ML20205T023
| ML20205T023 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 12/31/1998 |
| From: | Salas P TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9904270111 | |
| Download: ML20205T023 (120) | |
Text
IFA
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Tennem>e uky Aumny Post Ohm an ardby-Da.sy Tennessee 3D April 22, 1999 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:
In the matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) - ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT In accordance with Technical Specification 6.9.1.6 for SON Units 1 and 2, enclosed 1. the Annual Radiologic 1 Environmental Operating Report for 1998.
If you have any questions concerning this matter, please telephone me at (423) 843-7170 or J. D. Smith at (423) 843-6672.
Since l y ,,
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as /
Licensing and Industry Affairs Manager
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Enclosure cc: See page 2 Ca oI n
9904270111 981231 PDR ADOCK 05000327 R PDR _
U.S. Nuclear. Regulatory Commission Page 2 April 22, 1999 cc (Enclosure):
Mr. R. W. Hernan, Project Manager 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 Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303-3415 l
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Annual Radiological Environmental Operating Report 1
Nuc ear Plant 1998 TA
TABLE OF CONTENTS Table of Contents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ii T List of Tables. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . iv List of Figures. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . v Executive Summary. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Introd uction . . . . . . . . ' . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 Naturally Occurring and Background Radioactivity. . . . . . . . . . . . . . . . . 2 Electric Power Production. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 Site / Plant Description. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6
. Radiological Environmental Monitoring Program. . . . . . . . . . . . . . . . . . . . 8 Direct Radiation Monitoring. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 Measurement Techniques. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 Results . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 Atmospheric Monitoring. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 Sample Collection and Analysis. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 Results. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 Terrestrial Monitoring. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17
- Sample Collection and Analysis. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 Resu lts. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 Liquid Pathway Monitoring. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21 Sample Collection and Analysis. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21 Res ults . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 22 Assessment and Evaluation. ; . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . . . . 26 R esults . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 27 Concl us ions. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 28
- Re ferences. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 29
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r Appendix A Radiological Environmental Monitoring Program and Sampling Locations. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 35 l Appendix B 1998 Program Modifications. . . . . . . . . . . . . . . . . . . . . . . . . . . 46 1
Appendix C Program Deviations. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 49 Appendix D Analytical Procedures. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 52 Appendix E Nominal Lower Limits of Detection (LLD). . . . . . . . . . . . . . . . 55 Appendix F Quality Assurance / Quality Control Program. . . . . . . . . . . . . . . 61 Appendix G Land Use Smvey. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 67 Appendix H Data Tables and Figures. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 73 I
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LIST OF TABLES I' Table 1 Comparison of Program Lower Limits of Detection with Regulatory Limits for Maximum Annual Average Emuent Concentrations Released to Unrestricted Areas and Reporting Levels. . . . . . . . . . . . . 30 Table 2 . Results from the Intercomparison of Environmental Dosimeters. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 31 Table 3 Maximum Dose Due to Radioactive Effluent R el eas es . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . 32
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J LIST OF FIGIBES Figure 1 Tennessee Valley Region. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 33 i
Figure 2 . Environmental Exposure Pathways of Man Due
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to Releases of Radioactive Materials to the Atmosphere and Lake. . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . '34 1
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EXECUTIVE
SUMMARY
This report describes the radiological environmental monitoring program conducted by TVA in the vicinity of the Sequoyah Nuclear Plant (SQN) in 1998. The program includes the collection of samples from the environment and the detennination 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 pattems and projected radiation doses to the various areas around the plant. Monitoring includes the sampling of air, water, milk, foods, vegetation, soil, fish, clams, sediment, and the measurement of 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 radioactivity measured in environmental samples from the SQN program was contributed by naturally occurring radioactive materials or by materials commonly found in the environment as a result of atmospheric nuclear weapons fallout.
Small amounts of Co-58, Co-60, Cs-134 and Cs-137 were found in bottom sediment samples
- downstream from the plant. Trace levels of Cs-137 were also measured in fish and shoreline sediment and low levels of tritium were found in ground water from the on site monitoring well.
These levels of activity would result in no measurable increase over background in the dose to the general public.
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INTRODUCTION l This report describes and summarizes the results of radioactivity measurements made in the vicinity of SQN and laboratory analyses of samples collected in the area. The measurements are
. made to comply with the regnimments of 10 CFR 50, Appendix A, Criterion 64 and 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3 and IV.C and to determine potential effects on public health and s' afety. This repon satisfies the annual reponing requirements of SQN Technical Specification 6.9.1.6 and Offsite Dose Calculation Manual (ODCM) Administrative Control 5.1.
In addition, estimates of the maximum potential doses to the surmunding population are made from radioactivity measured both in plant effluents and in environmental samples. The data presented in this report include msults from the prescribed program and other information to help correlate the significance ofresults measured by this monitoring program to the levels of environmental radiation resulting from naturally occurring radioactive materials.
Naturally Occurrine and Backaround Radioactivity Most materials in our world today contain trace amounts of naturally occurring radioactivity.
Appmximately 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 pCi of K-40 which delivers a dose of 15 to 20 mrem per year to the bone and soft tissue of the body. Naturally occurring radioactive materials have always been in our environment. Other examples of naturally occurring radioactive materials are beryllium (Be)-7, bismuth (Bi)-212 and 214, lead (Pb)-212 and 214, thallium (TI)-208, actinium (Ac)-228, uranium (U)-238 and 235, thorium (Th)-234, radium (Ra)-
226, radon (Rn)-222, carbon (C)-14, and hydrogen (H)-3 (generally called tritium). These naturally occurring radioactive materials are in the soil, our food, our drinking water, and our 1 bodies. The radiation from these materials makes up a pan of the low level natural background I
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- radiation. The remainder of the natural background comes from cosmic ray radiation from outer space. We are all exposed to this natural radiation 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day. 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 in the following table is primarily adapted from References 2 and 3.
U.S. GENERAL POPULATION AVERAGE DOSE EQUIVALENT ESTIMATES Source Millirem / Year Per Person
. Natural background dose equivalent Cosmic 27 Cosmogenic 1 Terrestrial 28 In the body 39 Radon 200 Total 295 Release ofradioactive materialin natural gas, mining, ore processing, etc. 5 Medical (effective dose equivalent) 53 l
. Nuclear weapons fallout less than 1 Nuclear energy 0.28 Consumer products 0.03 Total 355 (approximately)
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l ' As can be seen from the table, natural background radiation dose equivalent to the U.S.
l population normally exceeds that from nuclear plants by several hundred times. This indicates j that nuclear plant operations normally result in a population radiation dose equivalent which is insignificant compared to that which results from natural background radiation.
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Ex Electric Power Production Nuclear power plants are similar in many respects to conventional coal burning (or other fossil fuel) electric 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 tum turbines and generators. However, nuclear plants include many complex systems to control the nuclear fission process and to safeguard against the possibility of reactor malfunction, which -
could lead to the release of radioactive materials. Very small amounts of these fission and activation products are released into the plant systems. This radioactive material can be -
transported throughout plant systems and some ofit released to the environment.
The pathways through which radioactivity is released are monitored. Liquid and gaseous - ,
emuent monitors record the radiation levels for each release. These monitors also pmvide alann mechanisms to prompt termination of any release above limits.
Releases are monitored at the onsite points ofrelease and through the environmental monitoring program which measures the environmental radiation in outlying areas around the plant. In this way, not only is the release of radioactive materials from the plant tightly controlled, but -
measurements are made in surrounding areas to verify that the population is not being exposed to significant levels of radiation or radioactive materials.
The SQN ODCM, which is required by the plant Technical Specifications, prescribes limits for the release of radioactive emuents, as well as limits for doses to the general public from the release of these emuents.
The dose to a member of the general public from radioactive materials released to unrestricted amas, as given in NRC guidelines and the ODCM, is limited as follows:
Liquid Emuents Totalbody 53 mrem / year Any organ 510 mrem / year 1
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Noble gases: I Gamma radiation 510 mrad / year Beta radiation 520 mrad / year Particulates:
Any organ 515 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 525 mrem / year Thyroid 575 mrem / year Any other organ 525 mrem / year Appendix B to 10 CFR 20 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 compares the nominal lower limits of detection for the SQN monitoring ,
program with the regulatory limits for maximum annual average effluent concentrations released to unrestricted areas and levels requiring special reports to the NRC. It should be noted that the levels of radioactive materials measured in the environment are typically below or only slightly above the lower limit ofdetection. The data presented in this report indicate compliance with the regulation. l i
o SITE / PLANT DESCRIPTION '
The SQN is located on a site near the geographical center of Hamilton County, Tennessee, on a peninsula on the westem shore of Chickamauga Lake at Tennessee River Mile (TRM) 484.5.
Figure I shows the site in relation to other TVA projects. The SQN site, containing approximately 525 acres, is approximately 7.5 miler northeast of the nearest city limit of Chattanooga, Tennessee,14 miles west-northwest of Cleveland, Tennessee, and approximately 31 miles south-southwest of TVA's Watts Bar Nuclear Plant (WBN) site.
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Population is distributed rather unevenly within 10 miles of the SQN site. Approximately 60 percent of the population is in the general area between 5 and 10 miles from the plant in the sectors ranging from the south, clockwise, to the nonhwest 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 nonhem most extent of the urbanization around Chattanooga is approximately 4 miles from the site. The pooulation 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 75,000.
I Residential subdivision gmwth has continued within a 10-mile radius of the plant. There is also some small-scale farming and at least three dairy fanns 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 l 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 1183 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.
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Most of the radiation and radioactivity generated in a nuclear power reactor is contained within the reactor itselfor one of the other plant systems. Plant effluent monitors are designed to detect the small amounts of radioactive material released to the environment. 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 radiological environmental monitoring program is outlined in Appendix A.
There are two primary pathways by which radioactivity can move through the environment to humans: air and water (see Figure 2). The air pathway can be separated into two components; the direct (airborne) pathway and the indirect (ground or terrestrial) pathway. The direct airborne pathway consists of direct radiation and inhalation by humans. In the terrestrial pathway, radioactive materials may be deposited on the ground or on plants and subsequently be ingested by animals and/or humans. Human exposure through the liquid pathway may result from drinking water, eating fish, or by direct exposure at the shoreline. The types ofsamples collected in this program are designed to monitor these pathways.
A number of factors were considered in determining the locations for collecting environmental samples. The locations for the atmospheric monitoring stations were determined from a critical pathway analysis based on weather pattems, dose projections, population distribution, and land use. Terrestrial sampling stations were selected after reviewing such factors as the locations of dairy animals and gardens in conjunction with the air pathway analysis. Liquid pathway stations were selected based on dose projections, water use information, and availability ofmedia 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 1998 are described in Appendix B and exceptions to the sampling and analysis schedule are presented in Appendix C.
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To detennine the amount of radioactivity in the environment prior to the operation of SQN, a preoperational radiological environmental monitoring program was initiated in 1971 and operated until the plant began operation in 1980. Measurements of the same types ofradioactive materials that are measured currently were assessed during the preoperational phase to establish
- normal background levels for various radionuclides in the environment.
The preoperational monitoring program is a very imponant part of the overall program.
Prwpsational knowledge ofpre-existing 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 ofimpact during the operating phase also considers the presence ofcontrol stations that have been established in the monitoring program. Results ofenvironmental 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 analyzal by the Radioanalytical Laboratory of TVA's Environmental Radiological Monitoring and Instrumentation group located at the Westem Area Radiological Laboratory (WARL)in Muscle Shoals, Alabama. 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 aa.nple analysis results are presented in Appendix H.
The radiation detection devices and analysis methods used to determine the radionuclide content of samples collected in the environment are very sensitive to small amounts of radioactivity. The sensitivity of the measurements process is defined in terms of the lower limit of detection (LLD).
A description of the nominal LLDs for the Radioanalytical Laboratory is presented in Appendix E.
5 The Radioanalytical Laboratory employs a comprehensive quality assurance / quality control program to monitor laboratory performance throughout the year. The program is intended to detect any problems in the measurement process as soon as possible so they can be corrected.
This program includes equipment checks to ensure that the radiation detection instruments are working properly and the analysis of quality control samples which are included alongside
- routine enviromnental samples. The laboratory participated in the Environmental Protection
- Agency (EPA)Interlaboratory Comparison Program for 1908. In addition, samples split with the State of Tennessee provide an independent verification of the overall perfonnance of the laboratory. A complete description ~of the program is presented in Appendix F.
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DIRECT RADIATION MONITORING
. Direct radiation levels are measured at a number of stations around the plant site. These measurements include contributions fmm 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 relatively 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 1998 were consistent with levels from previous years and with levels measured at other locations in the region.
i Measurement Techniaues l Direct radiation measurements are made with thermoluminescent dosimeters (TLDs). When certain materials are exposed to ionizing radiation, many of the electrons which become l
displaced are trapped in the crystalline structure of the material. They remain trapped for long l periods of time as long as the material is not heated. When heated (thermo), the electrons are i
released, producing a pulse oflight (luminescence). The intensity of the !!ght 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 TLDs.
I The Panasonic UD-814 dosimeter is used in the radiological environmental monitoring program ' i for the measurement of direct radiation. This dosimeter contains four elements consisting of one lithium borate and three calcium sulfate phosphors. The calcium sulfate phosphors are shielded 2
by approximately 1000 mg/cm plastic and lead to compensate for the over-response of the detector to low energy radiation.
1 The TLDs are placed approximately 1 meter above the ground, with two or more TLDs at each monitoring location. Sixteen monitoring points are located around the plant near the site i
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' boundary, one location in each of the' 16 compass sectors. One monitoring point is also located in each of the 16 compass sectors at a distance of approximately four to five miles from the plant.
Dosimeters are also placed at the perimeter and remote air monitoring sites and at 13 additional monitoring locations out to appmximately 32 miles from the site. The TLDs are exchanged l every 3 months and the accumulated exposure on the detectors is read with a Panasonic Model
- UD-710A automatic reader interfaced with a Hewlett Packard Model 9000 computer system.
Since the calcium sulfate phosphor is much more sensitive than the lithium borate, the measured exposure is taken as the median of the results obtained from the calcium sulfate phosphors in the -
dosimeter badge. The values are corrected for gamma response, system variations, and transit '
exposure, with individual gamma response calibrations for each element. The system meets or exceeds the performance specifications outlined in Regulatory Guide 4.13 for environmental
- applications of TLDs.
Since 1974, TVA has participated in intercomparisons of environmental dosimeters conducted by the U.S. Department of Energy and other interested parties. The results, shown in Table 2, i
demonstrate that direct radiation levels determined by TVA are generally within ten percent of the calculated or known values.
I Results
' 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 monitoring locations are grouped according to the distance from the plant. The first group consists of all monitoring points within 1 mile of the plant. The second gmup lies between 1 and 2 miles, the third group between 2 and 4 miles, the four.h between 4 and 6 miles, and the fifth group is made up of all locations greater than 6 miles from the plant. Past data have shown that the average results from all groups more than 2 miles from the plant are essentially the same. Therefore, for purposes of this report, all monitoring points 2 miles or less from the plant are identified as "onsite" stations and all others are considered "offsite."
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V l Prior to 1976, direct radiation measurements in the environment were made with dosimeters that t
were not as precise at lower exposures. Consequently, environmental radiation levels reported in the early years of the preoperational phase of the SQN monitoring program exceed current measurements of background radiation levels. For this reason, data collected prior to 1976 are not included in this report.
l The quarterly gamma radiation levels determined from the TLDs deployed around SQN in 1998 are summanzed in Table H-1. The results from all measurements at individual stations are l presented in Table H-2. The exposures are measured in milliroentgens (mR). For purposes of i
l this report, one milliroetgen, one millirem (mrem) and one millirad (mrad) are assumed to be i
' numerically equivalent. The rounded average annual exposures, as measured in 1998, are shown below. For comparison purposes, the average direct radiation measurements made in the' preoperational phase of the monitoring program are also shown.
Annual Average Direct Radiation Levels SQN mR/ Year j 1991 1976-79 Onsite Stations 59 79 Offsite Stations 54 63 The data in Table H-1 indicate that the average quarterly direct radiation levels at the SQN onsite l
stations are approximately 1.3 mR/ quarter higher than levels at the ofTsite stations. This !
I difference is consistent with levels measured for the preoperation and construction phases of l TVA nuclear power plant sites where the average levels onsite were generally 2-6 mR/ quarter higher than levels offsite. The causes of these differences have not been isolated; however, it is postulated that the differences are attributable to combinations ofinfluences such as natural variations in environmental radiation levels, earth-moving activities onsite, and the mass of concrete employed in the construction of the plant.- Other undetermined influences may also play a part.
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Figure H-1 compares plots of the data from the onsite or site boundary stations with those from i I the offsite stations over the period from 1976 through 1998.
The results reported in 1998 are consistent with direct radiation levels identified at locations which are not influenced by the operation of SQN. There is no indication that SQN activities increased the background radiation levels normally observed in the areas surrounding the plant.
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ATMOSPHERIC MONITORING The atmospheric monitoring network is divided into three groups identified as local, perimeter, l '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 k communities out to about 10 miles from the plant, and four remote air monitors are located out to approximately 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.
Samnle Collection and Analysis Air particulates are collected by continuously sampling air at a flow rate of approximately 2 cubic feet per minute (cfm) through a 2-inch glass fiber filter. The sampling system consists of a pump, 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 sampling system is housed in a metal building. The filter is contained in a sampling head i mounted on the outside of the monitor building. The filter is replaced weekly. Each filter is l analyzed for gross beta activity about 3 days after collection to allow time for the radon daughters to decay. Every 4 weeks composites of the filters from each location are analyzed by gamma spectroscopy.
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Gaseous radiciodine is collected using a commercially available cartridge containing TEDA impregnated charcoal. This system is designed to collect iodine in both the elemental form and as organic compounds. The cartridge is located in the same sampling head as the air particulate l filter and is downstream of the particulate filter. The cartridge is changed at the same time as the l
particulate filter and samples the same volume of air. Each cartridge is analyzed for I-131 by gamma spectroscopy analysis. !
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0 Rainwater is sampled by use of a collection tray attached to the monitor building. The collection -
~ tray is protected from debris by a screen cover. As water drains from the tray, it is collected in one of two 5-gallon containers inside the monitor building. A 1-gallon sample is removed from the container every 4 weeks. Any excess water is discarded. Rainwater samples are held to be analyzed only if the air particulate samples indicate the presence of elevated activity levels or if fallout is expected. For example, rainwater samples were analyzed during the period of fallout following the accident at Chernobyl in 1986. Since no plant related air activity was detected in other atmospheric monitoring media in 1998, no rainwater samples from SQN were analyzed in this reponing period.
Results The results from the analysis of air particulate samples are summarized in Table H-3. Gross beta activity in 1998 was consistent with levels reponed in previous years. The average level was 0.022 pCi/m' for both indicator and control locations. The annual average of the gross beta activity in air particulate filters at these stations for the years 1971-1998 are presented in Figure H-2. 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 pattems are consistent with data from monitoring programs conducted during the preoperation and construction lihases at other TVA nuclear plant sites.
Only naturally occurring radionuclides were identified by the monthly gamma spectral analysis of the air particulate samples. No fission or activation products were detected. As shown in .
Table H-4, I-131 was not detected in any of the charcoal cartridge samples collected in 1998.
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 ofit may be transferred to the milk and consumed by humans who drink the milk.
Therefore, samples of milk, vegetation, soil, and ' icrops are collected and analyzed to determine potential impacts from exposure threw is pathway. The results from the analysis of these samples are shown in Tables H-S throug~ R 3.
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 were located on the east side of the river between 4 and 6 miles from the plant. During 1998 one of the dairy farms went out of business. A modification in the monitoring program was made as a result of this change. Two farms with at least one milk producing animal have been identified within 2 miles of the plant. The three locations with the highest hypothetical calculated dose potential to individuals drinking the milk were included in the sampling program. The results of the 1998 land use survey are presented in Appendix G.
Samnie Collection and Analysis Milk samples are collected every 2 weeks from the three indicator locations and from at least one of three control dairies. These samples are placed on ice for transport to the Radioanalytical 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.
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
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taken not to include any soil with the vegetation. The sample is placed in a container with 1650 ml of 0.5 N NaOH for transport back to the Radioanalytical Laboratory 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 spectrcscopy. Once each quarter, the samples are ashed after the gamma analysis is completed ard analyzed for Sr-89,90. ,
Soil samples are collected annually from the air monitoring locations. The samples are collected with either a " cookie cutter" or an auger type sampler. After drying and grinding, the sample is l
analyzed by gamma spectroscopy. When the gamma analysis is complete, the sample is ashed !
and analyzed for Sr-89,90.
l Samples representative of food crops raised in the area near the plant are obtained from individual gardens, comer markets, or cooperatives. Types of foods may vary from year to year as a result of changes in the local vegetable gardens. In 1998 samples of apples, corn, green
, beans, tomatoes, and tumip greens were collected from local vegetable gardens. The edible portion of each sample is analyzed by gamma spectroscopy.
Results l The results from the analysis of milk samples are presented in Table H-5. N radioactivity attributable to SQN operations was identified. All I-131 results were less than the established nominal LLD of 0.4 pCi/ liter. Strontium-90 was detected above the nominal LLD in a total of six samples. The Sr-90 levels are consistent with historical data reported in milk as a result of !
fallout from atmospheric nuclear weapons tests (Reference 1). Figure H-3 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 i
the soil over the period. The average Sr-90 concentration reported in 1998 was 6.13 pCi/ liter. i By far the predominant isotope reported in milk samples was the naturally occurring K-40. An average of approximately 1350 pCi/ liter of K-40 was identified in all milk samples.
l F
As has been noted in this report for previous years, the levels of Sr-90 in milk samples from small farms producing milk for private consumption have been consistently higher than the levels found in milk from commercial dairy farms. This phenomenon was observed during the preoperational radiological monitoring near SQN at farms where only one or two cows were being milked for private consumption of the milk. 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. These phenomenon would account for the slightly higher levels of Sr-90 measured
. in milk samples from the two small farms near SQN compared to the levels of St-90 measured in milk from the dairy farms sampled in the program.
Results from the analysis of vegetation samples (Table H-6) were similar to those reported for milk. All I-131 values were less than the nominal LLD. All strontium-89 results were less than the analysis specific LLD. Strontium-90 was identified in a total of seven samples at concentrations ranging from 16.0 to 37.7 pCi/Kg. These concentrations are consistent with results produced by nuclear weapons fallout. Again, the largest concentrations identified were for the naturally occurring isotopes K-40 and Be-7.
A total of fourteen soil samples were collected and analyzed. The soil samples contained measurable levels of Cs-137 with the maximum concentration being 1.% pCi/g. These concentrations are consistent with levels previously reported from fallout. All other radionuclides reported were naturally occurring isotopes (Table H-7).
- A plot of the annual average Cs-137 concentrations in soil is presented in Figure H-4. Like the levels of Sr-90 in milk, concentrations of Cs-137 in soil are steadily decreasing as a result of the cessation of weapons testing iri the atmosphere, the 30-year half-life of Cs-137 and transport through the environment.
Radionuclides reported in food samples were all naturally occurring. The maximum K-40 value was 2450 pCi/kg in tomatoes. Analysis of these samples indicated no contribution from plant activities. The results are reported in Tables H-8 through H-12.
l l
l I
c LIQUID PATHWAY MONITORING Potential exposures from the liquid pathway can occur from drinking water, ingestion of edible
! fish and invertebrates, or from direct radiation exposure from radioactive materials deposited in the river sediment. The monitoring program includes the collection of samples of surface water, groundwater, drinking water supplies, fish, Asiatic clams (there is no known human consumption of these clams from the Tennessee River), and bottom and shoreline sediment. Samples from the reservoir are collected both upstream and downstream from the plant.
Samnle Collection and Analysis Pamples of surface water are collected from the Tennessee River downstream and upstream of the plant using automatic sampling systems. A timer turns on the system at least once every 2
-hours and the sample is collected into a compositejug. A 1-gallon sample is removed from the composite 3ag at 4-week fatervals and the remaining water in thejug is discarded. The composite sample is analyzed for gamma emitting radionuclides and for gross beta activity. A l quarterly composite sample is analyzed for Sr-89,90 and tritium.
l l
Samples are collected by an automatic sampling system at the first downstream drinking water j intake and at the water intake for the city of Dayton located approximately 20 miles upstream.
These samples are collected in the same manner as the surface water samples and analyzed by j gamma spectroscopy and for gross beta activity. At other selected locations, grab samples are collected from drinking water systems which use the Tennessee River as their source. These samples are analyzed every 4 weeks by gamma spectroscopy and for gross beta activity. A quarterly composite sample from each station is analyzed for Sr-89,90 and tritium. The sample collected at the water intake for the city of Dayton also serves as control sample for surface water.
l
. Groundwater is sampled frbm an onsite well and from a private well in an area unaffected by SQN. The quarterly composite samples are prepared for each location and analyzed by gamma spectroscopy. Analyses are also performed for gross beta activity, Sr-89,90 and tritium.
I Samples ofcommercial and game fish species are collected semiannually from each of two reservoirs: the reservoir on which the plant is located (Chickamcuga Reservoir) and the upstream reservoir (Watts Bar Reservoir). The samples are collected using a combination of netting techniques and electrofishing. Samples of all species are prepared from filleted fish.
After drying and grinding, the samples are analyzed by gamma spectroscopy.
x Bottom sediment samples are collected semiannually from monitoring locations using a dredging apparatus or divers. Samples of shoreline sediment are collected from two downstream recreational use areas and one upstream location. The samples are dried and ground and analyzed by gamma spectroscopy.
Samples of Asiatic clams are collected semiannually from one location below the plant and one Iccation above the plant. There is no known use of these clams for human consumption. The clams are usually collected in the dredging or diving process with the sediment. Enough clams are collected to produce approximately 50 grams of wet flesh. The flesh is separated from the shells, and the dried flesh samples are analyzed by gamma spectroscopy.
Results There were no fission or activation product radionuclides identified from the gamma spectroscopy or specific analyses performed on surface water samples. Gross beta activity above
- the nominal LLD value was measured in most surface water samples. Concentrations in samples fro.n the indicator and control locations averaged 2.9 pCi/ liter. The values were consistent with previsasly reported levels. ' A trend plot of the gross beta activity in surface water samples from 1971 through 1998 is presented in Figure H-5. A' summary table of the results is shown in Table -
H-13.
l I
I
There were no fission or activation product radionuclides identified in drinking water samples.
' Average gross beta activity was 2.7 pCiMiter for the downstream stations and 2.9 pCiMiter 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-6.
No fission or activation products were detected by the gamma spectroscopy analyses performed on well water. Gross beta concentrations in samples from the onsite well averaged 2.4 pCiditer, t while the average from the offsite well was 6.0 pCiditer. Tritium was identified in the quanerly composite samples from the on site well during the second halfof the year. The highest concentration measured in composite samples was 2,120 pCiSiter in the sample for the 4th quarter composite period (October through December). The presence of the tritium was first identified in the 3rd quaner composite. Additional tritium analyses were performed on the monthly samples used to make the quarterly composites and on special grab samples collected from the well. The results of these analyses established that the tritium was first detectable in concentrations above the nominal LLD of 300 pCi/ liter in May 1998. The tritium concentration measured in the routine continuous composite sample was approximately 600 pCiSiter in the sample collected during the period of May 7 to June 10. The highest tritium activity found in ground water from this well was 2,384 pCiniter in a special grab sample collected on December 10,1998. Various other ground water sampling wells on site were tested for the presence of radionuclides. These wells were used to monitor ground water for other hazards such as diesel oil and are not routinely sampled as part of the radiological environment monitoring program. Samples collected from these additional wells contained no measurable !
tritium. !
i
. Routine and special grab sampling conducted during the first two months of 1999 indicates that i
the tritium concentration is decreasing. A special grab sample collected on February 11,1999, i contained approximately 1260 pCiSiter. Site Radiological and Chemistry Control personnel are evaluating the potential sources for the tritium. The results of the special grab sampling will !
i be retained with the records from the radiological environmental monitoring conducted for SQN but are not included in the results summarized in Table H-15 of this report. Table H-15 provides the results from the scheduled SQN monitoring program samples.
Cesium-137 was identified in a total of six fish samples. The maximum concentration measured in samples from indicator locations was 0.05 pCi/g, while the maximum for control samples was 0.11 pCi/g. Plots of the annual Cs-137 concentrations in the fish are presented in Figures H-7, H-8, and H-9. Since the concentrations from indicator locations were less than control locations, the Cs-137 is most likely the result of fallout or other upstream effluents rather than activities at i
SQN. Other radioisotopes found in fish were naturally occurring with the most notable being K-
- 40. The concentrations of K-40 ranged from 10.2 pCi/g to 21.4 pCi/g. The results are summarized in Tables H-16, H-17, H-18.
Radionuclides of the types produced by nuclear power plant operations were identified in bottom sediment samples. The radionuclides identified were Cs-137, Cs-134, Co-60, and Co-58. The average Cs-137 concentration measured for samples from the downstream locations was 0.49 pCi/g and the average concentration for control locations was 0.71 pCi/g. The presence of Cs-137 was measured in all of the samples collected from downstream shoreNe sediment monitoring locations. The maximum concentration was 0.22 pCi/g. The maximum concentration measured in samples from the control location was 0.09 pCi/g. The concentrations of Cs-137 in sediment are consistent with previously identified fallout levels and are most likely not a result of SQN operations. The Co-60 concentrations measured in downstream bottom sediment samples averaged 0.26 pCi/g. A level of 0.03 pCi/g Co-60 was measured in one sample collected upstream. Cs-134 was identified in two downstream bottom sediment samples !
at an average concentration reported was 0.04 pCi/g. Co-58 was identified in one downstream !
sample at a concentration of 0.06 pCi/g. There was no Cs-134 or Co-58 detected in bottom sediment samples collected from the upstream location. A dose assessment of the impact to the ;
general public from this activity produces a negligible dose equivalent. Results from the analysis 1
I l L
c7 of bottom sediment samples are shown in Table H-19. Co-58, Co-60, and Cs-134 were not identified in shoreline sediment. Results from the analysis of shoreline sediment samples are shown in Table H-20.
Graphs of the Cs-137 and Co-60 concentrations in bottom sediment are presented in Figures H-10 and H-11, respectively. Figure H-12 presents a plot of the Cs-137 concentrations measured in shoreline sediment since 1980.
Only naturally occurring radioisotopes were identified in clam flesh samples. The results from the analysis of these samples are presented in Table H-21.
l l
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ASSESSMENT AND EVALUATION l
Potential doses to the public are estimated from measured effluents using computer models.
- l. ; These models were developed by TVA and are based on methodology provided by the NRC in ~
l 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
- maximum 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. at reality, the expected dose to actual individuals is significantly lower.
1 The area around the plant is analyzed to determine the pathways through which the public may receive an exposure. As indicated in Figure 2, the two major ways by which radioactivity is introduced into the environment are through liquid and gaseous effluents.
i 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 thei 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 bssed on specific conditions for the SQN area.-
For gaseous effluents, the public can be exposed to radiation from several sources: direct radiation from the radioactivity in the air, direct radiation from radioactivity deposited on the ground, inhalation of radioactivity in the air, ingestion of vegetation which contains radioactivity deposited from the atmosphere, and ingestion of milk 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.
l l.
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Results The estimated doses to the maximum exposed individual due to radioactivity released from SQN in 1998 are presented in Table 3. These estimates were made using the concentrations of the liquids and gases measured in the effluent monitoring points. Also shown are the regulatory limits for these doses and a comparison between the calculated dose and the corresponding limit.
The maximum calculated whole body dose equivalent from measured liquid effluents as presented in Table 3 is 0.021 mrem / year, or 0.7 percent of the limit. The maximum organ dose equivalent from gaseous effluents is 0.189 mrem / year. This represents 1.26 percent of the NRC limit. A more complete description of the effluents released from SQN and the corresponding doses projected from these effluents can be found in the SQN Annual 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 frorn each environmental sample are compared with the concentrations from the corresponding control stations and appropriate preoperational and background data to determine influences from the plant. During this report period, Co-60, Co-l 58, Cs-134, and Cs-137 were detected in bottom sediment. Measurable levels of Cs-137 were also detected in fish and shoreline sediment and tritium was detected in ground water from the on site monitoring well. The Cs-137 concentrations measured in shoreline sediment, bottom sediment and fish are consistent with levels identified previously that are the result of fallout from past atmospheric nuclear weapons testing. The Co-60, Co-58, and Cs-134 identified in sediment samples downstream from the plant would produce no measurable increase in the dose l to the general public. The tritium concentrations measured in ground water were well below any i levels requiring special actions. The presence of detectable tritium in the on site well does not represent an exposure pathway to the general public.
1 Dose estimates were made from concentrations of radioactivity found in samples of environmental media. Media evaluated included, but are not limited to, air, milk, food products, I l
7 drinking water, fish, soil and shoreline sediment. Inhalation, ingestion and direct doses estimated for persons at the indicator locations were essentially identical to those determined for persons at control stations. More than 99 percent of those doses were contributed by the naturally occurring radionuclide K-40 and by Sr-90 and Cs-137, which are long-lived radioisotopes found in fallout from nuclear weapons testing. Concentrations of Sr-90 and Cs-137 are consistent with levels measured in TVA's preoperational radiological environmental monitoring programs. Figures H-3 and H-4 and Figure H-8 through H-10 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 radiation exposure to Members of the Public.
I l
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RSFERENCES
- 1. Menil Eisenbud, Environmental Radioptivity. Academic Press, Inc., New York, NY,1987.
- 2. National Council on Radiation Protection end Measurements, Report No. 93, " Ionizing Radiation Exposure of the Population of the United States," September 1987.
- 3. United States Nuclear Regulatory Commission, Regulatery Guide 8.29, " Instruction Concerning Risks from Occupational Radiation Exposure, luly 1981.
- 4. Hansen, W.G., Campbell, J. E., Fooks, J. H., Mitchell, H.C., and Eller C.H., Farmine 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.
I l
Table 1 COMPARISON OF PROGRAM LOWER LIMITS OF DETECTION WITil THE REGULATORY LIMITS FOR MAXIMUM ANNUAL AVERAGE EFFLUENT CONCENTRATIONS RELEASED TO UNRESTRICFED AREAS AND REPORTING LEVELS Concentrations in Water. nCi/ Liter Concentrations in Air. nCi/ Cubic Meter 3 Effluent Reporting Lower limit Effluent Reporting Lower limit Concentrationi Level 2 of Detection' Concentration' Level' of Detection' H-3 1,000,000 20,000 3's; 100,000 Cr-51 500,000 45 30,000 0.02 Mn-54 30,000 1,000 5 1,000 0.005 Co-58 20,000 1,000 5 1,000 0.005 Co-60 3,000 300 5 50 0.005 Zn-65 5,000 300 10 400 0.005 Sr-89 8,000 5 1,000 0.0011 Sr-90 500 2 6 0.0004 Nb-95 30,000 400 5 2,000 0.005 Zr-95 20,000 400 10 400 0.005 i Ru-103 30,000 5 900 0.005 Ru-106 3,000 40 20 0.02 1-131 1,000 2 0.4 200 0.9 0.03 Cs-134 900 30 5 200 10 0.005 Cs-137 1,000 50 5 200 20 0.005 Ce.144 3,000 30 40 0.01 Ba-140 8,000 200 25 2,000 0.015 La-140 9,000 200 10 2,000 0.01
)
l Note: 1 pCi = 3.7 x10~' Bq.
Note: For those reporting levels that are blank, no value is given in the reference.
l 1 Source: Table 2 of Appendix B to 10 CFR 20.1001-20.2401 2 Source: SQN Offsite Dose Calculation Manual, Table 2.3-2 3 Source: Table E-1 of this report.
Table 2 Results from the Intercomparison of Environmental Dosimeters Calculated Average, all Exposure % Difference % Difference TVA Results Respondents (See Note 1) TVA: Respondents:
Y.fE BEED BEEHl Eggn Calculated Calculated Field Dosimeters 74 15.0 16.3 16.3 -8.0 0.0 77 30.4 31.5 34.9 -12.9 -9.7 79 13.8 16.0 14.1 -2.1 13.5 81 31.8 30.2 30.0 6.0 0.7 82 43.2 45.0 43.5 -0.7 3.4 j 84 73.0 75.1 75.8
-3.7 -0.9 86a 33.2 28.9 29.7 11.8 -2.7 86b 9.4 10.1 10.4 -9.6 -2.9 93a 24.4 26.4 27.0 -9.6 -2.2 93b 27.6 25.4 27.0 2.2 -2.2 96a 16.9 18.9 19.0 -10.9 -0.5 96b 17.6 18.9 19.0 -7.4 -0.5 Low Irradiated Dosimeters 74 27.9 28.5 30.0 -7.0 -5.0 79 12.1 12.1 12.2 -0.8 -0.8 86 18.2 16.2 17.2 5.8 -5.8 'i 93a 24.9 25.0 25.9 -3.9 -3.5 93b 27.8 25.0 25.9 7.3 -3.5 High Irradiated Dosimeters 77 99.4 86.2 91.7 8.4 -6.0 79 46.1 43.9 45.8 0.7 -4.1 81a 84.1 75.8 75.2 11.8 0.8 81b 102.0 90.7 88.4 15.4 2.6 82a 179.0 191.0 202.0 -11.4 -5.4 82b 136.0 149.0 158.0 -13.9 -5.7 84a 85.6 77.9 79.9 7.1 -2.5 84b 76.8 73.0 75.0 2.4 -2.7 93a 67.8 69.8 72.7 -6.7 -4.0 93b 80.2 69.8 72.7 10.3 -4.0 96 60.7 55.2 58.1 4.5 5.0 96b 59.4 55.2 58.1 2.2 -5.0 '
l Notes: 1. The calculated exposure is the "known" exposure determined by the testing agency.
31-
Table 3 r
Maximum Dose Due to Radioactive Effluent Re cases Sequoyah Nuclear Plant 1998 4 mrem / year Dose From Liquid Effluents 1998 NRC Percent of IXEE D2K Ljulit NRC Limit TotalBody 0.021 3 0.7 Any Organ ' O.027 10 0.3 Doses From Gaseous Effluents 1998 NRC Percent of IYDE D2K lid 1!! NRC Limit l
l Noble Gas 0.209 10 2.09 (Gamma) j Noble Gas 0.519 20 2.60 j (Beta) i j Any Organ 0.189 15 1.26 l
l Total Cumulative Dose 1998- EPA Percent of Iygg Q2K Limit EPA Limit Total Body or Any Other Organ 3.68E-01 25 1.5
. 'Ihyroid 3.52E-01 75 <l .0 l
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Table A 2 SEQUOYAH NUCLEAR PLANT i
I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS i
Map Approximate Indicator (I)
Location Distance or Samples Numbera Station Sector (Miles) Control (C) _Collectedb 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 LM4 NNE 1.8 i AP,CF,R,S 7 PM-2 SW 3.8 I AP.CF,R,5 8 PM-3 W 5.6 I AP,CF,R,S 9- PM-8 SSW 8.7 i AP,CF,R,S IO PM-9 .WSW 2.6 I AP,CF,R,5 II RM-1 ' SW 16.7 C AP,CF,R,S 12 RM-2 NNE 17.8 C AP,CF,R,S 13 RM-3 ESE 11.3 C AP,CF,R,S 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 M j 17 Farm S NNE 12.0 C M,V 18 Farm J WNW l.1 1 M 19 Farm HW NW l.2 1 M,WC 20 Farm EM N 2.6 I V 21 Farm HS E 4.6 I M 24 Well No. 6 NNE 0.15 I W 31 TRM 473.0 -
10.7d 1 PW (C. F. Industries) 32 TRM 469.9 -
13.Bd 1 PW (E. I. DuPont) pw 33 TRM 465.3 -
18.4d g i
(Chattanooga) 34 TRM 497.0 -
20.id C PW,SW (Dayton) 36 TRM 496.5 -
0.3d g s o,s w 39 TRM 480.8 - 2,9d i so i 40 TRM 479.0 -
4.7d i ss 44 ' TRM 480.0 -
3.7d g ss 46 Chickamauga Reservoir (TRM 471530) -
I/C F.CL 47 Watts Bar Rerervoir(TRM 530-602) - C F
- a. Se Figures A-1, A-2, and A-3
- b. Sample codes; AP = Air particulate filter PW = Public Water SS = Shoreline Sediment CF = Charcoalfilter R = Rainwater - SW = Surface water CL = Clams .S = Soil V = Vegetation F = Fish SD = Sediment W = Wellwater M = Milk
- c. A con:rol for well water,
- d. Distance from plant discharge (TRM 483.7).
p 1
l Table A-3 l SEQUOYAH NUCLEAR PLANT THERMOL11MINESCENT DOSIMETER (TLD) LOCATIONS
' Map Approximate Onsite (Onf I Location - Diatance or W 3 Smien SSW-IC Seum SSW .
Lu]u) OfTsite (Om
- 2.0 On
'4- NE-l A - NE 1.5 On 5 NNbl NNE 1.8 On :
7 SW-2 SW . 3.8 Off j 8 W-3 W 5.6 Off 9 SSW-3 SSW 8.7 Off 10 WSW-2A WSW 2.6 Off 11= SW3 SW - 16.7 Off 12 NN64 NNE 17.8 Off 13 ESE-3 ESE 11.3 ~ Off j 14 WNW-3 WNW l 8.9 - Off
' 49 N1 N 0.6 On 50 N-2 N 2.1 Off
$1 N-3 N 5.2 Off 52 N4 N '
10.0 Off 53 NNE NNE 4.5 oft 54 NNE3 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 l 59 El E 1.2 On i 60 E-2 E 5.2 Off !
61 ESSA ESE 03 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 I .4 On i 67 SE-2 SE 1.9 On i 68 SE-4 SE 5.2 Off 'I 69 SSE-1 SSE 1.6 On i 70 SSE-2 SSE 4.6 Off - l 71 S1 S 1.5 On 72 S-2 S 4.7 Off 73 - SSW-1 SSW 0.6 On 74 SSW-2 SSW 4.0 Off 75 SW-1 SW 0.9 On 76 WSW1 WSW 0.9 On 77 WSW-2 WSW 2.5 Off l 78- WSW-3 WSW 5.7 Off i 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 WNW1 WNW 0.4 On 84 WNW-2 WNW 53 Off 85 NW-1 NW 0.4 On 86' NW-2 NW 5 Off 87 NNW-1 NNW 0.6 On 88 NNW-2 NNW l .7 On 89 NNW-3 NNW 53 Off 90 SSW-1B SSW l .5 - On
- a. See Figures A l. A-2.and A 3.
- b. TLDs designated "onsite" are located 2 miles or less from the plant;"ofTsite" are located more than 2 miles from the plant.
1
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Figure A-1 Radiological Environmental Monitoring Locations Within 1 mile of the Plant 34s.75 N 11.25 NNW L NNE 326.25 33.75 NW 2 NE '
303.75 4 56.25 WNW . , ENE
/ j 281.25 %
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Scale O Mlle 1 Figure A-2 Radiological Environmental Monitoring Locations Between 1 and 5 milcs from the Plant 34a.75 N' 11.2s NNW ) l NNE 326.25 i 33.75 NW
- NE 303.76 66.25 e
- 56 WNW 5 55 ENE 8
e i
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Figure A-3 Radiological Environmental Monitoring Locations More than 5 milea from the Plant 34415 "
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1 APPENDIX B l
1998 PROGRAM MODIFICATIONS i
I t
l t
I i
l l
Appendix B Radiological Environmental Monitorine Program Modification One modification in the collection of milk samples was made in the SQN monitoring program in 1998. The Holder dairy farm went out of operation in May. The milk producing location with next highest projected dose based on the 1997 land use survey data was added to the milk collection schedule. The location added was the H. Smith dairy.
One other modification related to the sampling locations for shoreline sediment was implemented during 1998. Due to changes in the use of recreational areas, the two downstream sampling locations for shoreline sediment were changed from recreational areas at TRMs 477 and 478 to areas at TRMs 479 and 480. These changes are summarized in Table B-1.
l Table B-1 Radiolonical Environmental Monitorine Program Modifications Dals Station Location Remarks May 27,1998 Farm H 4.2 miles NE Dairy farm at this location went out of business. Location deleted from the monitoring program.
May 27,1998 Farm HS 4.6 miles E Location added for milk collection to j replace Farm H.
i May 1998 TRM 478 5.7 miles Deleted shoreline sediment sampling point l downstream and replaced with sampling point at TRM 480.
May 1998 TRM 477 6.7 miles Deleted shoreline sediment sampling point i downstream and replaced with sampling point at TRM 479.
May 1998 TRM 480 3.7 miles Added collection of shoreline sediment.
downstream l May 1998 TRM 479 4.7 miles Added collection of shoreline sediment.
l downstream i
l l
-4 8-
p APPENDIX C PROGRAM DEVIATIONS i
l I
i l
l--
1-Appendix C l Radiological Environmental Monitoring Program Deviations During 1998, there were two sampling periods when the air particulate filter and charcoal cartridge could not be collected from one of the twelve sampling locations due to equipment problems. The locations and dates are listed in the Table C-1. In each case the problem was corrected and a sample was collected as scheduled the next week.
The sample scheduled for collection from TRM 503.8 (Dayton) was not available on April 14, 1998 due to problems with the electrical power service to the sampling station. The sample from this location serves as a control for public water and surface water. The ps oblem was corrected and a sample was collected at the next scheduled collection period.
The continuous surface water sample scheduled for collection from TRM 497.0 on December 15, 1998, was not available due to problems with sampling equipment. The sampler was retumed to service and operated correctly for next sampling period.
A total of five milk samples were missed during the year because milk could not be collected from the farm or dairy.
These missed samples resulted in deviations from the scheduled program but did not represent a problem of noncompliance with the ODCM required program. Table C-1 provides additional details on the missed samples.
l Table C 1 Radiological Envin,iali a! Monitorine Proeram Deviatiana -
Dalt Slalga Location Remarks 02/04/98 Farm S 12.0 miles NNE He milk sample scheduled from this location could not be collected due to bad road conditions. This location is one of three controllocations. Samples were collected from the other two locations
' 04/07/98 RM-4 18.9 miles WNW ne air particulate filter and charcoal cartridge samples were not available due to broken drive belt on sampling pump. Repairs were made and samples were collected at -
the next scheduled sampling period.
-04/14/98 TRM 503.8 ' 20.1 miles upstream De water sample was not available due to temporary disruption of elec+rical power to the sampling system.
Power was restored in tirne for the next sampling period.
07/07/98 RM-4 18.9 rniles WNW The air particulate filter and charcoal cartridge samples were not available du: to broken drive belt on sampling pump. Repairs were made and samples were collected at the next scheduled sampling period.
l 11/10/98 Farm J 1.1 miles WNW This is a small farm with only one cow. Due to the death of the cow, milk was not available. The owner has' indicated that she intends to replace the cow and continue milk production at this location.
11/23/98 Farm J 1.1 miles WNW Milk production has not been restarted at this location.
l 12/08/98
.12/21/98 l
l 12/15/98 TRM 497.0 13.3 miles upstream The water sample was not available due to problems with the sampling equipment. Repairs were made and the sampler was returned to service for the next collection period.
-51 .
0 APPENDIX D ANALYTICAL PROCEDURES 1
l l
l 7
e Appendix D Analytical Procedures l Analyses of environmental samples are performed by the radioanalytical laboratory located at the Western Area Radiological Laboratory facility in Muscle Shoals, Alabama. 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 I samples to near dryness, transferring to a stainless steel planchet and completing the evaporation process. ' Air particulate filters are ccunted directly in a shallow planchet.
The specific analysis ofI-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 50 minutes.
With the beta gamma coincidence counting system, background counts are virtually eliminated i
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.
Water 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 multichannel analyzer system. Spectral data reduction is performed by the computer program HYPERMET.
The charcoal cartridges used to sample gaseous radioiodine are analyzed by gamma spectroscopy using a high resolution gamma spectroscopy system with germanium detectors.
The necessary efriciency values, weight-efficiency curves, and geometry tables are established and maintained on each detector and counting system. A series of daily and periodic quality control checks are performed to monitor counting instrumentation. System logbooks and control charts are used to document the results of the quality control checks.
1 I
E APPENDIX E OhflNAL LOWER LIMITS OF DETECTION (LLD) i
]
l
-ss- ,
I I
1
E Appendix E Nominal Lower Limits of Detection l
Ser.sitive radiation detection devices can produce a signal 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. 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 may vary from that average. In order to determine the ;
i 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.
1 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 ofits capability. For a sample with no measurable activity, which often happens, about half the time its signal should fall below the average machine background and half the time it should be above the background. If a signal above the background is present, the calculated activity is compared to the calculated LLD to determine if there is really activity present or if the number is !
, an artifact of the way radioactivity is measured.
I :
A number of factors influence the LLD, including sample size, count time, counting efficiency, chemical processes, radioactive decay factors, and interfering isotopes encountered in the l
sample. The most likely values for these factors have been evaluated for the various analyses performed in the envimnmental monitoring pmgram. The nominal LLDs calculated from these values, in accordance with the methodology prescribed in the ODCM, are presented in Table E-1.
The maximum values for the lower limits of detection specified in the ODCM are shown in
)
Table E-2.
The nominal LLDs are also presented in the data tables. For analyses for which LLDs have not been established, an LLD of zero is assumed in determining if a measured activity is greater than the nominal LLD.
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l Table E-2 Maximum Values for the Lower Limits of Detection (LLD)
Specified by the SQN Offsite Dose Calculation Manual l
Airborne Particulate Food Water or Gases Fish. Milk Products . Sediment Analysis G oCi/m' DCt/kg. wet oCi/L h wet h dry-gross beta '4 . - 1 x 104 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.
6 1 131' 1 7 x 104 N.A. I 60 .N.A.
Cs-134 15 5 x104 130 15 60 150 J
Cs-137 18 6 x 10 4 150- 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.
- a. If no drinking water pathway exists, a value of 3000 pCi/ liter may be used.
- b. If no drmkmg water pathway exists, a value of 15 pCi/ liter may be used.
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I APPENDIX F j QUALITY ASSURANCE / QUALITY CONTROL PROGRAM j i
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1 1
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Appendix F Ouality Assurance /Ouality Control Procram A thorough quality assurance program is employed by the laboratory to ensure that the environmental monitoring data are reliable. This program includes the use of written, approved procedures in performing the work, a complete training and retraining system, internal self assessments ofprogram performance, audits by various external organizations, and a laboratory quality control program.
The quality control program employed by the radioanalytic 1 laboratory is designed to ensure that the sampling and analysis process is working as intended. The program includes equipment checks and the analysis of quality control samples along with routine samples.
Radiation detection devices 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, and/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 retumed to 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 perfonnance I
of different podions of the analytical process. These quality control samples may be blanks, replicate samples, blind samples, or cross-checks.
Blanks are samples which contain no measurable radioactivity or no activity of the type being measured. Such samples are analyzed to determine whether there is any contamination of equipment or commercial laboratory chemicals, cross-contamination in the chemical process, or interference from isotopes other than the one being measured.
Duplicate samples are generated at random by the sample computer program which schedules the collection of the routine samples. For example, if the re dine program calls for four milk samples every week, on a random basis each farm might provide an additional saraple several times a year. These duplicate samples are analyzed along with other routine samples. They provide infonnation about the variability of radioactive content in 6 ' various sample media.
If enough sample is available for a panicular analysis, the laboratory staff can split it into two podions. Such a sample can provide infonnation 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. The lab stafiknow the radioactiu content of the sample. Whenever possible, the analytical knowns contain the same amount of radioactivity each time they are run. In this way, analytical knowns provide immediate data on the quality of the measurement process. A ponion 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 lab staff does not know the sample contains radioactivity. Since the bulk of the ordinary workload of the environmental laboratory contains no measurable activity or only naturally occurring radioisotopes, blind spikes can be
.used to test the detection capability of the laboratory or 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 the blind spikes 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 ofinternal cross-checks.
These samples have a known amount of radioactivity added and are presented to the lab staff labeled as cross-check samples. This means that the quality control staff knows the radioactive content or "right aitswer" but the lab personnel performing the analysis do not. Such samples test the best performance of the laboratory by determining if the lab 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. 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 laboatory performance. They provide an independent check of the entire measurement process that cannot be easily provided by the laboratory itself. That is, unlike intemal cross-checks, EPA cross-checks test the calibration of the laboratory detection devices since different radioactive standards produced 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 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.
64-
The results ofTVA's participation in the EPA Interlaboratory Comparison Program are presented in Table F-1. For 1998, all EPA cross -check sample concentrations measured by TVA's laboratory were within 3-sigraa of the EPA reported values.
TVA splits certain environmental samples with laboratories operated by the States of Alabama and Tennessee and the EPA National Air and Radiation Environmental Laboratory in Montgomery, Alabama. ' When radioactivity has been present in the environment in measurable quantities, such as following atmospheric nuclear weapons testing, following the Chernobyl-incident, or as naturally occurring radionuclides, the split samples have provided TVA with another level ofinformation about laboratory performance. These samples demonstrate performance on actual environmental sample matrices rather than on the constructed matrices used in cross-check programs.
The quality control data are routinely collected, examined and reported to laboratory supervisory
, personnel. They are checked for trends, problem areas, or other indications that a portion of the analytical process needs correction or improvement. The end results is a measurement process that provides reliable and verifiable data and is sensitive enough to measure the presence of radioactivity far below the levels which could be harmful to humans.
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APPEhTIX G LAND USE SURVEY i
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Appendix G Land Use Survey ;
J A land use survey is conducted annually to identify the location of the nearest milk producing animal, the nearest resideuce, 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 is conducted between April 1 and October 1 usmg appropnate 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. 'Ihey also assume 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 Section and Table 3).
In response to the 1998 SQN land use survey, annual dose projections were calculated for air submersion, vegetable ingestion, and milk ingestion. Extemal doses due to radioactivity in air j (air submersion) are calculated for the nearest resident in each sector, while doses from drinking l milk or eating foods produced near the plant are calculated for the areas with milk producing l animals and gardens, respectively.
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There were small changes in the location of the nearest resident as identified in 1998 compared to 1997. These changes made only a small or no difference in the dose projections calculated for the nearest resident. A garden was located in the ENE sector in 1998. No garden was identified in this sector in 1997. This was the only change in the dose projections calculated for ingestion of home-gmwn foods compared to 1997.
For milk ingestion, projected doses were consistent with those calculated for 1997, except for small variances due to a change in the feeding factor value at one location. The dairy. farm
' located in the NE sector went out of business prior to conducting the 1998 survey. ' Samples are being taken from the three farms with the highest projected doses and the highest X/Q values.
The 1998 survey identified the same potential milk producing location that was identified in the
' 1997 survey at approximately 1.5 miles NNW. There were milk goats at this location at the time of the survey but the animals were not currently producing milk. Periodic contact with the resident at this location has indicated that milk is still not being produced. No sampling is currently required or conducted at this location.
Tables G-1, G-2, and G-3 show the comparative relative calculated doses for 1997 and 1998.
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Table G-1 SEQUOYAH NUCLEAR PIANT Relative Projected Annual Air Subm rsion Dose to the Nearest Resident Within Five Miles of Plant mrem / year 1997 Survev 1998 Survey Approximate Approximate -
Distance Annual Distance Annual jigs 19I Milts Des.s Miles Dose N 0.8 0.12 0.8 0.12
-NNE 1.5 - 0.07 1.5 0.07 NE I.5 0.06 1.5 0.06 ENE 1.3 0.02 1.3 0.02 E .1.0 0.02 1.0 0.02 ESE 1.0 0.02 1.0 0.02 SE 1.1 0.02 1.1 0.02 SSE 1.3 0.03 1.3 0.03 S 1.2 0.10 1.2 0.09 SSW 1.3 0.15 1.3 0.15 SW 1.4 0.06 1.4 0.06 WSW 0.6 0.05 0.6 0.05 W 0.6 0.06 0.6 0.06-WNW 1.1 0.02 0.9 0.02 NW 0.8 0.04 0.8 0.04 NNW 0.5 0.14 0.5 0.14 !
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Table G-2 SEQUOYAH NUCLEAR PIANT l
Relative Projected Annual Dose to Child's Bone from Ingestion of Home-Grown Foods I
mrem / year i 1997 Survey 1998 Survey
-/spproximate Approximate Distance Annual Distance Annral Sts19I Milu 129st Miles Dose N 1.1 2.25 1.1 2.25 NNE 1.6- 2.10 1.6 2.10 l NE 2.7 0.78 2.7 0.78 ENE (a) 2.2 0.37 E 2.0 0.28 2.0 0.28 ESE 1.3 0.40 1.3 - 0.40 SE 2.0 0.30 2.0 0.30 SSE 1.3 1.00 1.3 1.00 S 1.4 2.45 1.4 2.45 SSW l.7 3.50 1.7 3.50 SW 2.4 1.02 2.4 1.02 WSW 0.7 ~ 1.32 0.7 1.32 W l.2 0.63 1.2 0.63 WNW l.1 0.62 1.1 0.62 NW 0.9 1.16 0.9 1.26 NNW 0.5 4.26 0.5 4.26 l
l (a) Garden not found within 5 miles.
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l Table G-3 SEQUOYAH NUCLEAR PLANT Relative Projected Annual Dose to Receptor Thyroid from Ingestion of Milk mrem / year Approximate Distance AnnualDose XQ Location SCElst (Mils.)* 1997 1998 gmi 5 Fwm H* NE 4.7 0.043 e Farm HS' E 4.6 0.009 0.009 6.74 E-8 Farm JH6d ESE 3.9 0.004 0.004 6.79 E-8 Farm J' WNW l.1 0.040 0.040 3.99 E-7 Farm HWS NW 1.2 0.040 0.057. 5.48 E-7 l
- a. Distances measured to nearest property line.
- b. Grade A dairy.
' c. Milk sampled at this location'
- d. Not currently sampled in the SQN monitoring program.
- c. The dairy farm at this location went out of business in May of 1998.
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APPENDIX H DATA TABLES AND FIGURES 1
1 1
l 1
i L s
1 I
I Table H - 1 l
DIRECT RADIATION LEVFI R
< Average Extemal Gamma Radiation Levels at Various Distances from Sequoyah Nuclear Plant for Each Quarter - 1998 mR / Quarter (a)
Distance per annum ,
Miles l. Average Extemal Gamma Radiation Levels (b) l mR/yr {
1st qtr 2nd otr 3rd qtr 4th qtr 0-1 15.6 i 1.5 15.6 i 1.6 16.6 i 1.5 15.9 i 1.4 64 1-2 13.3 i 1.6 13.2 i 1.8 14.3 i 1.7 13.7 i 1.5 55 2-4 12.7 i 1.8 12.9 i 2.3 14.4 i 2.1 13.2 i 2.3 53 4-6 12.9 i 1.4 13.6 i 1.3 14.711.6 13.311.4 54 l
)
>6 13.0 i 1.3 12.911.4 14.3 i 1.5 13.4 i 1.5 54 i Average, 0 - 2 miles 14.5 i 1.9 .14.512.1 15.5 i 1.9 14.9 i 1.8 59 l (onsite)
Average,
> 2 miles 12.9 i 1.5 13.2 i 1.7 14.5 i 1.7 13.311.7 54 (offsite)
(c) Field periods normalized to one standard quarter (2190 hours0.0253 days <br />0.608 hours <br />0.00362 weeks <br />8.33295e-4 months <br />)
(b) Average of the individual measurements in the set i 1 standard deviation of the set !
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