ML20246B393
| ML20246B393 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 12/31/1988 |
| From: | Fox C TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8905090036 | |
| Download: ML20246B393 (117) | |
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i TENNESSEE VALLEY AUTHORITY ;
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l ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT l
SEQUOYAH NUCLEAR PLANT 1988 l
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RADIOLOGICAL CONTROL
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ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ,
SEQUOYAH NUCLEAR PLANT ,
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1 TENNESSEE VALLEY AUTHORITY l l
NUCLEAR ASSURANCE AND SERVICES I RADIOLOGICAL CONTROL April 1989
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i TABLE OF CONTENTS ,
I Table of Contents . . . . . . . . . . . . . . . . . . . . . . . . . 11 List of Tables .......................... iv List of Figures . . . . . . . . . . . . . . . . . . . . . . . . . . v Executive Summary . . . . . . . . . . . . . . . . . . . . . . . . . 1 Introduction ........................... 2 Naturally Occurring and Background Radioactivity . . . . . . . . 2 Electric Power Production ................... 5 Site / Plant Description ...................... 8 Environmental Radiological Monitoring Program . .......... 10 Direct Radiation Monitoring . . . . . . . . . . . . . . . . . . . . 14 ;
Measurement Techniques . . . . . . . . . . . . . . . . . . . . . 14 l Results ............................ 15 i Atmospheric Monitoring
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...... ............... 18 i Sample Collection and Analysis . . . . . . . . . . . . . . . . . 18 Results ............................ 20 Terrestrial Monitoring ...................... 21 Sample Collection and Analysis . . . . . . . . . . . . . . . . . 21 Results ............................ 23 Aquatic Monitoring ........................ 25 Sample Collection and Analysis . . . . . . . . . . . . . . . . . 25 Results ..... .... .... ............ 27 Assessment and Evaluation . . . . . . . . . . . . . . . . . . . . . 30 Results ............................ 31 Conclusions .......................... 32 References ....
....................... 36 Appendix A Environmental Radiological Monitoring Program and Sampling Locations ..... ............ 39 Appendix B 1988 Program Modifications .............. 51 1
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Appendix C Missed Samples and Analyses . . . . . ........ 54 Appendix 0 Analytical Procedures . . . . . . . ........ 58 Appendix E Nominal Lower Limits of Detection (LLD) . ...... 61 Appendlx F Quality Assurance / Quality Control Program . . . . . . . 66 Appendix G Land Use Survey . . . . . . . . . . . ........ 76 Appendix H Data Tables . . . . . . . . . . . . . . . . . . . . . . 82 1
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LIST OF TABLES Table 1 Maximum Permissible Concentrations for Nonoccupational Exposure . . . . . . . . . . . . . . . . 34 1
Table 2 Maximum Dose Due to Radioactive Effluent Releases . . . . . . . . . . . . . . . . . . . . . . . . 35 i
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LIST Or FIGURES i
Figure 1 Tennessee Valley Region . . . . . . . . . . . . . . . . . 37 Figure 2 Environmental Exposure Pathways of Man Due . . . . . . . 38 to Releases of Radioactive Materials to the Atmosphere and Lake
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EXECUTIVE
SUMMARY
This report describes'the environmental radiological monitoring program conducted by TVA in the vicinity of the Sequoyah Nuclear Plant in 1988.
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 operati'ons. Station i 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, soll, fish, sediment, and direct radiation levels. Results-from stations f 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 materirls commonly found in the environment as a result of atmospheric nuclear weapons fallout. Small amounts of Co-60 were found in sediment samples downstream from the plant. This activity in stream sediment-would result in no measurable increase over background in the dose to the.
general public.
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l INTRODUCTION' q
This report describes and summarizes a huge volume of data, the results of I W
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- many thousands of measurements and laboratory analyses. The measurements are ,I i
made.to comply with regulations and to determine potential effects on pubile.
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health and safety. This report is prepared annually in partial fulfillment of the requirements of the plant operating license. 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 .l data are included which may be useful or interesting to individuals ~who do not work with this material routinely. I J
Naturally Occurring and Background Radioactivity All 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,.1s-one of the major types of radioactive materials found naturally in our:
environment. An individual weighing 150 pounds contains about 140 grams of potassium (reference 1). This is equivalent to approximately 100,000 pCi of 'f
.i K-40 which delivers a dose of 15 to 20 mrem per year to the bone and soft {
l tissue of the body. Naturally occurring radioactive materials have-always- )
I been in our environment. 0ther examples of naturally occurring radioactive materials are uraninum-238, uranium-235, thorium-234, radium-226, radon-222, 3
carbon-14, and hydrogen-3 (generally. called tritium). These naturally. l I
occurring radioactive materials are in the soil, our food, our drinking water,
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and our bodies, q
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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 fadiation) is about 27 mrem / year. This essentially doubles with each 6600-foot increase in altitude in the lower l 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 l 1
materials within each individual's body. We absorb these materials from the I food we eat which contains naturally occurring radioactive materials from the soll. An example of this is K-40 as described above. Even building materials affect the natural background radiation levels in the environment. Living or working in a building which is largely made of earthen material, such as concrete or brick, will generally result in a higher natural background radiation level than would exist if the same structure were made of wood.
This is due to the naturally occurring radioisotopes in the concrete or brick, such as trace amounts of uranium, radium, thorium, etc.
Because the city of Denver, Colorado, is over 5000 feet in altitude and the soll and rocks there contain more radioactive material than the U.S; average,
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l 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 l
natural background radiation dose equivalent, primarily because of the greater t \
quantity of radioactive materials in the soll and rocks in those locations. j 1
Scientists have never been able to show that these-levels of radiation have~
cause'd physical harm to anyone.
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It is possible to get an idea of the relative hazard of different types.of radiation sources by evaluating the amount of radiation the U.S. population j 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 Millirem / Year Per Person s
Natural background dose equivalent Cosmic 27 Cosmogenic 1 Terrestrial 28 In the body 39 Radon 200 Total 295 Release of radioactive material in 5 natural gas, mining, milling, etc.
Medical (effective dose equivalent) 53 Nuclear weapons fallout less than't Nuclear energy 0.28 i Consumer products 0.03 Total 355 (approximately) 4 4
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As can be seen from the table, natural background radiation dose equivalent to the U.S. population normally exceeds that from nuclear plants by several hundred times. This indicates that nuclear plant operations normally result in a population radiation dose equivalent which is insignificant compared to that which results from natural background radiation. It should be noted that the use of radiation and radioactive materials for medical uses has resulted i
in a similar effective dose equivalent to the U.S. population as that caused 1 by natural background radiation.
l Significant discussion recently has centered around exposures from radon. ,
1 Radon is an inert gas given off as a result of the decay of naturally occurring radium-226 in soil. When dispersed in the atmosphere, radon concentrations are relatively low. However, when the gas is trapped in closed spaces, it can build up until concentrations become significant. The National Council of Radiation Protection and Measurements (reference 2) has estimated that the average annual effective dose equivalent from radon in the United States is approximately 200 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.
-m However, nuclear plants require many complex systems to control the nuclear l 1
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 reieased into the plant systems. This radioactive material can be transported throughout plant systems and some of it released to the environment.
t All paths through which radioactivity is released are monitored. Liquid and )
i gaseous effluent monitors record the radiation levels for each release.- These I monitors also provide alarming mechanisms to allow for termination of any q
release above limits. 4 l
Releases are nonitored at the onsite points of release and through -an environmental monitoring program which measures the environmental radiation in outlying areas around the plant. In this way, not only is the release of radioactive materials from the plant tightly controlled, but measurements are made in surrounding areas to ensure that the population is not being exposed to significant levels of radiation or radioactive materials.
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> Plant Technical Specifications limit the release of radioactive effluents, as l well as offsite doses due to the release of these effluents.. Additional !
' limits are set by the Environmental Protection Agency (EPA) for doses to the i
public.
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l The dose to a member of the general public from radioactive materials released <
to unrestricted areas, as given in the Technical Specifications for each unit, l are limited to the following: i Liquid Effluents i 9
Total body 13 mrem / year per unit j Any organ 110 mrem / year per unit Gaseous Effluents !
Noble gases: ;
Gamma radiation 110 mrad / year per unit l Beta radiation 120 mrad / year per unit Particulate: !
Any organ 115 mrem / year per unit l l
The EPA limits for the total dose to the public in the vicinity of a nuclear power plant, established in the Environmental Dose Standard of 40 CFR 190, are as follows.
l Total body 25 mrem / year Thyroid 75 mrem / year Any other organ 25 mrem / year i
In addition, 10 CFR 20.106 provides maximum permissible concentrations (MPCs) l for radioactive materials released to unrestricted areas. HPCs for the principal radionuclides associated with nuclear power plant effluents are ,
presented in table 1. I l l
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SITE / PLANT DESCRIPTION l l
-The Sequoyah Nuclear Plant (SQN) is icicated on a site near the geographical center of Hamilton county, Tennessee, on a peninsula on the western shore of Chickamauga Lake at Tennessee River Mlle (TRM) 484.5. Figure 1 shows the site in relation to other TVA projects. The SQN site, containing approximately 525
. acres, is approximately 7.5 miles northeast of the nearest city limit of Chattanooga, Tennessee, 14 miles west-northwest of Cleveland, Tennessee, and approximately 31 miles south-southwest of TVA's Watts Bar Nuclear Plant (HBN).
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Population is distributed rather unevenly within 10 miles of the SQN site.
Approximately 60 percent of the population is in the general area between 5 and 10 miles from the plant in the sectors ranging from the SSH,. clockwise, to the NH tector. This concentration is a reflection of suburban Chattanooga and the town of Soddy-Daisy. This area is characterized by considerable vacant land witn scattered high quality residential subdivisions. The northern extent of the residential development is approximately 2 miles from the site.
The population of the Chattanooga urbanized area is over 250',000, while Soddy-Daisy has approximately 10,000 people.
l Hith the exception'of.the community of. Soddy-Daisy, the areas west, north, and I
east of the plant are sparsely settled. Development consists of scattered [
i semirural and rural dwellings with associated small-scale farming. At.least j one dairy farm is located within a 10-mile radius of the plant.
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Chickamauga Reservoir is one of a series of highly controlled multiple-use reservoirs whose primary uses are flood control, navigation, and the ,. _
generation of electric power. Secondary uses include industrial and public water supply and waste disposal, commercial fishing, and recreation. Public ~
access areas, boat docks, and residential subdivisions have been developed along the reservoir shoreline.
The SQN consists of two pressurized water reactors: each unit is rated at "
1171 megawatts (electric 3, Fuel was loaded in unit 1 on March 1, 1980, and the unit achieved critically on July 5, 1980. Fuel was loaded in unit 2 in July 1981, and the unit achieved initial criticality on November 5, 1981. The plant, shut down in August 1985, was restarted in 1988. .
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ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM lhe unique environmental concern associated with a nuclear power plant is its production of radioactive materials and radiation. The vast majority of this radiation and radioactivity is contained within the reactor itself or one of the other plant systems designed to keep the material in the plant. The retention of the materials in each level of control is achieved by system engineering, design, construction, and operation. Environmental monitoring is a final verification that the systems are performing as planned. The monitoring program is designed to check the pathways between the plant and the people in the immediate vicinity and to most efficiently monitor these pathways. Sample types are chosen so that the potential for detection of radioactivity in the environment will be maximized. The environmental radiological monitoring program is outlined in appendix A.
There are two primary pathways by which r:idioactivity can move through the environment to humans: air and water (see figure 2). The air pathway can be separated into two components: the direct (airborne) pathway and the indirect (ground or terrestrial) pathway. The direct airborne pathway consists of direct radiation and inhalation by humans. In the terrestrial pathway, radioactive materials may be deposited on the ground or on plants and subsequently be ingested by animals and/or humans. Human exposure through the liquid pathway may result from drinking water, eating fish, or by direct exposure at the shoreline. The types of samples collected in this program are designed to monitor these pathways.
A number of factors were considered in determining the locations for collecting environmental samples. The locations for the atmospheric monitoring stations were determined from a critical pathway analysis based on weather patterns, dose projections, population distribution, and land use.
Terrestrial sampling stations were selected after reviewing such things as the locations of dairy animals and gardens in conjuction with the air pathway analysis. Liquid pathway stations were selected based on dose projections, water use information, and availability of media such as fish and sediment.
Table A-2 lists the sampling stations and the types of samples collected from each. Modifications made to the program in 1988 are described in appendix B and exceptions to the sampling and analysis schedule are presented in appendix C. To determine the amount of radioactivity in the environment prior to the operation of SQN, a preoperational environmental radiological monitoring program was initiated in 1971 and operated until the plant began operation in 1980. Measurements of the same types of radioactive materials that are measured currently were assessed during the preoperational phase to establish normal background levels for various radionuclides in the environment. This is very important in that during the 1950s, 60s, and 70s, atmospheric nuclear weapons testing occurred which released radioactive material to the environment causing fluctuations in the natural background radiation levels. This radioactive material is the same type as that produced in the SQN reactors. Preoperational knowledge of natural radionuclides patterns in the environment permits a determination, through comparison and trending analyses, of whether the operation of SQN is impacting the environment and thus the surrounding population. The determination of impact during the operating phase also considers the presence of control stations l
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that have been established in the environment. Results of environmental samples taken at control stations (far from the plant) are compared with those from Indicator stations (near the plant) to establish the extent of SQN influence.
All samples are analyzed by the radioanalytical laboratory of TVA's Environmental Radiological Monitoring and Instrumentation Department located at the Western Area Radiological Laboratory (HARL) in Muscle Shoals, Alabama.
All analyses are conducted in accordance with written and approved procedures and are based on accepted methods. A summary of the analysis techniques and methodology is presented in appendix D. Data tables summarizing the sample analysis results are presented in appendix H.
The sophisticated radiation detection devices used to determine the radionuclides content of samples collected in the environment are generally quite sensitive to small amounts of radioactivity. In the field of radiation measurement, the sensitivity of the measurement process is discussed in terms of the lower limit of detection (LLD). A description of the nominal LLDs for the radioanalytical laboratory is presented in appendix E.
The radioanalytical laboratory employs a comprehensive quality assurance /
quality control program to monitor laboratory performance throughout the year. The program is intended to detect any problems in the measurement process as soon as possible so they can be corrected. This program includes equipment checks to ensure that the complex radiation detection devices are working properly and the analysis of special samples which are included
alongside routine environmental samples. A complete description of the program is presented in appendix F.
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DIRECT RADIATION MONITORING l
Direct radiation levels are measured at a number of stations around the plant site. These measurements include contributions from cosmic radiation, radioactivity in the ground, fallout from atmospheric nuclear weapons tests conducted in the past, and any radioactivity that may be present as a result of plant operations. Because of the 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 SQN site in 1988 were consistent with levels from previous years and with levels measured at other locations in the region.
Measurement Techniques Direct radiation measurements are made with thermoluminescent dosimeters (TLDs). When certain materials are exposed to ionizing radiation, many of the electrons which become displaced are trapped in the crystalline structure of the material. They remain trapped for long periods of time as long as the material is not heated. When heated, the electrons are released, along with a pulse of light. A measurement of the intensity of the light is directly l
proportional to the radiation to which the material was exposed. Materials which display these characteristics are used in the manufacture of TLDs.
TVA uses a manganese activated calcium fluoride (Ca2F:Mn) TLD material encased in a glass bulb. The bulb is placed in an energy compensating shield
to correct for energy dependence of the material. TLDs are placed i
approximately 1 meter above the ground, with three TLDs at each station.
l Twenty-two stations are located around the plant near the site boundary, at least one station in each of the 16 sectors. Dosimeters are also placed at the perimeter and remote air monitoring sites and at 22 additional stations out to approximately 10 miles from the site. The TLDs are exchanged every 3 months and read with a Victoreen model 2810 TLD reader. The values are corrected for gamma response, self-irradiation, and fading, with individual gamma response calibrations and self-irradiation factors determined for each l TLD. The system meets or exceeds the performance specifications outlined in l Regulatory Guide 4.13 for environmental applications of TLDs.
l 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 the plant. The second group i
lies between 1 and 2 miles, the third group between 2 and 4 miles, the fourth between 4 and 6 miles, and the fifth group is made up of all stations greater than 6 miles from the plant. Past data have shown that the results frone all l
stations greater than 2 miles from the plant are essentially the same.
Therefore, for purposes of this report, all stations 2 miles or less from the plant are identified as "onsite" stations and all others are considered "offsite."
Prior to 1976, direct radiation measurements in the environment were made with less sensitive dosimeters. Consequently, environmental radiation levels
reported in the preoperational phase of the monitoring program exceed current measurements of backgroand radiation levels. For this reason, data collected
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prior to 1976 are not included in this report.
The quarterly gamma radiation levels determined from the TL0s deployed around SQN in 1988 are given in table H-1. The rounded average annual exposures are shown below. For comparison purposes, the average direct radiation measurements made in the preoperational phase of the monitoring program are also shown.
Annual Average Direct Radiation Levels SQN mR/ year Preoperational 1988 Average Onsite Stations 73 79 Offsite Stations 64 63 The data in table H-1 indicate that the average quarterly radiation levels at the SQN onsite stations are approximately 2-3 mR/ quarter higher than levels at the offsite stations. This difference is also noted in the preoperational phase and in the stations at HBN and other nonoperating TVA nuclear power plant construction sites where the average levels onsite are generally 2-6 mR/ quarter higher than levels offsite. The causes of these differences have not been isolated; however, it is postulated that the differences are probably attributable to combinations of influences such as natural variations in environmental radiation levels, earth-moving activities onsite, and the mass
of concrete employed in the construction of the plant. Other undetermined intluences may also play a part.
Figure H-1 compares plots of the data from the onsite or site boundary stations with those from the offsite stations over the period from 1976 through 1988. To reduce the 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 smoothed considerably.
All results reported in 1988 are consistent with direct radiation levels identified at locations which are not influenced by the operation of SQN.
There is no indication that SQN operations increased the background radiation levels normally observed in the areas surrounding the plant.
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ATMOSPHERIC MONITORING The atmospheric monitoring network is divided into three groups identified as .
local, perimeter, and remote. Four local air monitoring stations are located on or adjacent to the plant site in the general areas of greatest wind frequency. Four perimeter air monitoring stations are located in communities out to about 10 miles from the plant, and four remote air monitors are located out to 20 miles. The monitoring program and the locations of monitoring stations are identified in the tables and figures of appendix A. The remote stations are used as control or baseline :tations.
1 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 SQN.
Sam1 1 e Collection and Analysis Air particulate 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 o passing through the filter. This system is housed in a building approximately i
2 feet by 3 feet by 4 feet. The filter is contained in a sampliag head l
mounted on the outside of the monitor building. The filter is replaced every 7 days. Each filter is analyzed for gross beta activity about 3 days after collection to allow time for the radon daughters to decay. Every 4 weeks composites of the filters from each location are analyzed by gamma spectroscopy. On a quarterly basis, all of the filters from one location are composited and analyzed for Sr-89,90.
Gaseous radiolodine 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. If activity above a specified limit is detected, a complete gamma spectroscopy analysis is performed.
Rainwater is collected by use of a collection tray attached to the monitor 1
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 containers inside the monitor building. A l-gallon sample is removed from the container every 4 weeks. Ary excess water is discarded. Rainwater 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. No rainwater sanples from SQN were analyzed in this reporting period.
Results The results from the analysis of air particulate samples are summarized in table H-2. Gross beta activity in 1988 was consistent with levels reported in previous years. The average level at both indicator and control stations was 0.020 pCi/m'. The annual averages of the gross beta activity in air particulate filters at these stations for the years 1971-1988 are presented in figure H-3. Increased levels due to fallout from atmospheric nuclear weapons testing are evident, especially in 1971, 1977, 1978, and 1981. Evidence of a small increase resulting from the Chernobyl accident can also be seen in 1986. These patterns are consistent with data from monitoring programs conducted by TVA at nonoperating nuclear power plant construction sites.
Only natural radioactive materials were identified by the monthly gamma spectral analysis of the air particulate samples. No fission or activation products were found at levels greater than the LLDs. Strontium was not identified in the quarterly composites.
As shown in table H-3, lodine-131 was detected in one charcoal canister sample at a level slightly higher than the nominal LLD.
_ TERRESTRIAL MONITORING Terrestrial monitoring is accomplished by collecting samples of environmental media that may transport radioactive material from the atnesphere to humans.
For example, radioactive material may be deposited on a vegetable garden and be ingested along with the vegetables or it may be deposited on pasture grass where dairy cattle are grazing. When'the cow ingests the radioactive material, some of it may be in the milk and consumed by humans who drink the milk. Therefore, samples of milk, vegetation, soll, and food crops are collected and analyzed to determine potential impacts from exposure to this pathway. The results from the analysis of these samples are shown in tables l
H-4 through H-12.
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, three farms with at least one milk producing animal have been identified within 5 miles of the plant. The dairy and the farms are considered indicator stations and routinely provide milk and/or vegetation a samples. The results of the 1988 land use survey are presented in appendix G.
Sample Collection and Analysis Milk samples are purchased every 2 weeks from the dairy from two of the farms within 5 miles of the plant and from at least one of three control dairies.
These samples are placed on ice for transport to the radicanalytical laboratory. A specific analysis for I-131 is performed on each sample and a gamma spectroscopy analysis and Sr-89,90 analysis are performed every 4 weeks. -
i Samples of vegetation are collected every 4 weeks for I-131 analysis. The l
l samples are collected from the same locations as milk samples and from selected air monitoring stations. The samples are collected by cutting or breaking enough vegetation to provide between 100 and 200 grams of sample.
Care is taken not to include any soil with the vegetation. The sample is placed in a container with 1650 ml of 0.5 N NaOH for transport back to the radioanalytical laboratory. A second' sample of between 750 and 1000 grams is also collected from each location. After drying and grinding, this sample is analyzed by gamma spectroscopy. Once each quarter, the sample is ashed after the gamma analysis is completed and analyzed for Sr-89,90.
Soil samples are collected annually from the air monitoring locations. The samples are collected with either a " cookie cutter" or an auger type sampler.
After drying and grinding, the sample is analyzed by gamma spectroscopy. When the gamma analysis is complete, the sample is ashed and analyzed for Sr-89,90.
Samples representative of food crops raised in the area near the plant are obtained from individual gardens, corner markets, or cooperatives. Types of foods may vary from year to year as a result of changes in the local vegetable gardens. In 1988 samples of cabbage, corn, green beans, 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 l prepared as if it were to be eaten and is analyzed by gamma spectroscopy.
l Af ter drying, grinding, and ashing, the sample is analyzed for gross beta l activity.
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I Results The results from the analysis of milk samples are presented in table H-4. No radioactivity which could be attributed to SQN was identified. All I-131 1 results were less than the established nominal LLD of 0.2 pC1/ liter.
Cesium-137 was identified in one sample at a level slightly higher than the i I
LLO. Strontium-90 was found in less than half of the samples. These levels' J are consistent with concentrations measured in samples collected prior to- j plant operation and with concentrations reported in milk as a result _of fallout from atmospheric nuclear weapons tests (reference 1). The average Strontium-90 concentration reported from indicator stations was 8.7 l
pC1/ liter. An average of 2.2 pC1/ liter was identified in samples from control J l
stations. By far the predominant isotope reported in milk samples was the j l
naturally occurring K-40. An average of approximately 1300 pCi/ liter of K-40 j was identified in all milk samples.
As has been noted in this series of reports for previous years, the levels of j Sr-90 in milk samples from farms producing milk for private consumption only are up to six times the levels found in milk from commercial dairy farms.
Samples of feed and water supplied to the animals were analyzed in'1979 in an effort to determine the source of the strontium. Analysis of dried hay samples indicated levels of Sr-90 slightly higher than those encountered in routine vegetation samples, Analysis of pond water indicated no significant strontium activity.
This phenomenon was observed during the preoperationa! radiological monitoring near SQN and near the Bellefonte Nuclear Plant (under construction) at farms
where only one or two cows were being milked for private consumption of the milk. It is postulated that the feeding practices of these small farms differ 1
from those <f the larger dairy farmers to the extent that fallout from l atmospheric nuclear weapons testing may be more concentrated in these instances. Similarly, Hansen, et al. (reference 4), reported an inverse relationship between the levels of Sr-90 in milk and the quality of l i
fertilization and land management. l i
Results from the analysis of vegetation samples (table H-5) were similar to those reported for milk. Five samples had an I-131 value slightly higher than the nominal LLD. Average Cs-137 concentrations were 42.4 and 27.7 pC1/kg for indicator and control stations, respectively. Strontium-90 levels averaged 127 pC1/kg from Indicator stations and 150 pCi/kg from control stations.
1 Again, the largest concentrations identified were for the naturally occurring isotopes K-40 and Be-7.
The only fission or activation products identified in so'1 samples was 1
Cs-137. The maximum concentration of Cs-137 was 0.98 pCi/g. These values are consistent with levels previously reported from fallout. All other radionuclides reported were naturally occurring isotopes (table H-6).
All radionuclides reported in food samples were naturally occurring. The maximum K-40 value was 4340 pCi/kg in potatoes. Gross beta concentrations for all indicator samples were consistent with the control values. Analysis of these samples indicated no contribution from plant activities. The results are reported in tables H-7 through H-12.
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AQUATIC MONITORING Potential exposures from the liquid pathway can occur from drinking water, l ingestion of edible fish and clams, or from direct radiation exposure from radioactive materials deposited in the river sediment. The aquatic monitoring I program includes the collection of samples of river (reservoir) water, groundwater, drinking water supplies, fish, Asiatic clams, and bottom and I shoreline 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-13
{
through H-22. Radioactivity levels in water, fish, and clams were consistent with background and/or fallout levels previously reported. The presence of i i
Co-60, Cs-134, and Cs-137 was identified in some samples; however, the j projected exposure to the public is negligible, j Sample Collection and Analysis Samples of surface water are collected from the Tennessee River using 1
automatic sampling pumps from two downstream stations and one upstream l l
station. A timer turns on the pump at least once every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. The line is l 1
flushed and a sample collected into a composite jug. A 1-gallon sample is l removed from the composite jug at 4-week intervals and the remaining water in the jug is discarded. The composite sample is analyzed by gamma spectroscopy I and for gross beta activity. A quarterly composite sample is analyzed for Sr-89,90 and tritium.
, l l l f i
i 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 j 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.
Groundwater is sampled from an onsite well and from a private well in an area unaffected by SQN. The samples are composited by location quarterly and analyzed by gamma spectroscopy and for gross beta activity and tritium content.
}
i Samples of commercial and game fish species are collected semiannually from each of three reservoirs: the reservoir on which the plant is located I
(Chibckamauga Reservoir), the upstream reservoir (Watts Bar Reservoir), and the downstream reservoir (Nickajack 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 i
drying and grinding, the samples are analyzed by gamma spectroscopy. When the
}
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{
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gamma analysis is completed, the sample is ashed and analyzed for gross beta. '
activity.
1 Bottom and shoreline sediment is collected semiannually from selected TRM l 1
locations using a dredging apparatus. The samples are dried and ground and i 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 semiannually from three of the the same !
locations as the bottom sediment. The clams are usually collected in'the dredging process with the sediment. However, at times the clams are difficult i to find. 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.
Results Gross beta activity was present in most surface. water samples. Concentrations I
in downstream samples averaged 2.9 pCi/L while the upstream samples averaged )
2.7 pCi/L. All other values were consistent with previously reported levels
.i from fallout. A trend plot of the gross beta activity in surface water I samples from 1971 through 1988 is presented in figure H-4. A summary table of I
the results is shown in table H-13. i 1
No fission or activation products were identified in drinking water samples.
The positive identification of Sr-89 at levels near the LLD is typically a 1
_ _ _ - - - . - - - . - - . - - i
result of artifacts in the calculational process. Average gross beta activity was 2.7 pCi/ liter at the downstream stations and 2.8 pCl/ liter at the control stations. The results are shown in table H-14 and a trend plot of the gross beta activity in drinking water from 1971 to the present is presented in figure H-5.
l Concentrations of fission and activation products in ground water were all l below the~LLDs. Only naturally occurring radionuclides were identified in.
these samples. The average gross beta concentration in samples from the l onsite well was 3.7 pC1/ liter, while the average'from the offsite well was 3.4 j_ pC1/ liter. The results are presented in table H-15.
Cesium-137 was identified in_11 fish samples. The down' stream samples contained a maximum of 0.14 pCi/g, while the upstream sample'had a maximum of 0 22 pCl/g. Other radioisotopes found in fish were naturally occurring with the most notable being K-40. The concentrations of K-40 ranged from 6.1 pCi/g to 21.1 pC1/g. These results, which are summarized in tables H-16, H-17, H-18, and H-19, indicate that the Cs-137 activity is probably a result of-I fallout or other upstream effluents rather than activities at SQN.
Radionuclides of the types produced by nuclear power plant operations were ;
identified in sediment samples. The materials identified were Cs-137, Co-60, and Cs-134. In bottom sediment samples the average levels of Cs-137 were 1.94 pCi/g in downstream samples and 0.99 pC1/g upstream.' In shoreline sediment, Cs-137 levels were 0.09 and 0.14 pC1/g, respectively, in downstream and )
upstream samples. These values are consistent with previously identified fallout levels; therefore, they are probably not a result of SQN operations.
In bottom sediment, Co-60 concentrations in downstream samples averaged 0.26 pC1/g, while concentrations upstream averaged 0.08 pCi/g. The maximum concentrations were 0.57 and 0.10 pCi/g, respectively. Cesium-134 concentrations in upstream samples were all below the LLD. Levels in downstream samples averaged 0.04 pCi/g, with a maximum of 0.04 pCl/g. A realistic assessment of the impact to the general public from this activity producesanegligibledoseeduivalent. Results from the analysis of bottom sediment samples are shown in table H-20.
i 1
Co-60 was identified in only one shoreline sediment sample. A concentration !
of 0.02 pC1/g was found in a downstream station. This is less than the Co-60 i
(
levels found in upstream bottom sediment samples, indicating no impact from SON. Results from the analysis of shoreline sediment samples are shown in table H-21.
i Co-60 was also identified in two downstream clam flesh samples. A maximum i concentration of 1.56 pCi/g was found at TRM 483.4. I The dose projected from j the ingestion of clams with this concentration is 0.3 mrem / year. However, i
clams are not known to be consumed; therefore, no dose will be received by humans through this pathway. The results from the analysis of clam samples are presented in table H-22.
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(
I -
-ASSESSMENT AND EVALUATION l Potential doses.to.the public are estimated from measured effluents using' computer models, These'models were developed by TVA and are based on guidance provided by the NRC in Regulatory Guide 1.109 for determining the potential l dose to individuals and populations'living in the vicinity of the plant. The doses calculated are a representation of the dose to a " maximum exposed individual." Some of the factors used in these calculations'(such as-I ingestion rates) are maximum expected values which will tend to overestimate i
i the dose to this " maximum" person. In reality, the~ expected dose to actual individuals is lower.
The area around the plant is analyzed to determine the pathways through.which.
the public may receive an exposure. As' indicated in figure 2, the two major i ways by which radioactivity is introduced into;the environment are.through liquid and gaseous effluents. -l 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.
f
)
Whenever possible, data used in the dose calculation are based onl specific !
conditions for the SQN area. i l
'i
1
- u. j 1 I For. gaseous effluents, the public can be' exposed.to radiation from several !
sources; direct radiation from the radioactivity in the air, direct radiation from radioactiv'ity deposited on the ground, inhalation of radioactivity in the air, ingestion of vegetation which contains radioactivity deposited from the-atmosphere, and ingestion of milk ~or meat from animals which consumed !
J vegetation'containing deposited radioactivity. The concentrations of- ;
radioactivity in the air and the soil are estimated by computer models which use the actual meteorological conditions to determine the distribution of the effluents'in the atmosphere. Again, as many of the parameters as possible are based on actual site _ specific data. !
Results The estimated doses to the maximum exposed individual due'to radioactivity ;
released from SQN in 1988 are presented in table 2. These estimates were made !
using the measured concentrations from the liquid and gaseous effluent monitors. Also shown are the regulatory limits for-these doses and a. 1 comparison between the calculated dose and the corresponding limit. A more complete description of the effluents released from SQN and the. corresponding doses projected from these effluents can be found in the SQN annual radiological impact reports.
As indicated, the estimated increase in radiation dose equivalent to the general public resulting from the operation of SQN is trivial when compared to l?
the dose from natural background radiation.
i i
- ________-_______-__D
The results.from each. sample are. compared with the concentrations from the
]
corresponding. control stations and appropriate _preoperational and background data to determine influences from the plant. .During this report period, Co-60, Cs-134, and Cs-137 were seen in aquatic media. Cs-137 in sediment is consistent with fallout levels identified in. samples both upstream and-downstream from the plant. Co-60 and Cs-134 were identified in sediment samples downstream from the plant in concentrations which would produce no..
measurable increase in the dose to the general public. No increases of radioactivity attributable to SQN have been seen in water. samples.
1 Dose estimates were made from concentrations of radioactivity found in. samples of environmental media. Media evaluated include, but are not limited to,. air, .
milk, food products, drinking water, and fish. Inhalation.and ingestion doses estimated'for persons at the indicator locations were essentially identical to those determined for persons at control stations. Greater than 95 percent of.
those doses were contributed by the naturally occurring radionuclides K-40 and by Sr-90 and Cs-137, which are long-lived radioisotopes;found.in fallout from i
nuclear weapons testing. Concentrations of Sr-90 and Cs-137 are consistent d 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 l
i of the general public which may have been attributable to SQN is negligible. i The radioactivity reported herein is primarily the result of fallout or
l 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.
The maximum calculated whole body dose equivalent from measured liquid effluents as presented in table 2 is 0.30 mrem / year, or 5.0 percent of the limit. The maximum organ dose equivalent from gaseous effluents is 0.014 mrem / year. This represents less than 1 percent of the Technical Specification limit.
I 1
1 1
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1 1
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Table 1 i
' MAXIMUM PERMISSIBLE CONCENTRATIONS
.i FOR NONOCCUPATIONAL EXPOSURE j 1
MPC I In Water In Air l pC1/l* PC1/m'*
t Gross beta 3,000 100 i I
H-3 3,000,000 200,000 I Cs-137 20,000 500 }
(
Ru-103,106 10,000 200 l
Ce-144 10,000 200 .!
l Zr Nb-95 60,000 1,000 l t
Ba-140 - La-140 20,000 1,000 1-131 300 100 Zn-65 100,000 2,000 i
Mn-54 100,000 1,000 Co-60 30,000 300 !
Sr-89 3,000 300 l
Sr-90 300 30 Cr-51 2,000,000 80,000 Cs-134 9,000 400 Co-58 90,000 2,000
- 1 pCi - 3.7 x 10-' Bq.
Source: 10 CFR, Part 20, Appendix B, Table II.
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l Table 2 >
j Maximum' Dose due to Radioactive Effluent Releases-Sequoyah Nuclear'. Plant >
1988 mrem / year +
- )
Liquid Effluents .
-l 1988 NRC- Percent of EPA Percent of '
, Type Dose Limit 'NRC Limit Limit EPA-Limit-
.1 Total Body 0.30a 6 5.0- 25 L 1.' 2. k 1
Any Organ 0.36 20 1.8 25 1,4: j J.,
il Gaseous Effluents ' '
-)
1
.il 1988 NRC ' Percent of . EPA ' Percent of' i Type Dose Limit NRC Limit -Limit- EPA Limit ..
Noble Gas 0.016 20 0.08 '25 0.06 (Gamma)
Noble Gas 0.087 40 0.22 25 0.35 i
(Beta) j Any Organ 0.014 30 0.05 25. '0.06 u
I'
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REFERENCES
- 1. Merril Eisenbud, Environmental Radioactivity, Academic Press, Inc., New York, NY, 1987.
- 2. National Council on Radiation Protection and Measurements, Report No. 93, "lonizing 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. Hansen, W. G., Campbell, J. E., Fooks, J. H., Mitchell, H. C., and Eller, C. H., Farming Practices and Concentrations of Emission Products in Milk, U.S. Department of Health, Education, and Welfare; Public Health Service Publication No. 999-R-6, May 1964.
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1 j
i APPENDIX A ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM AND SAMPLING LOCATIONS i
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esaa el vl a n raau t o h m c n i ti ti e t not m a oanr n c t a o o gsp r L pni i
ui r v e cki n l mul a E o odi m
a rome v f r S pfi e- of s l k n pl et o mil ai amp t s md a f ant 1 osas e
l o
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w h t t e a g P e V
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u .
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l
,1
. Table'A-2 l.
SEQUOYAH NUCLEAR PLANT Environmental Radiological Monitoring Program Sampling Locations I
Map Approximate Indicator (I)
Location Distance. or Station .SamplesCollected Number *__ Sector (miles)- Control (C) .. l 2 LM-2 N 0.8 I AP,CF,R,S,V.
3' LM-3 SSW 1.2 I 'AP,CF,R,S,V:
i 4 LM-4 NE 1.5 I J AP,CF,R,S,V 5 LM-5 NNE 1.8 I 'AP,CF,R,S,V 7 PM-2 3.8 SW I 'AP,CF,R,S,V' 8 .PM-3 5.6 W I AP,CF,R,S,V
9 PM-8 SSW 8.7 I AP,CF,R,S,V'-
10 i PM-9 WSW 2.6 I 'AP,CF,R S,V* 1 11 RM-1 SW 16.7 C 'AP,CF,R,S,V' .
12 RM-2 NNE 17.8 C ;AP CF,R,S,V' 13 RM-3 ESE 11.3 14 C 'AP,CF,R,S,V' i RM-4 WNW 18.9 C AP,CF,R,S,V 15 Farm B NE 43.0 C M,V' 16 Farm C NE 16.0 C M,V" q
17 Farm S 1 NNE 12.0 C M,V 18 Farm J WNW 1.1 I 19 M , V. j Farm HW NW 1.2 I, M,V,Wd 20 Farm EM N 2.6 I V 21 Farm Br" SSW 2.2 I VL 24 Well No. 6 NNE 0.15 I W 31 TRM 473.0 --
11.5' I PW (C.F. Industries) 32 TRM 470.5 --
14.0' I PW (E.I. DuPont) 33 TRM 465.3 --
19.2' .I PW (Chattanooga) 34 TRM 497.0 --
12 3' C8 SH 35 TRM 503.8 --
19.3' C PW i (Dayton) 36 TRM 496.5 --
12.0' C CL,SD I 37 TRM 485.0 --
0.5' '
39 TRM 480.8 3.7' I CL,SD =c 40 TRM 477.0 --
11.3' I SW.
42 TRM'472.8 --
1 1 '. 7 ' I SD 44 TRM 478.8 6.5' I SS j
~
i
. .g
-1 '
Tabl? A-2 SEQUOYAH NUCLEAR PLANT-Environmental Radiological Monitoring Program A Sampling Locations (Continued) ~i a
i l.
Map Approximate Indicator (I)
Location .
Distance' or Number *_ Station Sector (miles) Control (C) Samples Collectedd 45 TRM 425-471 -- --
I F (Nickajack Reservoir) 46 .TRM 471-530 -- --
I F.
(Chickamauga Reservoir) 47 TRM 530-602 -- --
C F l (Watts Bar Reservoir) 48 Farm H NE 4.2 I M,y .j l,
- a. See figures A-1, A-2, and A-3
-b. Sample Codes
-l AP Alr particulate filter l CF = Charcoal filter CL = Clams.
F - Fish M - Milk PW = Public water R - Rainwater S = Soil SD = Sediment SS = Shoreline sediment SW = Surface water V. - Vegetation )
I l W = Well water !
- c. Vegetation sampling discontinued in August 1988.
- d. A control for well water.
- e. J Milk producing animal not identified in 1988 land use survey - vegetation ;
sample collected until ODCM is revised to delete from sampling schedule.
- f. Distance from plant discharge (TRM 484.5) 1
- g. : Surface water sample also used as a control for.public water.
i i
i i
Table A-3 SEQUOYAH NUCLEAR PLANT Thermoluminescent Dostmeter (TLD) Locations l'
l Approximate. Onsite-(On)"
Map Distance- or Location Number Station Sector (Miles) Offsite-(Off) 3 SSW-1A SSW l.2 On ;
4 NE-1A NE 1.5 On 1
5 NNE-1. NNE 1.8 On 7' SH-2 SH 3.8 Off
'8 W-3 5.6 W Off 9 SSW-3 8.7 10 SSW Off WSW-2A 2.6 11 WSW Off SW-3 SW 16.7 Off 12 NNE-4 NNE 17.8' Off 13 ESE-3 ESE I1.3 Off 14 WNW-3 WNW l8.9 Off '
49 N-1 N 0.6 On 50 N-2 2.1 51 N Off N-3 N 5.2 Off 52 N-4 N 10.0 Off 53 NNE-2 4.5 54 NNE Off NNE-3 NNE 12.1 Off-55 NE-1 NE 2.4 Off 56 NE-2 NE 4.1 Off 57 ENE-1 ENE 0.4 On 58 ENE-2 ENE 5.1 Off 59 E-1 E 1.2 On 60 E-2 E 5.2 Off 61 ESE-A ESE 0.4 On 62 ESE-l ESE 1.2 On 63 ESE-2 ESE 4.9 Off' 64 SE-A SE 0.4 On 65 SE-B SE 0.4 On.
66 SE-1 SE 1.4 On 67 SE-2 SE 1.9 On 68 SE-4 SE 5.2 Off 69 SSE-1 SSE 1.6 On 70 SSE-2 SSE 4.6 Off:
71 S-1 S 1.5 On-72 S-2 S 4.7 off 73 SSN-1 74 SSW 0.6 On SSN-2 SSW 4.0 75 Off SW-I SW~ 0.9 On 76 WSW-l 77 WSW 0.9 On WSH-2 WSW 2.5 .Off
1 1
i 1
Table A-3 SEQUOYAH. NUCLEAR PLANT.
Thermoluminescent Dosimeter (TLD) Locations Approx'imate Onsite (On)"
Map. Distance or Location Number Station Sector (Miles) Offsite'(Off)-
78 WSW-3 WSW 5.7 Off 79' WSW-4' WSW 7.8' Off 80 WSW-5 WSW 10.1 Off 81 W-1 W 0.8 On 82 W-2 W 4.3 Off 83 WNW-1 WNW 0.4 On 84 WNW-2 WNW- 5.3 Off-'
'85 NH-1 NW 0.4 On 86 NH-2 NW '5.2 Off-87 NNH-1 NNW 0.6 On 88 NNW-2 NNW l.7 On !
89 NNH-3 NNW 5.3 Off I
'l 1
1 i
- a. 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.
l
Figuro A-1 Environmental Radiological Sampling Locations i
! Within 1 Mile of Plant 348.75 N 11.25 NNW NNE 326.25 33.75 NW 2 NE
- *) r 303.75 4 / 56.25 281.25 xe N ,
1
& f
/
78.75 i 8 % ,Y ,
/~~ ' s .
sEouoYAH W- . NUCLEAR -E
- -C ' - PLANT 258.75 OI ' '/
/ 101.25 j 5
/
76 / 4 WSW */. ! ESE
- $ 5 '
- l 236.25 * \ 123.75 7
I SW
%/ v# \ggs66 sd ** SE 213.75 I 146.25 l SSW i SSE 191.25 168.75 S
scale Mlle 1 48 f i
Lj i
Figure A-2 Environmental Radiological Sampling Locations From 1 to 5 Miles From The Plant j l
4 348.75 N 11.25 326.25 33.75 e
NW / @ NE 303.75 I 56.25 20 48 e
5 **
i WNW e55 ENE !
281.25 '
4' y gp gb 78.75 8,2 1 op W- 59 -E at 10 9 62 358.75 7b 66 , 101.25 1
69 63 WSW ESE
/
e 2
s 236.25 39* 123.75 i
- 4
- 70 213.75 4 7,2 146.25 SSW '
q) SSE 101.25 S 168.75 SCALE b 1 2 MILES 49
Figure A-3 Environmental Radiological Sampling 1.ocations Greater Than 5 Miles From The Plant
- 348.75 N j 9,pg CROSSylLLE NNW NNE 326.25 33.75 n
~
N 0\l PRIN Cf T Y
, McMINNVILLE 303.75 N /Mt 15 56.25 8WEET AT R j
f p ' eOAYTON
' g\fg g .,# -
~
/ .
2 'f,p 4%1
- 78.75 281.25 ,g 34 P .,j E OWAN too y f ,
84p. 6 0- 58 Cf . esovov4* nocL' ' ' '"A -E SEWANEE LEVELAND .
k 8 - - n
- 68 -
1,'L O' / -
958.7 , , 101.25-
/g<y gx
,g g _ -
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,,,, .e.om,0., g' x s ,,,
y' y N' ,
32 25 N N'~ g s _.-
y, 123.75 sw
~ .. .x,,E, YE sE pr N ~ -
213.75 \ 3 146.25 esw T ssE
~
191.25 e 8.75 SCALE p- e,., .c m MILE S 50
1 i
1 f
5 1
0 APPENDIX B j
j l
1988 PROGRAM MODIFICATIONS I I
I i
l 1
- - - - - _ - - _ - - . - - - - - - - - - - - . a-
Appendlx.B l
L Environmental Radiological. Monitoring Program Modification During.1988 the only modification to the environmental monitoring program ,
was the reduction in the number of locations from which vegetation samples were'taken.
I Through experience and data obtained with an extensive vegetation sampling program at the Browns Ferry, Sequoyah, and Watts'Bar Nuclear Plants it was determined'that fewer samples at selected locations,would provide adequate information and still exceed technical specification requirements.
1 See tables A-2 and B-1 for locations no longer sampled.
)
l i
i 4
Table B-1 SEQUOYAH NUCLEAR PLANT Environmental Radiological Monitoring Program Modifications 1988 Date Station Modification 4 8/88 PM-2, PM-3, PM-8, Vegetation sampling discontinued PM-9, RM-1, RM-2, RM-3, farm-8, and Farm C 1
)
i r
APPENDIX C ;
I MISSED SAMPLES AND ANALYSES j
1 I
I 1 1
1 i
Appendix C I
Misssed Samples and Analyses During the 1988 sampling period, a small number of samples were not collected and several analyses were not completed on some co~11ected samples. These occurrences resulted in deviations from the scheduled program but not from the program required by the Technical l
Specifications. A list of missed samples and analyses are found in table C-1.
The missed samples resulted from equipment malfunction, construction and repairs in the area of samplers, scarcity of sample media, sample unavailability, and samples " lost" or destroyed during analysis.
Equipment malfunctions were corrected, repaires completed, and analysts responsible for lost or destroyed samples received additional training to prevent recurrence.
1 Table C-1
,SEQUOYAH NUCLEAR PLANT.
Environmental Radiological _ Monitoring Program
' Exceptions Date Station Location Remarks 3/14/88 TRM 497 12.5 miles Surface water. sample-not available upstream because.of pump malfunction 3/22/88 RM-2 17.8 miles NNE Air particulate and charcoal filter 3/29/88 not collected - power'off for construction in area 3/29/88 LM-5 1.8 miles NNE Air particulate and charcoal filters unusable - heavy. dust / soot loading from brush fire 6/7/88 PM-8 8.7 miles SSH Air particulate and_ charcoal 6/14/88 filters not collected - equipment failure 6/27/88 TRM 496.5 12.0 miles Clam samples collected late -
upstream scarcity of clams made them difficult to locate TRM 483.4 1.1 miles downstream TRH 480.8 3.7 miles downstream -l 7/19/88 Farm C 16.0 miles NE Milk sample soured - sample collectors will check condition of.
sample before. leaving location and keep on ice untti delivery to laboratory 8/8/88 LM-4 1.5 miles NE Air particulate.and charcoal 8/16/88 filters not collected - storm blew tree over and broke power line 8/30/88 Farm C 16.0 miles NE Milk sample destroyed.during processing for I-131 - sample lost-because of cracked beaker.
Beakers examined more closely to prevent,possible recurrence.
\;
[:..
1, Table C-1
. .SEQUOYAH NUCLEAR PLANT Environmental Radiological Monitoring Program Exceptions (Continued) s 4
Date Station' Location Remarks 9/12/88 Farm HW 1.2 miles.NW Milk samples not available'- cow-9/26/88 " dry." ' Vegetation' samples. q routinely collected monthly, i 10/18/88 TRM 496.5 12.0 miles Clam samples not available for -
downstream collection. Could not locate.
In the' future, the search' area is '
l to be expanded. i 10/24/88 Farm J 1.1 miles HNH Milk samples not available'- cow l through " dry." Vegetation samples. i 12/31/88 routinely collected monthly.
10/25/88 LM-4 1.5 miles NE Air particulate and charcoal 11/1/88 filters not collected - equit. ment failure 11/15/88 TRM 480.8 3.7 miles Clam samples collected but downstream suffic_ lent quantitles not available; search area to be expanded in the future 12/5/88 LM-2 0.8 miles N Vegetation sample lost during-processing for I-131 analysis -
processed sample inadvertently turned over. Analyst. received instruction in careful handling of samples.
12/21/88 Farm B 43.0 miles NE Milk sample lost during processing for I-131 analysis - sample. lost ~
because of breakage of centrifuge tube. Thicker walled tubes are now in use.
1 12/28/88 TRM 465.3 19.2 miles Public water samples not available downstream for collection'- water line l temporarily disconnected for repairs j i
1 l
, r APPENDIX D ANALYTICAL PROCEDURES g .
]y m
APPENDIX D- 1 3
' Analytical: Procedures All analyses are performed by the radioanalytical laboratory located at
~
.y the Western Area' Radiological Laboratory facility'in Muscle-Shoals. All
- analysis-procedures'are based on accepted methods.
A summary of the analysis. techniques and methodology follows.
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 1s 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. With the beta-gamma coincidence counting system, background counts are
- virtually eliminated and extremely low levels of detection can-be obtained.
-S9-1)
l
-After a radiochemical separation, samples analyzed.for Sr-89,90 are counted on a low background beta counting system. The sample is counted i a second time after a 7-day ingrowth period. From the.two counts the' Sr-89 and Sr-90 concentrations can be determined.
Water. samples are analyzed for tritium content by first distilling a portion of the sample and then counting by liquid scintillation. A
~
s commerically available scintillation cocktall 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 mut11 channel analyzer system. Spectral data reduction is performed by the computer program HYPERMET. l I
The gaseous radioiodine analyses are performed.with well-type NaI- j i
detectors interfaced with a single channel analyzer. The system is calibrated to measure I-131. If activity above a specified limit is i
detected, the sample is analyzed by gamma spectroscopy.-
All of the necessary efficiency values, weight-efficiency curves,land i
geometry tables are established and maintained on each detector and' l counting system. A teries of daily an'd 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.
1
i i
APPENDIX E !
I i
NOMINAL LOWER LIMITS OF DETECTION (LLD) l 1
J l
4
l 1
-I Appendix E Nominal Lower Limits of-Detection Sensitive radiation detection devices can give a signal'or reading even when no radioactivity is present in a sample being analyzed. :This signal may come from trace amounts of radioactivity in'the components of the
. device, from cosmic rays, from naturally occurring radon gas, or from machine noise. Thus, therel1s 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 some well-defined average reading, but any-individual reading will vary from that average. In order.to-determine the activity'present in a sample that will produce a reading above the critical level, additional statistical analysis of the background readings is required. The
. hypothetical activity calculated from this analysis is called the lower limit of detection (LLD). .A listing of typical LLD values that a laboratory publishes is a guide to the sensitivity of the analytical measurements performed by the laboratory. l
Every time an activity is calculated from a. sample, the machine background must be subtracted from the sample signal. For the very-_ low levels encountered in environmental monitoring, the sample signals are often very close to the background. The measuring'_ equipment.is being-.
used at the limit of its capability. For~a sample with no measureable activity, which of ten .happens, about. half the time its ' signal should fall i below the average machine background and half the time it should be above.
the background. If a signal above-the background is present, the calculated activity.is compared to the calculated LLD to determine'if there is really activity present or if the number.is an artifact of'the way radioactivity is measured.
1 A number of factors influence the LLD, including sample size, count. time,:
counting efficiency, chemical processes, radioactive decay factors, and interfering-isotopes encountered in the sample. The most likely. values.
for these factors have been evaluated for'the various analyses performed in the environmental monitoring program. The nominal LLDs calculated ..
from these values, in accordance with the methodology prescribed in the y
Technical Specifications, are presented in the following table. I l
l
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od li 250 C -
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2 62 e/ 400 00 Vi 46 i 0 00 C 1 rC 0 00 t p ip e(
A( 0 00 H 90 90 89 89 a 1 - - a1 - -
t 3mm t3mm e 1 uu e1 uu B mii B - ii uett ett sinnn snnn sti oo sioo oidrr od rr rrott rott GTISS GISS
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50481 51 091 001 1 07730555 F .
. 591. . 91.1. .1. 1 . . 1 1 21 041 1 1 a .
1 9222 m/ 2 ai lC Co
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1 51
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8006008444004d02400008 2083292242224209440484 1 1 1 W e/ 4 2 gi eC Vo n y onr i id tara . 755958761 0001 024004001 65517031 0021 100002 51 21 tGa . . . . .
e / 1 gdi enc Vao k
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1 4 3647 00 244 1441 1- -531 1 10033558450 1 1 9955660l d 49 1
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APPENDIX F QUALITY ASSURANCE / QUALITY C0i4 TROL PROGRAM j
j i
)
d
-Appendix F Quality Assurance / Quality Control Program.
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 perforening the work, l
a.nonconformance and' corrective action tracking-system, systematic internal audits, a complete training and retraining system,' audits by:
~
various external organizations, and'a laboratory quality control program.
The quality control program employed by the radioanalytical laboratory'is designed to ensure that.the sampling and analysis process is-working as intended. The program includes equipment checks and-the analysis of.
3 special samples along with routine samples. !
l!
Radiation detection devices are complex and can be tested in a number of ways. There are two primary tests which are performed on all devices.
In the first type, the device is operated without a sample on the detector to determine the background count rate. The background counts j
(
are usually low values and are due to machine noise, cosmic rays, or i 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. ;
L l
l In the second test, the device is operated with a known amount of'
[I radioactivity presuit. The number of counts registered from such a i
.. q
___z______________.-_-.--- - - - - - - - - - - - - - - - - -
radioactive standard should be very reproducible. These reproducibility checks are also monitored to ensure that they are neither higher nor l
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.
Quality control samples of a variety of types are used by the laboratory to answer questions about the performance of the different portions of the analytical process. These quality control samples may be blanks, replicate samples, blind samples, or cross-checks.
Blanks are samples which contain no measureable radioactivity or no activity of the type being measured. Such samples are analyzed to determine whether there is any contamination of equipment or commercial laboratory chemicals, cross-contamination in the chemical process, or interference from isotopes other than the one being measured. .
Duplicate samples are generated at random by the same computer program which schedules the collection of the routine samples. For example, if the routine program calls for four milk samples every week, on a random
l i
basis each farm might provide an additional sample several times a year. l These duplicate samples are analyzed along with the other routine l
samples. They provide information about the variability of radioactive l
content in the various sample media. !
l There is another kind of replicate sample. From time to time, if enough sample is available for a particular analysis, the laboratory analyst-can split it into two portions. Such a sample can provide information about j the variability of the analytical process since two identical portions of j material are analyzed side by side.
I 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 radioactiu 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.
Bilnd spikes are samples containing radioactivity which are introduced into the analysis process disguised as ordinary environmental samples.
The analyst doe not know they contain radioactivity. Since the bulk of the ordinary workload of the environmental laboratory contains no measureable activity or only naturally occurring radioisotopes, blind spikes can be used to test the detection capability of the laboratory or they can be used to test the data review process. If an analysis I
l routinely generates numerous zeroes-for a particular. isotope, the .
)
1
. presence.of the isotope is brought to the attention of the laboratory l supervisor.in the daily review process. Blind spikes test this: process since they contain radioactivity at levels high enough to be' detected.
l Furthermore,. the activity can be put into such samples at the extreme
~
limit of detection to determine whether or not the laboratory can find any' unusual radioactivity. whatsoever.
At present, 5 percent of the laboratory workload ~1s in the category of f internal cross-checks. Th'ese 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. L) 4 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 l 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 laboratory itself. That.is, unlike' internal cross-checks, EPA cross-checks test-the calibration.of the' laboratory detection devices.since different radioactive standards produced by
. individuals.outside TVA are used.in the cross-checks. The results of the analysis of these samples are reported back to EPA which then issues'a report of all the results of all participant's. 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 M participation in the EPA Interlaboratory Comparison Program are presented in table F-1.
TVA splits certain environmental samples with laboratories operated by the States of Alabama and Tennessee and the EPA Eastern Environmental' Radiation Facility in Montgomery, Alabama. When radioactivity has been present in the environment in measureable quantitles, such as following atmospheric nuclear weapons testing, following the Chernobyl incident, or.
as naturally occurring radionuclides, the split samples have provided TVA j i
with yet another level of information about laboratory performance.
These samples demonstrate performance on actual environmental sample l matrices'rather than on the constructed matrices used in cross-check I programs. 5 i
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 help or improvement. The end result is a measurement process that provides accurate data and is sensitive enough !
to measure the presence of radioactivity far below the levels which could be harmful to humans.
3
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) E( ( E 3 5 2 M r O e r t e C l i t Y F a R / Ag 66 W An 3 4 8 3
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Footnotes for Table F-1 Results Obtained in Interlaboratory Comparison Program
- a. Apparently, self-absorption caused by sample mounting or preparation ,
caused all gross alpha and gross beta values to be consistently low. )1
- b. The low strontium result was investigated. A definitive cause for I the low result conid not be identified. Further evaluation of the i strontium radioanalytical procedure continues.
- c. Performance Evaluation Intercomparison Study. j
- d. Results not reported properly to EPA.
- e. Reanalysis of sample gave 4666 pCi/1. No errors could be found in our analysis. Subsequent analyses were good.
- f. Transcription error - 113 should have been the reported average.
- g. Units are milligram of total potassium per kilogram or liter rather than picrocuries of K-40 per kilogram or liter.
- h. Errors in K-40 measurement may be due to changes in temperature.
These samples are initially refrigerated and then warm gradually while they are counted, possibly causing a gain shift in the detector.
l l
( l i
1.,
I I
f l
i APPENDIX G f
i I,
LAND USE SURVEY,.
I i
i l
i
l i
Appendix G F' .
I Land Use Survey i
A land use survey is conducted annually to identify the location of the i
nearest milk animal, the nearest residence, and the nearest garden of l 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 l
gardens of greater than 500 square feet producing fresh leafy vegetables within a distance of 3 miles from the plant.
The land use survey is conducted between April 1 and October 1 using appropriate techniques such as door-to-door survey, mail survey, telephone survey, aerial survey, or information from local agricultural authorities or other reliable sources. ^
from these data, radiation doses are projected for individuals living I near the plant. Doses from breathing air (air submersion) are calculated for the nearest resident in each sector, while doses from drinking milk or eating foods produced near the plant are calculated for the areas with milk producing animals and gardens, respectively. These doses are f
calculated using design basis source terms and historical meteorological data. ;
i J
)
In response to the 1988 SQN land use survey,. annual doses were calculated for air submersion, vegetable ingestion, and milk Ingestion.
)
A change was made in the methodology used to calculate these doses. In ]
)
the past, receptor information reported in the land use survey and located on an aerial photo map were transferred to a topographic map. !
l The distances measured on this map were usually different from those I reported in the land use survey. Now, the distances reported in the land use survey were used for dose calculation.
l Doses calculated for air submersion varied slightly from those calculated I for 1987, reflecting the change in methodology as noted above.
Doses calculated for ingestion of home-grown foods changed in some sectors, reflecting the above methodology and shifts in the location of the nearest garden. The most notable increase occurred in the east-northeast sector where a garden had not been identified in 1987 but l
1 one was identified in 1988. l For milk ingestion, calculated doses varied slightly reflecting the above methodology. There were no new locations with milk-producing animals identified.
Annual doses projected for 1988 were not appreciably different from those I calculated for 1987. Tables G-1, G-2, and G-3 show the comparative calculated doses for 1987 and 1988.
._j
'l i
i l
Table G-1 I SEQUOYAH NUCLEAR PLANT Projected Annual Air Submersion Dose to the Nearest Resident i Within five Miles of Plant I (mrem / year / reactor) i l
1987 Survey 1988 Survey Approximate Approximate Sector Distance (Miles) Annual Dose Distance (Miles) Annual Dose !
N 0.9 0.12 0.8 0.12 NNE 1.7 0.06 1.5 0.07 NE 1.3 0.08 1.4 0.07 ENE 1.4 0.03 1.3 0.03 i E 1.1 0.02 1.0 0.03 l ESE 1.1 0.02 1.0 0.03 !
SE 1.0 0.03 1.0 0.03 SSE 1.4 0.03 1.2 0.04 S 1.3 0.06 1.4 0.05 4 SSH 1.4 0.13 1.3 0.16 l SW 1.9 0.04 1.8 0.04 HSW 0.7 0.08 0.7 0.08 W 1.1 0.03 0.6 0.08 HNW I.1 0.02 1.1 0.02 NH 0.7 0.05 0.9 0.03 NNH 0.5 0.14 0.6 0.12
J Table G-2 SEQUOYAH NUCLEAR PLANT Projected Annual Dose to Child's Critical Organ from Ingestion of Home-Grown foods (mrem / year / reactor) 1987 Survey 1988 Survey !
Approxima te Annual Dose Approximate Annual Dose Sector Distance (Miles) (Bone) Distance (Miles) (Bone)
N 1.0 2.54 1.1 2.25 i NNE 1.9 1.48 1.9 1.45 !
NE 1.3 2.30 1.4 2.03 l ENE a --
1.6 0.73 l E 1.6 0.39 a --
l ESE 1.2 0.59 1.1 0.68 I SE 1.9 0.37 2.0 0.35 SSE 1.4 0.92 1.2 1.11 S 1.4 1.60 1.5 1.53 SSH 1.4 3.83 1.7 3.05 l SH 2.3 0.92 2.1 1.04 HSH 1.0 1.34 0.9 1.55 W 1.1 0.93 1.2 0.83 HNH 1.1 0.66 1.2 0.61 NH 0.7 1.37 0.9 1.10 NNH 0.5 3.96 0.6 2.88 i
- a. No garden was identified in this sector whithin 5 miles of the plant.
f
?
l l
j Table G-3 SEQUOYAH NUCLEAR PLANT Projected Annual Dose to Receptor Thyroid from Ingestion of Milk (Nearest Milk Producing Animal Within Five Miles of Plant)
(mrem / year / reactor) i Approximate Distance Annual Dose !
Location No. Sector (Miles)* 1987 1988 Farm EM" N 2.6 0.05 0.04 .
Farm H" NE 4.2 0.03 0.02 Farm J6 HNH 1.1 0.04 0.03 l
Farm HH" NH 1.2 0.06 0.06
)
)
o l
1
- a. Distances measured to nearest property line,
- b. Vegetation sampled at this location.
- c. Milk sampled at this location.
l l
~ APPENDIX H l J
DATA TABLES 1
l l
l I
L Table H-1 DIRECT RADIATION LEVELS Average External Radiation Levels at Various Distances from )
Sequoyah Nuclear Plant for Each Quarter - 1988 '
mR/ Quarter
- 1 Average Eyternal Gamma Radiation Levels" )
Distance 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter '
Miles (Feb-Apr 88) (May-Jul 88) (Aug-Oct 88) (Nov 88-Jan 89)- !
0-1 20.4 1 1.7 19.7 1 2.9 19.5 1 1.6 19.1 1 3.3 ,
t 1-2 17.8 1 3.0 15.2 1 3.4 16.7 1 2.8 16.2 1 2.6 .l 2-4 17.4 1 3.2 14.5 1 3.4 16.5 1 2.8 15.6 1 1.9 4-6 16.8 1 2.4 14.5 1 3.4 16.6 1 2.0 15.5 1 2.4
>6 16.7 1 2.4 13.9 1 2.6 17.6 1 3.7 15.7 1 2.8 l
Average, 19.2 1 2.7 i).6 1 3.8 18.2 1 2.6 17.8 1 3.2 l 0-2 miles (onsite) '
l Average 16.9 2 2.5 14.4 1 3.1 16.9 1 2.7 15.6 1 2.4 !
>2 miles (offsite)
I f
- 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 il standard deviation of the set. j l
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.e TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 37401 l
SN 1578 Lookout Place APR 271989 10 CFR 50.71(a)
U.S. Nuclear Regulatory Commission ATTH: Document Control Desk Hashington, D.C. 20555 Gentlemen:
In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) UNITS 1 AND 2 - ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - OPERATING LICENSES DPR-77 AND DPR-79 In accordance with SQN technical specifications 6.9.1.6 and 6.9.1.7 for units 1 and 2, enclosed is the Annual Radiological Environmental Operating Report for 1988. This report contains no commitments.
If you have any questions concerning this submittal, please telephone M. J. Burzynski at (615) 843-6422.
Very truly your ,
TE E Y THORITY
/
/r C. H. Fox, Jr., Vice President and Nuclear Technical Director Enclosure cc: See page 2 Y
f (
An Equal Opportunity Employer
v; gj ~ o U.S. Nuclear Regulatory Commission APR 271989 cc (Enclosure):
Ms. S. C. Black, Assistant Director for Projects TVA Projects Division U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Ms. L. J. Watson, Acting Assistant Director for Inspection Programs TVA Projects Division U.S. Nuclear Regulatory Commission Region II -
101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Sequoyah Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road ;
Soddy Daisy, Tennessee 37379 U.S. Nuclear Regulatory Commission (2)
Material Radiation Protection Section 101 Marietta Street, NH, Suite 2900 Atlanta, Georgia 30323