ML20029C739
| ML20029C739 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 12/31/1993 |
| From: | Powers K TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9404280315 | |
| Download: ML20029C739 (125) | |
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DA Tentra,ee V&rfAuthorty, Post OMce Boe 2000, ScM/ Casy. Tentwssm 37370 200 Ken Powers Vce Presamt. Sop >yah Nuckxv Plant April 19, 1994 U.S. Nuclear Regulatory Commission ATTNr 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 ENVIRONMENTAL OPERATING REPORT In accordance with Technical Specificeticn 6.9.1.6 for SQN Units 1 and 2, enclosed is the Annual Radiological Environaental Operating Report for 1993.
No commitments are contained in this submittal. Please direct questions concerning this issue to W. C. Ludwig at (615) 843-7460.
Sincerely Ken Powers Enclosures cc: See page 2 bbkbbbb 7 /
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U.S. Nuclear Regulatory Commission Page 2 April 19, 1994 cc (Enclosure):
Mr. D. E.-LaBarge, Project Manager l U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike ;
Rockville, Maryland 20852-2739 NRC Resident Inspector Sequoyah Nuclear Plant-2600 Igou Ferry Road Soddy-Daisy, Tennessee 37379-3624 Regional Administrator U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323-2711 l
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ENCLOSURE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SEQUOYAH NUCLEAR PLANT 1993 (W46 940405 003) k f
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Operations Services / Technical Programs Annual Radiological Environmental Operating Report Sequoyah Nuclear Plant 1993 A
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT
.i SEQUOYAH NUCLEAD PLANT 1993 TENNESSEE VALLEY AUTHORITY OPERATIONS SERVICES TECHNICAL PROGRAMS April 1994
TABLE OF CONTENTS Table of Contents . . . . . . . . . . . . . . . . . . . . . . . . . 11 List of Tables .......................... iv List of Figures . . . . . . . . . . . . . . . . . . . . . . . . . . v Executive Summary . . . . . . . . . . . . . . . . . . . . . . . . . 1 Introduction ........................... 2 Naturally Occurring and Background Radioactivity . . . . . . . . 2 Electric Power Production . ......... ......... 5 Site / Plant Description . . . . . . . . .............. 8 Environmental Radiological Monitoring Program . . . . . . . . . . . 10 4
Direct Radiation Monitoring . . . . . . . . . . . . . . . . . . . . 14 Measurement Techniques . . . . . . . . . . . . . . . . . . . . . 14 Results ............................ 15 Atmospheric Monitoring . . . . .......... ........ 19 Sample Collection and Analysis . . . . . . . . . . . . . . . . . 19 Results ........................... 10 Terrestrial Monitoring . . . . ...... ............ 22 Sample Collection and Analysis . . . . . . . . . . . . . . . . . 22 Results ............................ 24 Aquatic Monitoring' . . . . . . . . . . .............. 27 Sample Collection and Analysis . . . . . . . . . . . . . . . . . 27 Results ............................ 29 Assessment and Evaluation . . . . . . . . . . . . . . . . . . . . . 32 Results ............................ 33 Conclusions .......................... 35 References ............................ 36 Appendix A Environmental Radiological Monitoring Program and Sampling Locations ........... ....... 41 Appendix B 1993 Program Modifications .............. 54 11 v'
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- Appendix C Program Deviations .................. 56 Appendix 0 Analytical Procedures . . . . . . . . . . . . . . . . . 60
. Appendix E Nominal Lower Limits of Detection (LLO) ........ 63 Appendix F Quality Assurance / Quality Control Program . ...... 69 Appendix G Land Use Survey . . . . . . . . . . . . . . . . . . . . 78 Appendix H Data Tables . . . . . . . . . . . . . . . . . . . . . . 84 j
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-l LIST OF TABLES Table 1 Comparison of Maximum Annual Average Effluent Concentrations Released to Unrestricted Areas With Reporting levels and Lower Limits of Detection . . . . . 37
-Table 2 Maximum Dose Due to Radioactive Effluent Releases . . . . . . . . . . . . . . . . . . . . . . . . 38 3
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1 LIST OF FIGURES Figure 1 Tennessee Valley Region . . . . . . . . . . . . . . ... 39 Figure 2 Environmental Exposure Pathways of Man Oue ....... 40 to Releases of Radioactive Materials to the Atmosphere and Lake 4
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EXECUTIVi
SUMMARY
This report describes the environmental radiological monitoring program conducted by TVA in the vicinity of the Sequoyah Nuclear Plant (SQN) in 1993.
The program includes the collection of samples from the environment and the determination of the concentrations of radioactive materials in the samples.
Samples are taken from stations in the general area of the plant'and from areas not influenced by plant operations. Station locations are selected after careful consideration of the weather patterns and projected radiation doses to the various areas around the plant. Material sampled includes air, eater, milk, foods, vegetation, soll, 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 operations.
The vast majority of the exposures calculated from environmental samples were contributed by naturally occurring radioactive materials or from materials commonly found in the environment as a result of atmospheric nuclear weapons fallout.
Small amounts of Co-58, Co-60, and Cs-134 were found in sediment samples downstream from the plant. This activity in stream sediment would result in no measurable increase over background in the dose to the general public.
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INTRODUCTION This report describes and summarizes a large volume of data, the results of thousands of measurements and laboratory analyses. The measurements are made to comply with regulations and to determine potential effects on public health and safety. This report satisfies the annual reporting requirements of SQN Technical Sp3cification 6.9.1.6. In addition, estimates of the maximum potential doses to the surrounding population are made from radioactivity measured both in plant effluents and in environmental samples. Some of the data presented are prescribed by specific requirements while other data are included which may be useful or interesting to individuals who do not work eith this material routinely.
Naturally Occurring and Background Radioactivity Most materials in our world contain trace amounts of naturally occurring radioactivity. Approximately 0.01 percent of all potassium is radioactive potassium-40 (K-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 pC) of K-40 which delivers a dose of 15 to 20 mrem per year to the bone and soft tissue of the body. Naturally occurring radioactive materials have always been in our environment. Other examples of naturally occurring radioactive materials are beryllium (Be)-7, bismuth (B1)-212 and 214, lead (Pb)-212 and 214, thallium (TI)-208, actinium (Ac)-228, uranium (U)-238, uranium-235, thorium (Th)-234, radium (Ra)-226, radon (Rn)-222, carbon (C)-14, and
. hydrogen (H)-3 (generally called tritium). These naturally occurring
radioactive materials are in the soll, our food, our drinking water, and our bodies. The radiation from these materials makes up a part of the low-level natural background radiation. The remainder of the natural background radiation comes from outer space. He are all exposed to this natural radiation 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day.
The average dose equivalent at sea level resulting from radiation from outer space (part of natural background radiation) is about 27 mrem / year. This essentially doubles with each 6600-foot increase in altitude in the lower atmosp' are. Another part of natural background radiation comes from naturally occurring radioactive materials in the soll and rocks. Because the quantity of naturally occurring radioactive material varies according to geographical location, the part of the natural background radiation coming from this radioactive material also depends upon the geographical location. Most of the remainder of the natural background radiation comes from the radioactive materials within each individual's body. 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 radiolsotopes in the concrete or brick, such as trace amounts of uranium, radlum, thorium, etc.
Because the city of Denver, Colorado, is over 5000 feet in altitude and the soll and rocks there contain more radioactive material than the U.S. average,
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'the people of Denver receive around 350 mrem / year total natural background radiation dose equivalent compared to about 295 mrem / year for the national average. People in some locations of the world receive over 1000 mrem / year 1
-natural background radiation dose equivalent, primarily because of.the greater quantity of radioactive materials in the soll and rocks in those locations.
Scientists have never been able to show that these levels of radiation have caused physical harm to anyone, j l
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 j l
primarily adapted from References 2 and 3. '
U.S. GENERAL POPULATION AVERAGE DOSE EQUIVALENT ESTIMATES ;
Source Milltrem/ Year Per Person Natural background dose equivalent Cosmic 27 Cosmogenic 1 Terrestrial 28 In the body 39 Radon 200 Total 295 Release of radioactive material in 5 natural gas, mining, ore processing, etc.
Medical (effective dose equivalent) 53 Nuclear weapons fallout less than 1 Nuclear energy 0.28 Consumer products 0.03 Total 355 (approximately)
As can be seen from the table, natural background radiation dose equivalent to the U.S. population normally exceeds that from nuclear plants by several hundred times. This indicates that nuclear plant operations normally result in a population radiation dose equivalent which is insignificant compared to that which results from natural background radiation. It should be noted that the use of radiation and radioactive materials for medical uses has resulted in a similar effective dose equivalent to the U.S. population as that caused by natural background cosmic and terrestrial radiation.
Significant discussion recently has centered around exposures from radon.
Radon is an inert gas given off as a result of the decay of naturally occurring radium-226 in soil. When dispersed in the atmosphere, radon concentrations are relatively low. However, when the gas is trapped in closed spaces, it can build up until concentrations become significant. The National Council of Radiation Protection and Measurements (Reference 2) has estimated that the average annual effective dose equivalent from radon in the United States is approximately 200 mrem / year. This estimated dose is approximately twice the average dose equivalent from all other natural background sources.
Electric Power Production Nuclear power plants are similar in many respects to conventional coal burning (or other fossil fuel) electrical generating plants. The basic process behind electrical power production in both types of plants is that fuel is used to heat water to produce steam which provides the force to turn turbines 1-d generators. However, nuclear plants include many complex systems tc Av rol the nuclear fission process and to safeguard against the possibility u.
reactor malfunction, which could lead to the release of radioactive materials.
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- Very small amounts of these fission and activation products are released into the plant systems. This radioactive material can be transported throughout plant systems and some of it released to the environment.
- All - "s through which radioactivity is released are monitored . Liquid and gasev_ ffluent monitors record the radiation levels for each release. These monitors also provide alarm mechanisms to prompt 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 made in surrot ig areas to verify that the population is not being exposed to significant levels of radiation or radioactive materials.
l The SON Offsite Dose Calculation Manual (ODCM), which is required by the plant Technical Specifications, prescribes limits for the release of radioactive effluents, as well as limits for doses to the general public from the release of these effluents.
The dose to a memberlof the general public from radioactive materials released to unrestricted areas, as given in NRC guidelines 0,,d the ODCH, is limited as follows:
.Llauld Effluents Total body <3 mrem / year Any organ (10 mrem / year Gaseous Effluents Noble gases:
Gamma radiation 110 mrad / year Beta radiation 120 mrad / year Particulates:
Any organ 115 mrem / year-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 Thyrold 75 mrem / year Any other organ 25 mrem / year 10 CFR 20.106 prescribes maximum permissible concentrations (MPCs) for radioactive materials released to unrestricted areas, and the revised regulation, 10 CFR 20.1302(b) (implemented by TVA on January l', 1994) presents annual average limits for the concentrations of radioactive materials released in gaseous and liquid effluents at the boundary of the unrestricted areas.
Table 1 of this report presents the annual average concentration limits for-the principal radionuclides associated with nuclear power plant effluents.
This table also presents-(1) the concentrations of radioactive materials in the environment which would require a special report to the NRC and (2) the I detection limits for the listed radionuclides. It should be noted that the i levels of radioactive materials measured in the environment are typically I below or only slightly abcve t ower limit of detection. The data presented j in this report indicate compilance with both versions of the regulation. l H
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l SITE / PLANT DESCRIPTION The SQN is located on a site near the geographical center of Hamilton County, Tennessee, on a peninsula on the western shore of Chickamauga Lake at.
Tennessee River Mlle (TRH) 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 (HBN) site.
Population is distributed rather unevenly within 10 miles of the SQN site.
Approximately 60 percent of the population is in the general area between 5 and 10 miles from the plant in the sectors ranging from the south, clockwise, to the northwest 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 northernmost extent of the urbanization around Chattanooga is approximately 4 miles from the site. The population of Chattanooga is about 160,000, while Soddy-Daisy has approximately 8,500 people. The population within a 10-mile radius of SQN is approximately 60,000.
With the exception of the community 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. At least three dairy farms are located within 10 miles 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 generation of electric power. Secondary uses include industrial and public water supply and waste disposal, commercial fishing, and recreation. Public access areas, boat docks, and residential subdivisions have been developed along the reservoir shoreline.
SQN consists of two pressurized water reactors: each unit is rated at 1171 megawatts (electrical). Fuel was loaded in unit 1 on March 1, 1980, and the unit achieved critically on July 5, 1980. Fuel was loaded in unit 2 in July 1981, and the unit achieved initial criticality on November 5, 1981. The plant, shut down in August 1985, was restarted in 1988.
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ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM The unique environmental concern associated with a nuclear power plant is its production of radioactive materials and radiation. The vast majority of this radiation and radioactivity is contained within the reactor itself or one of the other plant systems designed to keep the material in the plant. The retention of the materials in each level of control is achieved by system 4
engineering, design, construction, and operation. Environmental monitoring is a final verification that the systems are performing as planned. The monitoring program is designed to check the pathways between the plant and the people in the immediate vicinity and to most efficiently monitor these pathways. Sample types are chosen so that the potential for detection of radioactivity in the environment will be maximized. The environmental radiological monitoring program is outlined in Appendix A.
There are two primary pathways by which radioactivity can move through the environment to humans: air and water (see Figure 2). The air pathway can be separated into two components: the direct (alrborne) 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 i 1
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, i
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A number of factors were considered in determining the locations for l 1
collecting environmental samples. The locations for the atmospheric l l
monitoring stations were determined from a critical pathway analysis based on deather patterns, dose projections, population distribution, and land use.
Terrestrial sanpling stations were selected after reviewing such things as the locations of dairy animals and gardens in conjunction with the air pathway analysis. Liquid pathway stations were selected based on dose projections, eater use information, and availability of media such as fish and sediment.
Table A-2 (Appendix A, Table 2: This identification system is used for all tables and figures in the appendices.) lists the sampling stations and the types of samples collected. Modifications made to the program in 1993 are described in Appendix B and exceptions to the sampling and analysis schedule are presented in Appendix C.
To determine the amount of radioactivity in the envircnment prior to the operation of SQN, a preoperational environmental radiological mo11toring program was initiated in 1971 and operated until the plant began operation in 1980. Measurements of the same types of radioactive materials ttat are measured currently were assessed during the preoperational phase to establish normal background levels for various radionuclides in the environment.
The preoperational monitoring program is a very important part of the overall program. During tne 1950s, 60s, and 70s, atmospheric nuclear weapons testing released radioactive material to the environment causing fluctuations in background radiation levels. This radioactive material is the same. type as that produced in the SON reactors. Preoperational knowledge of pceexisting radionuclide patterns in the environment permits a determination, through comparison and trending analyses, of whether the operation of SQN is impacting
.the environment and thus the surrounding population.
The determination of impact during the operating phase also considers.the presence of control stations 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 group located at the Western Area Radiological Laboratory (WARL) 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 (LLO). 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
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process as soon as possible so they can be corrected. This program includes equipment checks to ensure that the complex radiation detection devices are working properly and the analysis of special samples which are included alongside routine environmental samples. The laboratory participates in the Environmental Protection Agency (EPA) Interlaboratory Comparison Program. In addition, samples split with the EPA 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.
't DIRECT RADIATION MONITORING Direct radiation levels are measured at a number of stations around the plant site. These measurements include contributions from cosmic radiation, radioactivity in the ground, fallout from atmospheric nuclear weapons tests conducted in the past, and any radioactivity that may be present as a result of plant operations. Because of the relative large variations in background radiation as compared to the small levels from the plant, contributions from the plant may be difficult to distinguish.
Radiation levels measured in the area around the SQN site in 1993 were consistent with levels from previous years and with levels measured at other locations in the region.
Measurement Techniques Direct radiation measurements are made with thermoluminescent dosimeters (TLDs). When certain materials are exposed to ionizing radiation, many of the electrons which become displaced are trapped in the crystalline-structure of the material. They remain trapped for long periods of time as long as the l material is not heated. When heated (thermo-), the electrons are released, producing a pulse of light (-luminescence). The intensity of the light pulse is proportional to the amount of radiation to which the material was exposed.
Materials which display these characteristics are used in the manufacture of 1
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From 1971 through 1989, TVA used a Victoreen dosimeter consisting of a manganese activated calcium fluoride (Ca:F:Mn) TLD material encased in a glass bulb.
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In 1989, TVA began the process of changing from the Victoreen dosimeter to the Panasonic Hodel UD-814 dosimeter, and completely changed to the Panasonic
' dosimeter in 1990. This dosimeter contains four elements consisting of one lithium borate and three calcium sulfate phosphors. The calcium sulfate phosphors are shielded by approximately 1000 mg/cm' plastic and lead to compensate for the over-response of the detector to low energy radiation.
The TLDs are placed approximately 1 meter above the ground, with three TLDs at each station. Sixteen stations are located around the plant near the sito boundary, one station in each of the 16 compass 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 expo'sure on the detectors is read with a Panasonic Model UD-710A automatic reader interfaced with a Hewlett Packard Model 9000 computer system. Six of the locations also have TLDs processed by the NRC. The results from the NRC measurements are reported in NUREG 0837.
Since the calcium sulfate phosphor is much more sensitive than 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 outilned in Regulatory Guide 4.13 for environmental applications of TLDs.
Results !
All results are normalized to a standard quarter (91.25 days or 2190 hours0.0253 days <br />0.608 hours <br />0.00362 weeks <br />8.33295e-4 months <br />).
The stations are grouped according to the distance from the plant. The first group consists of all stations within 1 mile of the plant. The second group lies between 1 and 2 miles, the third group between 2 and 4 miles, the fourth between 4 and 6 miles, and the fifth group is made up of all stations greater than 6 miles from the plant. Past data have shown that the results from all stations 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 dostmeters that were not as precise at lower exposures. Consequently, environmental radiation levels reported in the early years of the preoperational phase of the monitoring program exceed current measurements of background radiation levels. For this reason, data collected prior to 1976 are not included in this report.
The quarterly gamma radiation levels determined from the TLDs deployed around SQN in 1993 are given in Table H-1. The exposures are measured in milliroentgens and reported in millirem / standard quarter. For purposes of this report, one milliroentgen and one milltrem (mrem) are assumed to be equivalent. The rounded average annual exposures are shown below. For comparison purposes, the average direct radiation measurements made in the preoperational phase of the monitoring program are also shown.
Annual Average 01 rect Radiation Levels SQN meem/ year Preoperational 1993 Average Onsite Stations 61 79 Offsite Stations 55 63 The data in Table H-1 Indicate that the average quarterly radiation levels at the SQN onsite stations are approximately 2 mrem / 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 mrem / quarter higher than levels offsite. The causes of these differences have not been isolated; however, it is postulated that the differences are probably attributable to combinations of influences such as natural variations in environmental radiation levels, earth-moving activities onsite, and the mass 3
of concrete employed in the construction of the plant. Other undetermined l t
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 WBN 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 1993. To reduce the seasonal variations present in the data sets, a 4-quarter moving average was constructed for each data set. Figure H-2 presents a trend plot of the direct radiation levels as defined by the moving averages. The data follow the same general trend as the raw data, but_the curves are much smoother.
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All results reported in 1993 are consistent with direct radiation levels L identifled at locations which are not influenced by the operation of SQN.
There is no indication that SQN activities increased the backgrouno radiation 'i levels normally observed in the areas surrounding the plant. l i
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ATMOSPHERIC MONITORING The atmospheric monitoring network is divided into three groups identified as local, perimeter, and remote. Four local air monitoring stations are located on or adjacent to the plant site in the general directions of greatest wind frequency. Four perimeter air monitoring stations are located in communities out to about 10 miles from the plant, and four remote air monitors are located out to 20 miles. The monitoring program and the locations of monitoring stations are identified in the tables and figures of Appendix A. The remote stations are used as control or baseline 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 l Air particulates are collected by continuously sampling air at a flow rate of approximately 2 cubic feet per minute (cfm) through a 2-inch Hollingsworth and Vose LB5211 glass fiber filter. The sampling system consists of a pump, a magnehelic gauge for measuring the drop in pressure across the system, and a dry gas meter. This allows an accurate determination of the volume of air passing through the filter. This system is housed in.a building approximately 1
2 feet by 3 feet by 4 feet. The filter is contained in a sampling head j mounted on the outside of the monitor building. The filter is replaced ~every I 1
7 days. Each filter is analyzed for gross beta activity about 3 days after collection to allow time for the radon daughters to decay.
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Every 4 weeks composites of the filters from each location are analyzed for gamma-emitting radionuclides (gamma spectroscopy).
Gaseous radiolodine is collected using a commercially available cartridge containing TE0A-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 by a complete gamma spectroscopy analysis.
Rainwater is collected by use of a collection tray attached to the monitor building. The collection tray is protected from debris by a screen cover. As eater 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. Since no plant-related air activity was detected in 1993, no rainwater samples from SQN were analyzed in this reporting period.
Results The results from the analysis of air particulate samples are summarized in Table H-2. Gross beta activity in 1993 was consistent with levels reported in previous years. The average level at indicator and control stations was 0.020 and 0.020 pC1/m', respectively.
The annual averages of the gross beta activity in air particulate filters at these stations for the years 1971-1993 are presented in Figure H-3. Increased levels due to fallout from atmospheric nuclear weapons testing are evident, especially in 1971, 1977, 1978, and 1981. Evidence of a small increase resulting from the Chernobyl accident can also be seen in 1986. These patterns are consistent with data from monitoring programs conducted by TVA at nonoperating nuclear power plant construction sites.
1 Only natural radioactive materials were identified by the monthly gamma spectral analysis of the air particulate samples. No fission or activation products were found at levels greater than the LLDs. As shown in Table H-3, iodine-131 was not detected in any of the charcoal canister samples collected in 1993.
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TERRESTRIAL MONITORING Terrestrial monitoring is accomplished by collecting samples of environmental media that may transport radioactive material from the atmosphere to humans.
For example, radioactive material may be deposited on a vegetable garden and be ingested along with the vegetables or it may be deposited on pasture grass where dairy cattle are grazing. When the cow ingests the radioactive material, some of it may be transferred to the milk and consumed by humans who drink the milk. Therefore, samples of milk, vegetation, soll, and food crops are collected and analyzed to determine potential impacts from exposure through this pathway. The results from the analysis of these samples are shown in Tables H-4 through H-12.
A land use survey is conducted annually to locate milk producing animals and gardens within a 5-mile radius of the plant. Three dairy farms are located on the east side of the river between 4 and 6 miles from the plant. Two farms with at least one milk producing animal have been identified within 2 miles of the plant. The locations with the highest calculated doses to people drinking the milk are included in the sampling program. The dairy located about 5 miles northeast of the plant and the two farms near the plant are considered Indicator stations. The results of the 1993 land use survey are presented in Appendix G.
Sample Collection and Analysis Milk samples are purchased every 2 weeks from the dairy, from the two farms eithin 2 miles of the plant and from at least one of three control dairies.
These samples are placed on Ice for transport to the Radioanalytical g_
Laboratory. A specific analysis for I-131 and a gamma spectroscopy analysis are performed on each sample and Sr-89,90 analysis is performed quarterly.
Samples from the control stations, which are also control stations for the WBN monitoring program, are analyzed for Sr-89,90 monthly.
Vegetation is being sampled every 4 weeks from one farm that had milk producing animals in the past. An additional sample is collected 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 for I-131 analysis. A second sample of between 750 and 1000 grams is also collected from each location. After drying and grinding, these samples are analyzed by gamma spectroscopy. Once each quarter, the samples are ashed after the gamma analysis is completed and analyzed for Sr-89,90.
Soll samples are collected annually from the air monitoring locations. The samples are collected with either a " cookie cutter" or an auger type sampler.
After drying and grinding, the sample is analyzed by gamma spectroscopy. When the gamma analysis is complete, the saraple 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 1993 samples of apples, cabbage, corn, green. beans, potatoes, and I
tomatoes were collected from local vegetable gardens. The edible portion of each sample is analyzed by gamma spectroscopy.
,m
- - A Results
'The results from the analysis of milk samples are presented in Table H-4. No radioactivity which could be attributed to SQN was identified. All I-131 results were less that the established nominal LLO of 0.2 pCl/ liter.
Strontium-90 was found in less than one-third of the samples. The 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). Figure H-4 displays the average Sr-90 concentrations measured in milk since 1971. The concentrations have steadily decreased as a result of the 28-year half-life of Sr-90 and the washout and transport of the element through the soll over the period. The average Sr-90 concentration reported from indicator stations in 1993 was 3.85 pCl/ liter. An average of 2.75 pCl/ liter was identified in samples from control stations. By far the predominant isotope reported in allk samples was the naturally occurring K-40. An average of approximately 1300 pCl/ 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 i
l near SQN and near the Bellefonte Nuclear Plant (under construction) at farms
.obere only one or two cows were being milked for private consumption of the milk. It is postulated that the feeding practices of the:c 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 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 values were less than the nominal LLD, Strontium-90 was identified in one sample at a concentration only slightly higher than the LLO. Again, the largest concentrations identified were for the naturally occurring isotopes K-40 and Be-7.
The only fission or activation product identified in soll samples was Cs-137.
The maximum conceltration of Cs-137 was 1.62 pC1/g. This value is consistent with levels previously reported from fallout. All other radionuclides reported were naturally occurring isotopes (Table H-6).
A plot of the annual average Cs-137 concentrations in soll is presented in Figure H-5. Like the levels of Sr-90 in milk, concentrations of Cs-137 in soll are steadily decreasing as a result of the cessation of weapons testing in the atmosphere, the 30-year half-life of Cs-137 and transport through the environment.
1
i; All radionuclides reported in food samples were naturally occurring. The maximum X-40 value was 3900 pCl/kg in potatoes. Analysis of these samples indicated no contribution from plant activities. The results are reported in Tables H-7 through H-12.
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AQUATIC MONITORING Potential exposures from the liquid pathway can occur from drinking water, 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-58, Co-60, Sb-125, Cs-134 and Cs-137 was identified in some sediment samples; however, the projected exposure to the public through sediment is less than 0.1 mrem / year.
Sample Collection and Analysis Samples of surface water are collected from the Tennessee River using automatic sampling pumps from two downstream stations and one upstream station. A timer turns on the pump at least once every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. The line is flushed and a sample collected into a composite jug. A 1-gallon sample is removed from the composite jug at 4-week intervals and the remaining water in the jug is discarded. The composite sample is analyzed for gamma-emitting.
radionuclides and for gross beta activity. A quarterly composite sample'is analyzed for Sr-89,90 and tritium.
l l
1
Samples are also' collected by an automatic sampling pump at the first downstream drinking water intake. ihese samples are collected in the same manner as the surface water samples. These monthly samples are analyzed by gamma spectroscopy and for gross beta activity. At other selected locations, grab samples are collected from drinking water systems which use the Tennessee River as their source. These samples are analyzed every 4 weeks by gamma spectroscopy and for gross beta activity. A quarterly composite sample from each station is analyzed for Sr-89,90 and tritium. In addition, samples from teo 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 eater, not water processed through the water treatment plant, the control sample should also be unprocessed water. Therefore, the upstream surface eater 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 for strontium 1 and tritium content.
l l
Samples of commercial and game fish species are collected semlannually from i
each of three reservoirs: the reservoir on which_the plant is located (Chickamauga Reservoir), the upstream reservoir (Watts Bar Reservoir),_and the downstream reservolt (Nickajack Reservoir). The samples are collected using a combination of netting techniques and electroftshing. Most of the fish are ,
I filleted, but one group is processed whole for analysis. After drying and grinding, the samples are analyzed by gamma spectroscopy.
i
\
In additioq, whole commercial fish speCles are analyzed for Sr-89 and Sr-90 as a part of commitments in the HBN monitoring program.
Bottom and shoreline sediment are collected semiannually from selected TRM
~ locations using a dredging apparatus or divers. The samples are dried and ground and analyzed by gamma spectroscopy.
Samples of Asiatic clams are collected semlannually from two locations below the plant and one location above the plant. The clams are usually collected 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 Gross beta activity was present in most surface water samples. Concentrations in downstream samples averaged 2.3 pCl/ liter while the upstream samples averaged 2.5 pC1/Ilter. All other values were consistent with previously reported levels from fallout. A trend plot of the gross beta activity in surface water samples from 1971 through 1993 is presented in Figure H-6. A summary table of the results is shown in Table H-13.
The only fission or activation product identified in drinking water-samples was Sr-90 in one sample. The concentration reported was only slightly higher-than the LLD. Average gross beta activity was 2.5 pC1/ liter at the downstream stations and 2.7 pC1/ liter at the control stations.
The results are shown in Table H-14 and a trend plot of the gross beta activity in drinking water from 1971 to the present is presented in Figure H-7.
Concentrations of fission and activation products in ground water were all below the LLDs. Only naturally occurring radionuclides were identifled in these samples. The average gross beta concentration in samples from the onsite well was 3.3 pCl/ liter, while the average from the offsite well was 3.6 pCl/ liter. The results are presented in Table H-15.
Ceslum-137 was identified in six fish samples. The downstream samples contained a maximum of 0.10 pCl/g, while the upstream sample had a maximum of 0.11 pCl/g. Other radioisotopes found in fish were naturally occurring with the most notable being K-40. The concentrations of K-40 ranged from 5.2 pCl/g to 17.7 pCl/g. Sr-90 concentrations in whole commercial species averaged 0.12 pCl/g in downstream samples and 0.13 pC1/g in samples collected upstream. The results are summarized in Tables H-16 H-17, H-18, and H-19. Plots of the annual Cs-137 concentrations are presented in Figures H-8, H-9, H-10 and H-11. Since the concentrations downstream are essentially equivalent to the upstream levels, the concentrations of Cs-137 and Sr-90 are probably a result of fallout or other upstream effluents rather than activities at SQN.
Radionuclides of the types produced by nuclear power plant operations were identified in sediment samples. The materials identified were Cs-137, Cs-134, Co-60, and Co-58. Antimony (Sb-125) was identified in one bottom sediment sample at a concentration of 0.03 pCl/g. In bottom sediment samples the average levels of Cs-137 were 0.97 pC1/g in downstream samples and 0.65 pCl/g upstream. In shoreline sediment, Cs-137 levels averaged 0.07 pC1/g in
downstream samples and 0.01 pCl/g in upstream samples. These values are consistent with previously identified fallout levels; therefore, they are probably not a result of SQN operations.
In bottom sediment, Co-60 concentrations in downstream samples averaged 0.16 pCl/g, while concentrations upstream averaged 0.02 pC1/g. The maximum '
concentrations were 0.27 and 0.02 pCl/g, respectively. Co-60 was identified in one shoreline sediment sample at a concentration of 0.02 pCl/g.
Cs-134 was identifled in all six downstream stream sediment samples at a maximum concentration of 0.06 pC1/g. Co-58 was identified in five downstream samples. The maximum concentration was 0.09 pCl/g and the average was 0.07 pCl/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-58 and Cs-134 were not identified in shoreline sediment. Co-60 was identified in one downstream sample at a concentration of 0.02 pCl/g. Average Cs-137 concentrations downstream were essentially equivalent to previously reported levels. Results from the analysis of shoreline sediment samples are shown in Table H-21.
Graphs of the Cs-137 and Co-60 concentrations in stream sediment are presented in Figures H-12 and H-13, respectively. Figure H-14 presents a plot of the Cs-137 concentrations measured in shoreline sediment since 1980. i Only naturally occurring radioisotopes were identified in clam flesh samples.
1
'The results from the analysis of these samples are presented in Table H-22.
ASSESSMENT AND EVALUATION Potential doses to the public are estimated from measured effluents using computer models. These models were developed by TVA and are based on methodology provided by the NRC in Regulatory Guide 1.109 for determining the potential dose to individuals and populations living in the vicinity of a nuclear power plant. The doses calculated are a representation of the dose to a " maximally exposed individual." Some of the factors used in these calculations (such as ingestion rates) are maximum expected values which will tend to overestimate the dose to this " hypothetical" person. In reality, the expected dose to actual individuals is lower.
The area around the plant is analyzed to determine the pathways through which the public may receive an exposure. As indicated in figure 2, the two major days by which radioactivity is introduced into the environment are through liquid and gaseous effluents.
For liquid effluents, the public can be exposed to radiation from three sources: drinking water from the Tennessee River, eating fish caught in the Tennessee River, and direct exposure to radioactive material due to activities on the banks of the river (recreational activities). Data used to determine these doses are based on guidance given by the.NRC for maximum ingestion rates, exposure times, and distribution of the material in the river.
Whenever possible, data used.in the dose calculation are based on specific conditions for the SQH area.
For gaseous effluents, the public can be exposed to radiation from several 1
sources: direct radiation from the radioactivity in the air, direct radiation 1
'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 maximally exposed individual due to radioactivity released f om SQN in 1993 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 compariso, between the calculated dose and the corresponding limit. The maximun calculated whole body dose equivalent from measured liquid effluents as presented in Table 2 is 0.070 mrem / year, or 2.3 percent of the limit. The maximum organ dose equivalent from gaseous effluents is 0.034 mrem / year. This represents 0.23 percent of the 00CM limit. A more complete description of the effluents released from SQN and the corresponding doses projected from these effluents can be found in the SQN Radioactive Effluent Release Report.
As stated earlier in this report, the estimated increase in radiation dose equivalent to the general public resulting from the operation of.SQN.is negligible when compared to the dose from natural background radiation. The results from each environmental sample are compared with the concentrations
'f, rom the corresponding control. stations and appropriate
~
.-33--
preoperational and background data to determine influences from the t'. ant.
During this report period, Co-60, Co-58, Sb-125, Cs-134, and Cs-137 weJe seen in aquatic media. Cs-137 in sediment is consistent with fallout levels identified in samples both upstream and downstream from the plant. Co-60, Co-58, sb-125, and Cs-134 were identified ia sediment samples downstream from the plant in concentrations which would pioduce no measurable increase in the dose to the general public. No incredses of radioactivity attributable to SQN have been seen in water samples.
Dose estimates were made from concentrations of radioactivity found in samples of environmental media. Media evaluated include, but are not limited to, air, milk, food prodjCts, drinking water, and fish.. Inhalation and ingestion doses estimated for persons at the indicator locations were essentially identical to those determined for persons at control stations. More than 95 percent of those doses were contributed by the naturally occurring radionuclide K-40 a:d by Sr-90 and Cs-137, which are long-lived radioisotopes found in fallout from nuclear weapons testing. Concentrations of Sr-90 and Cs-137 are consistent with levels measured in TVA's preoperational environmental radiological monitoring programs. Figures H-4 and H-5 and Figures H-9 through H-12 indicate that concentrations of Sr-90 and Cs-137 in the environment have decreased since the cessation of atmospheric weapons testing in 1981. This decrease is the result of the decay of the two isotopes and the redistribution of the materials in the environment.
)
- Conclusions It is concluded from the above analysis of the environmental sampling.results and from the trend plots presented in Appendix H that the exposure to members of the general public which may have been attributable to SQN is negligible.
The radioactivity reported herein is primarily the result of fallout or natural background radiation. Any activity which may be present as a result of plant operations does not represent a significant contribution'to the exposure of members of the public.
,~
3 1
REFERENCES
- 1. Merril Eisenbud, Environmental Radioactivity, Academic Press, Inc., New York, NY, 1987.
- 2. National Council on Radiation Protection and Measurements, Report No. 93,
" Ionizing Radiation Exposure of the Population of the United States,"
September 1987.
- 3. United States Nuclear Regulatory Commission, Regulatory Guide 8.29,
" Instruction Concerning Risks From Occupational Radiation Exposure," July 1981.
- 4. Hansen, H. 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.
. . . . .m . < . i <
Table 1 -
3 COMPARISON OF MAXIMUM ANNUAL AVERAGE Ef f tOENT CONCENTRATIONS RELEASED TO UNRESTRICTED AREAS WITH REPORTING LEVELS AND LOWER LIMITS OF DETECTION Concentrations in Water. oCi/ Liter Concentrations in Air. oCi/ Cubic Meter Effluent Reporting Lower Limit Effluent Reporting Lower Limit Concentration' Leve12_ of Detection' Concentration' Leve12, _ , _ of Detection' H-3 1,000,000 20,000 250 100,000 Cr-51 500,000 45 30,000 0.02 ,
Kn-54 30,000 1,000 5 1,000 0.005 Co-58 20,000 1,000 5 1.000 0.005 Co-60 30,000 300 5 50 0.005 Zn-65 5,000 -300 10 400 0.005 Sr-89 8,000 3 1,000 0.0006 Sr-90 500 1.4 6 0.0003 g Nb-95 30,000 400 5 2,000 0.005 u Zr-95 20,000 400 10 400 0.005 Y Ru-103 30,000 5 900 0.005 Ru-106 3,000 40 20 0.02 1-131 1.000 2 1 200 0.9 0.02 Cs-134 900 30 5 200 10 0.005 Cs-137 1,000 50 5 200 20 0.005 Ce-144 3,000 33 40 0.01 Ba-140 8,000 200 25 2,000 0.01 La-140 9,000 200 8 2,000 0.005 Note: 1 pCi = 3.7 x 10-' Bq.
Notet For those reporting levels that are blank, no value is given in the reference.
I Source: Table 2 of Appendix B to 10 CFR 20.1001-20.2401 2 Source: SQN Offsite Dose Calculation Manual. Table 2.3-3 i
3 Source: Table E-1 of this report- !
4
- -A Table 2 Maximum Dose due to Radioactive Effluent Releases Sequoyah Nuclear Plant 1993 mrem / year Liquid Effluents 1993 ODCM Percent of EPA Percent of Type Dose Limit ODCM Limit Limit EPA Limit Total Body 0.070 3 2.3 25 0.3 Any Organ 0.095 10 1.0 25 0.4-Gaseous Efrluents 1993 00CM Percent of EPA Percent of Type Dose Limit ODCM Limit Limit EPA Limit Noble Gas 0.012 10 0.12 25 0.05 (Gamma)
Noble Gas 0.014 20 0.07 25 0.05 (Beta)
Any Organ 0.034 15 0.23 25 0.14 ytou.nus
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A ,- - - m APPENDIX A ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM AND SAMPLING LOCATIONS l
Table A-1 SEQUOYAH NUCLEAR PLANT Environmental Radiological Monitoring Program
- Exposure Pathway Number of Samples and Sampling and Type and Frequency and/or Samole locations
- Collection Freauency of Analysis
- 1. AIRBORNE
- a. Particulates 4 samples from locations Continuous sampler operation Particulate sampler.
(in different sectors) at or with sample collection once Analyze for gross beta near boundary site (LM-2. LM-3 per 7 days (more f requently radioactivity greater than LM-4. and LM-5) if required by dust loading) or equal to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following filter change.
4 samples from communities Perform gamma isotopic approximately 6-10 miles analysis on each sample distance from the plant when gross beta activity (PM-2, 3. 8 and 9) is greater than 10 times yearly mean of control j, 4 samples from control locations greater than 10 sampl es. Composite at least once per 31 days na I miles f rom the plant (RM-1. - (by location) for gamma
, RM-2. RM-3. and RM-4) scan.
- b. Radiciodine Same locations as air Continuous sampler operation I-131 at least once particulates with charcoal canister per 7 days collection at least once per 7 days
- c. Soil Samples from same locations Once per year Gamma scan, Sr-89. Sr-90 as air particulates . once per year ,
- d. Rainwater Same locations as air Composite sample at least Analyzed for gamma nuclides particulates once per 31 days only if radioactivity in other media indicates the presence of increased levels of fallout i
_ . . _ _
- _.-,_.______.r .__
,.m Table A-1 SEQUOYAH NUCLEAR PLANT Environmental Radiological Honitoring Program
- Exposure Pathway Number of Samples and Sampling and Type and Frequency and/or Samole tocations* Collection frecuency of Analysis
- 2. DIRECT RADIATION- 2 or more dosimeters (TLDs) At least once per 92 days Gamma dose at least once per placed at locations (in different 92 days sectors) at or near the site boundary in each of the 16 sectors 2 or more dosimeters placed at stations located approximately 5 miles from the plant in each of the 16 sectors 2 or more dosimeters in approximately 20 locations
, of special interest s~
id 3. WATERBORNE
- a. Surface Water TRM 497.0* Collected by automatic Gross beta and gamma scan on TRM 483.4_ sequential-type sampler
- with each composite sample.
TRM 473.2 composite samples collected Composite for Sr-89. Sr-90 over a period of less than or and tritium analysis at least equal to 32 days once per 92 days
- b. Ground Water 1 sample adjacent to the At least once per 31 days Composited for gross beta, gamma plant (Well No. 6) scan. Sr-89. Sr-90 and tritium i at least once per 92 days I sample from ground water At least once per 92 days Gross beta.' gamma scan. Sr-89, source upgradient (farm HW1 Sr-90 and tritium at least once per 92 days
, . % - ~ , _ me
Table A-1 1
SEQUOYAH NUCLEAR PLANT Environmental Radiological Honitoring Program
- Exposure pathway Number of Samples and Sampling and Type and Frequency and/or Samole tocatiens' Cnllection frecuencv of Analysis
- c. Drinking Water 1 sample at the first potable Collected by automatic Gross beta and gamma scan on surface water supply downstream sequential-type sampler
- each composite sample, from the plant (TRM 473.0) with composite sample collected Composite for. tritium. Sr-89 over a period of less than or and Sr-90 at least once per equal to 31 days 92 days i
I sample at the next 2 downstream . Grab sample once per 31 days potable surface water suppliers (greater than 10 miles downstream)
(IRM 470.5 and IRH 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
- as of less than or equal to j' 31 days
- d. Sediment TRM 496.5 At least once per 184 days 6amma scan of each sample TRH 483.4 TRH 480.8 TRM 472.8 4
- e. Shoreline TRH 485 At least once per 164 days Gamma scan of each sample Sediment TRM 478 TRH 477 I
Table A-1 SEQUOYAH WJCLEAR PLANT Environmental Radiological Monitoring Program
- Exposure Pathway Number of Samples and Sampling and Type and frequency
_ and/or Samole tocations* Collection Frecuency of Analvsis _.
- 4. INGESTION
- a. Milk I sample from milk producing At least once per 15 days Gamma isotopic and 1-131 animals in each of-1-3 areas analysis of each sample.
indicated by the cow census where Sr-89 and Sr-90 once doses are calculated to be per quarter highest. If samples are not available from a milk animal location, doses to that area will be estimated by projecting the doses from concentrations detected e
in milk from other sectors or by
- sampling vegetation where milk is if not available.
At least one sample from control location (Farm 5, C and/or B)
- b. Fish I sample each from Nickajack, At least once per 184 days. Gamma scan on edible portion Chickamauca and Watts Bar One sample of each of the Reservoi rs following species:
Channel Catfish Crappie Smallmouth Buffalo
- c. Invertebrates 2 samples downstream from At least once per 184 days Gamma scan on edible portion (Asiatic Clams) the discharge I sample upstream from the plant (No permanent stations established; depends on location of clams)
Table A-1 SEQUOYAli NUCLEAR PLANT F- Environmental Radiological Monitoring Program
- i Exposure Path =ay Number of Samples and Sampling and Type and frequency and/or Samole tocations' Collection Freauency of Analvsis
- d. Food Products I 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 gardens and/or farms in the foods available for sampling will immediate vicinity of the plant. vary. Following is a list of typical foods which may be available:
Cabbage and/or lettuce Corn Green Beans Potatoes Tomatoes e
d One sample of each of the f same foods grown at greater than 10 miles distance from the plant
- e. Vegetation Samples from farms producing milk At least once per 31 days I-131 and gamma scan at least but not providing a milk sample. cnce per 31 days. Sr-89 and (farm EM) Sr-90 analysis at least once per 92 days, 'l Control sample from one control dairy (farm 5)
- a. The sampling program outlined in this table is that which was in ef fect at the end of 1993.
- b. Sampling locations. sector and distance f rom plant, are described in Table A-2 and A-3 and shown in figures A-1, A-2, and A-3.
- c. Composite samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
- d. The surf ace water control sample shall be considered a control for the drinking water sample.
- . - . . - . . - . - - ~ - -
Table A-2 SEQUOYAH NUCLEAR PLANT Environmental Radiological Monitoring Program Sampling Locations Map Approximate Indicator (I) location Distance or Sanples Number
- Station Sector (miles) Control (C) Collected" 2 LM-2 N 0.8 I AP,CF.R.S 3 LM-3 SSW 2.0 I AP,CF.R,5 4 LM-4 NE 1.5 I AP,CF,R,5 5 LM-5 NNE 1.8 I AP,CF,R,S 7 PM-2 SW 3.8 I AP,CF,R,S 8 PM-3 W 5.6 I AP,CF,R,5 9 PM-8 SSW 8.7 I AP,CF,R,5 10 PM-9 WSW 2.6 I AP CF,R,S 11 RM-1 .SW 16.7 C AP,CF,R,5 12 RM-2 NNE 17.8 C AP,CF,R,S 13 RM-3 ESE 11.3 C AP,CF,R,5 14 RM-4 WNW 18.9 C AP,CF,R,S 15 Farm B NE 43.0 C M
- 16 Farm C NE 16.0 C H 17 Farm S NNE 12.0 C M,V 18 Farm J WNW l.1 I H 19 Farm HW NW l.2 I M,W" 20 Farm EM N 2.6 I V 24 Hell No. 6 NNE 0.15 I W 31 TRH 473.0 --
11.5' I PW (C.F. Industries) i 32 TRM 470.5 --
14.0' I PW (E.I. DuPont) 33 TRM 465.3 --
19.2' I PW (Chattanooga) 34 TRM 497.0 -- 12.5' C SW' 35 TRH 503.8 -- 19.3' C PW (Dayton) 36 TRM 496.5 -- 12.0* C SD 37 TRM 485.0 --
1.l* I SD,SW 39 .TRM 480.8 -- 3.7' I SD 40 TRM 477.0 --
11.3' I SH 42 .TRM-472.8 --
6.5' I SS
-- .._. _ _ . _ _ . 2,
Table A-2 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 -- --
I/C F,CL (Chickamauga Reservoir)
- l. 47 TRM 530-602 -- --
C
' F (Watts Bar Reservoir) i 48 Farm H NE 5.3 I M i a
- a. See figures A-1, A-2, and A-3
- b. Sample Codes AP - Air particulate filter CF - Charcoal filter CL - Clams F - Fish M Hlik PW Pubile water R - Rainwater I S - Soll SD Sediment SS - Shoreline sediment f
SW - Surface water V - Vegetation -
W - Well water
- c. A control for well water.
! d. Distance from plant discharge (TRM 484.5)
- e. Surface water sample also used as a control for public water, r
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Table A-3 SEQUOYAH NUCLEAR PLANT Thermoluminescent Dosimeter (?LD) locations Approximate Onsite (On)*
Map Distance or location Number Station Sector (Miles) Offsite (Off) 3 SSW-1A SSW 2.0 On 4 NE-1A NE 1.5 On 5 NNE-1 NNE 1.8 On 7 SW-2 SH 3.8 Off 8 W-3 W 5.6 Off 9 SSW-3 SSW 8.7 'Off 10 WSW-2A WSW 2.6 Off 11 SH-3 SW 16.7 Off 12 NNE-4 NNE 17.8 Off 13 ESE-3 ESE 11.3 Off 14 WNW-3 WNW 18.9 Off 49 N-1 N 0.6 On ,
50 N-2 N 2.1 Off 51 N-3 N 5.2 Off 52 N-4 N 10.0 Off 53 NNE-2 NNE 4.5 Off 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 63 ESE-2 ESE 4.9 Off 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' 73 SSW-1 SSW 10 . 6 On
.74 SSW-2 SSW 4.0 'Off 75 SW-1 SW 0.9 On 76 WSW-1 WSW 0.9 On 77 WSW-2 WSW 2.5 Off 4
.~ -- -. . .. . --
Table A-3 1
SEQUOYAH NUCLEAR PLANT l l
Thermoluminescent Dosimeter (TLD) locations !
Approximate Onsite (On)*
Hap Distance or Location Number Station Sector (Miles) Offsite (Off) 78 WSW-3 WSW 5.7 Off 79 WSW-4 WSW 7.8 Off 80 WSW-5 WSW 10.1 Off 81 W-1 W 0.8 On 82 W-2 W 4.3 Off 83 WNW-1 WNW 0.4 On 84 WNH-2 WNW 5.3 Off 85 NW-1 NW 0.4 On 86 NW-2 NW 5.2 Off 87 NNW-1 NNW 0.6 On 88 NNW-2 NNW 1.7 On 89 NNW-3 NNW 5.3 Off 90 SSW-1B SSW 1.5 On I
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- a. TL0s designated onsite are those located 2 miles or less from the plant.
TL0s designated offsite are those located more than 2 miles from the plant.
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i Figure A 1 ,
Environmental Radiological Sampling Locations Within 1 Mile of Plant 1
348.75 N 11.25 ,
NNW NNE 326.25 33.75 l
(
NW 2 NE 303.75 4 / 56.25 ENE WNW 3, x
/ *-
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$81.2 5 /s- N Y f / 78.75 !
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% ; EQUOYAH W- - - . , . - 5 NUCLEAR -E
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PLANT 81 ' yTI i 958.75 /
s /'aE '31 101.25 76 i 64 ,
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- 123.75 836.25
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SSE ,
191.25 168.75 ]
S Scale O Mile 1 1
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P Figure A 2 f
Environmental Radiological Sampling Locations From 1 to 5 Miles From the Plant 348.75 N 11.25 NNW ~ ~
NNE 4 33.75 326.25 i NW h ge*
NE 56.25 303.75 56 WNW
/ '
5 55 ENE !
8 e #I 78.75 4
281.25 82 1
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-E W- 1 e6 59 2
10 8 66 101.25 25875 77 .
9 71 69 ESE WSW 3 123,75 236.25 ' o
, g 4
'46 .70
'I 7,2 148.25 213.75 SSW ,
SSE 191.25 S 168.75 SCALE
' O 1 2 MILES l
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' Figure A 3 Environmental Radiological Sampling Locations Greater Than 5 Miles From the Plant 11.25 348.75 "4_
CR038vlLLE g
- 33.75 326,25 0
Nt PM ffy MehDNNVILLE .
15 66.25 303.75 SWEET AT M N
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- DAY 10N 12 Se #
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' 78.75 281.25
- 4 OWAN g4 2 44 q
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146.25 Tat sew .ssa 191.25 e 168.75 8CAtt e
0 6 10 15 20 24 heLES
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r APPENDIX 8 1993 PROGRAM MODIFICATIONS 1
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Appendix 8 Environmental Radiological Monitoring Program Modification During 1993, no modifications were made in the environmental monitoring program.
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- APPENDIX C PROGRAM DEVIATIONS is' l
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1 Appendix C l I
Program Deviations During the 1993 sampling period, twenty two of the scheduled samples were not collected. All scheduled analyses were not completed on two of the collected samples. These occurrences resulted in deviations from the scheduled program but not from the minimum program required by the Offsite Dose Calculation Manual. Table C-1 includes a list of missed samples and analyses and an explanation for the deviations.
Seven milk samples were not collected because of the unavailability of milk; six clam samples were not collected because of scarcity of clams; two air filter samples were not collected because of equipment malfunction and four were missed as a result of power interruptions at the station during construction activities; two water samples contained insufficient volume for gross beta analysis and three were not collected as a result of power Interruptions during construction activities.
Equipment malfunctions were corrected and construction activities which interrupted power to the water samplers were completed.
The missed samples and analyses are listed in the following table.
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l Table C-1 SEQUOYAH NUCLEAR PLANT Environmental Radiological Monitoring Program Exceptions Date Station Location Remarks 1/6/93 & Farm C 16.0 miles NE Milk had already been picked up by 1/20/93 the processor and there was no milk 4 available for a sample. This is one of three control stations.
1/19/93, Farm J 12 miles NNE Four milk samples were not 2/3/93, collected because the cow'was dry.
2/16/93 & Sampling resumed on 3/9/93. Two 3/2/93 of the samples were also scheduled for strontium analysis.
2/16/93 & TRH 503.8 19.3 miles Two drinking water samples .
9/28/93 upstream contained insufficient volume of '
water for gross beta. analysis as a result of reductions in the volume of water processed by the water treatment plant. All other scheduled analyses were completed. In December the sampler was relocated to the intake structure to reduce impacts ,
of shutdowns at the treatment plant.
4/20/93 RM-4 18.9 miles HNH Air particulate and charcoal filters not collected because of a malfunction of the sampling system. The system was repaired i and subsequent samples collected.
5/12/93, TRM 473.0 11.5 miles Three drinking water samples were 8/2/93 & Downstream not collected. As a result of 9/29/93 construction activities at the sample station, power was disrupted at various times. These <
activities were completed and all samples after 9/29/93 were collected as scheduled. These samples were scheduled for gross beta, gamma and I-131 analyses.
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h l Table C-1 l SEQUOYAH NUCLEAR PLANT
. Environmental Radiological Monitoring Program i Exceptions ;
__0 ate Station location Remarks 5/29/93 & Chickamauga SQN area Six clam samples not collected:
11/5/93 Reservoir setrcity of clams made them difficult to locate in sufficient-quantitles.
6/9/93 Farm S 12 miles NNE Milk-had already been picked up by the processor and there was no milk available for a sample. This is one of three control stations.
7/6/93 LM-2 0.8 miles N Air particulate and charcoal filter samples were not collected because of a broken belt on the pump. The belt was replaced and subsequent samples collected.
8/11/93 & RM-3 11.3 miles ESE Air particulate and charcoal 8/18/93 filters not collected as a result of problems with the electrical system. The system was repaired a1d placed back in operation for the weeA of 8/23.
8/31/93 PM-3 5.6 miles W Air particulate and charcoal filter samples were not collected as a result of loss of power to
, the pump. Power was restored and all other samples were collected, 11/9/93 LM-4 1.5 miles NE Air particulate and charcoal filter samples were not collected as a result of loss of power to the pump. Power was restored and all other samples were collected.
APPEN0lX D ANALYTICAL PROCEDURES 1
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APPENDIX D Analytical Procedures Analyses of environmental samples are performed by the radioanalytical laboratory located at the Western Area Radiological Laboratory facility in Muscle Shoals. All analysis procedures are based on accepted methods. A summary of the analysis techniques and methodology follows.
The gross beta measurements are made with an automatic low background counting system. Normal counting times are 50 minutes. Water samples are prepared by evaporating 500 ml of samples to near dryness, transferring to a stainless steel planchet and completing the evaporation process. For solid samples, a specified amount of the sample is packed into a deep stainless steel planchet. Air particulate filters are counted directly in a shallow pignchet.
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 activity can-be detected.
After a radiochemical separation, samples analyzed for Sr-89,90 are counted on a low background beta counting system. The sample is counted a second time after a 7-day ingrowth period. From the two counts the Sr-89 and Sr-90 concentrations can be determined.
' Hater samples are analyzed for tritium content by first distilling a portion of the sample and then counting by liquid scintillation. A commercially available scintillation cocktail is used.
Gamma analyses are performed in various counting geometries depending .on. the sample type and volume. All gamma counts are obtained with germanium type detectors interfaced with a computer based mutlichannel analyzer system.
Spectral data reduction is performed by the computer program HYPERMET.
The charcoal cartridges used to sample gaseous radiolodine were analyzed by gamma spectroscopy using a germanium detector.
All of the necessary efficiency values, weight afficiency curves, and geometry tables are established and maintained on each detector and counting system. A series of daily and periodic quality control checks are. performed to monitor counting instrumentation. System logbooks and control charts are used to document the results of the quality control checks.
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Y APPENDIX E ,.
NOMINAL LOWER LIMITS OF DETECTION (LLD) i J
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e Appendix E Nominal Lower Limits of Detection Sensitive radiation detection devices can give a signal or reading even when no radioactivity is present in a sample being analyzed. This signal may come from trace amounts of radioactivity in the components of the device, from cosmic rays, from naturally occurring radon gas, or from electronic noise. Thus, there is always some sort of signal on these sensitive devices. The signal registered when no activity is present in the sample is called the background.
The point at which the signal is determined to represent radioactivity in the sample is called the critical level. This point is based on statistical analysis of the background readings from any particular device. However, any sample measured over and over in the same device will give different readings, some higher than others. The sample should have a well-defined average reading, but any individual reading will vary from'that average. In order to determine the activity present in a sample that will produce a reading above the critical level, additional statistical analysis of the background readings is required. The-hypothetical activity calculated from this analysis is called the lower limit of detection (LLD). A listing of typical LLD values that~a laboratory publishes is a guide to the sensitivity of the analytical measurements performed by the laboratory.
Every time an activity is calculated from a sample, the background must be subtracted from the sample signal. For the very low levels encountered in environmental monitoring, the sample signals are often very close to the background. The measuring equipment is being used at the limit of its capability. For a sample with no measurable activity, which often happens, about half the time its signal should fall below the average machine background and half the time it should be above the background. If a signal-above the background is present, the calculated activity is compared to the calculated LLO 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 LL0s calculated from these values, in accordance with the methodology prescribed in the 00CH, are presented in Table E-1. The maximum values for the lower limits of detection specified in the 00CH are shown in Table E-2.
The LL0s are also presented in the data tables. For analyses for which LL0s have not been established, an LLO of zero is assumed in determining if a measured _ activity is greater than the LLO. ]
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,m Table E-1 Nominal LLD Values A. Radiochemical Procedures Charcoal Sediment Air Filters Filters Water Milk Fish Flesh . whole Fish food Crops and Soil f oCi/m L_. foci /m'1 IpCt/L) foci /L1 foci /o dry) f oci/o dry) foci /ka wet) foci /o dry)
Gross Beta 0.002 1.7 9 Tritium 250 lodine-131 .020' l.0 0.2 Strontium-89 0.0006 3.0 2.5 0.3 0.7 1.0 Strontium-90 0.00025 1.4 2.0 0.04 0.09 0.3 Wet Vegetation Clam Flesh Heat foci /ko Wet) foci /o Drvi foci /ko Wet)
I m Gross Beta 0.2 15 7 lodine-131 4 Strontium-89 140 Strontium-90 60
' The LLD for I-131 in charcoal filters analyzed by germanium spectroscopy is 0.03 pCi/m'.
4 Table E-1 Nominal LLD Values B. Gamma 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 oCi/m3 oCi/ko. wet oCi'/o. dry oCi/o. dry oCi/a. dry oCi/ko. wet oCi/ko. wet oCi/L oCi/o. dr_v 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 1-131 .005 10 .09 36 .02 .09 .18 10 20 Ru-103 .005 5 .05 20 .01 .05 .11 5 15 Ru-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 .11 .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
, Mn-54 .005 5 .05 20 .01 .05 .10 5 15 cn Zn-65 .005 10 .11 44 .01 .11 .21 10 25 if Co-60 K-40
.005
.04 5
150
.07 1.00 28 400
.01
.20
.07 1.00
.11 2.00 5
150 15 120 8a-140 .01 25 .23 92 .05 .23 .47 25 50 La-140 .005 8 .31 44 .02 .11 .17 8 20 fe-59 .005 5 .10 40 .01 .10 .13 5 15 Be-7 .02 45 .50 200 .30 .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 .02 .03 .35 7 Ra-224 .30 i Ra-226 .
.05 Ac-228 .014 25' .10 80 .10 .10 1.00 22 22 Pa-234m 700 3.00 k
Table E-2 Maximum Values for the Lower Limits of Detection (LLD)
Specified by the SQN Offsite Dose Calculation Manual Airborne Particulate Food Water or Gases Fish Milk Products Sediment Analysis pC1/L 1 PC1/m __ DC1/Kg, wet DC1/L pel/kg, wet pCl/Xq. dry 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.
Mn-54 15 N.A. 130 N.A. N.A. N.A.
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.
Zn-65 30 N.A. 260 N.A. N.A. N.A.
Zr-95 30 N.A. N.A. N.A. N.A. N.A.
Nb-95 15 N.A. N.A. N.A. N.A. N.A.
1-131 l' 7 x 10-' N.A 1 60 N.A.
Cs-134 15 5 x 10-8 130 15 60 150 Cs-137 18 6 x 10-' 150 18 80 180 Ba-140 60 N.A. N.A. 60 N.A. N.A.
La-140 15 N.A. N.A. 15 N.A. N.A.
If.no drinking water pathway exists, a value of 3000pC1/L may be used.
8 If no drinking water pathway exists, a value of 15 pCl/L may be used.
t APPENDIX F QUALITY ASSURANCE / QUALITY CONTROL PROGRAM 1
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__ :_ . . _ _ _ _ - _ - _ - _ _ = _ _ _ - _ _ _ . _ _ _ _ - _ . _ _ . _ _ - _ _ - _ - _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ = _ - _ _ _ _ .
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Appendix F Quality Assurance / Quality Control Program A thorough quality assurance program is employed by the laboratory to 4
ensure that the environmental monitoring data are reliable. This program includes the use of written, approved procedures in performing the work, a nonconformance and corrective action tracking system, systematic internal audits, a complete training and retraining system, audits by various external organizations, and a laboratory quality control program.
The quality control program eN 1oyed by the radioanalytical laboratory is designed to ensure that the sampling and analysis process is working as intended. The program includes equipment checks and the analysis of special samples along with routine samples.
Radiation detection devices are complex and can be tested in a number of
. ways. There are two primary tests which are performed on all devices.
In the first type, the device is operated without a sample on the detector to determine the background count rate. The background counts are usually low values and are due to machine noise, cosmic rays, or trace amounts of radioactivity in the materials used to construct the detector. Charts of background counts are kept and monitored to ensure that no unusually high or low values are encountered.
' In the second test, the device is operated with a known amount of
.. radioactivity present. The number of counts registered from such a
radioactive standard should be very reproducible. These reproducibility checks are also monitored to ensure that they are neither higher nor lower than expected. When counts from either test fall outside the expected range, the device is inspected for malfunction or contamination. It is not placed into service until it is operating properly.
In addition to these two general checks, other quality control checks are performed on the variety of detectors used in the laboratory. The exact nature of these checks depends on the type of device and the method it uses to detect radiation or store the information obtained.
Quality control samples of a variety of types are used by the laboratory to verify the performance of different portions of the analytical process. These quality control samples may be blanks, replicate samples, blind samples, or cross-checks.
Blanks are samples which contain no measurable radioactivity or no activity of the type being measured. Such samples are analyzed to -
determine whether there is any contamination of equipment or commercial laboratory chemicals, cross-contamination in the chemical process, or interference from isotopes other than the one being measured.
Duplicate samples are scheduled at random by the same computer program =l t:hich schedules the collection of the routine samples. For example, if j
.the routine program calls for four milk samples every week, on a random basis each farm might provide an additional sample several times a year.
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These duplicate samples are analyzed along with the other routine samples. They provide information about the variability of radioactive content in the various sample media.
If enough sample is available for a particular analysis, the laboratory analyst can split it into two portions. Such a sample can provide information about the variability of the analytical process since two identical portions of material are analyzed side by side.
Analytical knowns are another category of quality control sample. A known amount of radioactivity is added to a sample medium by the quality control staff or by the analysts themselves. The analysts are told the radioactive content of the sample. Whenever possible, the analytical knowns contain the same amount of radioactivity each time they are run.
In this way, the analysts have immediate knowledge of the quality of the measurement process. A portion of these samples are also blanks.
Blind spikes are samples containing radioactivity which are introduced into the analysis _ process disguised as ordinary environmental samples.
The analyst does not know they contain radioactivity. Since the bulk of i the ordinary workload of the environmental laboratory contains no 1
measurable activity or only naturally occurring radioisotopes, blind i 1
spikes can be used to test the detection capability of the laboratory or they can be used to test the data review process. If an analysis routinely generates numerous zeroes for a particular isotope, the
_ presence of the isotope is brought to the attention of the laboratory supervisor in the daily review process.
Blind spikes test this process since they contain radioactivity at levels high enough to be detected. Furthermore, the activity can be put into such samples at the extreme limit of detection (near the LLD) to determine whether or not the laboratory can find any unusual radioactivity whatsoever.
At present, 5 percent of the laboratory workload is in the category of internal cross-checks. These samples have a known amount of radioactivity added and are presented to the analysts labeled as cross-check samples. This means that the quality control staff knows the radioactive content or "right answer" but the analysts do not. They are atfare 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 since different radioactive standards produced by individuals outside TVA are used in the cross-checks. The results of the analysis of these samples are reported back to EPA which then issues a report of all the results of all participants. These reports are examined very closely by laboratory supervisory and quality control personnel. They indicate how well the laboratory is doing compared to others across the nation. Like internal cross-checks, the EPA cross-checks provide information to the laboratory about the precision and accuracy of the radioanalytical work it does.
The results of TVA's participation in the EPA Interlaboratory Comparison Program are presented in Table F-1. For 1993, all but one EPA cross-check sample concentrations measured by TVA's laboratory were within
- 3-sigma of the EPA reported values. During this year EPA reduced the number of samples in the intercomparison by approximately 30 percent.
TVA spilts certain environmental samples with laboratories operated by the States of Alabama and Tennessee and the EPA Eastern Environmental l
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 eith yet another level of information about laboratory performance.
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These samples demonstrate performance on actual environmental sample matrices rather than on the constructed matrices used in cross-check programs.
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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 !
l analytical process needs correction or improvement. The end result is a i measurement process that provides reliable and vertflable data and is sensitive enough to measure the presence of radioactivity far below the levels which could be harmful to humans. ;
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Table F-1 RESULTS OBTAINED IN INTEELABORATORY COMPARISON PROGRAM A. Air filter (pCi/ filter)
Gross Aloha Gross Beta Strontium-90 Cesium-137 EPA Value TVA EPA Value IVA EPA Value TVA EPA Value IVA W fr3 sioman arg. fr3 sioma) A A. 123 sioma) 6xg. (23 sioma) Arg.
8/93 1929 21 4729 50 1929 27 929 9 1
B. Radiochemical Analysis of Water (pCi/L)
Gross Beta $trontium-89 Strentium-90 Tritium Iodine-131 Plutonium-239
~
EPA Value TVA EPA Value TVA EPA Value TVA EPA Value TVA EPA Value TVA EPA Value IVA 7 [Lau ft3 siomal Ayg. fr3 sional Arg. f 3 sioma) Ayg. f-3 siomal Arg. fr3 sioman arg. fr3 sioma) M 1/93 44 9 45 1529 14 1029 8 20z3 19 4/93* 4129 34 2929 29 6/93 9844x1704 9070 7/93 43 12 40 3429 32 2.529 25 10/93 15e 9 17 117z21 104 10/93* 15:9 11 1029 8 11/93 739821281 7493
Table F-1 RESULTS O8TAINED IN INTERLABORATORY COMPARISON PROGRAM (Continued)
C. Gama-Spectral Analysis of Water (pCi/L}
Ba ri um--133 Cobalt-60 Zinc-65 Ruthenium-106 Cesium-134 Cesium-137 EPA Value TVA EPA Value TVA EPA Value TVA EPA Value IVA EPA Value IVA EPA Value IVA QAlt fe3 siomal Arg. fr3 siamal arg. fr3 siamal 812 I?3 ticmal AIS. Ir3 Si2P.Al hS . fr3 siamal Arg.
4/93* 3929 40 27:9 25 32:9 33 6/93 99:17 100 15 9 15 103:17 106 119:21 101 59 5 5:9 4 10/93* 10:9 10 1229 9 10:9 10 11/93 79:14 77 3029 30 150:26 157 201:35 182 5929 55 40 9 41 D. Milk (pCi/L)
Strontium-89 _itrontium-90 fedine-131 Cesium-137 _ Potassium 40*
, EPA Value TVA EPA Value TVA EPA Value IVA EPA Value TVA EPA Value TVA_
w QAlg i23 siomal Arg. fr3 siamal Arg. fr3 siomal arg. f23 siamal 6X9 I?3 5iomai AE9 w
9/93 3029 20' 25 9 22 120:21 117 4929 47 1679:146 1692 l
- a. Performance Evaluation Intercomparison Study.
- c. The Grand Average of non-outlier participants indicates that the Performance Evaluation Standard had a negative bias for Sr-89. If the Grand Average of 24.03 pCi/ liter were used for the known TVA's results would be -1.3 sigma from the known.
_ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ -)
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APPENDIX G 4
i LAND USE SURVEY d
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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 I 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 impact 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 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 based on measured effluents from the plant are well below applicable dose limits (see Assessment and Evaluation),
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In. response to the 1993 SQN land use survey, annual doses were calculated for air submersion, vegetable ingestion, and milk ingestion. External doses due to radioactivity in air (alr 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 1992, eith the resulting values almost identical to those calculated in 1992.
Doses calculated for ingestion of home-grown foods and milk also were similar to those calculated in 1992.
One farm with milk producing animals was identified in the 1993 survey that had not been identified in previous surveys. This farm is located in the west northwest sector at a distance of approximately 4 miles from the plant. At the time the survey was conducted, goats were being milked a
at the farm. The dose calculated to persons consuming milk from that farm were higher than doses projected from any other farm in the area.
However, the X/Q for that location was lower than the X/Q for any of_the milk sampling locations. Subsequent to the completion of the survey, the oeners of the farm discontinued milking the goats and Indicated they had no intention of resuming milking. Consequently, no changes to the monitoring program were initiated as a result of the' survey report.
Tables G-1, G-2, and G-3 show the comparative relative calculated doses for 1992 and 1993.
- . - . . . - .~_ - .. - _ . . . . . . . . - _ . - - _ . - _ - . . - . .. _. - ,
Table G-1 SEQUOYAH NUCLEAR PLANT Relative Projected Annual Air Submersion Dose to the Nearest Resident Within Five Miles of Plant (mrem / year / unit) 1992 Survey 1993 Survey Approximate Approximate Sector Distance (Miles) Annual Dose Olstance (Hiles) Annual Dose N 0.8 0.12 0.8 0.13 NNE 1.5 0.07 1.5 0.07 NE 1.4 0.07 1.5 0.07 ENE 1.3 0.03 1.3 0.03 E 1.0 0.03 1.0 0.02 4 ESE 1.0 0.03 1.0 0.03
, SW l.4 0.06 1.4 0.06 WSW 0.8 0.07 0.7 0.08
- W 0.6 0.08 0.6 0.07 WNW 1.1 0.02 1.1 0.02 NW 0.6 0.07 0.8 0.04 NNW 0.6 0.12 0.5 0.13 '
i l
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1 l
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y + 'My
Table G-2 SEQUOYAH NUCLEAR PLANT Relative Projected Annual Dose to Child's Critical Organ from Ingestion of Home-Grown Foods (mrem / year /untt) ;
1992 Survey 1993 Survey Approximate Annual Dose Approximate Annual Dose Sector Olstance (Miles) (Bone) 01 stance (Miles) (Bone)
N 1.1 2.41 1.1 2.41 NNE 1.6 1.97 1.6 1.97 NE 2.5 1.02 2.5 0.99 ENE 1.6 0.78 1.6 0.77 1 E 3.1 0.17 3.1 0.17 ESE 1.0 0.80 1.0 0.80 SE 1.2 0.37 1.1 0.86 1 SSE 1.2 1.19 1.3 1.04 5 1.5 1.64 1.4 1.76 SSH 1.6 3.44 1.7 3.23 SH 2.1 1.11 2.1 1.11
- HSH 1.0 1.44 1.0 1.49 H 1.2 0.89 1.2 0.87 HNH 1.2 0.65 1.1 0.73 NH 0.6 2.14 0.9 1.09 NNH 0.6 3.08 0.5 3.94
- i
Table G-3 1
SEQUOYAH NUCLEAR PLANT Relative Projected Annual Dose to Receptor Thyroid from Ingestion of Milk l (mrem / year / unit) 1 Approximate Olstance Annual Dose X/Q Location Sector (Miles)* 1992 1993 s/m 2 Farm H*
- NE 4.8 0.02 0.022 2.87 x 10-'
~ Farm HS* E 4.7 0.005 0.004 6.82 x 10-*
Farm JH* ESE 4.1 0.006 0.005 9.34 x 10-*
Farm J' HNW l.3 0.02 0.024 4.72 x 10-'
farm HH* NW 1.3 0.03 0.029 5.19 x 10-'
Farm OH HNH 4.3 e 0.054 9.16 x 10-*
(Goats) i l
- a. Distances measured to nearest property line,
- b. Vegetation sampled at this location,
- c. Grade A dairy .
- d. Hilk sampled at this location.
- e. Farm not identified in the 1992 survey.
p ma r. -c . -44'.3 A ..aw_-4 h,J.4._- -.k4 ,-.4 ..-.4_A,,3-.3 % 4-4J ur, .t+3 . Sam.. m 4
1 s
4 J
APPENDIX H DATA TABLES 9
J d
1 1
9 i
i Table H-1 DIRECT RADIATION LEVELS Average External Radiation Levels at Various Distances from Sequoyah Nuclear Plant for Each Quarter - 1993 mrem / Quarter
- Average External Gamma Radiation levels' Olstance 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Miles (Feb-Apr 93) (May-Jul 93) (Aug-Oct 93) (Nov 93-Jan 94) 0-1 16.5
- 1.6 16.8 2.1 16.4
- 1.4 15.7
- 1.5 1-2 14.1 1.6 13.9
- 2.0 14.2 1.8 13.3
- 1.8 2-4 13.7
- 1.5 15.4
- 1.8 13.7
- 2.1 12.9
- 1.8 4-6 13.9
- 1.3 13.8 2.4 14.0
- 1.7 13.0
- 1.6
>6 13.8 2 1.2 14.6
- 2.9 13.2
- 1.5 12.5
- 1.4 Average, 0-2 miles (onsite) 15.4 2.0 15.5
- 2.5 15.4 2 1.9 14.6 i 2.0 Average '
> 2 miles (offsite) 13.8 2 1.4 14.4
- 2.5 13.7
- 1.8 12.8
- 1.6
- a. Data normalized to one quarter (2190 hours0.0253 days <br />0.608 hours <br />0.00362 weeks <br />8.33295e-4 months <br />),
- b. Averages of the individual measurements in the set il standard deviation of the set.
4 e
._; .n . . - - .
TENTESSEE VALLEY AUTMC2 TTY TECH 21 CAL PROGRAMS EcV120kMENTAL RAD 10LCGICAL MC3ITC2sCG AND I:51RtME2TATION WESTER 3 AIEA RADIOLCCICAL LA80RATC2Y RADICACTIVITY IN A!R FILTER PC!/M3 - 0.037 E0/M3 NAME OF FACILITY: SEQUGTAH NUCLEAR PLANT DOCrET Wo.: 50-327,326 LOCATION OF FActLITY: HAMILTON TENNESSEE REPORT!hG PERICO: 1993 TTPE AND LOWER LIM!T ALL CONTROL MukBER CF TOTAL MUMBER OF tW!CATOR LOCAT10ks LOCATION titTH NICHEST AkNUAL MEAN LOCATIowS h0hR00T!kE OF ANALYS15 DETECTION MEAN (F) EAME MEAN (F) MEAN (F) REPOt1ED PERFORMED (LLD) RANGE DISTANCE AND O!RECTION RANCE RANCE ME ASUREME NTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE n0TE 2 GROSS BETA 618 2.00E-03 1.95E-02( 413/ 413) LM-4 SCLL ISLAC 1.98E-02( 51/ 51) 1.99E-02C 205/ 205) 9.05E 3.63E-02 1.5 MILES kE 1.01E 3.63E-02 1.03E 4.0SE-02 CA mA SCAM (GELI) 156 SE-7 2.00E-02 9.31E-02( 104/ 104) PM-2 CouuTY PARIC TN 9.88E-02( 13/ 13) 9.09E-02( 52/ 52) 5.79E 1.29E-01 3.75 MILES SW 6.94E 1.15E-01 5.88E 1.31E-07 s81-214 5.00E-03 8.01E-03( 11/ 104) LM-4 S CLL ISLAND 1.19E-02( 2/ 13) 6.24E-03( 5/ 52) -J
$ 5.30E 1.68E-02 1.5 MILES NE 7.10E 1.68E-02 5.70E 7.60E-03 y
& PS-214 5.00E-03 7.72E-03( 9/ 104) LM-4 SCLL ISLAND 1.81E-02( 1/ 13) 5.94E-03< 5/ 52) m 8
5.10E 1.81E-02 1.5 MILES ME 1.81E 1.81E-02 5.00E 7.00E-03 _
- i" N
WOTE: 1. NCMINAL LOWER LIMIT OF DETECTION (LLD) AS DESCRIBED It TABLE E-1.
NOTE: 2. PEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY. FRACTION CF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS ICICATED IN PARENTHESES (F).
l I
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TEkNESSEE VELEY AUTNC11TY TECHNICAL P1t0 GRAMS E::VIR0kstEttTAt RAD!OLOG! CAL MC:11TC3ING AND 1NSTRtJME:: TAT 104 WESTER 3 AREA RIDIOLOGIC E LA".01ATC77 RAD 10 ACTIVITY IN CHARCOAL FILTER PCI/M3 - 0.037 sc/M3 NAME CF FACILITY: SEQUOYAN NUCLEAR PLANT COCKET No.: 50-327,328 LOCATION OF FACILITY: ftAMILTON TENNESSEE REPORT!kG PEtt00: 1995 TYPE AND LOL:ER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER CF IM3!CATOR LOCATIONS LOCATION WITN MichEST ANNUAL MEAN LOCATIOWS NONROUTINE OF ANALYSIS DETECT!0ei MEAN (F) NAME FEAN (F) MEAN (F) REPORTED PERFOstMED (LLD) RANCE DISTANCE AND DIRECTION RANGE RANGE MEASUREMEhTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GAMMA SCAN (GELT) 618 31-214 NOT ESTA8 1.82E-02( 36/ 413) LM-5 moved oct 6 92 2.78E-02( 1/ 52) 2.57E-C2' 17/ 205) 5.60E 5.41E-02 SSW,1.5 Mi to 2.0 Mi 2.78E 2.78E-02 7.4CE 1.11E-01 K-40 NOT ESTA8 2 53E-01( 27/ 413) LM-3 moved oce 6 92 3.93E-01( 2/ 52) 2.36E-01C 14/ 205) 1.25E 4.80E-01 SSW,1.5 Mi to 2.0 Mi 3.06E 4.80E-01 1.50E 3.93E-01 Ps-212 NOT ESTAs 4.03E-03( 26/ 413) PM-2 COUNTY PARE TN 7.20E-03( 4/ 52) 205 VALUES < LLD 0.00E+00 1.08E-02 3.75 MILES SW 5.70E 1.08E-02 e '
Ps-214 NOT ESTA8 2.31E-02( 113/ 413) PM-S MARRISON, TN 3.08E-02( 15/ 52) 2.63E-02( 55/ 205) >
E 4
1.60E 7.78E-02 8.75 MILES SSW 1.60E 7.7BE-02 2.20E 1.60E-01 %
rrs NOTE: 1. WOMINAL LOWER LIMIT CF DETECTION (LLD) AS DESCRIBED IN TABLE E-1 . T W
NOTE: 2. MEAN AND RANGE BASED UPON DETECTABLE MEASUltEMENTS ONLY. FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS 15 INDICATED IN PARENTHESES (F). ,
TErkESSEE WALLEY teTHC21TY TECHNICAL PROGRAMS EtytR0kMENTAL RADIOLO:;ICAL MONITC2itG AND INSTRUMENTATION WESTERN AREA RADIOLOGICAL LASORATC2Y RADIOACTIVITY th it!LK Pct /L - 0.037 83/L
%AME OF FACILITY: SEQUOYAH NUCLEAR PLANT DOCKET wo.: 50-327,323 LOCA*10N OF FACILITY: NAMILTCis TEkuESSEE EEPORTING PERIOD: 1993
!vpE Ao LOWR LIMtT ALL CONTROL NUMBER CF TOTAL CABER OF INDICATOR LOCATIONS LOCATION WITH N! CHEST AN1RJAL MEAN LOCA!!Ok5 komROUT!kE OF ANALYSIS DETECTION MEAN (F) NAME MEAN (F) MEAN (F) REPORTED PERFORMED (LLD) RANCE DISTANCE AhD DIRECTION RANCE RANGE MEASUREMENi$
SEE NOTE 1 SEE 40TE 2 SEE NOTE 2 SEE NOTE 2 100!NE-131 149 2.00E-01 74 VALUES < LLD 75 VALUES < LLD CAMMA SCAX (GELI) 149 AC-223 2.50E+01 74 VALUES < LLD JCEES FARM 22 YALUES < LLD 2.90E+01( 1/ 75) 1.25 MILES W 2.90E+01- 2.90E+01 51-214 2.00E+01 3.06E+01( 3/ 74) N WALKEt FARM 3.57E+01( 1/ 26) 8.54E+01( 16/ 75) H 2.19E+01- 3.57E+01 1.25 MILES NW 3.57E+01- 3.57E+01 2.06E*01- 1.91E+02 >
b K-40 1.50E+02 1.27E+03( 73/ 74) NotDER DAIRY 4.25 MILES NE 1.36E+03< 25/ 26) 1.29E+03( 75/ 75) 9.76E+02- 1.53E+03 6.75E+02- 1.59E+C3 rrr CD 7.61E+02- 1.58E+03 PS-214 2.00E+01 74 VALUES < LLD JONES FARM 22 VALUES
- LLD 9.01E+01( 13/ 75) -
1.25 MILES W 2.12E+01- 1.79E+02 I SR 89 49 2.50E+00 11 VALUES < LLD 38 VALUES < LLD SR 90 49 2.00E+00 3.85E+00( 10/ 11) JONES FARM 5.84E+00( 3/ 3) 2.75E+00i 5/ 38) 2.10E+00- 6.83E+00 1.25 MILES W 4.27E+00- 6.83E+00 2.06E+f& 3.57E+00 kOTE: 1. NOMINAL LOWER LIMIT OF DETECTION (LLD) As DESCRIBED IN TABLE E-1.
NOTE: 2. MEAN AND RANCE BASED LIPON DETECTABLE MEASUREMENTS ONLY. FRACTIOff OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).
TEDkESSEE VOLLE7 AUTHOITY TECHNICAL PROGRAMS EOtf!RONMEUTAL RADIOLCSICAL MOITOING AND INSTRtMEDTATION WESTERN AREA RADIOLOGICAL LASCATOY RADIOACTIVITY IN VEGETATION PCl/KG - 0.037 BQ/KG (WET WEIGHT)
NAME OF FACILITY: SEQUOYAN NUCLEAR PLANT DOCKET NO.: 50-327,328 LOCATION OF FACILITY: HAMILTON TENNESSEE REPORTING PERIOD: 1993 TTPE AND LOWER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER OF ikDICATOR LOCATIONS LOCATION WITN HIGHEST ANNUAL MEAM LOCATIONS NONROUTINE OF ANALYSIS DETECTION MEAN (F) NAME MEAN (F) MEAN (F) REPORTED PERFORMED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 ICDINE-131 26 4.00E+00 13 YALUES < LLD 13 YALUES < LLD CAMMA SCAN (GELI) 26 BE-7 2.00E+02 1.80E+03( 13/ 13) EDGAR MALOkE FARM 1.80E+03( 13/ 13) 1.22E+03( 11/ 13) 2.15E+02- 5.70E+03 2.5 MILES N 2.15E+02- 5.70E+03 3.48E+02- 4.2TE+03 81-214 4.80E+01 8.21E+01C 4/ 13) EDGAR MALONE FARM 8.21E+01< 4/ 13) 2.50E+02( 1/ 13) g 5.73E+01- 1.24E+02 2.5 MILES N 5.73E+01- 1.24E+02 2.50E+02- 2.50E+02 >
e K-40 4.00E+02 4.95E+03( 13/ 13) EDGAR MALONE FARM 2.66E+03- 6.99E+03 2.5 MILES W 4.95E+03( 13/ 13) 5.15E+03( 13/ 13) 2.66E+03- 6.99E+03 2.41E+03- 6.72E+03 rn 8
PB-214 8.00E+01 1.22E+02( 1/ 13) EDGAR MALONE FARM 1.22E+02( 1/ 13) 1.84E+02( 1/ 13) 1.22E+02- 1.22E+02 2.5 MILES N 1.22E+02- 1.22E+02 1.84E+02- 1.84E+02 7 u
SR 89 8
1.40E+02 4 VALUES < LLD 4 VALUES < LLD SR 90 8
6.00E+01 7.24E+01( 1/ 4) EDGAR MALONE FARM 7.24E+01( 1/ 4) 4 VALUES < LLO 7.24E+01- 7.24E+01 2.5 MILES N 7.24E+01- 7.24E+01 NOTE: 1. NOMINAL LOWER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1.
NOTE: 2. MEAN AND RANGE BASED UPON DETECTABLE MEASUREM5NTS ONLY. FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).
TENCESSEE UALLEY AUTHOR!W .'
TECHNICAL PROGRAMS -
ENYlRONMENTAL RADIC1E31 COL M OIT O ING AO IOSTRUMENTAll O WESTERN QREA QCDIOLE3ICAL LABO AT O Y RADIOACTIVITY IN SOIL PCl/GM - 0.037 80/G (DRY WEIGHT)
NAME Of FACILITY: SEJUOTAN NUCLEAR PLANT DOCKET NO.: 50-327,328 LOCATION Of FACILITY: HAMILTON TENNESSEE REPORTING PERIOD: 1993 TYPE Ac LOWER LIMIT ALL CONTROL NUMBER OF TOTAL EMBER OF INDICATOR LOCATIONS LOCATION WITN HIGHEST ANNUAL MEAN LOCATIONS NONROUTINE OF ANALYSIS DETECTION MEAN (F) NAME MEAN (F) MEAN (F) REPORTED PERFORMED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANCE MEASUREMENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2
. GAMMA SCAN (GELI) 13 AC-228 1.00E-01 1.04E+00( 8/ 8) PM-8 MARRISON, TN 1.44E+00( 1/ 1) 1.20E+00( 5/ 5) 7.28E 1.44E+00 8.75 MILES SSW 1.44E+00- 1.44E+00 9.89E 1.36E+00 BE-7 1.00E-01 1.74E-01( 1/ 8) LM-3 moved Oct 6 92 1.74E-01( . 1/ 1) 5 VALUES < LLD 1.74E 1.74E-01 SSW,1.5 Mi to 2.0 MI 1.74E 1.74E-01 B1-212 2.50E-01 1.12E+00( 8/ 8) PM-8 NARRISON, TN 1.59E+00( 1/ 1) 1.26E+00( 5/ 5) 7.80E 1.59E+00 8.75 MILES SSW 1.59E+00- 1.59E+00 1.04E+00- 1.37E+00 g 81-214 4.00E-02 1.04E+00( 8/ 8) PM-9 LAKESIDE- 1.29E+00( 1/ 1) 1.07E+00( 5/ 5) >
E 6.52E 1.29E+00 2.7 MILES WSW 1.29E+00- 1.29E+00 9.55E 1.27E+00 %
o CS-137 1.00E-02 6.71E-01( 8/ 8) LM-3 moved Oct 6 92 1.62E+00( 1/ 1) 2.42E-01( 5/ 5) m 8
9.50E 1.62E+00 SSW,1.5 Mi to 2.0 MI 1.62E+00- 1.62E+00 1.22E 3.83E-01 K-40 2.00E-01 5.51E+00( 8/ 8) LM2 NORTHEAST 1.28E+01( 1/ 1) 7.48E+00( 5/ 5) 7 m
3.65E+00- 1.28E+01 0.75 MILES N 1.28E+01- 1.28E+01 4.46E+00- 9.99E+00 P8-212 2.00E-02 1.02E+00( 8/ 8) PM-8 HARRISON, TN 1.39E+00( 1/ 1) 1.14E+00( 5/ 5) 7.53E 1.39E+00 8.75 MILES SSW 1.39E+00- 1.39E+00 9.36E 1.27E+00 P8-214 2.00E-02 1.11E+00( 8/ 8) PM-9 LAKESIDE 1.37E+00( 1/ 1) 1.15E+00( 5/ 5) 6.82E 1.37E+00 2.7 MILES WSW 1.37E+00- 1.37E+00 1.02E+00- 1.37E+00 RA-224 3.00E-01 1.10E+00( 6/ 8) PM-8 HARRISON, TN- 1.50E+00( 1/ 1) 1.17E+00( 5/ .5) 7.72E 1.50E+00 '8.75 MILES SSW 1.50E+00- 1.50E+00 9.42E 1.41E+00 RA-226 5.00E-02 1.04E+00( 8/ 8) PM-9 LAKESIDE 1.29E+00( 1/ 1) 1.07E+00( 5/ 5) 6.52E 1.29E+00 2.7 MILES USW 1.29E+00- 1.29E+00 9.55E 1.27E+00 TN-227 9.00E-02 1.06E-01( 1/ 8) PM-8 HARRISON, TN 1.06E-01( 1/ 1) 5 VAtuES < LLD 1.06E 1.06E-01 8.75 MILES SSW 1.06E 1.06E-01 TL-208 2.00E-02 3.51E-01( 8/ 8) PM-8 NARRISON, TN 4.82E-01( 1/ 1) 3.92E-01( 5/ 5) 2.65E 4.82E-01 8.75 MILES SSW 4.82E 4.82E-01 3.27E 4.34E-01 SR 89 13 1.00E+00 - 8 VAttJES < LLD 5 VALUES < LLD SR 90 13
-3.00E-01 8 VALUES < LLD 5 VALUES < LLD i
NOTE: 1. NOMINAL LOWER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1.
NOTE: 2. MEAN AND RANGE SASED UPON DETECTABLE MEASUREMENTS ONLY. FRACTION OF DETECTABLE MEASM EMENTS AT SPECIFIED LOCATIONS !$ IlWICATED IN PARENTHESES (F).
i W< am - -r- 'e_ ' _ __ .__ ________ii___
TEWhESSEE t' ALLEY AUTHC3tTV TECHNICAL PQOCRAMS ENVIRONMENTAL RADIOLOGICAL MGJITC21CG AND 10STRtJMENTAT103 WESTERN ASEA RADIOLOGICAL LABC3ATOR7 RADICACTIVITY IN APPLES PCI/KG - 0.037 BQ/KG (WET WT)
NAME OF FACILITY: SEQUOYAH NUCLEAR PLANT DOCKET NO.: 50-327,328 LOCATION OF FACILITY: HAMILTON TENNESSEE REPORTING PER:00: 1993 TYPE AND LOWER LIMIT ALL CONTROL NUMBER CF TOTAL NUMSER OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANkUAL MEAN LOCATIONS NONROUTINE OF ANALYSIS DETECTION MEAN (F) NAME MEAN (F) MEAN (F) REPORIED PERFORMED (LLD) RANCE DISTAkCE AXD DIRECTION RANGE RANGE MEASUREMENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GAMMA SCAN (GELI) 2 K-40 1.50E+02 7.62E+02( 1/ 1) JONES FARM 7.62E+02( 1/ 1) 5.97E+02( 1/ 1) 7.62E+02- 7.62E+02 1.25 MILES U 7.62E+02- 7.62E+02 5.97E+02- 5.97C+02 NOTE: 1. NOMihAL LDKR LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1.
NOTE: 2. MEAN AND RANGE BASED UPON DETECTABLE MEASUREMEETS ONLY. FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED q LOCATIONS IS INDICATED IN PARENTHESES (F). g r
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TEt.NESSEE VALLEY AUTHC2ITY TECHNIC!.L Pit) GRAMS E::YIRONMENTAL RADIOLOGICAL MC2tTCOING AND 2%STRUMENTATIC:s WESTER 3 A2EA RADIOLC31Citt LABC2ATC2Y RAD 10 ACTIVITY IN CORN PCI/KG - 0.037 SQ/KG (WET WT)
MAME OF FACILITY: SEQUOYAH NUCLEAR PLANT DOCKET NO.: 50-327,328 LOCATION OF FACILITY: HAMILTON TENwESSEE REPORT!kG PERl(X): 1993 TYPE AkD LOWER LIMIT ALL CCHTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAM LOCAfl0NS NCNROUTikE OF ANALYSIS DETECTION MEAN (F) NAME MEAN (F) MEAN (F) REPORTED PERFORMED (LLC) RANGE DISTANCE AND DIRECTION RANGE RANCE MEASUREMENTS SEE NOTE 1 SEE kOTE 2 SEE NOTE 2 SEE NOTE 2 GAMMA SCAN (GELI) 2 K-40 1.50E+02 1.71E+03( 1/ 1) H WALKER FARM 1.71E+03( 1/ 1) 1.65E+03( 1/ 1) 1.71E+03- 1.71E+03 1.25 MILES NW 1.71E+03- 1.71E*03 1.65E+03- 1.65E+03 NOTE: 1. NOMINAL LOWER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1.
NOTE: 2. MEAN AND RANGE BASED UPON DETECTABLE MEASUREMEN15 ONLY. FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED q LOCATIONS IS IN01CATED IN PARENTHESES (F). >
'f "
=:
b
. TE!EESSEE WALLEY AUTHCQlTY '
TECH 21 CAL PRCGRAMS ENVIR0hMENTAL Rt.D10 LOGICAL MC31TC21NG A13 INSTRUMENTATION WESTERN t.REA RADIOLCGICAL Lt.8C2AT"JT RADI0 ACTIVITY IN GREEN BEAMS PC1/KG - 0.037 BQ/KG (WET WT)
NAME OF FAC!Llif: IEQUOTAN NUCLEAR PLANT DOCKEY NO.: 50-327,323 L %ATION OF FACIL2TY: MAMILTON TENNESSEE REPORTlWG PERIOD: 1993 TYPE AND LOWER LIMIT ALL CONTROL NUMSFR OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION WITN MIGHEST ANNUAL MEAM LOCATIONS NONROUTINE OF ANALYSIS DETECTION MEAN (F) NAME MEAN (F) MEAN (F) REPORTED PERFORMED (LLD) RANGE- DISTANCE AND DIRECTION RANGE RANCE MEASUREMENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GAMMA SCAM (GELI) 2 K-40 1.50E+02 1.8Ct+03< 1/ 1) H WALKER FARM 1.80E+03( 1/ 1) 2.08E+03( 1/ 1) 1.80E+03- 1.80E+03 1.25 MILES NW 1.80E+03- 1.80E+03 2.08C+03- 2.08E+03 NOTE: 1. NOMINAL LOWER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1.
NOTE: 2. MEAN AND RANGE BASED IJPON DETECTABLE MEASUREMENTS ONLY. FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED $
LOCATIONS IS INDICA!ED IN PARENTHESES (F). to b
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TERNESSEE VILLEY AUTHCQlTY TECH %ICAL FROGRAMS EC:VIRONMENTAL RADIOLOGICAL MONITCalEG AND INSTRUMENTATION WESTERM AREA RADictOGICAL LA90*d TC2Y RADIDACTIVITY IN POTATOES PC1/KG - 0.037 BC/KG (WET VT)
NAME OF FACILITY: SEQUOYAH WJCLEAR PLANT DOCKET No.: 50-327,328 LOCATION OF FACILITY: HAMILTON TENkESSEE REPORTING perla): 1993 TYPE ANO LOWER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCA110N WITH NIGHEST ANNUAL MEAN LOCATIONS NONROLIT INE OF ANALYSIS DETECT 10ei MEAN (F) NAME MEAN (F) MEAN (F) REPORTED PERFORMED (LLD) RANCE DISTANCd AND DIRECTION RANGE RANCE MEASUREMENTS SEE No1E 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GAMMA SCAN (GELI) 2 K-40 1.50E+02 3.05E+03{ 1/ 1) N WALKER FARM 3.05E+03( 1/ 13 3.90E+03( 1/ 1) 3.05E+03- 3.05E+03 1.25 MILES NW 3.05E+03- 3.05E+03 3.90E+03- 3.90E+03 NOTE: 1. NCMINAL LOWER LIMIT C DETECTION (LLD) AS DESCRIBED IN TABLE E-1. g NOTE: 2. MEAN AND RAX0E BASED UPON DETECTABLE MEASUREMENTS ONLY. FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED >-
LOCAil0NS IS INDICATED IN PARENTHESES (F). %m 8 =
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_ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ m_.._ ___2_ __ _ _ _ _ _ _
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TEliMESSEE t0LLEY AUTHOIT7 TECHO! CAL PROGRAMS EQUIRouMENTAL CADIClCSICAL MONITORICG AND ID3TRUMENTATI O WESTERN AREA RADIOLOGICAL LA80 ATC27 RADICACTIVITY IN SURFACE WATER (Total)
PC1/L - 0.037 BQ/L NAME OF FACILITY: SEQUOTAN WJCLEAR PLANT DOCKET No.: 50-327,328 LOCATION OF FACILITY: NAMILTON TENkESSEE REPORTING PERIOD: 1993 TYPE AND LOUER LIMIT ALL CONTROL NUMBER CF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION WITN HIGHEST ANNUAL MEAM LOCATIONS kONROUTINE OF ANALYSIS DETECTION MEAN (F) NAME MEAN (F) MEAN (F) REPORTED PERFORMED (LLD) RANGE DISTANCE AND DIRECTION RANCE RANCE MEASUREMENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOIE 2 GROSS BETA 39 l 1.70E+00 2.27E+00( 22/ 26) TRM 483.4 2.36E+00( 10/ 13) 2.54E+00( 12/ 13) 1.70E+00- 2.90E+00 1.75E+00- 2.87E+00 1.73E+00- 4.94E+00 C# MA SCAM (Gell) 39 3.00E+00 26 VALUES < LLD 13 VALUES < LLD SR 89 H
, 12 $
F e 3.00E+00 8 VALUES < LLD 4 VALUES < LLD M
"8 $4 90 12 :::
1.40E+00 8 VALUES < LLD 4 VALUES < LLD 12 2.$0E+02 8 VALUES < LLD 4 VALUES < LLD NOTE: 1. NOMINAL LOWER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1.
NOTE: 2. MEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY. FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).
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_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ______=____2___ _ _ _ - _ _ _ _ _ _ _ - _ _ _ . - - - - _ - _ _
TE CESSEE VI.LLEY AUTHCJITY TECHNICAL PROGRAMS ENVIRONMENTAL RADIOLOGICAL MCrilTORING AND INSTRUMENTAfl04 WESTERM AREA RADIOLOGICAL LASC2ATORY RADICACTIVITY IN PUBLIC WATER (Total)
PCl/L - 0.037 Bc/L NAME CF FACILITY: SEQUDYAN NUCLEAR PLANT DOCKET No.: 50-327,328 LOCATION OF FACILITY: NAMILTON TEkNESSEE REPORTING PERIOD: 1993 TTPE AND LOWER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER CF INDICATOR LOCAfl0NS LOCATION WITN NIGHEST ANNUAL MEAN LOCATIONS WONROUTIhE OF ANALYSIS DETECTION MEAN (F) NAME MEAN (F) 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 8 ETA 60 1.70E+00 2.47r+00( 18/ 36) CF IN00STRIES 2.55E+00( 8/ 10) 2.72E+00( 22/ 24) 1.76E+00- 4.73E+00 TRM 473.0 1.93E+00- 4.73E+00 1.73E+00- 4.94E+00 10 DINE-131 23 1.00E+00 10 VALUES < LLD 13 VALUES < LLD 62 =
i B1-214 2.00E+01 2.55E+01( 1/ 36) CNICKAMAUGA DAM 2.55E+01( 1/ 13) 26 VALUES < LLD E CD 2.55E+01- 2.55E+01 TRM 465.3 2.55E+01- 2.55E+01 8
SR 89 y 20 s 3.00E+00 12 VALUES < LLD 8 VALUES < LLO
- SR 90 20 1.40E+00 1.83E+00( 1/ 12) CNICKAMAUGA DAM 1.83E+00( 1/ 4) 8 VALUES < LLD 1.83E+00- 1.83E+00 TRM 465.3 1.83E+00- 1.83E+00 TRITIUM 20 2.50E+02 12 VALUES < LLD 8 VALUES < LLD NOTE: 1. NOMINAL LOWER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1.
NOTE: 2. MEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY. FRACTION CF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS 1NDICATED IN PARENTHESES (F).
_ _ _ . _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ m- _ -_ __, _ _ _ _ _ __ m-__ - w
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TENNESSEE VALLEY AUTNORITY TECNNICAL PROGRAMS EL*VIRONMENTAL RAD 1 CLOG 1 CAL MC21TCO1NG A@ !25iRUMEltiATIC:8 WESTER 3 AREA RADICLOGICAL LA8C ATC2Y BA330 ACTIVITY IN $MALLMOUTN BUFFALO WMOLE PC1/CM - 0.037 sc/G (DRY WEIGNT)
NAME OF FACILITT: SEQUOYAH WUCLEAR PLANT DOCKET NO.: 50-327,328 LOCATION OF FACILITY: NAMILTON TENNESSEE REPORTING PERico: 1993 TYPE AkD LOWER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER OF IkDICATOR LOCATIONS LOCATION W1TN NIGHEST ANNUAL MEAM LOCATIck$ WONROUTINE OF ANALYSIS DETECTION MEAN (F) NAME MEAN (F) MEAN (F) REPORTED PERFORMED (LLD) RANCE DISTANCE AND DIRECTION RANCE RANCE MEASUREMENTS SEE NOTE 1 SEE kOTE 2 SEE NOTE 2 SEE NOTE 2 GAM 4A SCAN (GELI) 6 51-214 1.20E-01 1.54E-01( 1/ 4) NICKAJAct RES 1.54E-01C 1/ 2) 2 VALUES < LLD 1.54E-C1- 1.54E-01 TRM 425-471 1.54E 1.54E-01 K-40 1.00E+00 6.05E+00( 4/ 4) CHICKAMAUCA RES 6.59E+00( 2/ 2) 5.81E+00( 2/ 2) 5.23E+00- 6.95E+00 TRM 471-530 6.22E+00- 6.95E+00 5.68E+00- 5.93E+00 SR 89 g 6 >
3.00E 01 4 VALUES < LLD 2 VALUES < LLD tc b
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y 4.00E-02 1.16E-01( 4/ 43 CNICKAMAUCA RES 1.50E-01( 2/ 2) 1.32E-01( 2/ 2) y 5.80E 1.57E-01 TRM 471-530 1.42E 1.57E-01 1.02E 1.63E-01 -
e NOTE: 1. NOMINAL LOWER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE E-1.
! NOTE: 2. MEAN AND RANCE BASED UPON CETECTABLE MEASUREMENTS ONLY. FRACTION OF DETECTA8tE MEASUREMENTS AT SPECIFIED LOCATIONS 15 INDICATED IN PARENTHESES (F).
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TEINESSEE YALLEY AUTHCQlTY TEDCICAL FQ0 GRAMS EtVIRONME* J TAL RADICLOGICAL MCIITC210G (kD INSTRtREhTAT104 WESTER 3 AREA RADIOLOGICAL LLS07JtTC:T RADIOACTIVITY IN SEDIMENT PCI/GM - 0.037 SQ/G (DRY WE!CHT)
NAME OF FACILITY: SEQUOYAH NUCLEAR PLANT DOCKET No.: 50-327,328 LOCATION OF FACILITY: RAMILTON TEh4ESSEE REPORT!hG PERIOD: 1993 TYPE AND LOWER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER CF INDICATOR LOCATious LOCATION WITH NIGHEST ANNUAL MEAN LOCATIONS kONROUTINE OF ANALYSIS DETECTION MEAN (F) NAME MEAN (F) MEAN (F) REPORTED PERFORMED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANCE ME ASUREMENT S SEE NOTE 1 SEE kOTE 2 SEE NOTE 2 SEE NOTE 2 CAMMA SCAN (GELI) 8 AC-228 1.00E-01 1.72E+00( 6/ 6) TRM 480.82 1.92E+00( 2/ 2) 1.26E+00( 2/ 2) 1.27E+00- 2.12E+00 1.91E+00- 1.93E+00 1.14E+00- 1.39E+00 BE-7 1.00E-01 7.70E-01( 6/ 6) TRM 472.80 8.84E-01( 2/ 2) 6.29E-01( 2/ 2) 1.70E 1.38E+00 5.20E 1.25E+00 2.75E 9.83E-01 81-212 2.50E-01 1.64E+00( 6/ 6) TRM 480.82 1.84E+00( 2/ 2) 1.16E+00( 2/ 2) g 1.26E+00- 2.01E+00 1.67E+00- 2.01E+00 1.13E+00- 1.19E+00 >
BI-214 4.00E-02 1.07E+00( 6/ 6) TRM 480.82 1.21E+00( 2/ 2) 8.01E-01( 2/ 2) W b 8.22E 1.38E+00 1.19E+00- 1.23E+00 7.70E 8.31E-01 $
o co-58 1.00E-02 6.66E-02( 5/ 6) TRM 472.80 7.BCE-02( 2/ 2) 2 VALUES < LLD 7 2.74E 9.43E-02 6.28E-M 9.33E-02 7 CO-60 1.00E-02 1.62E-01( 6/ 6) TRM 480.82 2.27E-01( 2/ 2) 1.76E-02( 2/ 21 N O
1.54E 2.70E-01 2.00E 2.55E-01 1.33E 2.20E-02 CS-134 1.00E-02 3.53E-02( 6/ 6) TRM 472.80 4.07E-02( 2/ 2) 2 VALUES < LLD 1.07E 5.95E-02 2.19E 5.95E-02 CS-137 1.00E-02 9.715-01( 6/ 6) TRM 480.82 1.26E+0c( 2/ 2) 6.50E-01( 2/ 2) 1.33E 1.51E+00 1.20E400- 1.32E+00 5.21E 7.80E-01 K-40 2.00E-01 1.52E+01( 6/ 6) TRM 483.4 1.55E+01( 2/ 2) 1.40E+01( 2/ 2) 1.15E+01- 1.83E+01 1.29E+01- 1.81E+01 1.32E+01- 1.49E+01 P8-212 2.00E-02 1.46E+00( 6/ 6) TRM 480.82 1.60E+00( 2/ 23 1.05E+00( 2/ 2) 1.05E+00- 1.92E+00 1.56E+00- 1.64E+00 9.97E 1.11E+00 PB-214 2.00E-02 1.17E+00( 6/ 6) TRM 480.82 1.31E+00( 2/ 2) 8.55E-01( 2/ 2) 9.00E 1.56E+00 1.26E+00- 1.36E+00 8.27E 8.83E-01 RA-224 3.00E-01 1.58E+00( 6/ 6) TRM 480.82 1.81E+00( 2/ 2) 1.09E+00( 2/ 2) 1.13E+00- 1.96E+00 1.74E+00- 1.87E+00 9.53E 1.22E+00 RA-226 5.00E-02 1.07E+00( 6/ 6) TRM 480.82 1.21E+00( 2/ 2) 8.01E-01( 2/ 2) 8.22E 1.38E+00 1.19E+00- 1.23E+00 7.70E 8.31E-01 58-125 NOT ESTAS 3.41E-02( II 6) TRM 472.80 3.41E-02( 1/ 2) 2 VALUES < LLD 3.41E 3.41E-02 3.41E 3.41E-02 TL-208 2.00E-02 4.98E-01( 6/ 6) TRM 480.82 5.46E-01( 2/ 2) 3.72E-01( 2/ 2) 3.59E 6.54E-01 5.28E 5.64E-01 3.53E 3.92E-01 NOTE: 1. NOMINAL LOWER LIMIT OF DETECTION (LLD) AS DEsta! BED IN TABLE E-1.
NOTE: 2. MEAN AND RANGE BASED UPON DETECTA8LF MEASUREMENTS ONLY. FRACTION OF DETECTABLE NEASUREMENTS AT SFICIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).
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- . Initial plant operation in July 1980.
n On-Site -
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. 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93
. Year / Quarter .!
Initial plant operation in July 1980. '
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m .______._m-_m_ _ m
.cm.. _.-,.ee-,%,-..--., ,e. . - + w ,is Annual Average Gross Beta Activity Air Filters, pCi/ Cubic Meter ,
0.25 -- -- ----
Initial plant operation in July 1980.
l 0.2 -
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0.1 -
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o ru , l lfl lil~I III3flERll][I 71 72 73 74 75 76 77 78 79 80p800 81 82 83 84 85 86 87 88 89 90 91 92 93 1
Year No measurements were made in 1974. O Indicator M Control '
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Annual Average: Sr-90 in Milk 14 -- ---
U Initial plant operation in July 1980.
12 -
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Sequoyah Nudear Plantj Note: No milk samples were collected in 1974 and 1975.
Annual Average: Cs-137 in Soil i
3 -
Initial plant operation in July 1980.
2.5 -
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71 72 73 74 75 76 77 78 79 % 81 82 83 M 85 % 87 88 89 90 91 92 93 Year v Indicator A Control - Preoperational Average lSequoyah Nuclear Plant'l Note: Detector system changed from Nal to GeLi in 1977.
2 ____.__ _ _ _ _ ________..__-.__..______-_.---_L_
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Annual Average Gross Beta Activity Surface Water, pCi/ Liter 6
4 A \ Initial plant operation in July 1980.
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, Year v Indicator A Control - Preoperational Average Sequoyah Nuclear Plant l
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InI$ual Average Cs-137 in Channel Catfish I
0.6 ----q
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l g Initial plant operation in July 1980. !
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71 72 73 74 75 76 77 78 79 80p800 81 82 83 84 85 86 87.88 89 90 91 92 93 .l Year ~l S Downstream A Upstream - - Preoperational Average l lSequoyah Nuclear Plant l Note: Detector system changed from Nal to GeLi in 1978. .
.___._________________m__.__________N-_..'_.__m_,A.-u_-_.__..u_ ^" ' - ' ' ' * ' ' ' - - - * " ' ' " ' "--" ""' ' ' " -" " - ' ' ~ - ' -
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Cs-137 in Fish: Crappie i
0.6 - - - -- -- -
0.5 - t Initial lant P operation in July 1980.
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71 '72 73 74 75 76 77 78 79 80p 80o .81 82 83 84 85 86 87 88 89 90 91 92 93 Year y Downstream A Ups'sream l Preoperational Average l -
(Sequoyah Nuclear Plant l Note: Detec's system changed rrom Nal to GcLi in 1978.
T
Annual Average Cs-137 in Fish: Smallmouth Buffalo, Flesh !
0.8 - - - - - -
- - -----~- 1 A initial plant operation in July 1980.
\
0.6 -
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0 71 72 73 74 75 76 77 78 79 80p 800 81 82 83 84 85 86 87 88 89 90 91 92 93 Year i
v- Downstream A Upstream - Preoperaional Average l {
[Sequoyah Nuclear Plant l Note: Detector system changed from Nal to GeLi in 1978.
Annual Average ,
Cs-137 in Fish: Smallmouth Buffalo, Whole !
0.8 i - ---- - -
l Initial plant operation in July 1980.
0.6 -
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[Sequoyah Nuclear Plant] Note: Detector system changed from Nal to GcLi in 1978.
s s
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' Annual Average !
I' Cs-137 in Sediment ;
10 - - - ---
i Initial plant operation in July 1980. I 8 1- 7 .
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71 72 73 74 75 76 77 78 79 80p 800 81 82 83 84 85 86 87 88 89 90 91 92 93 Year v Downstream A Upstream - Preoperational Average
[Sequoyah Nuclear Plant l - Note: Detector system changed from Nat to GeLi in 1977.
-,.,---...-.-.--m--muny.a-- -+,==--^w~w=,-+.'-mw_--- - - - - - - - + a - ==-
Annual Average l Co-60 in Sediment !
1.5 -- - ---- - --- - -
-i !
1 i
A i Initial plant operation in July 1980. j i
m 1 !
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71 72 73 74 75 76 77 78 79 80p 800 81 82 83 84 85 86 87 88 89 90 91 92 93 Year i l
l 7 Downstream A Upstream -- Preoperational Average l l lSequoyah Nuclear Plant l Note: Detector system changed from Nal to GeLi in 1977.
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l l -
3
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, Annual Average j j Cs-137 in Shoreline Sediment t
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