDICATOR LOCATIONS LOCATION 'WITH HIGHEST ANNUAL MEAN DETECTION MEAN (F)
NAME MEAN (F)
(LLD)
RANGE DISTANCE AND DIRECTION RANGE SEE NOTE 1
SEE NOTE 2 SEE NOTE 2 CONTROL LOCATIONS MEAN (F)
RANGE SEE NOTE 2 NUMBER OF NONROUTIHE REPORTED MEASUREMENTS GROSS BETA GAMMA SCAN (GELI)
.77 SR 89 24 1.70E+00
?.35E+00(
44/
51)
FLORENCE, AL 1.83E+00-3.96E+00 TRM 259.8 3.00E+00 5'I VALUES < LLD 2.46E+00(
11/
13) 2.31E+00(
19/
26) 1.83E+00-3.96E+00 1.76E+00- 3.17E+00 26 VALUES < LLD I
SR 90 I
TRITIUM 3.DOE+00 16 VALUES < LLD 24 1.40E<00 16 VALUES < LLD 24 2.50E+02 16 VALUES < LLD 8 VALUES < LLD 8 VALUES < LLD 8 VALUES < LLD NOTE:
1.
NOMINAL LOWER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1 NOTE:
2.
MEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY.
FRACTION OF DETECTABLE HEASUREMEHTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) ~
TENNESSEE VALLEY AUtHORITY TECHNICAL PROGRAMS ENVIRONMENT'AL RADIOLOGICAL MONITORING AND INSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN WELL WATER(Total)
PCI/L - 0.037 BQ/L NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT LOCA'IION OF FACILITY LIMESTONE ALABAMA DOCKET NO.:
50-259,260,296 REPORTING PERIOD:
1993 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT ALL OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL HEAN DETECTION MEAN (F)
NAME MEAN (F)
(LLD)
RANGE DISTANCE AND DIRECTION RANGE SEE NOTE 1
SEE NOTE 2 SEE NOTE 2 CONTROL LOCATIONS MEAN (F)
RANGE SEE NOTE 2 NUMBER OF NONROUTIHE REPORTED MEASUREMENTS GAMMA SCAH (GELI) 26 Bl-214 PB-214 SR 89 2.DOE+01 3.51E+01(
1/
13)
BFH WELL ¹6 3.51E+01-3.51E+01 0.02 MILES W 2.DOE+01 2.88E+01(
1/
13)
BFH WELL ¹6 2.88E+01-2.88E+01 0.02 MILES W 3.51E+01(
1/
13) 2.69E+02(
13/
13) 3.51E+01-3.51E+01
'l.33E+02-5.19E+02 2.88E+01(
1/
13) 2.66E+02(
13/
13) 2.88Et01-2.88E+01 1.35E+02-5.26E+02 SR 90 TRITIUH 8
3.DOE+00 4 VALUES < LLD 8
1.40E+00 4 VALUES < LLD 2.50E+02 4 VALUES < LLD 4 VALUES < LLD 4 VALUES < LLD 4 VALUES < LLD NOTE:
1.
NOMINAL LOWER LIMIT OF DETECTION (LLD) AS DESCRIBED IH TABLE E-1.
NOTE:
2.
MEAN AND RANGE BASED UPON DETECTABLE MEASUREHENTS ONLY.
FRACTIOH OF DETECTABLE HEASUREMEN'IS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).
TENNESSEE VALLEY TMORITY TECHNICAL PROGRAMS ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN CRAPPIE FLESH PCI/GM - 0.037 BQ/G (DRY WEIGHT)
NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIMESTONE ALABAMA DOCKET NO.:
50-259,260,296 REPOR'TING PERIOD:
1993 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 RAHGE SEE NOTE 1
SEE NOTE 2 SEE NOTE 2 CONTROL LOCATIONS MEAN (F)
RANGE SEE NOTE 2 NUMBER OF NONROUTINE REPORTED MEASUREMENTS GAMMA SCAH (GELI) 4 Bl-214 CS-137 K-40 1.20E-01 6.00E-02 1 AB ODE+00 1.23E-01(
1/
- 2) WHEELER RES 1.23E 1.23E-01 TRH 275-349 8.97E-02(
1/
2/
- 2) WHEELER RES 1.36E+01-1 '0E+01 TRH 275-349 1.23E-01(
1/
2)
'1.49E-0 I(
1/
2) 1.23E 1.23E-01 1.49E 1.49E-01 8.97E-02(
1/
2) 8.24E-02(
2/
2) 8.97E 8.97E-02 7.58E 8.90E-02 1.43E<01(
2/
2) 1.60E+01(
2/
2) 1.36Et01-1.50E+01 1.47E+01-1.72E+01 NOTE:
1.
NOMIHAL LOWER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1
~
NOTE:
2.
MEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY'RACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) ~
TENNESSEE VALLEY AUTKORITY TECHNICAL PROGRAMS ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IH SMALLMOUTH BUFFALO FLESH PCI/GM - 0.037 BQ/G (DRY WEIGNI')
NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIMES'TONE ALABAMA DOCKET NO.:
50-259,260,296 REPORTING PERIOD:
1993 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT ALL OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN DETECTION MEAN (F)
NAME MEAN (F)
(LLD)
RANGE DISTANCE AND DIRECTIOH RANGE SEE NOTE 1
SEE NOTE 2 SEE NOTE 2 CONTROL LOCATIONS MEAN (F)
RANGE SEE NOTE 2 NUMBER OF NONROUT INE REPORTED MEASUREMENTS GAMMA SCAN (GELI) 4 K-40 1.DOE+00 1.22E+01(
2/
2)
WHEELER RES 1.14E+01-1.30E+01 TRH 275-349 1 '2E+01(
2/
2) 9.44E+00(
2/
2) 1.14E+01-1.30E+01 8.97E+00-9.91E+00 NOTE:
1 ~
NOMIHAL LOWER LIMIT OF DE'TECTION (LLD) AS DESCRIBED IN TABLE E-1 NOTE:
2.
MEAN AND RANGE BASED UPON DETECTABLE HEASUREHENTS ONLY.
FRACTION OF DETECTABLE MEASUREMEHTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) ~
TENNESSEE VALLEY AUTHORITY TECHNICAL PROGRAHS ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN SMALLMOUTH BUFFALO WKOLE PCI/GH - 0.037 BO/G (DRY WEIGHT)
NAME OF FACILITY: BROWNS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIMESTONE ALABAMA DOCKET NO.:
50-259,260,296 REPORTING PERIOD:
1993 TYPE AND TOTAL NUHBER OF ANALYSIS PERFORHED LOWER LIMIT ALL OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN DETECTION MEAN (F)
NAME MEAN (F)
(LLD)
RANGE DISTANCE AND DIRECTION RANGE SEE NOTE 1
SEE NOTE 2 SEE NOTE 2 CONTROL LOCATIONS HEAN (F)
RANGE SEE NOTE 2 NUHBER OF NONROUTINE REPORTED MEASUREMENTS GAMMA SCAN (GELI) 4 K-40 1.DOE+00 5 '9E+00(
2/
- 2) WHEELER RES 4.87E+00- 6.30E+00 TRH 275-349 5.59E+00(
2/
2) 6.11E+00(
2/
2) 4.87E+00-6.30E+00 5.33E+00-6.89E+00 NOTE:
1 ~ HOMINAL LOWER LIMIT OF DETECTIOH (LLD) AS DESCRIBED IN TABLE E-'I NOTE:
2.
MEAH AND RANGE BASED UPON DETECTABLE MEASUREHEHTS ONLY.
FRACTION OF DETECTABLE MEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATED IH PARENTHESES (F).
TENNESSEE VALLEY AUTHORITY TECHNICAL PROGRAMS ENVIRONMENTAL RADIOLOGICAL HONITORING AND INSTRUHENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN SEDIMENT PCI/GH - 0.037 BQ/G (DRY WEIGHT)
NAME OF FACILITY: BROWS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIMESTONE ALABAMA DOCKET NO.:
50-259,260,296 REPORTING PERIOD:
1993 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT ALL OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN DETECTION MEAN (F)
NAME HEAN (F)
(LLD)
RANGE DISTANCE AND DIRECTIOH RANGE SEE NOTE 1
SEE HO'IE 2 SEE NOTE 2 CONTROL LOCATIONS HEAN (F)
RANGE SEE NOTE 2 NUHBER OF NONROU'TINE REPORTED HEASUREHENTS GAMMA SCAN (GELI) 10 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 ZN-65 SR 89 1.00E-01 1.00E.01 2.50E-01 4.00E-02 1.00E-02 1.00E-02 1.00E-02 2 ~ OOE-01 2.00E-02 2.00E-02 3.00E-01 5 ~ OOE-02 2.00E-02 1.00E-02 1.45E+00(
5 '2E 2.76E-01(
2.76E 1.54E+00(
6.56E 1.21E+00(
4.11E 1.54E-01(
1.87E 1.72E-02(
1.67E - 5.77E-01(
6.33E 1.24E+01(
1.42E+00-1.36E+00(
5.19E 1.32E+00(
4.42E 1.48E+00(
6.22E 1.21E+00(
4.11E-O'I-4.71E-01(
1.74E 6.10E-02(
6.10E 7/
7) 2.32E+00
'I/
7) 2.76E-01 7/
7) 2.45E+00 7/
7) 1.e2E+oo 7/
7) 5.41E-01 2/
7) 1.78E-02 7/
7) 1.03E+00 7/
7) 1.70E+01 7/
7) 2.16E+00 7/
7) 2.02E+00 7/
7) 2.37E+00 7/
7) 1.82E+00 7/
7) 7.68E-01 1/
7) 6.10E-02 TRH 293.7 BFN DISCHARGE TRM 288.78 TRH 277.98 TRM 293.7 BFN DISCHARGE TRH 288.78 TRM 293.7 BFN DISCHARGE TRH 293.7 BFH DISCHARGE TRH 288.78 TRH 293.7 BFN DISCHARGE TRM 293.7 BFN DISCHARGE TRH 277.98 TRM 293.7 BFN DISCHARGE TRH 293.7 BFN DISCHARGE TRH 288.78 1.46E+00(
1.44E+00-2.76E-Oi(
2.76E 1.55E+00(
6.56E 1.29E+00(
1.21E+00-2.96E-01(
5.19E 1.78E-02(
1.78E 6.38E-01(
5.90E 1.44E+01(
1.44E+01-1.40E+00(
1.37E+00-1.39E+00(
1.29E+00-1 ~ 50E+00(
6.22E 1.29E+00(
1.21E+00-4.85E-01(
4.70E 6.10E-02(
6.10E 3/
3) 1.47E+00 1/
2) 2.76E-01 2/
2) 2.45E+00 3/
3) 1.45E+00 2/
2) 5.41E-01 1/
3) 1.78E-02 3/
3) 6.74E-01 2/
2) 1.45E+01 3/
3) 1.44E+00 3/
3) 1.57E+00 2/
2) 2.37E+00 3/
3) 1.45E+00 3/
3) 5.02E.01 1/
2) 6.10E-02 1.34E+00(
3/
3) 1.28E+00-1.43E+00 3 VALUES < LLD 1.48E+00(
3/
3) 1.41E+00-1 '7E+00 1.13Etoo(
3/
3) 9.57E 1.29E+00 3 VALUES < LLD 3 VALUES < LLD 1.22E-01(
3/
3) 4.87E 1.60E-01 1.36E+01(
3/
3) 1.23E+01-1.60E+01 1.29E+00(
3/
3) 1 '6E+00-1.36E+00 1.21E+00(
3/
3) 1.06E+00-1.34E+00 1.46E+00(
3/
3) 1 '0E+00-1.59E+00 1.13E+00(
3/
3) 9.57E 1.29E+00 4.56E-01(
3/
3) 4.06E 4.89E-01 3 VALUES < LLD 1.DOE+00 6 VALUES < LLD 3 VALUES < LLD NOTE:
1.
NOMINAL LOWER LIHIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1 NOTE:
2.
MEAN AND RANGE BASED UPON DETECTABLE HEASUREMENTS ONLY'RACTION OF DETECTABLE HEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) ~
TENNESSEE VALLE THORITY TECHNICAL PROGRAMS ENVIROHHENTAL RADIOLOGICAL HONITORIHG AHD INSTRUMEHTATIOH IIESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IH BED IHEHT PCI/GH - 0.037 BQ/G (DRY HEIGHT)
HAHE OF FACILITY: BROWS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIMESTONE ALABAMA DOCKET NO.:
50-259,260,296 REPORTING PERIOD:
1993 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LONER LIHIT ALL OF INDICATOR LOCATIONS LOCATION IIITH HIGHEST'HHUAL MEAN DETECTION HEAH (F)
HAHE HEAH (F)
(LLD)
RANGE DISTANCE AND DIRECTION RANGE SEE NOTE 1
SEE NOTE 2 SEE NOTE 2 CONTROL LOCATIONS HEAH (F)
RANGE SEE NOTE 2 HUHBER OF HONROUTIHE REPORTED HEASUREHENTS SR 90 9
3.00E-01 6 VALUES c LLD 3 VALUES c LLD NOTE:
1.
NOMINAL LOWER LIHIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1
~
NOTE:
2.
MEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY.
FRACTION OF DETECTABLE HEASUREHEHTS AT SPECIFIED LOCATIONS IS IHDICATED IN PARENTHESES (F).
A 0
ft C
OP
TENNESSEE VALLE THORITY TECHNICAL PROGRAHS ENVIRONMENTAL RADIOLOGICAL HONITORING AND INSTRUHENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IH CLAN FLESH PCI/GH - 0.037 BQ/G (DRY WEIGHT)
NAHE OF FACILITY: BROWNS FERRY NUCLEAR PLANT LOCATION OF FACILITY: LIHESTONE ALABAHA DOCKET NO.:
50-259,260,296 REPORTING PERIOD:
1993 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORHED LOWER LIHIT ALL OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL HEAN 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 NUHBER OF NONROU'IINE REPORTED HEASUREHENTS GAHHA SCAN (GELI)
Bl-214 K-40 PB-214 2.50E-01 2.00E+00 2.50E-01 7.37E-01(
2/
2)
DOWNSTREAH LOCATION 5.51E 9.23E-01 DOWNSTREAH 2.34E+00(
1/
2)
DOWNSTREAH LOCATION 2.34E+00-2.34E+00 DOWNSTREAH 7.83E-01(
'I/
2)
DOWNSTREAH LOCATION 7.83E 7.83E-01 DOWNSTREAH 7.37E-01(
2/
2) 3.40E-01(
1/
2) 5.51E 9.23E-01 3.40E 3.40E-01 2.34E+00(
1/
2) 2.84E+00(
1/
2) 2.34E+00-2.34E+00 2.84E+00-2.84E+00 7.83E-01(
1/
2) 4.89E-01(
1/
2) 7.83E 7.83E-01 4.89E 4.89E-01 NOTE:
1.
NOHINAL LOWER LIHIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1
~
NOTE:
2.
HEAN AND RANGE BASED UPON DETECTABLE KEASUREHEHTS ONLY'RACTION OF DETECTABLE HEASUREHENTS AT SPECIFIEO LOCATIONS IS INDICATED IN PARENTHESES (F).
Direct Radiation Levels Browns Ferry Nuclear Plant 24 22 e
20 18 16 E
14 12 10 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 Year/Quarter
+ On-Site
-z-Off-Site
Direct Radiation Levels Four Quarter Moving Average 22 20
~
18 g) 16 E
14 12 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 Year/Quarter On-Site
-+
Off-Site Browns Ferry Nuclear Plant
Direct Radiation Levels Watts Bar Nuclear Plant 24 22 0
20 (3
18 C
CO E
16 E
14 12 77 78 79 80 81 82 83 84'5 86 87 88 89 90 91 92 93 Year/Quarter
+ On-Site
-+ Off-Site
Direct Radiation Levels Four Quarter Moving Average 24 22 20 (3
18 M
E 16 P
E 14
~~ ~ ~~>~~A, 12 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 Year/Quarter
+ On-Site + Off-Site Watts Bar Nuclear Plant
Annual Average Gross Beta Activity AirFilters (pCi/Cubic Meter) 0.25 0.2 Initialplant operation in August 1973.
0.15 O
O 0.1 O
0.05 Preoperational Average 0
68 70 72 73o 75 77 79 81 83 85 87 89 91 93 69 71 73p 74 76 78 80 82 84 86 88 90 92 Year Browns Ferry Nuclear Plant Indicator E3 Control
Annual Average:- Sr-90 in Milk 20 Initialplant operation in August 1973.
15 68 70 72 73o 75 77 79 81 83 85 87 89 91 93 69 71 73p 74 76 78 80 82 84 86 88 90 92 Year
~ Indicator w Control Preoperational Average Browns Ferry Nuclear Plant
Annual Average: -Cs-'i 37 in Soil 2.5 Initialplant operation in August 1973.
E co
$.5 O
0.5 68 70 72 73o 75 77 79 81 83 85 87 89 91 93 69 71 73p 74 76 78 80 82 84 86 88 90 92 Year
~ Indicator
~ Control Preoperational Average Browns Ferry Nuclear Plant Note: Detector system changed from Nal to GcLi in 1977.
Annual Average Gross Beta Activity Surface Water, pCilLiter Initialplant operation in August, 1973.
L C3 CL 68 69 70 71 72 73p73o 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 SO 91 92 93 Year
~ Indicator
-> Control Preoperational Average Browns Ferry Nuclear Plant Note: No gross beta measurements were made in 1978.
Annual Average Gross Beta Activity Drinking Water, pCi/Liter Iuitialplaut operatiou iu August 1973.
4 OO.
68 69 70 71 72 73p73o 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 Year
~ Indicator
+- Control Preoperational Average Browns Ferry Nuclear Plant
Annual Average Cs-137 in Fish: Crappie 0.5 Initialplant operation in August 1973.
04 Z
E 03
- o. 0.2 0.1 69 70 71 72 73p73o 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 Year
~ Downstream z Upstream Preoperational Average Browns Ferry Nuclear Plant Note: Detector system changed from Nal to GeLi in 1978.
Annual Average Cs-137 in Fish: Smallmouth Buffalo, Flesh 0.25 0.2 Initialplant operation in August 1973.
E 015 o.
0.1 0.05 69 70 71 72 73p73o 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 Year
~ Downstream
-a Upstream Preoperational Average Browns Ferry Nuclear Plant Note: Detector system changed from Nal to GeLi in 1978.
Annual Average Cs-137 in Fish: Smallmouth Buffalo, Whole 0.14 0.12 Initialplant operation in August 1973.
0.1 0.08 0.06 0.04 0.02 69 70 71 72 73p73o 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 Year
~ Downstream
~ Upstream Preoperational Average Browns Ferry Nuclear Plant Note: Detector system changed from Nal to GeLi in 1978.
Annual Average Cs-137 in Sediment Initial plant operation in August 1973.
-0 69 70 71 72 73p73o 74 75 76 77 78 79 80 8'i 82 83 84 85 86 87 88 89 90 91 92 93 Year
~ Downstream w Upstream Preoperational Average Browns Ferry Nuclear Plant Note: Detector system changed from Nal to GeLi in 1977.
Annual Average Co-60 in Sediment 0.8 Initialplant operation in August 1973.
0.6 El6n 0.4 (3
0.2 69 70 71 72 73p73o 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 Year
~ Downstream
~ Upstream Preoperational Average Browns Ferry Nuclear Plant Note: Detector system changed from NaI to GeLi in 1977.
ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS 1~
2 g AND 3 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT