ML20246M887
| ML20246M887 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 12/31/1988 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| References | |
| NUDOCS 8905190289 | |
| Download: ML20246M887 (116) | |
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I I ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SEQUOYAH NUCLEAR PLANT 1988 I .
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E I ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SEQUOYAH NUCLEAR PLANT 1988 I
I I TENNESSEE VALLEY AUTHORITY NUCLEAR ASSURANCE AND SERVICES RADIOLOGICAL CONTROL I
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I April 1989 I
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. TABLE OF CONTENTS Table of Contents . . . . . . . . . . . . . . . . . . . . . . . . . 11 List of Tables- ........................... iv Listsof: Figures . . . . . . . . . . . . . . . . . . . . . . . . . . .
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- 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 Results ............................ 15 Atmospheric Monitoring ...................... 18 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 i
References ............................ 36 f Appendix A Environmental Radiological Monitoring Program and Sampling Locations . . . ............... 39
.j Appendix 8 1988 Program Modifications ............ .. 51 L
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, I Appendix C Missed Samples and Analyses . . . . . . . . . . . . . . 54 Appendix D Analytical Procedures . . . . . . . . . . . . . . . . 58 Appendix E Nominal Lower Limits of Detection (LLD) . . . . . . , 61 Appendix F Quality Assurance / Quality Control Program . . . . . . . 66 Appendix.G Land U'se Survey . . . . . . . . . . . . . . . . . . . . 76 Appendix H Data Tables . . . . . . . . . . . . . . . . . . . . . . 82 I
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I LIST OF TABLES I
Table 1 Maximum Permissible Concentrations for Nonoccupational Exposure . . . . . . . . . . . . . . . . 34 I Table 2 Maximum Dose Due to Radioactive Effluent Releases . . . . . . . . . . . . . . . . . . . . . . . . 35 I
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E LIST OF FIGURES l
I Figure 1 Tennessee Valley Region . . . . . . . . . . . . . . . . . 37 L 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 1
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 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 near the plant are compared with concentrations from control stations and with preoperational measurements to determine potential imp: ts 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 were found in sediment I
l samples downstream from the plart. This activity in stream sediment would result in no measurable increase over background in the dose to the
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L general public.
INTRODUCTION This report describes'and summarizes a huge volume of data, the results.of many thousands of measurements and laboratory analyses. The measurements are made to comply with regulations and to determine potential effects on public l 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 I
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.
1 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, is one of the major types of radioactive materials found naturally in our environment. An individual weighing 150 pounds contains about 140 grams of potassium (reference 1). This is equivalent to approximately 100,000 pCi of l K-40 which delivers a dose of 15 to 20 mrem per year to the bone and soft Naturally occurring radioactive materials have always
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been in our environment. Other examples of naturally occurring radioactive l l- . materials are uraninum-238, uranium-235, thorium-234, radium-226, radon-222, carbon-14, and hydrogen-3 (generally called tritium). These naturally l occurring radioactive materials are in the soll, our food, our drinking water, i and our bodies.
I I The radiation from these materials makes up a part of the low-level natural background radiation. The remainder of the natural background radi& tion comes from outer space. We are all exposed to this natural radiation 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day.
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 1
atmosphere. Another part of natural background radiation comes from naturally occurring radioactive materials in the soil and rocks. Because the quantity I 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 uterials within each individual's body. We absorb these materials from the l l food we eat which contains naturally occurring radioactive materials from the l
i 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.
_g This is due to the naturally occurring radioisotopes in the concrete or brick, ,
E such as trace amounts of uranium, radium, thorium, etc.
I 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, i
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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 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 U.S. population 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 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 1 Nuclear energy 0.28 Consumer products 0.03 Total 355 (approximately) l
I r i As can be seer) from the table, natural background radiation dose equivalent to the U.S. population normally exceeds that from nuclear plants by several hundred times. This indicates that nuclear plant operations normally result in a population radiation dose equivalent which is insignificant compared to that which results from natural background radiation. It should be noted that the use of radiation and radioactive materials for medical uses has resulted in a similar effective dose equivalent to the U.S. population as that caused by natural background radiation.
Significant discussion recently has centered eround exposures from radon.
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 s
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 asarage annual effective dose equivalent from radon in the United
! States is approximately 200 arem/ year. This estimated dose is approximately twice the average dose equivalent from all other natural background sources.
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Electric Power Production l
I 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.
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However, nuclear plants require 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.
All paths.through which radioactivity is released are monitored. Liquid and gaseous effluent monitors record the radiation levels for each release. These monitors also provide alarming mechanisms to allow for termination of any release above limits.
I Releases are monitored 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 l
radioactive materials from the plant tightly controlled, but measurements are made in surrounding areas to ensure that the population is not being exposed j to significant levels of radiation or radh active materials.
l Plant Technical Specifications limit the release of radioactive effluents, as 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 public.
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1 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, are. limited to the following:
Liquid Effluents.
Total body 13 mrem / year-per-unit-Any organ 110 mrem / year per unit' Gaseous Effluents Noble gases:
Gamma radiation 110 mrad / year per unit Beta radiation 120 mrad / year per unit Particulate:
Any organ 115 mrem / year per unit.
The EPA limits 'for.the total dose to the public in the vicinity of a nuclear-
!c power plant, established in the Environmental Dose Standard of 40 CFR 190, are as follows.
i Total body 25 mrem / year Thyroid 75 mrem / year Any other organ 25 mrem / year L .
b In addition, 10 CFR 20.106 provides maximum permissible concentrations (MPCs) for Radioactive materials released to unrestricted areas. MPCs for the principal radionuclides associated with nuclear power plant effluents are presented in table 1.
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SITE / PLANT DESCRIPTION The Sequoyah Nuclear Plant (SQN) is located.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, iennessee, 14 miles west-northwest of Cleveland, Tennessee, and approximately 31 miles south-southwest of TVA's Watts Bar Nuclear Plant (WBN) site.
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 SSW, clockwise, to the NH sector. This concentration -15 a reflection of suburban Chattanooga and the town of Soddy-Daisy. This area is characterized by considerable vacant land with 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 l
Soddy-Daisy has approximately 10,000 people.
4 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 l semirural and rural dwellings with associated small-scale farming. At least 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 l
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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.
i The SQN consists of two pressurized water reactors: each unit is rated at 1171 megawatts (electrical). 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 l t
plant, shut down in August 1985, was restarted in 1988. :
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ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM The unique environmental concern associated with a nuclear power plant is its production of radioactive materials and radiation. The vast majority of this radiation and radioactivity is contained within the reactor itself or one of the other plant systems designed to keep the material in the' plant. The retention of th'e materials in each level of control is achieved by system engineering, design,. construction, and operation. Environ.nental 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 l
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 indire'ct (ground or terrestrial) pathway. The direct airborne pathway consists of I
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 f:
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
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designed to monitor these pathways.
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t A number of fact'rso 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-7.. lists the sampling stations and the types of samples collected from each. Modifications made to the program in 1988 are described in appendix B l
.and exceptions.to the sampilng 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 i.
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 1
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 L
patterns in the environment permits a determination, through comparison and l trending analyses, of whether the operation of SQN is impacting the i
environment and thus the surrounding population. The determination of impact during the operating phase also considers the presence of control stations
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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.
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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 t
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 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 proportional to the radiation to which the material was exposed. Materials l
which display these characteristics are used in the manufacture of TLDs. r 1
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TVA uses a manganese activated calcium fluoride (Ca,F:Mn) TLD material 1
( encased in a glass bulb. The bulb is placed in an energy compensating shield l
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to correct for energy dependence of the material. TLDs are placed approximately 1 meter above the ground, with three TLDs at each station.
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 TLD. The system meets or exceeds the performance specifications outlined in
egulatory Guide 4.13 for environmental applications of TLDs.
I 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 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 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."
l Prior to 1976, direct radiation measurements in the environment were made with
( less sensitive dosimeters. Consequently, environmental radiation levels t
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.
The quarterly gamma radiation levels determined from the TLDs 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 1 also shown.
Annual Average Direct Radiation Levels SQN l 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 l phase and in the stations at WBN and other nonoperating TVA nuclear power
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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 i
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of_ concrete. employed in.the construction of the plant. Other undetermined int luences may also play a part.
Figure H-l' 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 backgrouad 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 frequent.y. F.,sr 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 stations.
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.
I Sample Collection and Analysis Air particulate are collected by continuously sampling air at a flow rate of approximately 2 cubic feet per minute (cfm) +hrough 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 I
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 ga'nma spectroscopy. On a quarterly basis, ali 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 todine 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 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 1-gallon sample is removed from the container every 4 weeks. Any excess water is discarded. Rainwater samples are held to be analyzed only i' the air particulate samples inalcate the presence of elevated activity lavels or if fallout is expected. For example, r&inwater samples were analyzed during the period of fallout following the accident at Chernobyl. No rainwater samples 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 pC1/m'. The annual averages of the gross beta activity in air I 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 sarnple at a level slightly higher than the nominal LLD.
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l TERRESTRIAL MONITORING 1
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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 d posited on a vegetable garden and be ingested along with the vegetables or it may be deposited on pasture grass I l
where dairy cattle are grazing. When'the cow ingests the radioactive ]
l material, some of it may be in 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 potential impacts from exposure to this pathway. The.results from the analysis of these samples are shown in tables 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 samples. The results of the 1988 land use survey are presented in appendix G.
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) Sample Collection and Analysis Milk samples are purchased every 2 weeks from the dairy from two of the farms I
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 radioanalytical f
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.
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Samples of vegetation are collected every 4 weeks for I-131 an'alysis. The 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.
, Carejs'takennottoincludeanysoilwiththevegetation. The sample is placed in a container with 1650 ml of 0.5 N Na0H for transport back to the fadioanalytical 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 gearter, the sample is ashed after the gamma analysis is completed and analyzed for Sr-89,90.
Soll samples are collected annually from the air monitoring locations. The samples are collected with either a " cookie cutter" or an auger type sampler.
_ Af ter 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 i
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 L
i 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 prepared as if it were to be eaten and is analyzed by gamma spectroscopy.
After drying, grinding, and ashing, the sample is ana'lyzed for gross beta activity.
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4 Results-The results from the analysis of milk samples are presented in table H-4. No radioactivity which could be attributed to SON was identified. All I-131 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 LLD. Strontium-90 was found in less than half of the samples. These levels are consistent with concentrations measured in samides collected prior to
- plant operation and with concentrations reported in milk as a result of
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fallout from atmospheric nuclear weapons tests (reference 1). The average Strontium-90 concentration reported from indicator stations was 8.7 pC1/ liter. An average of 2.2 pC1/ liter was identified in samples from control stations. By far the predominant isotope reported in milk samples was the naturally occurring X-40. An average of approximately 1300 pCi/ liter of K-40 was identified in all milk samples.
As has been noted in this series of reports for previous years, the levels of 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 I
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 preoperational radiological monitoring near SQN and near the Bellefonte Nuclear Plant (under construction) at farms L
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 from those of the larger dairy farmers to the extent that fallott from atmospher.ic nuclear weapons testing may be more concentrated in these instance $. Similarly, Hansen, et al. (reference 4), reported an inverse relationship between the levels of_Sr-90 in milk ard'the quality of fertilization and land management.
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 pCi/kg for indicator and control stations, respectively. Strontium-90 levels averaged 127 pCi/kg from indicator stations and 150 pC1/kg from control stations.
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 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).
i 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.
p
f AQUATIC HONITORING Potential exposures from the 11guld pathway can occur from drinking. water, ingestion of edible fish and clams, or from direct radiation exposure from radioactive materials deposited in the river sediment. The aquatic monitoring program includes the collection of samples of river (reservoir) water, groundwater, drinking water supplies, fish, Asiatic clams, and bottom and 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 Co-60, Cs-134, and Cs-137 was identified in some samples; however, the projected exposure to the public is negligible.
Sample Collection and Analysis Samples of surface water are collected from the Tennessee River using automatic sampling pumps from two downstream stations and one upstream station. A timer turns on the pump 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 flushed and a sample collected into a composite jug. A 1-gallon sample is renoved 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 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 b downstream drinking water intake. These samples are collected in the same l
manner as the surface water samples. These monthly samples are analyzed by l
l 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
)
L the automatic pumping device is taken directly from the river at the intake l
structure. Since the sample at this point is raw water, not water processed l
through the water treatment plant, the control sample should also be i unprocessed water. Therefore, the upstream surface water sample is also I
considered as a control sample for drinking water.
u 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.
Samples of commercial and game fish species are collected semiannually from each of three reservoirs: the reservoir on which the plant is located (Chihckamauga Reservoir), the upstream reservoir (Watts Bar Reservoir), and i the downstream reservoir (Nickajack Reservoir). The sarrales 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. When the 1
y-h gamma analysis is completed,-the sample h ashed.and analyzed for gross beta activity. ..
Bottom'and shoreline sediment is collected semiaa.nually from selected TRM i
. locations using a dredging apparatus. 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 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 to find. Enough clams are collected to produce approximately 50 grams of wet i
i flesh. The flesh is separated from the s5 ells, and the dried flesh samples '
are analyzed by. gamma spectroscopy.
Results '
Gross beta activity wa, present in most surface water samples. Concentrations in downstream samples averaged 2.9 pC1/L while the upstream samples averaged I 2.7 pCi/L. All other values were consistent with previously reported levels from fallout. A trend plot of the gross beta activity in surface water. I l 1 l .. samples-from 1971 through 1988 is presented in figure H-4. -A summary table of ;
1 the results is shown in table H-13.
I 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 l
I I
. -_ _ _ - _ -_ _-_ _a
result of artifacts in the-calculational process. Average gross beta activity was 2.7 pCi/ liter at the downstream stations and 2.8 pCi/ liter at the control stations. The results are shown 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.
i Concentrations of fission and activation products in ground water were all below the LLDs. Only naturally occurring radionuclides were identified in these samples. The average gross beta concentration in samples from the onsite well was 3.7 pCi/ liter, while the average from the offsite well was 3.4 pCi/ liter. The results are prescated in table H-15.
Cesium-137 was identified in 11 fish samples. The downstream samples contained a maximum of 0.14 pC1/g, while the upstream sample had a maximum of 0.22 pC1/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 pCl/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 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 pC1/g in downstream samples and 0.99 pCi/g upstream. In shoreline sediment, Cs-137 levels were 0.09 and 0.14 pCi/g, respectively, in downstream and l
l I
l l
q
.c l
' upstream samples. These values are consistent with previously identified 3
i fallout levels; therefore, they are probably not a result .f SQN operations. -)
i In bottom sediment, Co-60 concentrations l'n downstream emples averaged 0.26 )
pC1/g,.while concentrations upstream averaged 0.08 pC1/g. The maximum concentrations were 0.57 and 0.10 pC1/g, respectively. Cesium-134 concentrations in upstream samples were all below the LLD. Levels in downstream samples averaged 0.04 pCi/g, wit;1 a maximum of 0.04 pC1/g. A realistic assessment of the impact to the general public from this activity produces a negligible dose equivalent. Results from the analysis of bottom sediment samples are shown in table H-20.
Co-60 was identified in only one shoreline sediment sample. A concentration of 0.02 pCi/g was found in a downstream station. This is less than the Co-60 levels found in upstream bottom sediment samples, indicating no impact from SQN. Results from the analysis of shoreline sediment samples are shown in table P.21.
Co-60 was also identified in two downstream clam flesh samples. A maximum concentration of 1.56 pC1/g was found at TRM 483.4. The dose projected from f the ingestion of clams with this concentration is 0.3 mrem / year. However, clams are not known to be consumed; therefore, no dose will be r .eived by humans through this pathway. The results from the analysis of cr im samples are presented in table H-22.
)
i
I l upstream samples. These values are consistent with previously identified '1 l
fallout levels; therefore, they are probably not a result of SON operations.
1 In bottom sediment, Co-60 concentrations in downstream samples averaged 0.26 pCi/g, while concentrations upstream averaged 0.08 pC1/g. The maximum i 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 pCl/g, with a maximum of 0 04 pC!/g. A rtalistic assessment of the impact to the general public from this activity produces a negligible dose equivalent. Results from the analysis of bottom sediment samples are shown le table H-20.
I 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 levels found in upstream bottom sediment samples, indicating no impact from SQN. Results from the an; lysis of shoreline sediment samples are shown in table H-21.
l Co-60 was also identified in two downstream clam flesh samples. A maximum concentration of 1.56 pCi/g was found at TRM 483.4. The dose projected from 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.
I I E
ASSESSMENT ANJ EVALUATION 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 Guitle 1.109 for determining the potential dose to individuals and populations li'ing in the vicinity of the plant. The doses calculated are a representation of the dose to a " maximum exposed i nrii v i dual . " 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 " maximum" person. In reality, the expected dose to actual l inriividuals is lower.
l 1
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 11guld and gaseous effluents.
For liquid effluents, the public can be exposed to radiation from three sources: drinking water from the Tennessee River, eating fish caught in the Tennessee River, and direct exposure to radioactive material due to activities on the banks of the river (recreational activities). Data used to determine these doses are based on guidance given by the NRC for maximum ingestion
> rates, exposure times, and distribution of the material in the river.
Whenever possible, data used in the dose calculation are based on specific conditions for the SQN area.
1 1
f 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 radioactivity 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 vegetation containing deposited radioactivity. The concentrations of radioactivity in the air and the soll 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 l 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.
1 As indicated, the estimated increase in radiation dose equivalent to the general public resulting from the operation of SQN is trivial when compared to the dose from natura'l background radiation.
l f
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.
)
r Dose estimates were made from concentrations of radioactivity found in samples 1,
of environmental media. Media evallated include, but are not limited to, air, '
mllk, food products, drinking water, and fish. Inhalation and ingestion doses estimated for persons at the indicator locations were essentially identicai 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 nucle;r 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 '( H and from the trend plots presented 'in appendix H that the exposure to members 4
of the general public which may have been attributable to SON is negligible.
The radioactivity reported herein is primarily the result of fallout or
.n. ;
L 1
natural background radiation. Any activity which may be present as a result l 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 equ' valent from gaseous effluents is 0.014 ,
mrem / year. This represents less than 1 percent of the Technical Specification limit.
s
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Table 1 MAXIMUM PERMISSIBLE CONCENTRATIONS .
FOR NONOCCUPATIONAL EXPOSURE i l
MPC In Water In Air 4 pCi/l* PCi/m'*
Gross beta 3,000 100 H-3 3,000,000 200,000 Cs-137 20,000 500 Ru-103,106 10,000 200 Ce-144 10,000 200 Zr Nb-95 60,000 1,000 Ba-140 - La-140 20,000 1,000 I-1 31 300 100 Zn-65 100,000 2,000 Mn-54 100.000 1,000 Co-60 30,000 300 Sr-89 3,000 300 Sr-90 300 30 Cr-51 2,000,000 80,000 Cs-134 9,000 400 Co-58 90,000 2,000
- 1 pCi - .7 x 10-' Bq.
Source: 10 CFR, Part 20, Appendix B, Table II.
r
Table 2 Maximum Dose due to Radioactive Effluent Releases Sequoyah Nuclear Plant 1988 mrem / year Liquid Effluents 1988 NRC Percent of EPA Percent of
- Type Dose Limit NRC Limit Limit EPA Limit ;
Total Dody 0.30 6 5.0 25 1.2 Any Organ 0.36 20 1.8 25 1.4 Gaseous Effluents 1988 NRC Percent of EPA Percent of 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 (Beta)
Any Organ 0.014 30 0.05 25 0.06 i
i f
l
)
f
)
REFERENCES l
- 1. Merril Eisenbud, Environmental Radioactivity, 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, "InstructP,.i 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 Helfare; Public Health Service Publication No. 999-R-6, May 1964.
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APPENDIX A 1
l L
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Table A-2 SEQUOYAH NUCLEAR PLANT
. Environmental Radiological Monitoring Program Sampling Locations Map Approximate Indicator (I) location Distance or Number
- Station Seffor (miles) Control (C) Samples Collected" 2 LM-2 N 0.8 I AP,CF,R S,V 3 LM-3 SSW l.2 I AP,CF,R,S,V 4 LM NE 1.5 I AP,CF.R.S,V 5 LM-5 NNE 1.8 I AP,CF,R,S,V 7 PM-2 SW 3.8 I AP,CF,R,S,V' 8 PM-3 W 5.6 I AP,CF,R,S,V' 9 PM-8 SSW 8.7 I AP,CF,R,S,V' 10 PM-9 WSW 2.6 I AP,CF,R,S V' 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 LSE 11.3 C AP,CF,R,S,V' 14 RM-4 WNW 18.9 C AP,CF,R.S,V 15 Farm 8 NE 43.0 C M,V' 16 Farm C NE 16.0 C M,V*
17- Farm S NNE 12.0 C M,V 18 farm J WNW l.1 I M,V 19 Farm HW NW l.2 I M,V,Wd 20 Farm EM N 2.6 I V 21 Farm Br' SSW 2.2 I V 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) l t
33 TRM 465.3 --
19.2' I PW (Chattanooga) 34 TRM 497.0 --
19.3' C PW
(' (Dayton) 36 TRM 496.5 --
0.5' C SS
! 38 TRM 483.4 --
1.I' I CL,SD,SW 39 TRM 480.8 --
3.7' I CL,SD 40 TRM 477.0 7.5' I SS 41 TRM 473.2 --
11.3' I SW 42 TRM 472.8 11.7' I SD 44 TRM 478.8 6.5' I SS Table A-2 SEQUOYAH NUCLEAR PLANT Environmental Radiological Monitoring Program Sampling Locations (Continued)
Map Approximate Indicator (I) location Distance or Number
- __ Station Sector (miles) Control (C) Samples Collected" 45 TRM 425-471 -- --
I F (Nickajack Reservoir) 46 TRM 471-530 -- --
I F j (Chickamauga '
Reservoir) 47 TRM 530-602 -- --
C F (Watts Bar Reservoir) 48 Farm H NE 4.2 I M,V
- a. See figures A-1, A-2, and A-3
- b. Sample Codes AP - Air particulate filter CF - Charcoal filter CL - Clams F - Fish M - Milk PW - Public water R - Rainwater S = Soll SD - Sediment
{ SS - Shoreline sediment SW - Surface water V - Vegetation
} W - Hell water 1
- c. Vegetation sampling discontinued in August 1988.
- d. A control for well water.
- e. 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)
- g. Surface water sample also used as a control for public water.
Table A-3 SEQUOYAH NUCLEAR PLANT Thermolumlaescent Dosimeter (TLD) locations Approximate Onsite (On)"
Map .
Distance or L_ocation Number Station Sector (Miles) Offsite (Off) 3 SSW-1A SSW 1.2 On !
4 NE-1A NE 1.5 On 5 NNE-1 NNE 1.8 On 7 SW-2 SH 3.8 Off E W-3 W 5.6 Off 9 SSH-3 8.7 SSW Off 10 WSW-2A 2.6 11 WSW Off SW-3 SW 16.7 Off :
12 NNE-4 17.8 NNE Off 13 ESE-3 ESE 11.3 Off 14 WNW-3 18.9 WNW Off 49 N-1 N 0.6 On 50 N-2 2.1 N Off 51 N-3 5.2 N Off 52 N-4 N 10.0 Off 53 NNE-2 4.5 NNE Off 54 NNE-3 NNE 12.1 Off 55 NE-1 2.4 NE Off 56 NE-2 4.1 NE 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-1 ESE 1.2 On 63 ESE-2 4.9 ESE Off
{ SE Off j 69 SSE-1 SSE 1.6 On 70 SSE-2 4.6 SSE Off
) 71 S-1 S 1.5 On i 72 S-2 S 4.7 Off 73 SSW-1 SSW 0.6 On 74 SSH-2 4.0 75 SSW Off SH-1 SW 0.9 On 76 WSW-1 WSW 0.9 On 77 WSW-2 WSW 2.5 Off
Table A-3 i
SEQUOYAH NUCLEAR PLANT Thermoluminescent Dosimeter (TLD) locations Approximate 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 WNH-1 WNW 0.4 On 84 WNW-2 WNW 5.3 Off 85 NW-1 NW 0.4 On 86 NH-2 NW 5.2 Off 87 NNW-1 NNW 0.6 On 88 NNH-2 NNW 1.7 On 89 NNH-3 NNW 5.3 Off t
l
)
l 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.
)
Figure A-1 Environmental Radiological Sampling Locations Within 1 Mile of Plant l
348.75 N 11.25 NNW NNE 326.25 33.75 NW 2 NE 9 56.25 303.75 /
WNW
\ '8 ,
ENE 85 \, '
N A ./ /
281.25 '
/ 78 75 8 3 ' h *Y / / e'
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EQUOYAH ;
W- NUCLEAR -E !
, , \ ,-
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,' y Ci t ' '5 258.75 / E
- 5 101.25 WSW 76 f.
[ /
/ f 64 ESE i
/ 73 g 75 .
236.25 123.75
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j g6 SW ## ' 6 SE 213.75 O Ig# 6sS (146.25 SSW , SSE 191.25 168.75 S
Scale ,
O Mile 1 l
. 48
1 Figure A I Environmental Radiological Sampling Locations From 1 to 5 Miles From The Plant I
i I.
348.75 N 11.25 NNW NNE 326.25 _
33.75 NW h 3 NE 30s.75 56.25 20 4
/4 s.8 I WNW e55 ENE 281.25 C '
I* Op? 78.75 37' 82 1 .
'pS poG <
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/ 39' 7
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^ '
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.g 49
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Environmental Radiological Sampling Locations Greater Than 5 Miles From The Plant I
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'I A
k APPENDIX 8 1988 PROGRAM MODIFICATIONS i
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Appendix B 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.
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 I
requirements.
1 See tables A-2 and B-1 for locations no longer sampled.
I
Table B-1 i
SEQUOYAH NUCLEAR PLANT Environmental Radiological Monitoring Program Modifications 1988 I Date Station Modification 8/88 PM-2, PM-3, PM-8, Vegetation sampling discontinued I PM-9, RM-1, RM-2, RM-3, Farm-B, and Farm C i
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APPENDIX C MISSED SAMPLES AND ANALYSES i
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Appendix C Misssed Samples and Analyses l
During the 1988 sampling period, a small number of samples were not collected and several analyses were not completed on some collected samples. These occurrences resulted in deviations from the scheduled program but not from the program required by the Technical Specifications. A list of missed samples and analyses are found in table C-1.
l 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 l
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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 SSW 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 TRM 480.8 3.7 miles downstream 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 until 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.
Table C-1 SEQUOYAH NUCLEAR PLANT Environments.! Radiological Monitoring Program Exceptions (Continued)
Date Station Location Remarks 9/12/88 Farm HW 1.2 miles NW Milk samples not available - cow 9/26/88 " dry." Vegetatt samples routinely collected monthly.
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 to be expanded.
10/24/88 Farm J 1.1 miles WNW Milk samples not available - cow through " dry." Vegetation samples ;
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 - equipment failure 11/15/88 TRM 480.8 3.7 miles Clam samples collected but downstream sufficient 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 I
tube. Thicker walled tubes are now in use.
[-
) 12/28/88 TRM 465.3 19.2 miles Public w 'er samples not available downstream for collection - water line temporarily disconnected for repairs I
APPENDIX D ANALYTICAL PROCEDURES I
l
I
- 1 l
APPENDIX D l
Analytical Procedures 1
All analyses are performed by the radioanalytical laboratory located at 1 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 t
counting system. Normal counting times are 50 minutes. Water samples i
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.
1 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.
i
1 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.
Water samples are analyzed for tritium content by first distilling a portion of the sample and then counting by liquid scintillation. A commerically available scintillation cocktail is used.
Gamma analyses are performed in sarious 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 l HYPERMET.
The gaseous radiolodine analyses are performed with well-type NaI detectors interfaced with a single channel analyzer. The system is calibrated to measure I-131. If activity above a specified limit is ;
detected, the sample is analyzed by gamma spectroscopy.
All of the necessary efficiency values, weight-efficiency curves, and I- 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.
i i
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.i l
i APPENDIX E NOMINAL LOHER LIMITS OF DETECTION (LLD) l
)
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1 d.A.
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, 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.
I i
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 l
vary from that average. In order to determine the activity present in a !
L sample that will produce a reading above the critical level, additional l
statistical analysis of the background readings is required. The h hypothetical activity calculated from this analysis is called the lower limit of detection (LLD). A listing of typical LLD values that a j l
laboratory publishes is a guide to the sensitivity of the analytical
. measurements performed by the laboratory.
p 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'often.happens, about half the time its signal should fall below the average machine background and half the time it should be above the background. If a signal above the background is present, the
~
calculated activity 1's 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 ror 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 Technical Specifications, are presented in the following table.
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APPENDIX F QUALITY ASSURANCE / QUALITY CONTROL PROGRAM I
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i Appendix F q 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 performing the work, a nonconformance and corrective action tracking system, systematic internal audits, a complete training and retraining system, audits by various external organizations, and a laboratory quality control program.
The quality control program employed by the radioanalytical laboratory is designed to ensure that the sampling and analysis process is working as
' intended. The program includes equipment checks and the analysis of special samples along with routine samples.
Radiation detection devices are complex and can be tested in a number of ways. There are two primary tests which are performed on all devices.
In the first type, the device is operated without a sample on the t
detector to determine the background count rate. The background counts are usually low values and are due to machine noise, cosmic rays, or trace amounts of radioactivity in the materials used to construct the detector. Charts of background counts are kept and monitored to ensure that no unusually high or low values are encountered In the second test, the device is operated with a known amount of radioactivity present. The number of counts registered from such a
radioactive standard should be very reproducible. These reproducibility checks are also monitored to ensure that they are neither higher nor lower than expected. When counts from either test fall outside the expected range, the device is inspected for malfunction or contamination. It is not placec' 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 iso'; opes other than the one being measured.
l Duplicate samples are generated at random by the same computer program which schedules the collection of the routine samples. For example, if the routine program calls for four milk samples every week, on a random basis each farm might provide an additional sample several times a year.
These duplicate samples are analyzed along'with the other routine samples. They provide information about the variability of radioactive content in the various sample media.
1 There is another kind of replicate sample. From time tc 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 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 environmental samples.
The analyst does 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 routinely generates numerous zeroes for a 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 to determine whether or not the laboratory can find any unusual radioactivity whatsoever.
I At present, 5 percent of the laboratory workload is in the category of i
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 analysa 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 "rigct 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 j I
independent check of the entire measurement process that cannot be easily provided by the laboratory itself. Th'at 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 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 r esults of TVA's 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 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.
_ _ . 1 _ _ __ _ _ __.____._.____.____________._ __._________
All the quality control data are routinely collected, examined, tr.d 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 prui.ess that provides accurate data and is sensitive enough to measure the presence of radioactivity far below the levels which could be harmful to humans.
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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.
- b. The low strontium result was investigated. A definitive cause for the low result could not be identified. Further evaluation of the strontium radioanalytical procedure continues.
- c. Performance Evaluation Intercomparison Study.
I
- 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 pierocuries 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 I
i l
_ -----,--------------------..s---- _ .
APPENDIX G LAND USE SURVEY p
Appendix G Land Use Survey A land use survey is conducted annually to identify the location of the nearest milk animal, the nearest residence, and the nearest gardr of greater than 500 square feet producing fresh leafy vegetables in each of 16 meteorological sectors within a distance of 5 miles from the plant.
The land use survey also identifies the location of all milk animals and gardens of greater than 500 square feet producing fresh leafy vegetables within a distance of 3 miles from the plant.
The land use survey is conducted between April 1 and October 1 using appropriate techniques such as door-to-door survey, mail survey, telephone survey, aerial survey, or information from local agricultural authorities or other reliable sources.
From these data, radiation doses are projected for individuals living 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 calculated using design basis source terms and historical meteorological I data.
~77-
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.
The distances measured on this map were usually different from those reported in the land use survey. Now, the distances reported in the land use survey were used for dose calculation.
Doses calculated for air submersion varied slightly from t' hose calculated 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 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 calculated for 1987. Tables G-1, G-2, and G-3 show the comparative calculated doses for 1987 and 1988.
f I
Table G-1 SEQUOYAH NUCLEAR PLANT l Projected Annual Air Submersion Dose to the Nearest Resident Within five Miles of Plant (mrem / year / reactor) i 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 l ENE 1.4 0.03 1.3 0.03 E 1.1 0.02 1.0 0.03 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 ;
SSW l.4 0.13 1.3 0.16 l SW 1.9 0.04 1.8 0.04 WSW 0.7 0.08 0.7 0.08 W 1.1 0.03 0.6 0.08 WNW 1.1 0.02 1.1 0.02 NW 0.7 0.05 0.9 0.03 NNW 0.5 0.14 0.6 0.12 i
i
t Table G-2 SEQUOYAH NUCLEAR PLANT Proje'cted Annual Dose to Child's Critical Organ from.
Ingestion of Home-Grown Foods (mrem / year / reactor) 1987 Survey 1988 Survey-Approximate. Annual Dose Approximate Annual-Dose
-Sector- - Distance-(Miles) (Bone) Distance (Miles) (Bone)
N 1.0 - 2.54 1.1 -2.25 NNE 1.9 1.48 1.9 1.45 NE- 1.3' '2.30 1.4 2.03 ENE- a --
1.6 0.73 E. 1.6 0.39 a -
ESE. 1.2 0.59 1.1 0.68
.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 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 E NH; 0.7 1.37 0.9 1.10 NNH 0.5 3.96 0.6 2.88 L
)
- a. No garden was identified in this sector whithin 5 miles of the plant.
f
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)
Approximate Distance Annual Dose Location No. Sector (Miles)* 1987 1988 6
Farm EM N 2.6 0.05 0.04 Farm H* NE 4.2 0.03 0.02 Farm J6 WNW l.1 0.04 0.03 6
Farm HW NW l.2 0.06 0.06 I
l f
- a. Distances measured to nearest property line, f b. Vegetation sampled at this location.
l c. Milk sampled at this location.
APPENDIX H DATA TABLES I
l
) ,
l l
Table H-1 DIRECT RADIATION LEVELS Average External Radiation Levels at Various Distances from Sequoyah Nuclear Plant for Each Quarter - 1988 mR/ Quarter" Average External 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 1-2 17.8 1 3.0 15.2 1 3.4 16.7 1 2.8 16.2 1 2.6 2-4 17.4 1 3.2 14.5 1 3.4 16.512.8 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 Average, 19.2 1 2.7 17.6 1 3.8 18.2 1 2.6 17.8 1 3.2 0-2 miles (onsite) '
Average 16.9 1 2.5 14.4 1 3.1 16.9 1 2.7 15.6 1 2.4
>2 miles (offsite)
- 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.
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