ML20073G476

Annual Radiological Environ Operating Rept,Sequoyah Nuclear Plant,1990

ML20073G476
Person / Time
Site:	Sequoyah
Issue date:	12/31/1990
From:	Wallace E TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9105030332
Download: ML20073G476 (116)

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l A lenne$see Vabey Authnrdy 1101 Market Street Chmtanooga Tennessee 37402 April 29, 1991 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen: In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) - ANNUAL RADIOLOGICAL ENVIRCNMENTAL OPERATING REPORT In accordance with Technical Specification 6.9.1.6 for SQN Units 1 and 2, enclosed is the Annual Radiological Environmental Operating Report for 1990. No commitments are contained in this submittal. Please direct questions concerning this issue to W. C. Ludwig at (615) 843-7460. Very truly yours, TENNESSEE VALLEY AUTHORITY E. G. Wallace, Manager Nuclear Licensing and Regulatory Affairs Enclosure cc: See page 2 i [ 7 / h R-(I l \\

l 1 2 U.S. Nuclear Regulatory Commission April 29, 1991 1 cc (Enclosure): Ms. S. C Black, Deputy Director Project Lirectorate II-4 I U.S. Nuclear Regulatory Commission l J One White Flint, North j 11555 Rockville Pike Rockville, Maryland 20852 a Mr. D. E. LaBarge, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North "7 11555 Rockville Pike Rockville, Maryland 20852 NRC Resident Inspector -l Sequoyah Nuclear Plant i 2600 Igou Ferry Road l Soddy Daisy, Tennessee 37379 j i Mr. B. A. Wilson, Project Chief i U.S. Nuclear Regulatory Commission i Region II i 101 Marietta Street, N'W, Suite 2900 Atlanta, Georgia 30323 9 l s i i I 3 1 L 1 1 L 1. J

a e ) i o 1 . l 0 1 l 1 J-i W t I i t ENCLOSURE 1i i 1 4 i i ' AhWUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT a 1 SEQUOYAH NUCLEAR PLANT - r

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1 TENNESSEE VALLEY AUTHORITY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SEQUOYAH NUCLEAR PLANT 1990 CHEMISTRY AND RADIOLOGICAL SERVICES

} i ? ? -v l 1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SEQUOYAH NUCLEAR PLANT 1990 TENNESSEE VALLEY AUTHORITY NUCLEAR OPERATIONS SERVICES CHEMISTRY AND RADIOLOGICAL SERVICES l l l l l April.1991 l-l i

j TABLE OF CONTENTS I J i Table of Contents......................... 11 List of Tables iv I List of figures........,.................. Y Executive Summary......................... I 1 4 4 Introduction 2 Naturally Occurring and Background Radioactivity........ 2 Electric Power Production 5 Site / Plant Description 8 i Environmental Radiological Monitoring Program........... 10 l Direct Radiation Monitoring.................... 14 Measurement Techniques..................... 14 Results 15 Atmospheric Monitoring 18 Sample Collection and Analysis.................. 18 Results 19 Terrestrial Monitoring 21 Sample Collection and Analysis....,............ 21 j Results 22 Aquatic Monitoring 25 Sample Collection and Analysis.....,........... 25 Results 1 27 Assessment and Evaluation..................... 30 l Results 31 Conclusions 32 References 33 Appendix A Environmental Radiological Honitoring Program and 3 Sampling Locations 38 1 Appendix B 1990 Program Modifications 51 i , i i i l 11

Appendix C Hissed Samples and Analyses.............. 54 Appendix 0 Analytical Procedures................. 57 Appendix E Nominal Lower Limits of Detection (LLD) 60 Appendix f Quality Assurance / Quality Control Program....... 66 Appendlx G Land Use Survey.................... 74 Appendix H Data Tables...................... 80 til

LICT OF TABLES Table 1 Maximum Permissible Concentrations for Nonoccupational Exposure................ 34 Table 2 Maximum Dose Oue to Radioactive Effluent Releases........................ 35 i Y I l

f i LIST OF FIGURES i i Figure 1 Tennessee Valley Region....... 36 1 Figure 2 Environmental Exposure Pathways of Man Due 37 to Releases of Radioactive Materials to the Atmosphere and Lake t a y P c 4 s d V

2 EXECUTIVE

SUMMARY

This report describes the environmental radiological monitoring program d conducted by TVA in the vicinity of the Sequoyah Nuclear Plant in 1990. 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 impacts of plant l 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 l nuclear weapons fallout. l Small amounts of Co-58 and Co-60 were found in sediment samples l downstream from the plant. This activity in stream sediment would result in no measurable increase over background.in the dose to the aeneral public.

_ _ _ _ _. _ _. _ _. _ _ _ _. _ _ -. _. ~. _ _. _ _ _.. I 1 i 4 i INTRODUCTION i k This report describes and summarizes a large volume of data, the results of I l thousands of measurements and laboratory analyses. The measurements are made 1 1 to comply with regulations and to determine potential effects on public health and safety. This report satisfies the annual reporting requirements of the SQN Technical Specification 6.9.1.6. In addition, estimates of the maximum potential doses to the surrounding population are made from-radioactivity 1 1 measured both in plant effluents and in environmental samples. Some of the i j data presented-are prescribed by specific requirements while other data are included which may be useful or interesting to individuals who do-not work j with this material routinely. Naturally Occurring and Backaround Radioactivity Most materials in our world contain trace amounts of naturally occurring 2 radioactivity. Approximately 0.01 percent _of all potassium.is radioactive i 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 ^ [ K-40 which delivers a dose of 15 to 20 mrem per year to the bone and soft tissue of the body. Naturally occurring radioactive materialsLh' ave always been in our environment. Other examples of naturally occurring radioactive materials are bitmuth-212 and 214,. lead 212 and 214, thallium-208, l actinium-228,~ uranium-238, uranium-235, thorium-234, radium-226, radon-222, carbon-14, and hydrogen-3 (generally called tritium)'. These naturally _ i l occurring radioactive materials are in the soil.our food, our_ drinking water;, and~our bodies.. l ~a -.,. a .-.w

The radiation from these materials makes up a part of the low-level natural d j background radiation. The remainder of the natural background radiation comes i from outer space. We are all exposed to this natural radiation 24 hours per day. The average dose equivalent at sea level resulting from radiation from outer f space (part of natural background radiation) is about 27 mrem / year. This J i essentially doubles with each 6600-foot increase in altitude in the lower atmosphere. Another part of natural background radiation comes from naturally occurring radioactive materials in the soil and rocks. Because the quantity of naturally occurring radioactive material varies according to geographical location, the part of the natural backgiound radiation coming from this radioactive material also depends upon the geographical location. Most of the remainder of the natural background radiation comes from the radioactive materials within each individual's body. We absorb these materials from the 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 emounts of uranium, radium, thorium, etc. Because the city of Denver, Colorado, is over 5000 feet in altitude and the soil and rocks there contain more radioactive material than the U.S. average,the people of Denvm receive around 350 mrem / year total natural l i . 1

background radiation dose equivalent compared to about 295 mrem / year for the l national average. People in some locations of the world receive over 1000 mrem / year natural background radiation dose equivalent, primarily because of { the greater quantity of radioactive materials in the soil and rocks in those locations. Scientists have never been able to show that these levels of radiation have caused physical harm to anyone. It is possible to get an idea of the relative hazard of different types of radiation sources by evaluating the amount of radiation the 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 i Total 295 i Release of radioactive material in 5 l natural gas, mining, ore processing, etc. Medical (effective dose equivalent) 53 Nuclear weapons fallout less than 1 l l Nuclear energy 0.28 Consumer products 0.03 Total 355 (approximately) 1 As can be seen from the table, natural background radlatten 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 j that which results from natural background radiation. It should be noted that l the use of radiation and radioactive materials for medical uses has resulted j in a similar effective dose equivalent to the U.S. population as that caused by natural background cosmic and terrestrial radiation. i I Cignificant discussion recently has centered around exposures from radon. ] Racon 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 J) has estimated that the average annual effective dose equivalent from radon in the United i States is approximately 200 mrem / year. This estimated dose is approximately l twice the average dose equivalent from all other natural background sources. 4 Electric Power Production Nuclear power plants are similar in many respects to conventional coal burning (or other fossil fuel) electrical generating plants. The basic process behind electrical power production in both types of plants is that fuel is used to heat water to produce steam which provides the force to turn turbines'and. generators. However, nuclear plants include many complex systems to control the nuclear fission process and to safeguard against the possibility of I reactor malfunction, which could lead to the release of radioactive materials. 1.

l j Very small amounts of these fission and activation products are released into 1 i the plant systems. This radioactive material can be transported throughout plant systems and some of it released to the environment. i f i All paths through which radioactivity is released are monitored. Liquid and J 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. 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 radioactive materials from the plant tightly controlled, but measurements are j made in surrounding areas to verify that the population is not being exposed to significant levels of radiation or radioactive materials. The SQN Offsite Dose Calculation Manual (00CM), which is required by the plant Technical Specifications, prescribes limits for the release of radioactive effluents, as well as doses to the general public from the release of these effluents. Additional limits are set by the Environmental Protection Agency (EPA) for dotes to the public. The dose to a member of the general public from radioactive materials released i l to unrestricted areas 4 as given in the Offsite Dose Calculation Manual, are limited to the following: I I l l L l

LLqul_ d_ _E f fl uen t s Total body <3 mrem / year Any organ (10 mrem / year i Gaseous Effluents Noble gases: i Gamma radiation 110 mrad / year Beta radiation 120 mrad / year f Particulates: } Any organ 115 mrem / year 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. Total body 25 mrem / year Thyroid 75 mrem / year 4 i Any other organ 25 mrem / year 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. Dower plant effluents are presented in table 1, h ( ~7

V SITE / PLANT DESCRIPTION The SQN is located on a site near the geographical center of Hamilton county, Tennessee, an a peninsula on the western shore of Chickamauga Lake at Tennessee River Mile (TRM) 484.5. Figure I 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 (WBN) site. Population is distributed rather unevenly within 10 miles of the SQN site. d 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 NW sector. This concentration is a reflection of suburban Chattanooga and the town of Soddy-Daisy. This area is characterized by considerable vacant land with scattered residential subdivisions. The northern extent of the re:1dential development is approximately 2 miles from the site. The population of the Chattanooga urbanized area is over 250,000, while Soddy-Dalsy has approximately 10,000 people. l Hith the exception of the ccmmunity of Soddy-Daisy, the areas west, north, and east of the plant are sparsely settled. Development consists of scattered semirural and rural dwellings with associated small-scale farming. /.t least one dairy farm is located within a 10-mile radius of the plant. Chickamauga Reservoir is one of a series of highly controlled multiple-use reservoirs whose primary uses are flood control, navigation, and the I -

i generation of electric power. Secondary uses include industrial and pubile water supply and waste disposal, commercial fishing, and recreation. Public access areas, boat docks, and residential subdivisions have been developed along the reservoir shoreline. SON consists of two pressurized water reactors: each unit is rated at 1171 ] megawatts (electrical). Fuel was loaded in unit I on March 1, 1980, and the unit achieved critically on July 5, 1980. Fuel was loaded in unit 2 in July j 1981, and the unit achieved initial criticality on November 5, 1981. The plant, shut down in August 1985, was restarted in 1988. 1 i 1 l I l t l l l -9

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 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 environinental radiological monitoring program is outlined in appendix A. There are two primary pathways by which radioactivity can move through the environment to humans: air and water (see figure 2). The air pathway can be separated into two components: the direct (airborne) pathway and the indirect (ground or terrestrial) pathway. The direct airborne pathway consists of direct radiation and inhalation by humans. In the terrestrial pathway, radioactive materials may be deposited on the ground or on plants and subsequently be ingested by animals and/or humans. Human exposure through the liquid pathway may result from drinking water, eating fish, or by direct exposure at the shoreline. The types of samples collected in this program are designed to monitor these pathways. , l

_. -. - - - - - - - - ~ . ~. - -. _. -. -. - -. -.. i i I A number of factors were considered in determining the locations for } collecting environmental samples. The locations for the atmospheric j monitoring stations were determined from a critical pathway analysis based on j weather patterns, dose projections, population distributton, and land use. l Terrestrial sampling stations were selected Oer reviewing such things as the j locations of dairy animals and gardens *n conjunction with the. air pathway analysis. 1.1guld pathway stations we,e s( <cted based on dose projections, water use information, and availability of inedia such as fish and sediment. i Table A-2 lists the sampilng stations and the types of samples collected from i each. Modifications e.ede to the program in 1990 are described in appendix 8 l and exceptions to the sampling and analysts schedule are presented in appendix C. i j To determine the amount of adioactivity in the environment prior to the operation of SQN, a preoperational environmental radiological monitoring. 1 j program was initiated in 1971 and operated until the plant began operation in 1980. Measurements of the same types of radioactive materials-that are j measured currently were assessed during the preoperational-phase to establish l normal background levels for various radionuclides in the environment. j The preoperational monitoring program is,a very important part of the overall' r i program. During the 1950s, 60s, and 70s, atmospheric nuclear weapons testing l l . 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 radionuclide patterns in-the. environment permits'a determination,- i i through comparison and trending' analyses, of whether. the operation'of SQN is. Impacting the-environment and thus the surrounding population. - _1 1..

The determination of impact during the operating phase also considers the presence of control stations that have been established in the environment. Results of environmental samples taken at control stations (far from the plant) are compared with those from indicator stations (near the plant) to establish the extent of 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 radionuclide content of samples collected in the environment are generally quite sensitive to small amounts of radioactivity. In the field of radiation measurement, the sensitivity of the measurement process is discussed in terms of the lower limit of detection (LLD). A description of the nominal LLDs for the radioanalytical laboratory is presented in appendix E. The radioanalytical laboratory employs a comprehensive quality assurance / quality control program to monitor laboratory performance throughout the year. The program 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 -12 l

4 alongside routine environmental samples. In addition, samples split with the Environmental Protection Agency and with the State of Tennessee provide an independent verification of the overall performance of the laboratory. A complete description of the program is presented in appendix F. 4 I 1 I I 1 i l t

s i 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 tetts i 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. i Radiation levels measured in the area around the SQN site in 1990 were consistent with levels from previous years and with levels measured at othe'- locations in the region. Measurement Techniaues 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 rema!n trapped for long periods of time as long as the material is not heated. When heated (thermo-), the electrons are released, 4 along with a pulse of light (-luminescence). The intensity of the light pulse is directly proportional to the radiation to which the material was exposed. Materials which display these characteristics are used in the manufacture of TLDs. i l From 1968 through 1989, TVA used a Victoreen dosimeter consisting of a l manganese activated calcium fluoride (Ca,F:Mn) TLD material encased in a glass bulb. L w

In 1989, TVA began the process o; changing from the Victoreen dosimeter to the Panasonic Model U0-814 dosimeter, and completely changed to the Panasonic dosimeter in 1990. This dosimeter contains four elements consisting of one lithium borate and three calcium sulfate phosphors. The calcium sulfate phosphors are shleided by approximately 1000 mg/cm' plastic and lead to compensate for the over-response of the detector to low energy radiction. The TLDs are placed approximately 1 meter above the ground, with three TLDs at each station. S xteen stations are located around the plant near the site boundary, one station in each of the 16 sectors. Dosimeters are also placed at the perimeter and remote air monitoring sites and at 19 additional stations out to approximately 32 miles from the site. The TLDs are exchanged every 3 months and the accumulated exposure on the detectors is read with a Panasonic Model UD-710A automatic reader interfaced with a Hewlett Packard Model 9000 computer system. Since the calcium sulfate phosphor is much more sensitive that the lithium borate, the measured exposure is taken as the median of the results obtained from the nine calcium sulfate phosphors in three detectors. The values are corrected for gamma response, system variations, and transit exposure, with individual gamma response calibrations for each element. -The system meets or exceeds the performance specifications outlined in Regulatory Guide 4.13 for environmental applications of TLDs. Results All results are normalized to a standard quarter (91.25 days or 2190 hours). The stations are grouped according to the distance from the plant. The first i i group consists of all stations within -1 mile of the plant. / t a

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 more 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 dosimeters that were not as precise at lower exposures. Consequently, environmental radiation levels reported in the preoperational phase w 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 1990 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 preeperational phase of the monitoring program are also shown. Annual Average Direct Radiation Levels SQN mR/ year Preoperational 1990 Average Onsite Stations 62 79 Offsite Stations 54 63 l 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 WBN 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 influences may also play a part. These conclusions are supported by the fact that similar differences between onsite and offsite stations were measured in the vicinity of the Watts Bar Nuclear Plant construction site. 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 1990. To reduce the seasonal variations present in the data sets, a 4-quarter moving average was constructed for each data set. Figure H-2 presents a trend plot of the direct radiation levels as defined by the moving-averages. The data follow the same general trend as the raw data, but the curves are smoothed considerably. All results reported in 1990 are consistent with direct radiation levels identified at locations which are not influenced by the operation of SQN. There is no indication that SQN activities increased the background radiation levels normally observed in the areas surrounding the plant. _

i l 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 directions of greatest wind frequency. Four perimeter air monitoring stations are located in communities y 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. 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. Sample Collection and Analysis Air particulates are collected by continuously sampling air at a flow rate of approximately 2 cubic feet per minute (cfm) through a 2-inch Hcilingsworth and Vose LBS2tl glass fiber filter. The sampling system consists of a pump, a magnehelic gauge for measuring the drop in pressure'across the system, and a dry gas meter. This allows an accurate determination of the volume of air passing through the filter. This system is housed in a building approximately 2 feet by 3 feet by 4 feet. The filter is contained in a sampling head mounted on the outside of the monitor building. The filter is replaced every 7 days Each filter is analyzed for gross beta activity about 3 days after collection to allow time for the radon daughters to decay. l

Every 4 weeks composites of the filters from each location are analyzed by gamma spectroscopy. Gaseous radiolodine is collected using a com/nercially 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 1-131. If activity above a specified-limit is detected, a complete gamma spectroscopy analysis is performed. Ratnwater 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 if the air particulate samples Indicate the presence of elevated activity levels or if fallout is expected. For example, rainwater samples were analyzed during the period of fallout following the accident at Chernobyl in 1986. No rainwater samples from SQN were analyzed in this reporting period. -Results The results from the analysis of air-particulate samples arel summarized in table H-2, Gross beta activity in 1990 was consistent with levels reported-in previous years. The average level at both indicator and control stations was i 0.020 pCl/m, - _ _ _ _ _ _ _ _

The annual averages of the gross beta activity in air particulate filters at j these stations for the years 1971-1990 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 Cherr.obyl 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 radioac tve materials were identified by the monthly gamma spectral analysis or the air particulate samples. No fission or activation products were founn at levels greater than the LLDs. As shown in table H-3, iodine-131 was det.ected in eighteen charcoal canister samples at a level slightly higher than the nominal LLO. The highest levels reported are 0.052 3 and 0.031 pC1/m, respectively, for indicator and control stations. Gamma spectral analyses of these samples Indicated that the positive values were a result of interference from radon daughters in the samples. _- - _ _ _ - _ _ _ _ _ - - _ - _.

~ _. _ i TERRESTRIAL MONITORING 4 Terrestrial monitoring is accomplished by collecting samples of environmental media that may transport. radioactive material from the atmosphere to humans, j For example, radioactive material may be deposited on a vegetable garden and f-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 1 [ milk. Therefore, samples of milk, vegetation, soil, and food crops are J collected and analyzed to determine potential impacts from exposure to-this

[

pathway. The results from-the analysis of these samples are shown in tables' 3 H-4 through-H-12. ] i 3 j A land use survey is conducted annually to locate milk producingfanimalsland 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 1 have been identified within'5 miles of the plant. The' dairy and the1farmsiare l [ -considered indicator-stations and routinely provide milk'and/or vegetation samples. The results of the 1990 land Use survey are presented.in appendix G. 4 f i

Sample Collection and Analysis a

_. Milk samples are:-purchased every 2 weeks from the~ dairy from two ofs the.: farms '. t)lthin 5 miles'of the' plant and from:at'least'one-of three: control: dairies These samples are placed on lce:forf transportito the :radioanalytical -: laboratory. A= specific-analysis for.1-131=and a gammaispectroscopy: analysis. i are performed on each sample and Sr-89,'90~ analysis is' performed every 4 weeks. -21. b _m ,.-r ,,m.. ...-~~.m. 1.,,, ,~,.,,y..., ,m.,.* r e --- -r ---J' w-+ 8-

Samples of vegetation are collected every 4 weeks for I-131 analysis. The samples are collected from the farm producing milk but unable to provide a milk sample, and from one control station. 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 soll 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 1990 samples of apples, cabbage, corn, green beans, potatoes, and tomatoes were collected from local vegetable gardens. The edible portion of each sample is prepared as if it were to be e'aten and is. analyzed by gamma spectroscopy. After drying, grinding, and ashing, the sample is analyzed for gross beta activity. 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. __

l Only two samples contained 1-131 values above the established nominal LLO of 0.2 pCl/ liter. Both of these samples were from control stations. 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. The Cs-137 and Sr-90 levels are consistent with concentrations measured in samples collected prior to plant operation and with concentrations reported in milk as a result of fallout from atmospheric nuclear weapons tests (reference 1). The average Strontium-90 concentration reported from indicator stations was 5.7 pC1/11ter. An average of 2.8 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 pC1/ 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 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 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 fallout from atmospheric nuclear weapons testing may be more concentrated in these '

i instances. Similarly, Hansen, et al. (reference 4), reported an inverse relationship between the levels of Sr-90 in milk and the quality of fertilization and land management. Results from the analysis of vegetation samples (table H-5) were similar to those reported for milk. All I-131, Cs-137, and Sr-90 values were less than the respective nominal LLDs. Again, the largest concentrations identified were for the naturally occurring isotopes K-40 and Be-7. The only fission or activation products identifled in soil samples were Cs-137 (identified in all 13 samples) and Sr-90 (identified in I sample). The maximum concentration of Cs-137 was 1.16 pCl/g and the Sr-90 concentration was j 0.45 pC1/g. These values are consistent with levels previously reported from fallout. All other radionuclides reported were naturally occurri_ng isotopes V (table H-6). All radionuclides reported in food samples were naturally occurring. The maximum K-40 value was 4310 pCl/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. 1 , i ,__________-,--.x_--.---a-

A_QUATIC MONITORING Potential exposures from the liquid 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 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 hours. The line is flushed and a sample collected into a composite jug. A 1-gallon = sample is 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 and for gross beta activity. A quarterly composite sample is analyzed for Sr-89,90 and tritium. Samples are also collected by an automatic sampling pump at the-first downstream drinking water intake.... O

These samples are collected ir, the same manner as the surface water samples. These monthly samples are analyzed by gamma spectroscopy and for gross beta activity. At other selected locations, grab samples are collected from drinking water systems which use the Tennessee River as their source. These samples are analyzed every 4 weeks by gamma spectroscopy and for gross beta activity. A quarterly composite sample from each station is analyzed for Sr-89,90 and tritium. In addition, samples from two of the stations are analyzed for I-131 content. 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. Samples of commercial and game fish species are collected semiannually from each of three reservoirs: the reservoir on which the plant is located (Chickamauga Reservoir), the upstream reservoir (Hatts 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 drying and grinding, the samples are analyzed by gamma spectroscopy. When the gamma analysis is completed, the sample is ashed and analyzed for gross beta. 1 activity. _

Bottom and shoreline sediment is collected semiannually from selected TRM locations using a dredging apparatus or Scuba divers. The samples are dried and ground and analyzed by gamma spectroscopy. Samples of Asiatic clams are collected semiannually from two locations below the plant and one location above the plant. The clams are usually collected l in the dredging or diving process with the sediment. However, at times the clams are difficult 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 l Gross beta activity was present in most surface water samples. Concentrations in downstream samples averaged 3.0 pCl/L while the upstream samples averaged 2.7 pC1/L. All other values were consistent with previously reported levels from fallout. A trend plot of the gross beta activity in surface water samplesfrom1971throIJgh1990ispresentedinfigureH-4. A summary table of the results is shown in table H-13. No fission or activation products were identified in drinking water samples. The positive Identification of Sr-89 at levels near the' LLO is typically a result of artifacts in the calculational process. Average gross beta activity-was 2.6 pC1/llter at the downstream stations and 2.7 pCl/llter 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. -

. -. -.-... ~... 4 4 i Concentration. ~ tion and activation products in ground water were all below the LLDs. Only...sially occurring radionuclides were identified in these samples. The average gross beta concentration in samples from the onsite well was 3.9 pC1/ liter, while the average from the offsite well was 7.1 pC1/ liter. The results are presented in table H-15. i Cesium-137 was identified in 7 fish samples. The downstream-samples contained I a maximum of 0.09 pC1/g, while the upstream sample.had a maximum of 0.12-pCi/g. Other radioisotopes found in fish were naturally occurringlwith the ^ most notable being K-40. The concentrations of K-40 ranged-from'3.7 pC1/gsto; 18.7 pC1/g. These results, which are-summarized in tables? H-16, H-17e H-18, and H-19, indicate that the Cs-137 activityils probably a result of falloutlor. other upstream effluents rather than activities at SQN. t Radionuclides of the-types produced by nuclear power plant operations werel identified.in sediment samples. The materials. identified!were Cs-137, Co-60, . s L and Co-58. In bottom sediment samplesLthe average;1evels of'Cs-137iwere 0.99i pCI/g'in downstream samples and 1.23'pCl/g. upstream.- - In ' shoreline sediment, p - Cs-137 levels-averaged 0.07 pCl/g-in downstream samples. Allivalues in j . upstream samples-were below the.LLO -These values are= consistent with [ previously identified fallout levels;:therefore..-they;are probably,not-a'

result of SON operations.

L.- In bottom sediment,:Co-60 concentrationseln downstream samplesfaveraged 0.:15 i [ pC1/g..while concentrations upstream averaged 0.07 pC1/g. 1 The: maximum s l_ concentrations were'0.28 and 0.09 pC1/g, respectively. 4 L 28-b v v n. 4 +--w-- x. m.. m +r w4%..- ,--,,,-v n'-s e,, e-~w,, -w.,,- w-,.r. e Y-e - -

Co-58 was identified in 3 downstream samples. The maximum concentration was 0.04 pCi/g and the average was 0.03 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 0.01 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 analysis of shoreline sediment samples are shown in table H-21. Only naturally occurring radioisotopes were identified in clam flesh samples. The results from the analysis of these samples are presented in table H-22. ___

-f s ASSESSMENT AND EVALUATION l j Potential doses to the public are estimated from' measured effluents using 'l l computer models. These models were developed by TVA and are based on i i methodology provided by the NRC in Regulatory Guide 1.109 for determining-the l potential dose to individuals'and populations living in the vicinity of a nuclear power plant. The doses calculated are a representation of the dose-to_ i a " maximum exposed Individual." Some of.the factors used in these calculations (such as ingestion rates) are maximum _ expected values _.which will'- t tend to overestimate the dose to this-" maximum" person. In reality,Lthe expected-dose to actual-individuals is lower. i l The area around the plant is analyzed to determine'the pathways through which-i the public may receive an exposure. i 'As11ndicatedL n_ figure 2, the7two' major i 4 l ways by which radioactivity is introduced into_the environmentiare through-4 liquid and gaseous effluents. i d for liquid effluents,.the public can be exposed.to radiation from three 1 l . sources: l drinking water from the Tenne'ssee River, eating; fish' caught:In the l { Tennessee River, and direct exposure to ' radioactive' material dueJto activities: on the banks of.the river (recreational activities). Data used.to determine .i e these_ doses are based hon-guidance given byf the 'NRC for maximum ingestion Lrates, exposure 1 times,-and' distribution of?the materialiln-the river.- t Whenever:possible,' data used in-theidose calculationfare-based on~ specific: conditions for-the SQN-area. 9 i-i For: gaseous effluents,_the publ.ic can be exposed to radiationLfrom several: ' sources: direct : radiation from the Lradioactivity 1n thei air.,Idirect radiation ? ~

30--

-i a

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 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 1990 are presented in table 2. These estimates were made using the concentrations of the liquids and gases measured at the effluent monitoring points. Also shown are the regulatory limits for these doses,and a comparison between the calculated dose and the corresponding limit. The maximum calculated whole body dose equivalent from measured liquid effluents as presented in table 2 is 0.006 mrem / year, or 0.2 percent of the limit. The maximum organ dose eaulvalent from gaseous effluents is 0.009 mrem / year. This l represents 0.1 percent of the ODCM limit. A more complete description of the effluents released from SQN and the corresponding doses projected from these effluents can be founu in the SQN Semlannual Radioactive Effluent Release Report. I As stated earlier in this report -the estimated increase in radiation dose equivalent to the-general public resulting from the operation of SON is trivial when compared to the dose from natural background radiation. The results from each environmental sample are compared with the concentrations from the corresponding control stations and appropriate preoperational and i

4 i background data'to determine influences from the. plant. During this report period, Co-60, Co-58, and Cs-137 were seen.in aquatic media. Cs~-137 in-sediment is consistent with -fallout levels identified in samples both upstream i l_ and downstream from the plant. Co-60 and Co-58 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 j i radioactivity attributable to SQN have been seen in water samples, i- } Oose estimates were made from concentrations of radioactivity.found-_in samples of environmental media. Media evaluated include, but are.not: limited to, Lair,_ 1 a milk, food products, drinking water, and fish. Inhalation _and ingestion doses-estimated -for persons at the indicator locations were essentially l' entical to' d i those determined for persons at. control stations. Greater than 95 percent _of- -i" those doses were contributed by the naturally: occurring radionuclide-K-40 and? i t j by Sr-90 and Cs-137, which are long-lived radioisotopes found in fallout from' nuclear weapons testing. Concentrations of.Sr-90-and Cs-137--:are consistent-- l with levels measured l_n TVA's preoperational environmental-radiological, i-monitor __ing programs. Conclustons { It is concluded from thelabove analysis of the environmental _ sampling'results -and from the -trend plots presented in appendix.H that the exposure to members: of the general public.which may have been attributable-to SQN is'neglig'ible.- .The radioactivity. reported herein is primarily'the result of fallout or natural background radiation. Any activity which may be present=as_-a~ result-i l of plant operations does not represent'a significant contribution'toithe exposure of' members of the public. i

i 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. j f ? i )

l i Table ! MAXIMUM PERMISSIBLE CONCENTRATIONS FOR NONOCCUPATIONAL EXPOSURE MPC In Hater In Air pCi/1* DC1/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 1-131 300' 100 Zn-65 -100,000 2,000 Mn 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

• ) pC1 - 3,7 x 10-# Bq.

Source: K CFR, Part 20, Appendix B, Table II. i

l -f l Table 2 -f ~ Maximum Dose due to Radioactiv'e Effluent Releases Sequoyah Nuclear Plant

1990

'mremlyear. a '!u Liquid Effluents-1990.- NRC: Percent of;

EPA

!. Percent-of J Type -Dose Limit NRC Limit: Limit EPA' Limit 4 -r 4 Total Body 0.006 3 0.2 25 0.024 i Any Organ 0.011-10-0.1 . 25

- 0.04 -

~ iu 1 I i 3 Gaseous-Effluents s 1990 NRC l Percent of EPA -Percent of. Type Dose Limit-NRC-Limit' JLimit' EPA Limit-L I 4 Noble Gas 0.42- -- 10 ' 4.2 25' L1571 J (Gamma) ,1 in Noble Gas ' f, 1.1 -- 20 ' 5. 5 ;- ~25 4.4 '1 (Beta) .i Any Organ 0.009-- ' 15 - 10.1: ?25 ', 0.031 L 1 k =-(- +

.0

.r. r j:. 11 5 .l 9 l:

i I

^V 4 a h :. d 1 : >;i i < 3 ~ a n

N (, e ur D. f). d 3 TENNESSEE VALLEY REGION \\ I N \\ f

1. r 0 - [ $. ".'..%

(TVA NUCLEAR PLANT SITES) ' \\, 0'N W V A. 5 Vc g hs ,D d' Y t )' g. " ~ ' " " J ,[- \\ 2 M O. / \\ /\\ 9 Y}JJ,:.... / ,(' M- / 4.-.. fi/ .(--..gdgKx v _M \\ ,..a t M 'l W. *' 1'j jg 'S S,.(

1. N 7

t / b l 9W , ~ f s -. y,) _Q)A - - t -[ c-s~u o, ,.j A i ? 3 ^ --3 fS [ )4 ,8 ~ N ,C A R. N\\N E% S T 4, j b ) %,/\\, ,' }' -* /-~' ? ** ascesong l O b,/?y l 0* j< G j% g i i t G ,~-. p.. - fh _f ,o cG - !. 9 O M [:..v.3 %> 1~1 f' S C A P- - / u1 \\ \\') :5 ',\\,j ~.) s>um,vun n 'y g u fEGEND \\ s j 5% e- % / l l $,_.I ~, '% Q M i S'S. If Li I -=rTs saa wetEma a4=r A L A.8 A M A GEORGI A -scouoraa =ctEma naar ,I g -SELLEFONTE MJCLEAR PLJuvT i -SAOwNS FERRY NUCLEAR PLANT -l l \\ \\ i t...__

Figure 2 ENVIRONMENTAL E XPOBURE P ATHW AYS C1F M AN DUE TO RELE ASES OF R ADIO ACTIVE MATERI AL TO THE ATMOBPHERE AND LAKE. 9~ hy $ N\\ L 1 ,ru Q.

u. M

[ ::. v f 3' @ - vt Diluted By Atmosphere Airborne Releases \\\\ Plume Exposure l Liquid Releases V Diluted By Lake E MAN O Animals Consumed By Man (Milk, Meat) Shoreline O Exposure Consumed 3x By Animals \\\\ V v E4_ Drink,ng

gggg_gg?gg i

Water ! Fish Vegetation Uptake From Soil, a

APPENDIX A ENVIRONMENTAL RADIOLOGICAL HONITORING PROGRAM AND SAMPLING LOCATIONS-l l { l 5 ')

Table A-1 SEQt10YAH f."JCLEAR PLANT Environmental Radiological Monitoring Program

• Sampling and Enoosure Pathwav and/or Samole Samole locations
• Collection Frecuency Tyc* and Frecuency of Analysis 1.

AIRBORNL l a. Particulates 4 samples from locations (in Continuous sampler operation Analyze for gross beta dif ferent sectors) at or near the with sample collection once radioactivity greater than or site boundary (LM 2. 3, 4. and 5) per 7 days (more frequentiy equal to 24 hours following if required by dust loading) filter change. Perform gamma isotopic analysis on each sample if gross beta is greater than 10 times yearly mean of control sample. Composite at least once per 31 days (by location for gamma scan). y e 4 samples from communities approximately 6-10 miles distance from the plant (PM 2, 3, 8, and 9) 4 samples from control locations greater than 10- ~ miles from the plant (RH 1,

2. 3, and 4) b.

Radioiodine Samples from same location as Continuous sampler cperation I-131 at least once per 7 days air particulates with filter collection once per 7 days c. Soil Samples from same locations as Once per year Gamma scan, $r-89, Sr-90 air particulates once each year w__ - - ~ - -

..~,_ _.- --, _ ..,_ ~,., _., _... _ ~ -.. _.. _..._. _.m. _. -._ i Li .1 - Table A-1 ' SEQUOYiH NUCLEAR PLANT f Environmental' Radiological Monitoring Program

• I' Sampiing and-L[gosure Pathway 'and/or Samole Samole locations' Collection Frecuencv Twee and Freauency of Analvs;s d.

Rainwater Same locations as air particulate - Composite sample at least Analyzed f or gansna nuclides once per 31 days only if. radioactivity in other in media' indicates the presence of 5 increased levels of fallout 2." DIRECT RADIATION c2 or more-dosimeters (TLDs) ' -Once per.92 days' Gasuna dose at least once per -placed (in different sectors). 92 days = at or near the site boundary' in each of the 16 sectors. 4 '2'or more dosimeters;placec at' -i 8.. -stations located approximately. ] /5 miles from the. plant in each -of-the 16 sectors-r ~ 2 or more dosimeters::in approximately - + 20 locations:of special' interest .l 4 .3. . WATERBORNE-~ 'ali Surface TRM 497.0* .. Collected by automatic Gross' beta and gamma scan + ~ iTRM 483.41 sequential-type sampler" with. of each composite sample. 3

. TRM 473.2-

. composite' samples collected-Composite for Sr-89,'Sr-90, over 'a period ofiless than or and' tritium analysis at least _ equal -to 32 days .once per 92 days. { b. ~. Gr;ound '

1 sample adjacent to. plant.'

At least once per 31 days Composited for gross beta, ganana ?(well.no.6). scan, and~ tritium analysis at least once per 92 days. 1 sa ple from ground water ~ At least ~once per[92 days Gross beta, gasuna scan, and m source upgradient. (Farm HW): . tritium analysis atsleast.once per 92 days t t i + ,,,.Cs+6,.m .#%wa, .e6 Meg W NA'* bi g* I 'Y bY

L Table A-1 SEQUOYAri NUCLEAR PLANT Environmental Radiological Monitoring Program

• Sa pling and Enocsure Pathwav and/or Samole Samole tocations*

Collection Frecuency Tvoe and Freauency of Analysis c. Drinking 1 sample at the first potable Collected by automatic Gross beta and gamma scan of surface water supply downstream sequential-type sampler

• each composite sample.

from the plant (TRM 473.0) with composite sample collected Composite for tritium. S r-89, over a period of less than or Sr-90, at least once per 92 equal to 31 days days. I sample at the next 2 downstream Grap sample once per 31 days potable surf ace water suppliers [ (greater than 10 miles downstream) l (TRM 470.5 and 465.3) 2 samples at control locations Samples collected by sequential-(TRM 497.0" and TRM 503.8) type sampler

• with composite sample collected over a period a

of less than or equal to 31 di days - a

d.. Sediment TRM 496.5 At least once per 184 days Gamma scan of each sample l

tim 483.4 TRM 480.8 TRM 472.8 i e. Shoreliae Sediment TRM 485 At least once per 164 days. Gamma scan of each sample TRM 478 TRM 477 4. INGESTION I I

..~.. -. _ .g.. '? Vable A-1 SEQUDYAH NUCLEAR PLANT. I; Environmental. Radiological Monitoring Program * ..) Sampling and. lEncosure Pathway and/or Samole' "Samole tocations* Collection Freauency-Twoe and Freauencv of Analvsis ca. Milk' I sample from milk producing - ' At lest once per 15 days Ganssa isotopic and I-131 ~ . animals in each of-1-3 areas indicated by the cow census inhere. analysis of each sample. " I Sr-89. Sr-90, once per. doses are calculated to be' quarter

highest. 'If samples are not "ailable'from a milk animal socation., doses to that' area will be estimated by projecting the doses,from concentrations detected

-in' milk' from other sectors or by .l sampling vegetation where milk is ~

not-available.

] At least 1 sample' from a control bo - . location- ' ' ' ' .;b. ~Tish fl sample each for Nickajack,; At lest' once per:.184 days; ~ Gamma scan on edible portion

Chickamauga.- and Watts Bar..

One sample of each of the

Reservoirs '

followieg species: 1 . Channel Catfish 1 Crappie. Smallmouth.Butfalo'- -c. -Invertebrates' -

2 samples downstream fromi At'least. once;per 184 days :

Gasuna scan on edible portion- .(Asiatic. Clams)

- " the

discharge'"

1 sample._ upstream from the plant-

(No permanent stations established;.

depends'of; locations of class) .r W D ~ I .u + a it 1 ,wg b-a ha. A M v.m. i. 4 i -.- 4 e b 2 GE M. - -- - X Wr. 1% + . 4 Ak-- "* A r-- J' AU-W- - n--- - - ' " - - - - ~ - - - * * " ' - ~ ~ ' + - ' < - ^- -

Table A-1 SEQUOYAH WJCLEAR ptANT Environmental Radiological Monitoring Program

• Sampling and EERRiure Fathway and/or Samole Samole Locations
• Colle1 tion Freauency Type and Frecuency of Analviis 4.

Food Products 1 sample each of principal food At least once per 365 days at Gamma scan on edible portion products grown at private time of harvest. The types of garcer.s and/or farms in the foods available for sampling will inmediate vicinity of the plant. vary. Following is a list of typical foods which may be available: Cabbage and/or lettuce Corn Green Beans l Potatoes Tomatoes e e. Vegetation 1 sample from up to three locations At fest once per 31 days Gaema scan at least once per 31 of milk-producing animals where a days. Sr-89. Sr-90 analysis e sample of milk is not available at least once per 92 days. and at five air particulate stations a. The sampling program outlined in this table is that which was in effect at the end of 1990. b.- Sampling locations, sector and distance from plant, are described in Table A-2 anc A-3 and shown in Figures A-1, A-2, and A-3. Costposite samples shall be collected by co1Tecting an aliquot at intervals not enreeding 2 hocrs. c. d. The surface water control sample shall be considered a control for the drinking w.ter sample. 1 ' ~ " ' " ' ' ' ' ' ' ' ' ' ' ' ' ' ' - ' ' - " ' E--_____.__...2 'rf-..l'2 ..9C

l 1 i j l j Table A-2 i i { SEQUOYAH NUCLEAR PLANT ? Environmental Radiological Monitoring Program j Sampling Locations Map Approximate Indicator (I) { Locatton Distance or _ Samples-j Number" Station Sector (miles) Control (C) Collected" i j 2 LM-2 N 0.8 I AP CF R.S-j 3 LM-3 SSW 1.2 I -AP,CF.R.S 4 LM-4 NE 1.5 I-AP.CF R,5 1-5 LM-5 NNE - 1. 8 I AP,CF,R.S-7 PM-2 SH 3.8 I AP,CF.R.S } 8 PM-3 W 5.6 I AP CF.R.S j 9 PM-8 SSH 8.7 I -AP,CF.R.S 10 PM-9 WSW 2.6 I ,AP,CF R.S j 11 RM-1 SW 16.7 C AP,CF R.S-i 12 RM-2 NNE 17.8 C AP,CF.R.S. i. 13 RM-3 ESE 11.3 C. AP.CF,R.S E 14 RM-4 WNW 18.9 -C .AP,CF,R,5 15 Farm B NE 43.0 C. M l 16 Farm C NE - 16.0 C M 17 Farm 5 -NNE-12.0 C' M.V 18 Farm J WNW- '1.1 I M 19 Farm HW NW 1.2 I.

M,W*

20 Farm EM N

2. 6.

.I V i-24 Well.No. 6 NNE 0.15 I. W [ 31 TRM 473.0-11.5" I-PN (C.F.-Industries) t 32 TRM 470.5 14.0* I .PW (E.I. DuPont)' i-33 TRM 465.3 19.2' I =PW -(Chattanooga) s 34 TRM 497.0 12.5" C- -SW' MS. TRM 503.8-19.3' -C -PW' i-(Dayton) 36 TRM 496.5 12.0'L C SD l 37 TRM 485.0 0.5' C SS-38 TRM 483.4 .1.I' I SD,SW 39 TRM 480.8 3.7' II SD. -40

TRM 477.0 d

7.5 I lSS. 41 TRM 473.2 11.3' -I

SW l'

42-TRM 472.8 11.7'. I -SD' 44l IAM 478.8' 6.5"- - IK .SS [ z i ~

r

[ - f ? i' j

1 Table A-2 I SEQUOYAH NUCLEAR PLANT Environmental Radiological Monitoring Program Sampling Locations (Continued) Map Approximate Indicator (I) Location Distance or Samples _ Number" Station Sector (miles) Control (C) Collected

• 45 TRM 425-471 I

F (Nickajack Reservoir) 46 TRM 471-530 1/C F.CL (Chickamauga Reservoir) 47 TRH 530-602 C F (Watts Bar Reservoir) 48 Farm H NE 4.2 I M a. See figures A-1, A-2, and A-3 b. Sample Codes AP - Air particulate filter CF = Charcoal filter i CL = Clams F = Fish H = Milk PW = Public water R = Rainwater S = Soll SD - Sediment SS - Shoreline sediment SH - Surface water V - Vegetation H = Well water c. A control for well water. 1 d. Distance from plant discharge (TRH 484.5) e. Surface water sample also used as a control for public. water. i

j i

l \\

^ i T&ble A-3 SEQUOYAH NUCLEAR PLANT Thermoluminescent Dosimeter (TLD) locations Approximate Onsite (On)* Hap Olstance or Location 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 SW 3.8 Off 8 W-3 H 5.6 Off 9 SSN-3 SSW 8.7 Off 10 WSW-2A HSW 2.6 Off 11 SW-3 SW 16.7 Off 12 NNE-4 NNE 17.8 Off 13 ESE-3 ESE 11.3 Off 14 WNH-3 WNW 18.9 Off 49 N-1 N 0.6 On 50 N-2 N 2.1 Off i 51 N-3 N 5.2 Off 52 N-4 N 10.0 Off 53 NNE-2 NNE 4.5 Off 4 54 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 0.3 On 62 ESE-1 ESE 1.2 On l 63 ESE-2 ESE 4.9 Off i 64 SE-A SE 0.4 On 65 E-A E 0.3 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 l 73 SSW-1 SSW 0.6 On l 74 SSN-2 SSW 4.0 Off l 75 SH-1 SW 0.9 On 76 WSW-1 WSW 0.9 On 77 WSW-2 WSW 2.5 Off ! l

Table A-3 SEQUOYAH NUCLEAR PLANT Thermoluminescent Dosimeter (TLD) locations Approximate Onsite (On)* Map Distance or Location Number Station Sector (Miles) Offsite (Off) 78 HSH-3 HSH 5.7 Off 79 HSH-4 HSH 7.8 Off 80 HSH-5 HSH 10.1 Off 81 H-1 H 0.8 On 82 H-2 H 4.3 Off 83 HNH-1 HNH 0.4 On 84 HNH-2 HNH 5.3 Off 85 NH-1 NH 0.4 On 86 NH-2 NH 5.2 Off 87 NNH-1 NNH 0.6 On 88 NNH-2 NNH 1.7 On 89 HNH-3 NNH 5.3 Off TLDs designated onsite are those located 2 miles or less from the plant. a. TLDs designated offsite are those located more than 2 miles from the plant. _ -A

~_ i Figure A-1 DVllonmental nag;ogD9 Cal Sampling Locations f Within 1 Mile of Plant ?, 11.2s NNE NNW y 320.2 33.7s l N 2 NE aca.7 s \\ +87 d ENE WNW N \\e ~ l M('f f '* ! S ea t.2s 3 fy, e

.T, 0%4^n"

~ W- -E PLANT ~% -r. ys 1 2s8 7s 5 ,n /( 'I 1 e4 I 76 WSW y ESE A f \\ 'O 5 ' s rs 2se.2s / 73 9 $ / 4 Sw ,o .SE N 3pp\\ e t s.7 s 14 0.e s / SSW n f 273 SSE 191.e s Scale t 0 Mlle. -48.

Figure A-2 ) Environmental Radiological Sampling Locations From 1 to 5 Miles From The Plant i 348.75 N 11.25 '~ NNW NNE s 7-326.25 j 33,75 NW ) NE 56.25 303.75 -1 / 66 Y! i WNW .E ENE S e55 M v gb 4 B '78.75 281.25 gb 82 19 j@ E l -E W -- 18 59 ob 10 2 258.75 77 D' 66 101.2 1 y 69. 71 63 WSW 'ESE 7 i 230.25 39I 74 SW SE ~ e46 )

• 70 213.75 4 72 148.25 S SW--

d .q SSE j 191.25 S-188.75 SCALE l-o. I 2. l MILES j l 3 J

i i l ) Figure A-3 i i l Environmental Radiological Sampling Locations i Greater Than 5 Miles From The Plant i l 348.75 4 1.25 www [ cnossa N " #"*""' 33.75 32825 1 O 1 PneNp ety ' pui nit 303.76 IB 6.26 ~ ewet At n 4 we Qs 4 12 So s 3f ie p* .78.76 281.25 g'4 2 6 54 E owAn N 9 3( g 00 * .) i y 58 N 60 i -t' i W-esewee.. EVELANO StWANet 1 6 j I fg ,e 258.76' -101.26 D> CH At I AN000 A - enso0E POM t l ,g, B6e i l 'l 2 .123.76 320 25 ,,g, I f LeFAttitt et 1 w e nis.7s i 4,,,5 I i-TRtO uw .I r l to 2s i6e.7 5 SCAtt { o a to is so se 1 natte.

3 J

i i i t t i i d 1 1 l 1 t 4 J s APPENDIX B 4 l 1990 PROGRAM HODIFICATIONS f i i \\ l t i I~ f k i I f I f-l I i r.. m.

Appendix B Environmental Radiological Monitoring Program Modification i During 1990, a small number of modifications were made in the environmental monitoring program. The abundance of Asiatic Clams is steadily decreasing in the reservoirs i of the Tennessee River. As a result, populations of the clams are becoming more and more difficult to find. In 1990, the monitoring program was revised to discontinue the collection of clams from specific Tennessee River Mile locations. Instead, samples are collected from three areas where clams are found, two areas downstream from the plant 3 and the other upstream. Beginning in May strontium analyses were initiated for well water samples. The following table lists the changes in t:ia nonitoring program in 1990. Table B-1 SEQUOYAH NUCLEAR PLANT Environmental Radiological Monitoring Program Modifications 1990 Date Station Modification 1/1/90 Wheeler Clam sampling from the general Reservoir areas in which clams are found rather than from specific river mile locations. 5/90 Onsite Well No. 6 Initiated quarterly strontium ~ and Farm HW analyses for well water samples . _________j

.ms am . - 4 5-.,_ ~., -,, a J Qi .a ._m _.-__.,m. m i l 1 1 l 4 i 1 q i 1 l i i i 4 i i ,i 1 i 3 APPENDIX C 4 1 i l MISSED SAMPLES AND ANALYSES i 1 i ? I i l - 1 1 J. j 'l L. ~ l b

1 i k l 1 1 { Appendix C ) i i Missed Samples and Analyses I i l During the 1990 sampling period, eleven of the scheduled samples were not- ? l collected. All scheduled analyses were not. completed on one of the i j. collected samples. These occurrences resulted in deviations from the scheduled program.but not from the minimum program required by the i j Offsite Dose Calculation Manual. Table C-1 includes a' list of missed samples and analyses and an_ explanation for the deviations, q 4 i Three milk samples were not. collected _because the cow being milked went. l dry for a short period of time and two were unavailable because the milk had already been picked up by the processor; three clam samples'were not i collected because of scarcity of clams; one air'fl.lter. sample was.not collected because.of equipment malfunction; and' a control. sample fbr 7 tomatoes was not available. Equipment _ malfunctions were corrected. l-additional care was taken to preserve milk samples, and efforts were l' increased to coordinate the milk-collection with the; farmers. I i The missed sample's and analyses are" listed in the following' table. 1 i 1 - l k a t t i r i j e j .-55. U a ~ =.

i I I i ) Tab?e C-1 1 SEQUOYAH NUCLEAR PLANT i Environmental Radiological Monitoring Program { Exceptions I j Date-Station _ Location Remarks 1 } 4/25/90 Chickamauga SQN area Three clam samples not collected: j 10/31/90 Reservoir scarcity of clams made them difficult to locate f 7/17/90 farms SQN area An oversight by the sample i collector resulted in failure to i collect tomatoes from a control station before all locally grown tomatoes were gone. f 8/7/90 PM-2 3.8 miles SW Air particulate and charcoal i filters not collected - equipment i failure i 8/21/90 farm J 1.1 miles HNH Farm.J 1s a single cow farm. Milk l must be composited for 2-3 days to provide sufficient volume for a j l sample. As'a result of the longer I time for collecting'the sample.and the time required to complete lodine and gamma analyses, one sample spoiled before the strontium' analyses were completed. i 9/4/90 Farm C 16.0 miles NE-Milk had already>been picked ~up by t i the processor, therefore no sample l l was available.= - Milk had already'been: picked-up by 9/1.9/90 Farm H-4.2 miles NE the. processor, therefore.no sample L was available. I 10/2/90 Farm J 1.1 miles.HNW Milk samples were;not available' 10/17/90 ~because.the cow was dry. 10/31/90 l i 'i I. d

) APPENDIX D ANALYTICAL PROCEDURES + d s 'i e l i o -

J

APPENDIX 0 Analytical Procedures Analyses of environmental samples are performed by the radioanalytical laboratory located at the Western Area Radiological Laboratory facility in Muscle Shoals. All analysts 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. Water samples are prepared by evaporating 500 ml of samples to near dryness, transfering to a stainless steel planchet and completing the evaporation process. For solid samples, a specified amount of the sample is packed into a deep stainless steel planchet. Air particulate filters are counted directly in a shallow planchet. The specific analysis of I-131 in milk, water, or vegetation samples is performed by first isolating and purifying the iodine by radiochemical separation and then counting the final precipitate on a beta-gamma coincidence counting system. The normal count time is 100 minutes. With the beta-gamma coincidence counting system, background counts are virtually eliminated and extremely low levels of detection can be obtained. I - - -- N

4 l 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 i after a 7-day ingrowth period. From the two counts the Sr-89 and Sr-90 concentrations can be determined. 1, Hater samples are analyzed for tritium content by first distilling a portion of the sample and then :ounting by liquid scintillation. A commercially available scintillation cocktail is used. 1 Gamma analyses are performed in various counting geometries depending on the 1 sample type and volume. All gamma counts are obtained with germanium type detectors interfaced with a computer based mutlichannel analyzer system. 4 Spectral data reduction is performed by the computer program HYPERMET. i the charcoal cartridges used to sample gaseous radioiodine are analyzed with well-type Na! 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 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 4 document the results of the quality control checks. i -S9-I

eL.e _4 A--A i i li 1 4 l i ii l i 1 r i 1 ) J APPENDIX E 4 6 'I NOMINAL LOWER LIMITS OF DETECTION (LLD) a s i i h t i A 8 .i 1 e 4. w -e g e e e ar, e% r- -v---.g r,.4-e

Appendix E l 1 Nominal Lower Limits of Detection i 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 2 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. l 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 measurid over and over in the same device j elli 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 l laboratory publishes is a guide to the sensitivity of the analytical l measurements performed by the laboratory. l 1 I' i i 1 , t \\' t

i j Every time an activity is calculated from a sample, the machine { background must be subtracted from the sample signal. For the very low 1 i levels encountered in environmental monitoring, the sample signals are i often very close to the background. The measuring equipment is being 1 used at the limit of its capability. For a sample with no measurable ] activity, which often happens, about half the time its signal should fall below the average machine background and half the time it should be above the 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. A number of factors influence the LLO, 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 f 00CH, are presented in table E-1. The maximum values for the lower limits of detection specified in the OOCH are shown in table E-2. 1 The LL0s are also presented in the data tables. For analyses for which LLDs have not been established, an LLO of zero is assumed in determining if a result is greater than the LLO. d -

t i fable E-1 taominal LLD Values A. Radiochemical Procedures Charcoal Sedi e t Air Filters filters W.ter Milk Fish Flesh Whole fish Food Crops and Soil 1pfiLe*l loci /m'l (oCi/l) 1pCi/L) foci /o dr_v) foci /o drv) foci /ka wet) inCi/a drv) Grass beta 0.002 1.7 9 Tritium 250 locine-131 .020 1.0 0.2 Strontium-89 0.0006 3.0 2.5 0.3 0.7 1.0 Strontium-90' O.00025 1.4 2.0 0.04 0.09 0.3 Wet Vagetation Clam Flesh Neat (cCi/ko Wet) foci /o Drv) foci /ko Wet) em Y-Gross Beta 0.2 15 Iodine-131 4 ~ Strontium-89 140 5trontium-90 60 1 Y 9 m .-.mm. w-.- ._.-:.w. ..e-_>- s%_.__ -+. - f 7 +-

m Table E-1 Nominal LLD Values 8. Gama Analyses (GeLi) Air Water Vegetation Wet Soil and Foods, Tomatoes Meat and Particulates and Milk and Grain Vegetation Sediment Fish Clam Flesh Potatoes. etc. Poultry DCi/m3 oCi/t gCi/o. dry g[i/JAwat oCi/o. dry oCi/o. drv oCi/c. dry _pCi/ka. wet afi/12. -et Ce-141 .005 10 .07 28 .02 .07 .15 10 25 Ce-144 .01 33 .25 100 .06 .25 .50 33 50 Cr-51 .02 45 .45 180 .10 .45 .94 45 90 I-131 .005 10 .09 36 .02 .09 .18 10 20 Ru-103 .005 5 .05 20 .01 .05 .11 5 15 Ro-106 .02 40 .48 190 .09 48 .95 40 95 Cs-134 .005 5 .07 28 . 01 .07 .11 5 15 Cs-137 .005 5 .06 24 .01 .06 10 5 15 Zr-95 .005 10 .11 44 .02 .II .19 10 25 Nb-95 .005 5 .06 24 .01 .06 .11 5 15 Co-58 '.005 5 .05 20 .01 .05 .10 5 15 Nn-54 .005 5 .05 20 .01 .05 .10 5 15

• . In-65

.005 10 .11 44 .01 .il .21 10 25 , ' Co-60 .005 5 .07 28 .01 .07 .11 5 15 K-40 .04 150 1.00 400 .20 1.00 2.00 150 300 Ba-140 .01 25 .23 92 .05 .23 .47 25 50 La-i40 005 8 .11 44 .02 11 17 8 20 Fe-59 .005 5 .10 40 .01 .10 .13 5 15 Be-7 .02 45 .50 200 .10 .50 .90 45 100 Pb-212 .005 20 .10 40 .02 .10 .25 20 40 Pb-214 .005 20 .20 80 .02 .20 .25 20 40 Bi-214 .005' 20 .12 48 .04 .12 .25 20 40 Bi-212 53 .40 40 .25 .40 53 T1-208 .001 7 .03 26 92 .03 35 7 Ra-224 -- .30 Ro-226 .05 Ac 228- .014 25 .10 80 10 .10 1.00 22 22 - Po-234m 700 3.00 -,,ww6--w a-m-w--

) i t i r e j Table E-2 i i Maximum Values for the Lower Limits of Detection (LLD) Specified by the SQN Offsite Dose Calculation Manual Airborne Particulate Food i Water or Gases Fish Hilk Products Sediment' j Analysis pC1/L DCi /M_ DC1/Ka. wet DCi/L pei/ka. wet pCi/Ka. dry i gross beta 4 1 x 10-' N.A. N.A. N.A. N.A. H-3 2000' N.A. N.A. N.A.- N.A. N.A. I j Mn-54 15 N.A. 130 N.A. N.A. N.A. f Fe-59 30 N.A. 260-N.A. N.A. N.'A. ) Co-58,60 15 N.A. 130 N.A. N.A.- N.A. i j Zn-65 30 N.A. 260-N.A. .N.A. N.A. 1 i Zr-95 30 N.A. N.A. N. A'. N.A.- N.A. l Nb-95 15 N.A. N.A.- 'N.A. N. A.. N.A. .1 l I-131 -l' 7 x 10 N.A. 'l-60 N.A. l Cs-134 15 5 x 10 130 .15 60 150 l l Cs-137 18 6 x 10-' 150 18 80-180 l Ba-140 60 N.A. N.A. 60 N.A. N.A. La-140 15 N.A. N.A. 15 N.A. N.A. I i J If no drinking water pathway exists, a'value'of 3000pC1/L mayfbe: Used.; i. ' -If no drinking' water pathway exists,.a value'ofL15 pC1/L may be used.. l 1 l H -1 1 + m

APPENDIX F QUAlliY ASSURANCE / QUALITY CONTROL PROGRAM L _ __ _ _ _ _ __ _ _ _ ___ __. .I

. ~ } i Appendix F l 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 j includes the use of written, approved procedures in performing the work, i { a nonconformance and corrective action tracking system, systematic internal audits, a complete training and retraining system, audits by i various external organizations, and a laboratory quality control program,- i i The quality control program employed by the radioanalytical laboratory l's-designed to ensure that the sampling and analysis process is working as i

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 j-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-are usually low values-'and are-due-to machine noise, cosmic-rays, or trace amounts of _ radioactivity.in the materials used to construct l the detector. Charts.of-background c'ounts are kept and monitored to ensure

that no unusually high' or low values are encountered.

2 q In the second. test, the' device-is operatediwith a known amount'~of.. l radl.oactivity present. The number of. counts registered from-such a-i,

-~. i 1 i 1 l radioactive standard should be very reproducible. These reproducibility i checks are also monitored to ensure that they are neither higher nor s lower than expected. When counts from either test fall outside the expected range, the device is inspected for malfunction or j contamination. It is not placed into scrvice until it is operating properly. i In addition to these two general checks, other quality control checks are l 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, j replicate samples, blind samples, or cross-checks. I j Blanks are samples which contain no measurable radioactivity or no 1 ~ l activity of the type being measured. Such samples are analyzed.to l= determine whether there is any contamination of equipment or commercial I I l laboratory chemicals, cross-contamination-in the' chemical process, or interference from isotopes other than the one being measured, i Duplicate. samples are scheduled at-random by the'same computer program which schedules the collection of the routine samples. For: example,21f~ the routine program: calls'for-four'mlik' samples every. week', on a-random basis each farm might provide an additional sample several times a year. ' i

l These duplicate samples are analyzed along with the other routine samples. They provide information about the variability of radioactive l content in the various ample media. 4 There is another kind of replicate sampie. 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. 1 l Analytical knowns are another category of quality control sample. A j 1 i 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 l 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 i measurable activity or only naturally occurring radioisotopes, blind spikes can be used to test the detection capability of the laboratory or l they can be used to test the data review process. If an analysis ( routinely generates numerous.eroes for a particular isotope, the. presence of the isotope is brought to the attention of the laboratory supervisor in the daily review' process. -.

Slind spites 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. At present, 5 percent of the laboratory workload is in the category of internal cross-checks. These samples have a known amount of radioactivity added and are presented to the analysts labeled as cross-check samples. This means that the quality control staff knows the radioactive content or "right answer" but the analysts do net. They are aware they are being tested. Such samples test the best performance of the laboratory by determining if the analysts can find the "right answer." These samples provide information about the accuracy of the measurement process. Further information is available about the variability of the process if multiple analyses are requested on the same sample. Internal cross-checks can also tell if there is a difference in performance between two analysts. Like blind spikes or analytical knowns, these samples can also be spiked with low levels of activity to test detection limits. A series of cross-checks is produced by the EPA in Las Vegas. These interlaboratory comparison samples or " EPA cross-checks" are considered to be the primary indicator of laboratory performance. They provide an independent check of the entire measurement process that cannot be easily provided by the laboratory itself. That is, unlike internal cross-checks, EPA cross-checks test the calibration of the laboratory detection devices sin.e different radioactive standards produced by individuals outside TVA are used in the cross-checks. -

I The results of the analysis of these samples are reported back to EPA which then issues a report of all the results of all participants. These reports are examined very closely by laboratory supervisory and quality control personnel. They indicate how well the laboratory is doing compared to others across the nation. Like internal cross-checks, the EPA cross-checks provide information to the laboratory about the precision and accuracy of the radioanalytical work it does. The results of TVA's participation in the EPA Interlaboratory Comparison Program are presented in table F-1. 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 measurable 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. All the quality control data are routinely collected, examined, and reported to laboratory supervisory personnel. They are checked for trends, problem areas, or other indications that a portion of the analytical process needs correction or improvement. The end result is a measurement process that provides reliable and verifiable data and is sensitive enough to measure the presence of radioactivity far below the levels which could be harmful to humans. 1

Table F-1 RESULTS OBTAINED IN INTERLABORATORY COMPARISON PROGRAM A. '.ir Fi s ter (pCi/ filter) Gross Aloha Gross Beta ' Strontium-90 Cesium-137 EPA Value TVA EPA talue TVA EPA Value TVA EPA Value TVA Daig fr3 siama) Am. (e3 siamal M. (r3 siamal arg. (r3 simal arg. 3/90 5:9 7 3129 32 10:2.6 11 10 9 9 8/90 10:9 14 62:9 64 20:9 20 20:9 20 B. Radiochemical Analysis of Water (pCi/L) Gross Beta Strontium-89 Strentium-90 Tritium Iodine-131 EPA Value .IVA EPA Value TVA EPA Value TVA EPA Value TVA EPA Value TVA i 'A g. (r3 siama) arg. (r3 siamal arg. (t3 siama) agg. (r3 simal M. QAlg ie3 siamal 2 sy 1/90 12 9 a 25 9 25 20:2.6 18 4976:863 4943 2/90 1 3/90 l 4/90*' 10:9 10 10:2.6 8 l 4/90 5/90 15 9 15 729 7 79 6 i 6/99 .2933:620 2830 7/90 39%10 36 8/90 9/90 10:9 10 - 10/90 7203:1247 7340 t 10/90* 20:9 21 15:9. 13 l 11/9~- l '12/90 l f L i r, g

) 0 Table F ' RESULTs OBTAINED IN INTERLABORATORY COMPARISON PROGRAM (Continued) C. vamma-Spectral Analysis of Water (pCi/L) Ba-133 or _ utheniun 105_ Cesium-134 Cesium-137 Q Chromium-51 Cobalt-60 Z i nc-65 EPA value TVA EPA Value TVA EPA Talue TVA EPA Val-+ TVA LPA Value TVA EPA Value TVA Date 423 siamal Agg. fr3 siomal.Ayg. f r 3 s i <na ', arg. f 3 sigm_al Ayg. f23 sioma) A_yg. (r3 siam.at AE. 2/90 74:12 74 15 9 15 139:24 137 139:24 130 1829 18 18 9 18 15:9 15 15 9 16 4/90* 6/90 99:17 100 24:9 26 148:26 144 210:36 200 24:9 23 2529 25 10/90' 110:14 112 20:9 22 115:21 113 151:26 140 1229 12 12:9 11 10/90* 7:9 7 5:9 6 D. Milk (pCi/L) -I S t ron t i um-89 _ Strontium-90 Iodine-131 Cesium-137 Potassium-40* [j EPA Value TVA EPA Value TVA EPA Value TVA EGA Value TVA EPA Value TVA_ l [ QAle (23 siemal aE2 fr3 siomal arg. fr3 siamal arg. fr3 siomal Ayg. .(-3 sional ayg. l f 4/90 23:9 23 23:9 21 99:17 100 24=9 24 1550:135 1577 9/90 16:9 14 20:9 16 58:10 59 20:9 20 1700:147 1790 l l l a. Results invalid as a result of inaccuracies in sample weights. b. Performance Evaluation Intercomparison Study. c. Results were not received by EPA in time to be included in their report. d. Units are milligrams of total potassium per liter rather than picocuries of K 40 per liter.

APPENDIX'G LAND USE SURVEY 5 __ -

l l 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 garden of greater than 500 square feet producing fresh leafy vegetables in each of 16 meteorological sectors within a distance of 5 miles from the plant. The land use survey also identifies the location of all milk animals and gardens of greater than-500 square feet producing fresh leafy vegetables within a distance of 3 miles from the plant. The land use survey is conducted between-April 1 and October 1 using appropriate techniques such as door-to-door survey, mail survey, telephone survey, aerial survey, or information from local agricultural authorities or other reliable sources. In order to identify the locations around SQN which have the greatest relative' potential for.):npact by the plant, radiation doses are projected for individuals living near SQN. These projections use the data obtained in the survey and historical meteorological data. They also assume that the plant is operating and that releases are equivalent to the design 7 basis source terms. The calculated doses are relative in nature and do not reflect actual exposures received by individuals living near SQN, Calculated doses to individuals bas 6d on measured effluents from the plant are well below applicable dose limits-(see Assessment and Evaluatlon).. _

in response to the i990 SQN land use survey, annual doses were calculated for air submersion, vegetable ingestion, and milk ingestion. External doses due to radioactivity in 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. Air submersion doses were calculated for the same locations as in 1989, with the resulting values almost identical to those calculated in 1989. Doses calculated for ingestion of home-grown foods and milk also were = almost identical to those calculated in 1989. No significant changes in land use were identified in the 1990 land ust

survey, As a result, no changes to the monitoring program were initiated as a rewlt of the survey report.

,y. Tables G-1, G 2, and G-3 show the comparative relative calculated doses for 1989 and 1930. j _ - _ _ - _ _ - _ _ _ - - - _ _ _

Table G-1 SEQUOYAH NUCLEAR PLANT Relative Projected Annual Air Submersion Dose to the Nearest Resident Within Five Miles of Plant (mrem / year / unit) 1989 Survey 1990 Survey Approximate Approximate Sector Distance (Miles) Annual Dose Distance (Miles) Annual Dose N 0.8 0.12 0.8 0.12 NNE 1.5 0.07 1.5 0.07 NE 1.4 0.07 1.4 0.07 ENE 1.3 0.03 1.3 0.03 E 1.0 0.03 1.0 0.03 ESE 1.0 0.03 1.0 0.03 SE 1.0 0.03 1.0 0.03 SSE 1.2 0.04 1.2 0.04 S 1.4 0.05 1.4 0.05 SSH 1.2 0.15 1.2 0.16 SH 1.8 0.04 1.8 0.04 WSW 0.7 0.08 0.7 0.08 H 0.6 0.08 0.6 0.08 HNH 1.1 0.02 1.1 0.02 NH 0.9 0.03 0.9 0.03 NNH 0.6 0.12 0.6 -0.12 - - - _ - - -__-_______-__-_ -

Table G-2 SEQUOfAH NUCLEAR PLANT Relative Projected Annual Dose to Child's Critical Organ from Ingestion of Home-Grown Foods (mrem / year / unit) 1989 Survey 1990 Survey Approximate Annual Dose Approximate Annual Dose Sector Distance (Miles) (Bone) Distance (Miles) (Bone) N 1.1 2.41 1.1 2.41 NNE 1.9 1.56 1.9 1.56 NE 1.4 2.18 a ENE 1.6 0.78 1.6 0.78 E a a ESE 1.1 0.73 1.1 0.73 SE 2.0 0.37 2.0 0.37 SSE 1.2 1.19 1.2 1.19-S 1.5 1.64 1.5 1.64 SSW l.7 3.27 1.7 3.27 SW 2.1 1.11 2.1 1.11 WSW l.0 1.67 l '. 0 1.67 N 1.2 , 0.,89 1.2 0.89 HNW l.2 0.65 -1. 2 0.65 NW 0.8 1.18 0.8 1.18. NNW 0.6 3.08 06 3.08 No garden was identified in this sector.whithin 5 miles of the plant. a. - I

c Table G-3 i SEQUOYAH NUCLEAR PLANT Relative Projected Annual Dose to Receptor _ Thyroid from Ingestion of Milk (mrem / year / unit) y Approximate Distance Annual Dose Location No. Sector (Miles)* 1989 1990 Farm EM" N 2.6 0.04 0.04 Farm H" NE 4.2 0.02 0.02 Farm J" HNW l.1 0.03 0.03 Farm HW" NW l.2 0.05 0.06 ~ Distances measured to nearest property line. a. b. Vegetation sampled at this location. c. Milk sampled at this location..

APPENDIX H DATA TABLES e e

) / Table H-1 DIRECT RADIATION LEVELS Average External Radiation Ltvels at Various Distances from ) Sequoyah iuclear Plant for Each Quarter - 1990 } mR/ Quarter

• 6 Average External Gamma Radiation Levels Distance 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Miles (Feb-Apr 90)

(May-Jul 90) (Aug-Oct 90) (Nov 90-Jan 91) 0-1 16.0 1.0 16.0

• 1.7 18.5 s 1.5 15.0 2.0 1-2 14.0
• 1.9 14.4 2 2.1 16.2
• 2.2 12.9
• 1.8 2-4 13.3
• 1.9 13.2 i 2.1 15.3
• 2.1 12.2
• 1.6 4-6 13.2
• 1.7 13.3 1.7 15.3 1.7 12.5 2 1.5 6+

13.2 i 1.5 12.9

• 1.6

'14.9 2 1.8 12.3 1.7

Average, 0-2 miles (onsite) 15.1

• 1.8 15.3
• 2.0 17.5 2.2 14.1 2.2 Average 6+

miles (offsite) 13.2 2 1.7 13.'1

• 1.8 15.2 1.8 12.4 i 1.6 a.

Data normalized to one quarter (2190 hours). b. Averages of the individual measurements in the set *1 standard deviation of the set. . l q

Table H-2 TENNESSEE VALLEY NJTHORITY CHEMISTRY AND RADIOLOGICAL SERVICES ENVIRONMENTAL RADIOLOGICAL MONITOPING AND INSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY ENVIRONMENTAL MONITORING REPORTING SYSTEM RADIOACTIVITY IN AIR FILTER PCI/M3 - 0.037 BC/M3 NAME OF FACILITY: SEQUDYAH PJCLEAR PLANT DOCKET Wo.: 50-327,328 LOCATION OF FACILITY: HAMILTON TENNESSEE REPORTING PERIOD: 1990 TYPE AND LOWER LIMIT ALL CONTROL NUMBER OF TOTAL NLH8ER OF INDICATOR LOCATIONS LOCATION U!TH HIGNEST ANWJAL MEAN LOCATIGNS NONROIKINE CF ANALYSIS DETECTION MEAN (F) NAME MEAN (F) MEAN (F) REP 0F.TED PERFORMED (LLD) RANCE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS l SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 l I GROSS BETA 623 2.00E-03 2.02E-02( 415/ 415) PM-3 DAISY TN 2.07E-02( 52/ 52) 2.03E-02C 208/ 208) 1.08E 4.40E-02 5.5 MILES W 1.19E 4.20E-02 1.05E 4.12E-02 CA.9tA SCAN (GELI) l 156 l EE-T 2.00E-02 8.10E-02( 104/ 104) LM-3 1ST TN BANK REC 8.53E-02( 13/ 13) 8.18E-02( 52/ 52) 5.09E 1.05E-01 1.5 MILES S$W 5.64E 1.00E-01 5.23E 1.25E-01 l 00 81-214 5.00E-03 1.25E-02( 47/ 104) LM-31ST TN BANK REC 2.07E-02( 5/ 13) 1.30E-02( 21/ 52) [ 7 5.10E 4.25E-02 1.5 MILES SSW 7.10E 4.25E-02 5.10E 3.60E-02 PA-234M 5.00E-03 2.01E-01( 1/ 104) PM-3 DAISY TN 2.01E-01( 1/ 13) 52 VALUES < LLD l' 2.01E 2.01E-01 5.5 MILES W 2.01E 2.01E-01 PB-214 5.00E-03 1.13E-02( 44/ 104) (M-3 1ST TN BANC REC 1.82E-02( 5/ 13) 1.27E-02( 18/ 52) 5.00E 4.21E-02 1.5 MILES SSW 6.60E 4.21E-02 5.20E 2.81E-02 TL-208 1.00E-03 104 VALUES < LLD PM-2 COUNTY PARK TN 13 VALUES < LLD 1.35E-03C 2/ 52) 3.75 MILES SW 1.3M 1.40E-03 NOTE:

1. NO(INAL LOWER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1.

NOTE:

2. MEAN AND RANCE BASED UPON DETECTABLE MEASUREMENTS ONLY. TRACTION OF DETECTABLE MEASUREENTS AT SPECIFIED l

LOCATIONS IS INDICATED IN PARENTHESES (F). l i

Ilili!l4 S T FEDN ONFE I TM RTRE EUOR BOPU MRES UNRA NO E N M )2 D 80 E 0 - I 8 2E F 2 2 I 3, ) 2 /1 C SF 0 E 7 LN( E 13 P 2 OO T S 30 RI NEO 9 TTAGN (2 T 09 20 A MAENCMAE 0 - 51 CO RE E S L S E0 T D 70 N O 32 M E I R 2 E E R

P U

12 S oG 20 A N WW 5 - E O t E M I TT 2 T ER /2 E A KO 2 L T CP M) 2 5 B N OE AF A E DR E( E T M M M T (2 C U E NEO 20 E RYT LACN 0 - T TRS AEN E E SOYR UMAE E8 D SNTSE N RE 05 EI A T N S C RGL A 92 .F0 DONI 3 I YVNBIF T N 1 fO TRAAT S O IE LRL3 E I EI RSG OAM H T T O WLPO/ C C EC NLl AECc E LA 3 TARCRRs H R BR UCOI A I W AF AITGGR7 HED s T H GI ONC3 TM Ev YONLI 0 AD D N. I ELOORN WNN S IY e LOD I OI0 s A ISE L LI DT p EL DN l ADLAI Y - O E KI EO b VAARKT I C AM B a RC OI3 T N L I S AMVM A A 7 RT E I T EDGE I / C T 9 CN SNORLTI O' S - 2 SE SALAACC L I M EM E O TAP D P DE NYI NNC R. NRDREI )2 SU) ETAEMD S 50 ASF 7 SRThA N 1 - A( I S0R T O 4E )E MLER N I 2 DMS EAWI A T 2 /2 L E HT V L A) S LES CN N PE CF E 5 (LE E E E O(ET .BH M RS LL CO AT N AS L NNN (2 NTN O EE ARAA 20 OCE R LN OERE 0-IER CN TM E - E TTA I V UE A S E3 CEP N NT C 22 ED E I

0. 2 T

N HN D ENI AO N 3 DO YT I PD OL FUE UI O T QM T 1 2 DA EA I N 0 TEC SH M O E I SI I I)T E MAD LFTLO 0 IBN YY OCLN 0 L I TT R EL E II E T(E 2 RGS LL W E I I O D - E ENI S J A CC L QRs AA L FF 3 Dm 2 LN! FF 6 AAT OO N A I NC EN A MAO MO ES OEL AI DBID NM NT NMSE A AUYS 1 C NLR 3 12 O E AO 1 L PLNF YAAR E TT E OO N EE OFP TT TO 0 C NN $Y l l, t lI lil. l' lt

Table H-4 TENNESSEE VALLEY AUTHORITY CHEMISTRY AND RADIOLOGICAL SERVICES ENVIRONMENTAL RAD 1QLOGICAL MONITORING AND INSTRtMENTATION WESTERN AREA RADIOLOGICAL LABORATORY ENVIRONMENTAL MONITORING REPORTING SYSTEM RADICACTIVITY IN MILK PCl/L - 0.037 BC/L DOCE T No.: 50-327,328 f NAME OF FACILITY: SEQUOTAH NUCLEAR PLANT REPORTING PERIOD: 1990 LOCATION OF FACILITY: NAMILTON TENNESSEE CONTROL NU8BER OF TTPE AND LCUER LIMIT ALL TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION VITH HIGHEST ANWAL MEAN LOCATIONS NONROUTINE OF ANALYSIS DETECTION MEAN (F) NAME MEAN (F) PEAN (F) REPORTED FfRFCRMED (LLD) RANCE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS SEE NOTE 2 SEE NOTE 2 SEE NOTE 1 SEE NOTE 2 !(D1NE-131 151 23 VAttES < LLD 2.82E-01( 2/ 77) 2.00E-01 74 VALUES < LLD JONES FARM 2.81E 2.53E-01 1 1.25 MILES W GAMMA *CAN (CEtt) - 152 B1-214 2.00E+01 4.17E+01( 6/ 75) HOLDER DA!RY 5.52E+01( 3/ 25) 7.05E+01( 15/ 77) 2.08E+01-1.06E+02 4.25 MILES FE 2.71E+01-1.06E+02 2.10E+01-1.99E+02 co CS-137 5.00E+00 5.27E+00( 1/ 75) HOLDER DAIRY 5.27E+00( 1/ 25) 77 VALUES < LLD s 5.27E+00- 5.27E+00 4.25 MILES NE 5.27E+00- 5.27E+00 K-40 1.50E+02 1.27E+03( 75/ 75) HOLDER DAIRY 1.34E+03( 25/ 25) 1.28E+03( 77/ 77) i 9.17E+02-1.51E+03 4.25 MILES NE 1.17E+03-1.51E+03 3.53E+02-1.58E+03 PB-214 2.COE+01 4.23E+01( 3/ 75) HOLDER DAIRY 6.19E+01( 1/ 25) 8.42E+01( 10/ 77) 2.72E+01-6.19E+01 4.25 MILES NE 6.19E+01-6.19E+01 2.13EC)1-1.82E+02 SR 89 l 51 39 VALUES < LLD 2.50E+00 12 VALUES < LLD l SR 90 j 51~ . 5.72E+00( 12/ 12) JONES FARM 8.83E+00( 4/ 4) 2.80E+00( 10/ 39) l . 2.00E+00' 2.06E+00- 1.04E+01 1.25 MILES W 6.82E+00- 1.04E+01 2.06E+00- 4.89E+00 NOTE:

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

FRACTION Of OETECTABLE MEASUREMENTS AT SPECIFIED NOTE:

2. MEAN ANO RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY.

LOCATIONS IS INDICATED-IN PARENTffESES (F). 1 1 L.-n. ' * - + emse.

L Table H-5 TENNESSEE VALLET AUTHC5tITY CHEMISTRY AND RADIOLOGICAL SERVICES ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATION WESTERN AREA RADIOLOGICAL U BORATORY ENVIRONMENTAL MONITORING REPORTING SYSTEM i RADIDACTIVITY IN VECETATION ( PCI/KG - 0.037 BQ/KG (WET WEIGHT) l NAME OF FACILITY: SEQUGfAH NUCLEAR PLANT DOCKET No.: 50-327,328 LOCATION OF FACILITY: HAMILTON TENNESSEE REPORTING PERIOD: 1990 CONTR0' NUMBER OF TYPE AND LOWER LIMIT ALL TOTAL WLMBER OF -INDICATOR LOCATIONS LOCATION WITH NIGHEST ANNUAL MEAM LOCATIONS NONROUTINE OF ANALYSIS DETECTION MEAN (F) NAME MEAN (F) MEAN (F) REPORTED PERFOR9ED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 100!NE-131 26 4.00E+00 13 VALUES < LLD 13 VALUES < LLD GAMMA SCAN (GELI) 26 AC-228 8.00E+01 1.03E+02( 1/ 13) EDGAR MALONE FARM 1.03E+02( 1/ 13) 13 VALUES

• LLD 1.03E+02-1.03E+02 2.5 MILES N 1.03E+02-1.03E+02 BE-7 2.00E+02 2.23E+03< 13/ 13) EDGAR MALOWE FARM 2.23E+03( 13/ 13) 2.46E+03( 13/ 13) 3.96E+02-8.90E+03 2.5 MILES N 3.95E+02-8.90E+03 6.01E+02-9.95E+03 Y

B1-214 4.80E+0i 8.34E+01( 3/ 13) EDGAR MALONE FARM 8.34E+01( 3/ 13) 7.1&E+01( 4/ 13) 6.11E+01-1.21E+02 2.5 MILES N 6.11E+01-1.21E+02 5.00E+01-8.71E+01 E-40 4.00E+02 6.04E+03( 13/ 13) EDGAR MALOWE FARM 6.04E+03( 13/ 13) 6.03E+03( 13/ 13) 2.28E+03-8.79E+03. 2.5 MILES N 2.28E+01-8.79E+03 1.65E+03-1.21E+04 PS-212 4.00E+01 ' 4.83E+01( 1/ 13) EDGAR MALONE FARM 4.83E+01( 1/ 13) 13 VALUES < LLD 4.83E+01-4.8tE+01 2.5 MILES N 4.83E+01-4.83E+01 P9-214 8.00E+01 1.32E+02(- 1/ 13) EDGAR MALONE FARM 1.32E+02( 1/ 13) 13 VALUES < LLD 1.32E+02-1.32E+02 2.5 MILES N 1.32E+02-1.32E+02 SR 89 '8 1.40E+02 4 VALUES < LLD 4 VALUES < LLD SR 90 8 6.00E+01 4 VALUES < LLD 4 VALUES < LLD, NOTE:

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

NOTE:

2. MEAN AND RANGE BASED UPOW DETECTABLE MEASUREMENTS ONLY. FRACTION OF DETECTABLE E ASURE M NTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).

. a..

{)1)l a m_ S T FEDN ONEE IT M RTRE EUOR BOPU MRES

t. NRA NO E

N M )0 )0)1 )1 )1 )0)0)0)1)1 D 50 505050505050505050 E + + + + + + I 8 ED E E E E E E E E E D D F 2 6L 9 3 3 2 0 1 2 3 6 L L I /7 L L C ) 2 / 4. L / 4. 5/35/ 2. 5/ 8. 5/ 4. 5/04/55/ 3. 5 3, E 5 5 SF 7 LN( E 1 < 1 9 6 1 1 1 1 - 9 4 PS 2 OO T 30 RI NEO - S S S - 9 TTAGN (1E (1 (1 (2(0(1 (1(1(1(1 E E T 09 NAEN 10U 001010001010001010 U U A 51 OCMAE 0 - L 0 0+0 0 0 0 L L. CO RE - EA + E-E - E+E - E E+ E - E-E A / S L S E1V E6E4E6E8E5E1 E6E4E1 Y V T 6529 N 29605.5T.1 E 6537929 9.3.67225 425 515 5 5 D

0. 8

6. 7

0. 7

7. 7 O

5 I R 9 1 7 2 6 9 8 1 7 3 ER E U

P

)0)1 )0)0)0)1 )0)0)0)0)1 )1 S oG 1010101010101010101010 10 A N NN + + + + + + + + + E O I E E E E E E E E E E E E M I TT 3 4 0 7 6 5 - 3 3 6 7 9 4 / /7 /5 E T ER / 5.1/1.15.1/1.1/ 1.1/ 8.1/ 4.1/ 2.1/ 5.1/ 1.1 1 L A KO 1 T CP N) 2 1 2 1 1' 1 1 1 1 1 1 4 4 BA N OE AF E DR E( E T M M M T (0(1 (0(0(0(1 (0(0(0(0(1 (1 C t E NEO 0010000000100000000010 10 E 0+0+0+0+0+0+0+0+0-0 - T RYT LAGN 0+0 - TRS AEN +E - E2 E+E+E+E+E+r+E+E E E E SOY UMAE E3E4E0E7E6E5E3E3E6E7E9 E4 D 97 45 657174 54 6 1 5 8 3 4 3 2.5.1 35.124 1 5.105.1.17 1.1.1 SNTS ) N RE .FO 8.1 4.12.1 1.1 EI A T P S 5.1 C RG H A DON G 1 2 1 1 1 1 1 1 1 1 4 4 I 1N YVNBI I T N - O TRAAT E S O C' C EI IE LR W E I C RSG O H T E E E T O NLP T C C R R ' R EC HLI AE R I E N LA K K SR TARCRLD N R TW KNWTE' NW NW TE AF 6 UCOI ! ( I S AITGG0 HEO N ,S NASNM k NAS kAS M NN T GI ON$G TM T N T BSI NT T BST RST I W YONLI / I AD SSOSSS O SSSS SS SS O N. 1 ELOOP 4Q WNN AESEAENSPSAEAENSAENSAE PS IY 1 LOMI O1 a A ELI LELTE EELELTEELTEEL E L e LI DT N HIRI HI LELHI HI LHI LHI EL DN l ADLAIY7 O ' E TMRMTMTIRITMTM7ITMTITM RI EO b VAARNT3 I C R A R SMAMR R 5MR SMR AM B O5I O5 W IS 7.O5O51N 7. N 7 35.N735. N 7 5 T N O5M5O5I W RC OI0 7 RT a E I N 7.87. N 7. 35. 5 AMV A A CN EOGE I0 C T T SNORLT O S 20 820 1 - 12020 120 12O - 1 S N M M M M M M M M-.M M M EE SALAAC - L U L .P L L L L L ( L L L L DE E O TA R. NTI NNOM )0)1 )0)0)'0) ) 0 ) 0 ) 0 ) 0 )'1 )1 SU) 80808080808A8080S08080 80 ASF NRDREI G ETAEMD/ S TSRTNAI N + - + + + + + + + + A( I SORC T O E E E E E E E~ E E E E D E )E MLER P N I 3 4 0 7 6 5 3 3 6' 7 9 L 4 DMS /7 L /5 L E /5/1/1/8/4/2.5/58/1. C EAW! A T 2 /52/18 8 8 8 8 8 1 LES 8 HT V L A) CN N PE CF E 1 2 1 1 1 1 1 1 1' 1 4 4 (LE BH E E E O{ET M RS LL CO S - AT N AS L NNN (1(1(1 (1(2(0(1(1(1C1 (1 E (1 NTN O EE ARAA 10100010100010100010i0 U 10 OCE R LN OERE 0 0 0 0+0 0 0 - 0 O-L 0-IER I CN TM E - E - E+E E - E+E - E E+E-E - E A- - E T T. A V UE A S E2E6E4E4E1E9E6E3E5E4E8 V E4 C8 P 90 45 E0 025933.156586 7.2.2 1 6 0 9.78 0 4 4.1 56 5.2.2 N NT C 8 T N 617 54 ENI

6. 5

9. 60.10. 6 E

I 6 NN D YT I 1 8 4 6 - 9 81 8 3 4 DO AO N 9 2 PD FUE OL O T UI QM T 1 1 1 1 2 2 1 2 2 1 2 2 0 1 DA EA I N 0 0 0 0 0 0 0 0 0 0 0 0 0 TEC + IS! SR M O E - - E E E E E E E E E E MA) I I )T E E E E LFTDO 0' 0 0 0 0 0 0 0 0 0 0 0 0 IBI YY OCLN 0 0 0 0 0 0 0 0 0

0. '

0 L I .0 E TT R EL II E T(E 1 1 2 4 1 2 2 2 3 5 2 1 - 3 RGS ENI LL W E E WA II O D S ORS CC L L N AA FF 3 3 .3 DO 1 1 1 LNI AAT FF ) N A OO I INC L EN R E MAO MO ES C OEL NM AI 3 BID ( NT NMSE A AUYM N C NLR A 12 O E AO C L PLNF S 8 2 4 7 2 4 4 6 8 TAAR 2 1 1 3 1 1 2 2 0 TT E A 2 7 2 2 1 0 2 2 2 2 2 9 0 EE OFP M 4 8 9 TT TO M C E 1 1 S 9 S A A L OO A A S B 8 C K P P R R T R a MN G S s ,o? t IIlt! llil .l

v4 ,m* L-- 4 A a d i_Je.s. aem km 4 r- -+A w JS -h-1 l a M-4 BW8" "5 .* Eg a l w$ + i Om OG 8 3 a i eC'N kk. >? U E m 0:s-w ~ mg s _A- - _A gg=. y? y? R-r n u ~ ~ 8 .53 8 ): R a a a-w i

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- ~. -~..- -. -, -. Table H-8 TENNESSEE VALLEY AUTHORITY-CHEMISTRY AND RADIOLOGICAL SERVICES f Effv!RONMENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATION f ~. 1ESTERN AREA RADIOLOGICAL LABORATORY ENVIRONMENTAL MON!TORING REPORTING SYSTEM BADIDACTIv1TY IN CABBAGE PC1/KG'- 0.037 BC/KG (WET WT) i .. NAME OF FACILITY:-SEQUOYAH NUCLEAR PLANT DOCKET No.: '. 50-327,323 LOCATION OF FACILITT: HAMILTON TENNESSEE REPORTING PERIOD: 1990 TYPE AND LOWER LIMIT ALL COITROL NUMBER OF TOTAL' NUMBER 0F INDICATOR LOCATIONS (OCATION WITH HIGHEST ANNUAL MEAM LOCATIchs NONROUTINE .OF ANALYSIS DETECTION MEAN (F) NAME MEAN U) , MEAN (F) REPORTED -PERFORMED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS SEE NOTE 1- - SEE NOTE 2 SEE NOTE 2 - SEE NOTE 2 ' GROSS BETA ~ '2 2.86E+03( 1/ 1)

2. W +03(

1/ 1) '.9.00E+00 2.86E+03(, 1/ - 1) H WALKER FARM 2.86E+03-2.86E+03 1.25 MILES WW. 2.86E+03-2.86E+03 2.48E+03-2.48E+03 GAPMA SCAN (GELI) 2 ' K-40. '1.50E+02 1.38E+03( 1/ 1) H WALKER FARM. '1.38E+03(. 1/

1) 1.27E+03(

1/ 1) I 't.38E+03-1.38E+03 ~ 1.25 MILES NW. 1.38E+03-1.38E+03 1.27E+03-1.27E+03 m mE NOTE: 1.' NOMINAL LOWER LIMIT OF DETECit0E (LLD) AS DESCRIBED IN TABLE E-1. ~ NOTE: 2 2.~MEAN AND RANGE 8ASED UPON DETECTA8tE MEASUREMENTS ONLY. FEACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED ' LOCATIONS IS INDICATED IN PARENTHESES (F). .t. .~ b i .v 45 t ~ .m 'M Y Y d ~ Y 9 Y D-' M* T'"O'"i-' 'T'-

Table 11-9 TENNESSEE VALLEY AUTHORITY CMEMISTRY ANE RADIOLOGICAL SERV!CES ENVIRONMENTAL RAD!rX.0G! CAL MONITORING AIR) INSTRtDENTATION WESTLEN AREA RADIOLOGICAL LABORATORY ENVIRONf'dNTAL le0DITORING REFORTING STSTEM RADICACTIVITY 73 CORN PCI/KG - 0.037 BG/KG (WET UT) [ NAME OF FACILITY: SEQUOTAN kUCLEAR PLANT DOCKET No.: 50-327,328 LOCATION Of FACILITY: MAMILTON TENNESSEE REPORT!4G PERIOD: 1990 (%WTROL NUMBER OF TYPE AND ~ LOWER LIMIT ALL TOTAL NUMBER OF INDICATCR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS NONRtifTINE OF ANALYSIS DETECTION MEAN (F) NAME MEAN (F) MEAN (F) REPORTED PERFORMED (LLD) RAME DISTANCE A W OIRECTION RANE RANGE MEASLREMENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 CROSS BETA 2 9.00E+00 5.05E+03( 1/ 1) H WALKER FARM 5.05E+03( 1/ 1) 5.46E+03( 1/ 1) 5.05E+03-5.05E+03 1.25 MILES WW 5.05E+03-5.05E+03 5.46E+03-5.46E+03 GA?mA SCAN (GELI) 2 K-40 1.50E+02 2.50E+03( 1/ 1) H WALKER FARM 2.50E+03C 1/ t) 2.60E+03( 1/ 1) 2.50E+03-2.50E+03 1.25 MILES NV 2.50E+03-2.50E+03 2.60E+03-2.60E+03 i NOTE:

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

NOTE:

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

e

Table 11-10 TENNESSEE VALLEY AUTHORITY CNEMISTRY AND RADIOLOGICAL SERVICES ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRtMENTATION WESTERN AREA RADIOLOGICAL LABORATORY ENVIRONMENTAL MONITORING REPORTING SYSTEM RADI0 ACTIVITY IN GREEN BEANS PCI/KG - 0.037 82/KG (WET WT) NAME OF FACILITY: SEQUOYAN NUCLEAR PLANT DOCKET No.: 50-327,328 LOCATION OF FACILITY: MAMILTON TENNESSEE REPORTING PERIOD: 1990 . TYPE AND LOWER LIMIT Att CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS NONROUTINE l OF ANALYSIS DETECTICsi MEAN (F) NrdE MEAN (F) MEAN (F) REPORTED l PERFORMED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANCE MEASUREMWIS l SEE NOTE 1 SEE NOTE 2 SEE NOTC 2 SEE NOTE 2 CROSS BETA 2 9.00E+00 4.82E+03( 1/

1) N uALKER FARM 4.82E+03(

1/ 1) 2.81E+03( 1/ 1) 4.82E+03-4.82E+03 1.25 M!LES NW 4.82E+03-4.82E+03 2.81E+03-2.81E+03 l GAPWEA SCAN (GELI) 2' '91-214 2.00E+01 4.87E+01( 1/

1) H WALKER FARM 4.87E+01(

1/ 1) 1 VALUES < LLD 4.87E+01-4.87E+01 1.25 MILES NW 4.87E+01-4.87E+01 C-K-40 ,1.50E+02 2.03E+03( 1/

1) N WALKER FARM 2.03E+03(

1/ 1) 1.34E+03( 1/ 1) ? 2.03E+03-2.03E+03 1.25 MILES NW 2.03C+03-2.03E+03 1.34E+03-1.34E+03 PS-214' 2.00E+01 3.20E+01( 1/

1) N WALKER FARM 3.20E+01(- 1/

1) 1 VALUES < LLD 3.20E+01-3.20E+01 1.25 MILES tM 3.20E+01-3.20E+01 NOTE:

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

NOTE:

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

l 1 1 M BWS" 4 .-~$- sHfg g*W.5W Og Og 8 b sk sE U w a m gge, a g 9 9 a! 5:5lw o9' s9' o ggW 9 s 53 $4 E 8 a a~

t 5-i 4

l 22 "? "? g g -= W "g 39 d E Ew 50 N N -W, E i w, 5= w~ s p i E-W si 99 99 L gE8E l*gS $M E4 e 85 gs gm .B i, g C E <g 5 0 5 TB [WW ES$ '5 5 [U -gg5WE- =-W g"s E--gog5 5 E E = b $!!d55N 5 $ 3d g"35#~abg:-4 = l-5 uf .E 88' e3 9 W W Em -5 E* g-g9 "9 gs e g8 5-e- . d:553

1. c-

.e Eg g-a wng5W~5 Og 09 250 4 5tWg32 ~2 u 8 r ~ s5 sA-

2" w 9ewg

= ~. i 5E ? gO w "a "A 93 s!! ]l.~ 3[ 5"Gl= !I xs -A N vs

Ws E

UW 5 -* WM MA -88" <g g ne ns m =gW s m o .l, d-B wl = 8 9 y m _5 3 - s _ "w -8 . Bnel. s 2 88-c- t 53; i seg. d de .[s. 33 m 1sg! ~- a BB-0 1*~ E 5 'N .lh i '{g

9Igl 2

g 3; u butt .'S WW- ~B t-g --A S S-l ~D g 4 6 ;lc h f g N F-- 9

w a 4 ag J+1 n.- m.m+m...u.,,2s,-A e--,;> ,n da-. a i i BW8 y a a Y S 2 9 9., 5 !:$e ~ m, s u t b Y W ) ?E f f,l w 8 E-i w n e 8 5" o o G

• E E

i -r "g II ~? E l 5 +- 5 C 5 >5 gi d. s a a ~ E -I =x W~ .A og n ase - _, z H -se s. e wm g,s Eg -s- + s-u -y 5 ge gm .B ct$ =g u~5 78 wg re c L _ g _g ! ! ee w-gss_ gu =m We a T g=ss x swa 0 E Es 52! 50 i ::: dd 8 =E <5 "J 4 e -e s s agg! ts 8 98 4 _<Iss g

== - En .-e .o sn gg8gg. 5<a 54 5- - 5 .j sE" lii!ljl y-8 -o a is!s 1 08 08 g s_.

• g g -

g 2g grw- _-,~ s'g -gg w -a, _., a u= e.- ' " g. E m _g g!y ge. eA. vA E-

• s se

. av g _e-a g gm 3 w .Eg ce! gs- + wa. 7 L - as .s se ss- ~- mBS a 8 ~{., og ~ g. b$ . E' l z:.g. g r -ge + UG- - Iaw ig!=g. s w8 -- o hg. a IE 5-E- i -g .t[ei-- E o v Evar s . - ~ i -smr- - - c) - ss 4 .g; 4 '-o gg i .1 'f 'I 11 l -i w ,e u- --c

Table 11-13 TENNESSEE VALLEY AUTHORITY CHEMISTRY AND RADIOLOGICAL SERVICES ENVIRONMENTAL RADIOLOGICAL MON!TORING AND INSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY ENVIRONMENTAL MONITORING REPORTING SYSTEM RADI0 ACTIVITY IN SURFACE WATER (Total) PCI/L - 0.037 so/L NAME OF FACILITY: SEQUOYAN NUCLEAR PLANT DOCKET No.: 50-327,328 LOCATION OF FACILITY: HAMILTON TENNESSEE REPORTING PERICD: 1990 TYPE AND -LOWER LIMIT ALL CONTROL NUMSER OF TOTAL NUMBER O' INDICATOR LOCAT!CWS LOCATION WITH HICHEST ANNUAL MEAN LOCATIONS NONROUTINE OF ANALYSIS DETECTION MEAN (F) KAME MEAN (F) MEAN (F) REPORTED PERFORMED (LLD) RANCE DISTANCE AND D!RECTION RANGE RANGE MEASUREMENTS SEE NOTE 1 SEE NOTE 2 SLE NOTE 2 SEE NOTE 2 l CROSS BETA 39 1.70E+00 2.99E+00( 21/ 26) TRM 483.4 3.16E+00( 11/ 13) 2.66E+00( 10/ 13) 1.83E+00- 6.74E+00 2.06E+00- 6.74E+00 1.96E+00- 4.46E+00 GAMMA SCAN (GELI) 39 BI-214 2.00E+01 2.12E+01( 1/ 26) TRM 483.4 2.12E+01(. 1/ 13) 4.06E+01( 4/ 13) 2.12E+01-2.12E+01 2.12E+01-2.12E+01 '2.42E+01-7.22E+01 .r to P8-214 2.00E+01 26 VALUES < LLD TRM 473.2 13 VALUES < LLD 2.57E+01( 4/ 13) l 7 2.02E+01-3.55E+01 i SR 89-12 3.00E+00 8 VALUES < LLD 4 VALUES < LLD SR 90 12 1.40E+00 8 VALUES < LLD 4 VALUES < LLD l-TRITItM 12 2.50E+02' 8 VAltES < LLD ', VALUES < LLD NOTE:

1. NOMINAL LOWER LIMIT OF DETECTION (LLD) AS DESCR19ED IN TABLE E '.

.l NOTE:

2. MEAN AND RANCE BASED UPOW DETECTABLE MEASUREMENTS ONLY. FRACTIOi OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).

l ) ~ - ~ - - - ~ '

eu. w .6 .n e i -l 1 1 a 4 M ] gw-l r5 l ng N. N?N? g. nene 2 s5 sS dM 9 S S t m, ,e ~ gg. g-R.,, y,gn s-a s u s v s n v v v-9 e: s Rg -gg$g.s 8@ E E g g-W y?g? a s mz g s s - s w og u ~ a c; 82nw = a ~ w N. M N 8 N h N sM ~5nE ss-sE

E

,3 s Er <e. .n .~ s m; a a a l 50 E n. '*8 X5x5 ~ 3.Ne?+v+ E @g- - gB. m: - -E 8 H8 r 4 . !as: a + G-5 asa-Ms-35-8: = za e-- n ar %4 -.s - - s 9 5 <=,= " - N M N 's E 0"*5*5 E_,EgbS !E '$h 1 4 a gss_ Eg -e n. g:8W EWa I T m 'Oe g g-- d sag to toWo-n do "U = g =. n-n e6

O :0g a

2-sgg3 C' 5 E i0 l0l! ~!~ - I, 5 3 1se e o . e- _3 -m 0g8g5agg-5G y a t 8 'E b .b' b-5 - b .E WG3*E=g i;~ f .y S@ S ? S ?- -# E,l: g-n .nnn-n e K sG.5 rs;s as s -s -n m e e a 3 me ge e m.

r. x, -

24 s- ~ w a ...w .e. n m. v 4. -m ~. I j_ j_j. f. %-I ;j!. s,jju-g ga e-s. s g g! 'ji8 j i s s a-a~a~ .a-14 ~ 55 ' w h8- ~ 8" .wI p 8 @ l-0 - @l ' g.. ? ? ?- t$5' E w m

Bess.

E. E sa s s ' 's : 588 -ge? =

g. geg aa s

a 2:

N e a a $ ~H. BB - a . a 4 me g

glg; o

a -g5 j Aj,I[, g 5 'g -a a - x ax s s u ~ ~ a a y -o-8 5 m-EB M 8 ~ -E.2L> .m i ) i

Table H-15 TENNESSEE VALLEY AUTh0RITY CHEMISTRY AND RADIOLOGICAL SERVICES ENV!RONMENTAL RADIOLOGICAL MONITORING AND INSTRt.ptENTATION WESTERN AREA RADIOLOGICAL LABORATORY -ENVIRONMENTAL MONITORING REPORTING STSTEM RAD 10 ACTIVITY IN WELL WATER (Total) PCI/L - 0.037 80/L NAME OF FACILITY: SEQUOYAH NUCLEAR PLANT DOCKET WO.: 50-327,328 LOCAft0N OF FACILITY: RAMILTON TENNESSEE REPORTING PERIOD: 1990 CONTROL 2RJMBER OF -TYPE AND' LOWER LIMIT ALL TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION W:TN HIGMEST ANNUAL MEAN LOCATIONS NONROUTINE OF ANALYSIS DETECTION MEAN (F) MAME MEAN (F) MEAN (F) REPORTED PERFORMED' (LLD) RANCE DISTANCE AND DIRECTION RANGE RANGE 8EASUREMENTS l SEE NOTE 1 SEE WCTE 2 SEE NOTE 2 SEE NOTE 2 o l GROSS BETA 8 1.70E+00 3.94E+00( 4/

4) SON WELL #6 3.94E+00(

4/ 4) 7.12E+00( 3/ 4) 1.84E+00- 4.83E+00 ONSITE NNE 1.84E+00- 4.83E+00 2.61E+00- 1.01E+01 GANIA SCAN (GELI) 8 81-214 2.00E+01. 2.33E+01( 2/ 4) SON WELL #6 2.33E+01( 2/

4) 2.00E+02(

4/ 4) 2.08E+01-2.58E+01 ONSITE NNE 2.08E+01-2.58E+01 9.74E+01-2.95E+02 to PB-214 2.00E+01 4 VALUES < LLD SON WELL #6 4 VALUES < LLD 1.91E+02( 4/ 4) ONSITE kNE 8.43E+01-2.89E+02 7 SR 89 6 3.00E+00 3 VALUES < LLD 3 VALUES < LLD SR 90 6 1.40E+00 3 VALUES < LLD 3 VALUES < LLD j j ' TRITItJM l ,8 4 VALUES < LLD 2.50E+02 4 VALUES < LLD NOTE:

1. Net!NAL LOWER LIMIT OF DETECTION CLD) AS DESCRIBED IN TABLE E-1.

NOTE:

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

e 4 +

~ Table H-16 TENNESSEE VALLEY AUTHORITY CHEM!$TRY A W RADIOLOGICAL SERVICES ENVIRONENTAL RADIOLOGICAL MONITORING A2 INSTRisENTATION WESTERN AREA RADIOLOGICAL LABORATORY ENVIRONMENTAL MONITORING REPORTING SYSTEM 'RADIGACTIVITY IN CNANNEL CATFISM FLESH PCI/Gt - 0.037 SQ/C (DRY WEICHT) bMAME OF FACILITY:'SEQUOYAN NUCLEAR dANY LOCATION OF FACILITY: NAMILTON TENPChEE. ' DOCKET No.: 50-327,328 REPORTING PEtt0D: 1990 l-TYPE A2 - LOER LIMIT ALL. CONTROL NtAtBER OF

TOTAL NUMBER'.

- 0F1 . INDICATOR LOCATIONS LOCATION WITH H! CHEST ANNUAL M AN LOCATIONS NONROUTInE OF ANALYSIS DETECTION MEAN (F) MAME MEAN (F) MAN (F) REPORTED -PERFORE D -(LLD) _ RANGE - DISTANCE AND DIRECTION RANGE-RANGE MASURDENTS SEE NOTE 1) SEE NOTE 2 - SEE NOTE 2 SEE NOTE 2 - GAfstA SCAN '(GELI) -.CS-137 . 6.00E-02 7.72E-02( 1/ 4) CHICKAMAUGA RES 7.72E-C2( 1/ 2) 9.30E-02( 2/ 2) 7.72E 7.72E-02 1 TRM 471-530 - 7.72E 7.72E-02. 7.15E 1.15E-01 K 1.00E+00 1.10E+01( 4/ e 4) CHICKAMAUGA RES 1.16E+01(1 2/ 2) 1.39E+01: 2/. ' 2) - 8.64E+00 '1.23E+01: TRM 471-530 1.09E+01-1.23E+01-9.11E+00- 1.87E+01 NOTE: 1-5.: NOMINAL LOWER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1. LMOTE: 2.-MEAN AND RANGE 8ASED UPON DETECTA8tE MEASUREE NTS ONLY. FRACTION OF DETECTA8tE MEASUREMENTS AT SPECIFIED - s '~ - LOCATIONS IS INDICATED IN PARENTHESES (F). ? t 1 ( ':@ m. A. / r.,,,. .T e 4r-1 i- i .+.,.v., ..6 '9 mmr',-...-'8N1 bL.w+ e..%1.M4-m. '"M'l I8'm4 +'" W %'.M8 d-o'- 6 '*N sb g- etM^ 8- Ob=-'m w - hwre- .su- .g-i-+45 9

__.-.c. 52o-, e 4 a y, 4 a E 4 C l B_WSg l= 280s. S 1 R*h* i 9 .O g { s 9 ig- - wa a! g:gIl2 8?'se ~ c l s sE$5 E 1 u a~a-8 55 c?c? 8 = w 2 g anan e 9 50 N i W" *9 A a-G W r E8 8?g? -W aW "" g ' 0 NWE. 4Wmg 8 Gs I "W E9 -d*E.

• g

= 205 J" CE$ Od-3 5 5 W

• ~

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• Ns 5r-[e 3

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w-Es 2 $s =! $U m yss-ge T = 7 ESI!ssi EE!

• @ i d 3

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1. g 5 d5

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• !g n

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\\ y I b .g g r .j s t l n e 4 a v 1 eP L r r e n a t 1 o e r i a H l t c e a 4 u r u O i u N g d / a r iF R h a a e i t y t n. Y t o r c i a u et e t q r n a I e ir s.a@ i S D l .g i e t g t ts i. f m O f o X i + _ C rL ~ g 1 ta . $sDCE 3 ll llliI f,fl lf ll

Figure 11-2 Direct Radiation Levels Sequoyah Nuclear Plant 4-Quarter Moving Rverage I = l '1 25 - L I' i 0 l P 1 c 7 N (d as - 3 l O d 5O xx%xxx e. i i h b g3 _ 16 h O i C ~ l fd g l in - N I 1 E i 0 Onstte Begin Plant 5 - Cheration X Offette ...f...I.. l...!,,.I ..I.. 1...l.. l...I...I ..f.. l...I... l 1s 77 7e 7s as si et as M ss as s7 se a se 31 l h l Year / Quarter

Figure H-3 Annual Average Gross Beta Activity Air Filters (pCi/ Cubic Meter) Sequoyah Nuclear Plant l P E Indicator E Control C 0.25 Preoperational Phase Operational Phase u b 0.15 i 8 0.05 .M s e 2 8 2 0 i 71 72 73 74 75 76 77 78 79 80p800 81 82 83 84 85 86 87 88 89 90 e

• Data not collected in 1974 l

Figure H-4 Annual Average Gross Beta Activity Drinking Water (pCi/ Liter) Sequoyah Nuclear Plant E Indicator Control Preoperational Phase Operational Phase 5.. 4.5 -- Preoperational Average C 4 bdJ

EEE, i

.5 -- E u 3 tiiIhdiI.IIIIIIIII1.11I. O 71 72 73 74 75 76 77 78 79 80p800 81 82 83 84 85 86 87 88 89 90 \\ l ~

Figure H-5 Annual Average Gross Beta Activity Surface Water (pCi/ Liter) Sequoyah Nuclear Plant E Indicator E Control 6-Preoperational Phase Operational Phase P 5-Preoperational Average i-Y I 4 9 Ihdllll-'ll111h'-"n~~ ^ 0 71 72 73 74 75 76.77 78 79 80p 800 81 82 83 84 85 86 87 88 89 90}}