ML20082P988
| ML20082P988 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 12/31/1994 |
| From: | Shell R TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9504280002 | |
| Download: ML20082P988 (133) | |
Text
f nn Tennessee Vailey Authorrty Posi Office fles 2000. Sodcly-Daisy Tennessee 37379 April 21,1995 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:
In the Matter of
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Docket Nos. 50-327 Tennessee Valley Authority
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50-328 SEQUOYAH NUCLEAR PLANT (SON) - ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT in accordance with Technical Specification 6.9.1.6 for SON Units 1 and 2, enclosed is the Annual Radiological Environmental Operating Report for 1994.
No commitments are contained in this submittal. Please direct questions concerning this issue to W. C. Ludwig at 843-7460.
Sincerely,
>Y R. H. Shell Manager SON Site Licensing Enclosure cc: See page 2
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esO usOOO2 94t23t PDR ADOCK 05000327 1
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U.S. Nuclear Regulatory Commission Page 2 April 21,1995 cc (Enclosure):
Mr. D. E. LaBarge, Project Manager 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 ll 191 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323-2711
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ENCLOSURE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SEQUOYAH NUCLEAR PLANT-1995 (W46 950404 002)
J Annual E
Radiological E
Environmental E
Operating Report E
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$*ufea"r*eSant 1994
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I ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SEQUOYAH NUCLEAR PLANT 1994 I
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TENNESSEE VALLEY AUTHORITY ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATION I
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I April 1995 I
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l TABLE OF CONTF.NTS I
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Table of Contents.........................
iv List of Tables 1
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List of Figures..........................
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Executive Summary.........................
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Naturally Occurring and Background Radioactivity........
2 Introduction...........................
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Electric Power Production 8
Site / Plant Description......................
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Environmental Radiological Monitoring Program...........
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Direct Radiation Monitoring....................
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Heasurement Techniques.....................
14 15 Results 19 j
Atmospheric Monitoring
'E Sample Collection and Analysis.................
19 20 5
Results l
L Terrestriai Monitoring......................
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Sample Collection and Analysis................. 22 1
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Results l
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Aquatic Monitoring Sample Collection and Analysis.................
27 29 E
Results L_
Assessment and Evaluation..................... 33 34 l
Results r
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Conclusions 37 References Appendix A Environmental Radiological Monitoring Program and 42 Sampling Locations Appendix B 1994 Program Modifications
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I 57 Appendix C Program Deviations
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61 Appendix D Analytical Procedures.................
Appendix E Nominal Lower Limits of Detection (LLD) 64
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f i E Appendix F Quality Assurance / Quality Control Program....... 70
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Appendix G Land Use Survey....................
86 Appendix H Data Tables......................
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<f LIST OF TABLES 1I i
Comparison of Maximum Annual Average Effluent Table 1 Concentrations Released to Unrestricted Areas With E
Reporting' Levels and Lower Limits of Detection.....
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Table 2 Maximum Dose Due to Radioactive Effluent 39 Releases........................
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LIST OF FIGURES I
Figure 1 Tennessee Valley Region......
40 Figure 2 Environmental Exposure Pathways of Man Due 41 to Releases of Radioactive Materials to the Atmosphere and Lake I
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EXECUTIVE S'JMMARY l
l This report describes the environmental radiological monitoring program conducted by TVA in the vicinity of the Sequoyah Nuclear Plant (SQN) in 1994.
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The program includes the collection of samples from the environ"~ " nd the determination of the concentrations of radioactive materials in the samples.
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Samples are taken from stations in the general area of the picnt and from areas not influenced by plant operations. Station locations are selected I
after careful consideration of the weather patterns and projected radiation doses to the various areas around the plant. Material sampled includes air, l
water, milk, foods, vegetation, soil, fish, sediment, and direct radiation h
levels. Results from stations near'the plant are compared with concentrations from control stations and with preoperational measurements to determine l
l 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
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commonly found in the environment as a result of atmospheric nuclear weapons fallout.
I 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 d6termine potential effects on public health and safety.
This report satisfies the annual reporting requirements of SQN Technical Specification 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 with this material routinely.
Naturally Occurring and Background Radioactivity l
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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 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 (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 f
hydrogen (H)-3 (generally called tritium). These naturally occurring 1 - - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
C radioactive materials are in the soil, 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
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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
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atmosphere. 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 rcdiation coming from this radioactive material also depends upon the geographical location. Most of the remainder of the natural background radiation comes from the radioactive materials within each individual's body. We absorb these materials from the food we eat which contains naturally occurring radioactive materials from the soll. An example of this is K-40 as described above.
Even building materials affect the natural background radiation levels in the environment.
Living or working in a building which is largely made of earthen material, such as concrete or brick, will generally result in a higher natural background radiation level than would exist if the same structure were made of wood.
This is due to the naturally occurring radioisotopes in the concrete or brick, such as trace amounts of uranium, radium, thorium, etc.
E Because the city of Denver, Colorado, is over 5000 feet in altitude and the
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soll'and rocks there contain more radioactive material than the U.S. average, - _ - - _ - _ - _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
u the people of Denver receive around 350 mrem / year total natural background radiation dose equivalent compared to about 295 mrem / year for the national People in some locations of the world receive over 1000 mrem / year r
average.
natural background radiation dose equivalent, primarily because of the greater quantity of radioactive materials in the soil and rocks in those locations.
Scientists have never been able to show that these levels of radiation have F
caused physical harm to anyone.
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 primarily adapted from References 2 and 3.
1 U.S. GENERAL POPULATION AVERA'i DOSE EQUIVALENT ESTIMATES Millirem / Year Per Person Source l
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 0.28 Nuclear energy 0.03 Consumer products Total 355 (approximately)
I 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 This indicates that nuclear plant operations normally result hundred times.
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 use; has resulted in a similar effective dose equivalent to the U.S. population as that caused
'I 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 The National spaces, it can build up until concentrations become significant.
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 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.
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I 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.
I All paths through which radioactivity is released are monitored.
Liquid and gaseous effluent monitors record the radiation levels for each release.
These monitors also provide alarm mechanisms to prompt termination of any release above limits.
I Releases are monitored at the onsite points of release and through an environmental monitoring program which measures the environmental radiation in outlying areas around the plant.
In this way, not only is the release of 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.
I 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.
I The dose to a member of the general public from radioactive materials released to unrestricted areas, as given in NRC guidelines and the ODCH, is limited as follows:
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Liauld Effluents Total body
<3 mrem / year Any organ
<10 mrem / year I
Gaseous Effluents Noble gases:
i Gamma radiation 110 mrad / year Beta radiation 120 mrad / year f
Particulates:
1 5 mrem / year 1
Any organ l
l The EPA limits for the total dose to the public in the vicinity of a nuclear power plant, established in the Environmental Dose Standard of 40 CFR 190, are E
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as follows.
Total body 25 mrem / year l
Thyrod 75 mrem / year Any other organ 25 mrem / year
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l 10 CFR 20.1302(b) 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 l
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 detection limits for the listed radionuclides.
It should be noted that the levels of radioactive materials measured in the environment are typically below or only slightly above the lower limit of detection. The data presented in this report indicate compliance with the regulation.
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s SITE / PLANT DESCRIPTION The SQN is located on a site near the geographical center of Hamilton County, L
Tennessee, on a peninsula on the western shore of Chickamauga Lake at Tennessee River Mile (TRM) 484.5.
Figure I shows the site in relation to other TVA projects.
The SQN site, containing approximately 525 acres, is approximately 7.5 miles northeast of the nearest city limit of Chattanooga, Tennessee,14 miles west-northwest of Cleveland, Tennessee, and approximately 31 miles south-southwest of TVA's Watts Bar Nuclear Plant (WBN) site.
Population is distributed rather unevenly within 10 miles of the SQN site.
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 s
three dairy farms are located within 10 miles of the plant..
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>I Chickamauga Reservoir is one of a series of highly controlled multiple-use i
reservoirs whose primary uses are flood control, navigation, and the generation of electric power. Secondary uses include industrial and public
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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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I ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM l
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.
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retention of the materials in each level of control is achtued by system l
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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
!I radioactivity in the environment will be maximized.
The environmental radiological monitoring program is outlined in Appendix A.
l 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 ccnponents:
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 j's 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.
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A number of factors were considered in determining the locations for I
collecting environmental samples.
The locations for the atmospheric monitoring stations were determined from a critical pathway analysis based on i
weather patterns, dose projections, population distribution, and land use.
L Terrestriai samplin9 stations were seiected 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, water 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 1994 are described in Appendix B and exceptions to the sampling and analysis schedule are presented in Appendix C.
To determine the amount of radioactivity in the environment prior to the j
l operation of SQN, a preoperational environmental radiological monitoring l
l program was initiated in 1971 and operated until the plant began operation in 1980. Measurements of the same types of radioactive materials that are measured currently were assessed during the preoperational phase to establish normal background levels for various radionuclides in the environment.
The preoperational monitoring program is a very important part of the overall During the 1950s, 60s, and 70s, atmospheric nuclear weapons testing program.
released radioactive material to the environment causing fluctuations in background radiation levels. This radioactive material is the same type as that produced in the SQN reactors. Preoperational knowledge of preexisting radionuclide patterns in the environment permits a determination, through 11
comparison and trending analyses, of whether the operation of SQN is impacting the environment and thus the surrounding population.
The determination of !mpact during the operating phase also considers the 1
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 genereily quite sensitive to small amounts of radioactivity.
In the field of radiacion measurement, the sensitivity of the measurement process is discussed in terms of the lower limit of detection (LLD). A description of the nominal LLDs for the Radioanalytical Laboratory is presented in Appendix E.
The Radioanalytical Laboratory employs a comprehensive quality assurance /
quality control program to monitor laboratory performance throughout the year. The program is intended to detect any problems in the measurement._.
process as soon as possible so they can be corrected.
This program includes equipment checks to ensure that the complex radiation detection devices are working properly and the analysis of special samples which are included alongside routine environmental samples.
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.
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DIRECT RADIATION HONITORING Direct radiation levels are measured at a number of stations around the plant site. These measurements include contributions from cosmic radi=. tion, 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 i'
the plant may be difficult to distinguish.
r" Radiation levels measured in the area around the SQN site in 1994 were consistent with levels from previous years and with levels measured at other locations in the region.
Measurement Ter.hniques L
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 L
the material. They remain trapped for long periods of time as long as the 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 TLDs.
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From 1971 through 1989, TVA used a Victoreen dosimeter consisting of a
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manganese activated calcium fluoride (Ca2F: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 Model UD-814 dosimeter, and completely changed to the Panasonic dosimeter in 1990. This dosimeter contains four elements consisting of one I
lithium borate and three calcium sulfate phosphors.
The calcium sulfate l
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 site 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 exposure on the detectors is read with a Panasonic Model UD-710A automatic reader interfaced with a Hewlett Packard Model 9000 computer system. Seven of the locations also have TLDs processed by the NRC.
The results from the NRC measurements are reported in NUREG 0837.
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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 outlined in Regulatory Guide 4.13 for environmental applications of TLDs.
Results All results are normalized to a standard quarter (91.25 days or 2190 hours0.0253 days <br />0.608 hours <br />0.00362 weeks <br />8.33295e-4 months <br />). _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ -
lI 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 l
i lies between 1 and 2 miles, the third group between 2 and 4 miles, the fourth between 4 and 6 miles, and the fifth group is made up of all stations greater l
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.
l 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 i
"offsite."
Prior to 1976, direct radiation measurements in the environment were made with f
dosimeters that were not as precise at lower exposures. Consequently, environmental radiation levels reported in the early years of the l
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.
l The quarterly gamma radiation levels determined from the TLDs deployed around l
SQN in 1994 are summarized in Table H-1.
The results from all measurements at individual stations are presented in Table H-2.
The exposures are measured in t
1 milliroentgens and reported in millirem / standard quarter.
For purposes of l
this report, one milliroentgen and one millirem (mrem) are assumed to be equivalent. The rounded average annual exposures are shown below.
For l
l 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 mre:n/ year Preoperational 1994 Average Onsite Stations 59 79 Offsite Stations 53 63 t
The data in Table H-1 indicate that the average quarterly radiation levels at
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the SQN onsite stations are approximately 2 mrem / quarter higher than levels at the offsite stations. This difference is also noted in the preoperational i
phase and in the stations at NBN 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 I
attributable to combinations of influences such as natural variations in environmental radJation levels, earth-moving activities onsite, and the mass j
of concrete employed in the construction of the plant. Other undetermined l
Influences may also play a part. These conclusions are supported by the fact that similar differerces between onsite and offsite stations are currently
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observed in the vicinity of the HBN construction site.
l Figure H-1 compares plots of the data from the onsite or site boundary l
stations with those from the offsite stations over the period from 1976 through 1994.
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 The data follow the same general trend as the raw data, but the averages.
curves are much smoother. I i
All results reported in 1994 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.
r ATMOSPHERIC MONITORING L
The atmospheric monitoring network is divided into three groups identified as L
local, perimeter, and remote.
Four local air monitoring stations are located
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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.
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Results from the analysis of samples in the atmospheric pathway are presented in Tables H-3 and H-4.
Radioactivity levels identified in this reporting period are consistent with background and radionuclides produced as a result of fallout from previous nuclear weapons tests.
There is no indication of an increase in atmospheric radioactivity as a result of SQN.
Sample Collection and Analysis Air particulates are collected by continuously sampling air at a flow rate of approximately 2 cubic feet per minute (cfm) through a 2-inch Hollingsworth and Vose LB5211 glass H ber filter.
The sampling system consists of a pump, a
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magnehelic gauge for measuring the drop in pressure across the system, and a dry gas meter.
This allows an accurate determination of the volume of air passing through the filter. This system is housed in a building approximately-2 feet by 3 feet by 4 feet. The filter is contained in a sampling head mounted on the outside of the monitor building. The filter is replaced every 7 days. Each filter is analyzed for gross beta activity about 3 days after collection to allow time for the radon daughters to decay..
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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 1
containing TEDA-impregnated charcoal. This system is designed to collect iodine in both the elemental form and as organic compounds.
The cartridge is located in the same sampling head as the air particulate filter and is downstream of the particulate filter. The cartridge is changed at the same time as the particulate filter and samples the same volume of air.
Each cartridge is analyzed for I-131 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 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 hcid 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..
ce no plant-related air activity was detected in 1994, 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-3.
Gross beta activity in 1994 was consistent with levels reported in previous years. The average level at indicator and control stations was 0.019 and 0.019 pCi/m', respectively.
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l The annual averages of the gross beta activity in air particulate filters at these stations for the years 1971-1994 are presented in Figure H-3.
Increased I
levels due to fallout from atmospheric nuclear weapons testing are evident, 1
l especially in 1971, 1977, 1978, and 1981.
Evidence of a small increase
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resulting from the Chernobyl accident can also be seen in 1986.
These patterns are consistent with data from monitoring programs conducted by TVA at FL nonoperating nuclear power plant construction sites.
Only natural radioactive materials were identified by the monthly gamma f
spectral analysis of the air particulate samples.
No fission or activation t
products were found at levels greater than the LLDs. As shown in Table H-4, lodine-131 was not detected in any of the charcoal canister samples collected in 1994.
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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
.I 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-5 through H-13.
A land use survey is conducted annually to locate milk producing animals and l
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 1994 land use survey are presented in Appendix G.
I Sample Collection and Analysis Milk samples are purchased every 2 weeks from one dairy, from the two farms within 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 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 HBN monitoring program, are analyzed for Sr-89,90 monthly.
I 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 soil with the vegetation.
The sample is placed in a container with 1650 ml of 0.5 N Na0H 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 sample is ashed and analyzed for Sr-89,90.
I 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 1994 samples of apples, collard greens, corn, green beans, potatoes, and tomatoes were collected from local vegetable gardens.
The edible portion of each sample is analyzed by gamma spectroscopy.
I I
Results
'he results from the analysis of milk samples are presented in Table H-5.
No radioactivity which could be attributed to SQN was identified. All I-131 results were less that the established nominal LLD of 0.4 pC1/ liter.
==
N Strontium-90 was found in less than one-fourth of the samples.
The Sr-90 levels are consistent with concentrations measured in samples collected prior l
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 l
period.
The average Sr-90 concentration reported from indicator stations in 1994 was 5.31 pC1/ liter. An average of 3.54 pC1/ liter was identified in I
samples from control stations.
By far the predominant isotope reported in I
milk samples was the naturally occurring K-40.
An average of approximately 1300 pCi/ liter of K-40 was identified in all milk samples.
1 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.
l Samples of feed and water supplied to the animals were analyzed in 1979 in an l
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.
i This phenomenon was observed during the preoperational radiological monitoring i
l j l
l
B l
near SQN and near the Bellefonte Nuclear Plant construction site at farms l
where only one or two cows were being milked for private consumption of the milk.
It is postulated that the feeding practices of these small farms differ L
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-6) were similar to those reported for milk. All I-131 values were less than the nominal LLD.
Strontium-90 was identified in five samples at concentrations ranging from 12.5 to 63.5 pC1/Kg.
These concentrations are consistent with levels in vegetation from nuclear weapons fallout. Again, the largest concentrations identified were for the naturally occurring isotopes K-40 and Be-7.
l The only fission or activation product identified in soil samples was Cs-137.
The maximum concentration of Cs-137 was 0.55 pCi/g. This value is consistent with levels previously reported from fallout. All other radionuclides i
reported were naturally occurring isotopes (Table H-7).
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 i
in the atmosphere, the 30-year half-life of Cs-137 and transport through the
{
I environment. _
B I-All radionuclides reported in food samples were naturally occurring. The maximum K-40 value was 2970 pC1/kg in potatoes. Analysis of these samples indicated no contribution from plant activities.
The results are reported in o
Tables H-8 through H-13.
P r
u T
I A00ATIC HONITORING I
Potential exposures from the liquid pathway can occur from drinking water, ingestion of edible fish and clams, or from direct radiation exposure from l
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, A;1atic clams, and bottom and shoreline sediment.
Samples from the reservoir are collected both upstream l
and downstream from the plant.
i Results from the analysis of aquatic samples are presented in Tables H-14 I
through H-23.
Radioactivity levels in water, fish, and clams were consistent with background and/or fallout levels previously reported.
The presence of l
l Co-58, Co-60, 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.
4 l
Samples are also collected by an automatic sampling pump at the first downstream drinking water intake. These samples are collected in the same manner as the surface water samples. These monthly samples are analyzed by gamma spectroscopy and for gross beta activity. At other selected locations,
[
grab samples are collected from drinking water systems which use the Tennessee River as their source. These samples are analyzed every 4 weeks by gamma spectroscopy and for gross beta activity. A quarterly composite sample from each station is analyzed for Sr-89,90 and tritium.
In addition, samples from two of the stations are analyzed for I-131 content.
f The sample collected by the automatic pumping device is taken directly from the river at the intake structure. Since the sample at this point is raw water, not water processed through the water treatment plant, the control sample should also be unprocessed water.
Therefore, the upstream surface
)
water sample is also considered as a control sample for drinking water.
Groundwater is sampled from an onsite well and from a private well in an area unaffected by SQN.
The samples are composited by location quarterly and analyzed by gamma spectroscopy and for gross beta activity and for strontium and tritium content.
Samples of commercial and game fish species are collected semiannually from each of three reservoirs:
the reservoir on which the plant is located (Chickamauga Reservoir), the upstream reservoir (Watts Bar Reservoir), and the downstream reservoir (Nickajack Reservoir).
The samples are collected using a l
l combination of netting techniques and electroffshing. Most of the fish are filleted, but one group is processed whole for analysis. After drying and grinding, the samples are analyzed by gamma spectroscopy.In addition, whole commercial fish species are analyzed for Sr-89 and Sr-90 as a part of commitments in the HBN monitoring program.
l 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 semiannually 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 sepirated 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 2.7_pC1/11ter while the upstream samples averaged 2.7 pC1/ liter. 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 1994 is presented in Figure H-6.
A summary table of the results is shown in Table H-14. I
No fission or activation product were identified in drinking water samples.
Average gross beta activity was 2.5 pC1/11ter at the downstream stations and 2.7 pC1/ liter at the control stations. The results are shown in Table H-15 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 identified in these samples. Gross beta concentrations in samples from the onsite well were all below the lower limit of detection, while the average from the offsite well was 6.4 pCi/ liter. The results are presented in Table H-16.
Cesium-137 was identified in six fish samples. The downstream samples contained a maximum of 0.09 pC1/g, while the upstream sample had a maximum of 0.10 pC1/g. Other radioisotopes found in fish were naturally occurring with the most notable being K-40.
The concentrations of K-40 ranged from 4.6 pC1/g to 20.2 pC1/g.
Sr-90 concentrations in whole commercial species averaged 0.09 pC1/g in downstream samples and 0.12 pCl/g in samples collected upstream. The positive identification of Sr-89 in environmental media at levels near the LLD is typically a result of artifacts in the calculational process and the low concentrations the laboratory is attempting to detect and is not an indication l
of the presence of Sr-89 in the environment. The results are summarized in Tables H-17 H-18 H-19, and H-20.
Plots of the annual Cs-137 concentrations 1 l
)
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 f.
1 I
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. In bottom sediment samples the average levels of Cs-137 7
were 0.59 pC1/g in downstream samples and 0.58 pCi/g upstream.
In shoreline l
sediment, Cs-137 levels averaged 0.05 pC1/g in downstream samples and were I
below the LLD in upstream samples. These values are consistent with
)
previously identified fallout levels; therefore, they are probably not a l
result of SON operations.
)
In bottom sediment, Co-60 concentrations in downstream samples averaged 0.11 pC1/g, while levels upstream were below the LLD.
The maximum concentration in downstream samples was 0.21 pC1/g. Co-60 was not identified in shoreline sediment samples.
Cs-134 was identified in one downstream stream sediment sample at a concentration of 0.05 pC1/g. Co-58 was identified in one downstream sample at l
a concentration of 0.15 pC1/g. A realistic assessment of the impact to the general public from this activity produces a negligible dose equivalent.
I Results from the analysis of bottom sediment samples are shown in Table H-21.
) E-_--_-----_---____-----_---_-_---_---------_--------_---------_-------_________--
l Co-58, Co-60, and Cs-134 were not identified in shoreline sediment. 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-22.
[
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 1
Only naturally occurring radioisotopes were identified in clam flesh samples.
The results from the analysis of these samples are presented in Table H-23.
i 4 i
l l
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 ways 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 drinking water from the Tennessee River, eating fish caught in the sources:
Tennessee River, and direct exposure to radioactive material due to activities on the banks of the river (recreational activities). Data used to determine these doses are based on guidance given by the NRC for maximum ingestion rates, exposure times, and distribution of the material in the river.
Whenever possible, data used in the dose calculation are based on specific conditions for the SQN area.
For gaseous effluents, the public can be exposed to radiation from several direct radiation from the radioactivity in the air, direct radiation sources:
I i
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 f
radioactivity in the air and the soil are estimated by computer models which l
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 from SQN in 1994 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 The comparison between the calculated dose and the corresponding limit.
maximum calculated whole body dose equivalent from measured liquid effluents
)
I The I
as presented in Table 2 is 0.023 mrem / year, or 0.8 percent of the limit.
This maximum organ dose equivalent from gaseous effluents is 0.025 mrem / year.
J represents 0.17 percent of the ODCM limit. A more complete description of the i
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 The negligible when compared to the dose from natural background radiation.
results from each environmental sample are compared with the concentrations I
from the corresponding control stations and appropriate.,
preoperational and background data to determine influences from the plant.
During this report period, Co-60, Co-55, Cs-134, and Cs-137 were seen in aquatic media. Cs-137 in sediment is censistent with fallout levels identified in samples both upstream and downstream from the plant. Co-60, Co-58, and Cs-134 were identified in sediment samples downstream from the plant in concentrations which would produce no measurable increase in the dose to the qeneral public.
No increases of radioactivity attributable to SQN have been sein 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, all'., food products, drinking water, and fish.
Inhalation and ingestion doses f
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 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.
i s l
B l'
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.
l....
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, W. G., Campbell, J.
E., Fooks, J. II., Mitchell, H.
C.,
and Eller, C.
H., Farming Practices and Concentrations of Emission Products in Milk, U.S. Department of Health, Education, and Welfare; Public Health Service Publication No. 999-R-6, May 1964.
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E Table 2 i
Maximum Dose due to Radioactive Effluer.t Releases Sequoyah Nuclear Plant 1994 mrem / year j
1 Liquid Effluents 1994 ODCM Percent of EPA Percent of Tyge Dose Limit ODCM Limit Limit EPA Limit Total Body 0.023 3
0.8 25 0.09 Any Organ 0.027 10 0.3 25 0.11 Gaseous Effluents 1994 ODCM Percent of EPA Percent of Typ.e, Dose Limit ODCM Limit Limit EPA Limit Noble Gas 0.014 10 0.14 25 0.06 (Gamma)
Noble Gas.
0.035 20 0.18 25 0.14 (Beta)
Any Organ 0.025 15 0.17 25 0.10
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APPENDIX A f
ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM AND SAMPLING LOCATIONS
---g g-g g
g--g-i Table A-l SEQUOYAH NUCLEAR PLANT Environmental Radiological Nonitoring Program *
(
Exposure Pathway Number of Samples and Sampling and Type and Frequency l
.and/or Samole Locations
- Collection Freauency of Analvsis 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 (LW2, LS3 per 7 days (more frequently radioactivity greater than LM-4, and LW 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 (PS2, 3, 8 and 9) is greater than 10 times yearly mean of control 4 samples from control samples. Composite at I
locations greater than 10 least once per 31 days C
miles from the plant (R&l, (by location) f or gama e
RS2, RW3, and R&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 lea-t once per 7 days c.
Soil Samples from same locations Once per year Gama scan, Sr-89, Sr-90 as air particulates once per year d.
Rainwater Same locations as air Composite sample at least Analyzed for gaeuna nuclides particulates once per 31 days only if radioactivity in other media indicates the presence of increased levels of fallout
Table A-1 l
SEQUOYAH NUCLEAR PLANT Environmental Radiological Monitoring Program
- l l
l l
l Exposure Pathway Number of Samples and Sampling ano Type and Frequency l
and/or Sagle__
tocationf Collection Frtaugnu of Analysis i
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 iy 3.
WATERBORNE e
a.
Surface Water TRM 497.0*
Collected by automatic Gross beta and gama scan on TRM 483.4 sequential-type sampler' with each composite sample.
IRM 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 at least once per 92 days f
f I sample from ground water At least once per 92 days Gross beta, gamma scan, Sr-89, source upgradient (Farm HW)
Sr-90 and tritium at least once per 92 days
t
. m W
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.FU UW Table A-1 SEQUOYAH NUCLEAR ptANT Environmental Radiological Monitoring Program" Exposure Pathway Number of Samples and Sampling and Type and Frequency and/or Samole locations
- Collection Freauency of Analvsis 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
1 sample at the next 2 downstream Grab sample once per 31 days potable surface water suppliers (greater than 10 miles downstream)
(TRM 470.5 and TRM 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 of less than or equal to i$
31 days e
d.
Sediment TRM 4%.5 At least once per 184 days Gamma scan of each sample TRM 483.4 TRM 480.8
-TRM 472.8 e.
Shoreline TRM 485 At least once per 184 days Gamma scan of each sample Sediment TRM 478 TRM 477 G
._.--_c,_w_._
m.
-___.o_
u_______-____._______._
r m
m m
m O
y
-}
p
~- g q'q i
Table A-1 l
I SEQUOYAH NUCLEAR PLANT I
Environmental Radiological Honitoring Program
- i Exposure Pathway Number of Samples aM Sampling and Type and Frequency and/or Samole Locations
- Collection Freauency of Analysis 4.
INGE$ TION a.
Hilk 1 sample from milk producing At least once per 15 days Gassna isotopic and I-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 I
in milk f rom other sectors or by I
sampling vegetation where milk is not available.
s I
At least one sample from control location (Farm S.
C and/or 8) b.
Fish 1 sample each from Nickajack, At least once per 184 days.
Gaevna scan on edible portion Chickamauga and Watts Bar One sample of each of the l
Reservoirs following species:
Channel Catfish Crappie Smallmouth E ~ralo i
c.
Invertebrates 2 samples downstream from At least once per 184 days Gamma scan on edible portion i
(Asiatic Clams) the discharge 1 sample upstream from the plant (No permanent stations established; j
l depends on location of clams) i
'm pm m
m W EM M M
M M
M
'm" ' W W ~ mR Table A-1 SEQUOYAH NUCLEAR PLANT Environmental Radiological Monitoring Program" Esposure Pathway Number of Samples and Sampling and Type and Frequency
_and/or Samole Locations
- Collection Freauency of Analysis 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 f arms 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
One sample of each of the f) same foods grown at greater e
than 10 miles distance from the plant e.
Vegetation Samples from farms producing milk At least once per 31 days 1-131 and gamma scan at least but not previding a milk sample.
once per 31 days. Sr-89 and (Farm EM)
Sr-90 analysis at least once per 92 days.
Control sample from one control dairy (Farm :i The sampling program outilned in this table is that which was in ef fect at the end of 1993.
a.
b.
Sampling locations, sector and distance from plant, are described in Table A-2 and A-3 and shown in Fi gures A-1, A-2, and A-3.
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 />.
c.
d.
The surf ace water control sample shall be considered a control for the drinking water semple.
I l
1 a
I Table A-2 SEQUOYAH NUCLEAR PLANT Environmental Radiological Monitoring Program Sampling Locations Map Approximate Indicator (I)
I Location Distance or Samples Number" Station Sector (miles)
Control (C)
Collected" 2
LM-2 N
0.8 I
LM-3 SSH 2.0 I
LM-4 NE 1.5 I
PM-2 SH 3.8 I
PM-3 H
5.6 I
PM-8 SSH 8.7 I
10 PM-9 HSH 2.6 I
13 RM-3 ESE 11.3 C
M 16 Farm C NE 16.0 C
M 17 Farm S NNE 12.0 C
M,V 18 Farm J HNH 1.1 I
M 19 Farm HH NH 1.2 I
M,W*
I 20 Farm EM N
2.6 I
V 24 Hell No. 6 NNE 0.15 I
H 31 TRM 473.0 11.5' I
PH I
(C.F. Industries) 32 TRM 470.5 14.0' I
PH (E.I. DuPont) 33 TRM 465.3 19.2' I
PH I
(Chattanooga) 34 TRM 497.0 12.5" C
SH' 35 TRM 503.8 19.3' C
PH I
(Dayton) 36 TRM 496.5 12.0' C
SS I
38 TRM 483.4 1.l*
SH 42 TRM 472.8 11.7' I
SS Table A-2 l
SEQUOYAH NUCLEAR PLANT Environmental Radiological Monitoring Program Sampling Locations (Continued)
. Map Approximate Indicator (I)
Location Distance or Samples Number" Station Sector (elles)
Control (C)
Collected" h
45 TRM 425-471 I
F
{-
(Nickajack Reservoir) 46 TRM 471-530 I/C F CL r
(Chickamauga u
Lf Reservoir) 47 TRM 530-602 C
F (Watts Bar
(
Reservoir) 48 Farm H NE 5.3 I
M a.
See figures A-1, A-2, and A-3 h
b.
Sample Codes AP - Air particulate filter
[.
CF - Charcoal filter CL - Clams F - Fish r
M - Milk L
PW - Public water R - Rainwater S - Soll SD - Sediment SS - Shoreline sediment 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. E
I k
Table A-3 L
SEQUOYAH NUCLEAR PLANT Thermoluminescent Dosimeter (TLD) Locations Approximate Onsite (On)*
Map Distance or Location Number Station Sector (Miles)
Offsite (Off) 3 SSW-1C SSW 2.0 On 4
NE-1A NE 1.5 On 5
NNE-1 NNE 1.8 On 7
SW-2 SW 3.8 Off 8
W-3 W
5.6 Off 9
SSN-3 SSW 8.7 Off 10 WSW-2A WSW 2.6 Off 11 SW-3 SW 16.7 Off 12 NNE-4 NNE 17.8 Off 13 ESE-3 ESE 11.3 Off 14 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 0.6 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
. [
Table A-3 SEQUOYAH NUCLEAR PLANT 4
Thermoluminescent Dosimeter (TLD) Locations I
Approximate Onsite (On)*
Map Distance or Location Number Station Sector (Miles)
Offsite (Off) 78 WSW-3 WSW 5.7 Off 79 WSW-4 WSW 7.8 Off 80 WSW-5 WSW 10.1 Off 81 W-1 W
0.8 On 82 W-2 W
4.3 Off I
83 WNW-1 WNW 0.4 On 84 WNH-2 WNW 5.3 Off 85 NH-1 NW 0.4 On 86 NH-2 NW 5.2 Off I
87 NNW-1 NNW 0.6 On 88 NNH-2 NNW 1.7 On 89 NNW-3 NNW 5.3 Off I
90 SSN-1B SSW l.5 On I
I I
I l
a.
TLDs designated onsite are those located 2 miles or less from the plant.
TLDs designated offsite are those located more than 2 miles from the plant.
. I.
l
I t
Figure A-1 E
Environmental Radiological Sampling Locations Within 1 Mile of Plant I
E N
11.2s 248.7s NNW NNE 33.7s l
s 28.2 s 2
NE NW g
4 se.2 s
/
303.7s ENE WNW 3
g
/
y'
/
78.7s N
281.2s 1/
-e g,.;
,,p maqn E
'vIis j,31 I
81 l
2sa.7s p
64 i
76 g
- /.
ESE
/
WSW
,/
\\
t 75
,,3,7 3
- e # s4*
4,p I
238.2s J
9 I
SW O a#
s SE 14e.2 s 21 s.7 s l
1 e 8.7 s 191.2s g
I scale O
Mile 1 E l
I Figure A-2 I
Environmental Radiological Sampling Locations I
From 1 to 5 Miles From the Plant I
34a.75 N
11.25 NNW NNE I
33.75 326.25 I
NW NE 303.75 20 56 5
ENE WNW 55 8
I 281.25 estpe?
78.75 82 1
b6 W-1 I
~
59 2
10 101.25 8
66 258.75 77 I
9 71 69 63
/
ESE WSW 3
7 236.25 9'
'46
)
e70 I
191.25 S
16s.75 SCALE O
1 2
MILES I
-2 I
Figure A-3 l
Environmental Radiological Sampling Locations I
I Greater Than 5 Miles From the Plant
{
l 348.75
?A 11.25 cnossviLE g
33.75 f
326.25 I
o t
McMINNVILLE 15 56.25 303.75 swerT A n p
L 12 Se THEN 16 78.75 281.25 OwAN 3'4 2
S.
48 l
E
%N.
.8-VELAND
(
s('WANgg 68 3
,2
,n, yy 258.75 s
i L
?
CHATTANOOGA
'"'088
- T j
i set 123.75 326.25 d
LAFAYETTE
/
as sw 213.75 146.25 saw see 191.25 168.75 s
BCALE O
6 19
\\b 20 as.
[
1
L E
F L
E L
E L
APPENDIX B c
L 1994 PROGRAM MODIFICATIONS
(
1
(;
i I
L
[-
Appendix B L.-
h:
Environmental Radiological Monitoring Program Modification P
L.
f During 1994, no modifications were made in the environmental monitoring q..
- program, o
L' E
[-
[
[
[
[
{
, {
E
b L
m
]
{
APPENDIX C PROGRAM DEVIATIONS 1
b E
[
[
[
[
{
{.
l l
Appendix C ProJram Deviations During the 1994 sampling period, approximately eighteen of the scheduled samples were not collected. All scheduled analyses were not completed on four 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.
Eleven milk samples were not collected because of the unavailability of milk; three clam samples were not collected because of scarcity of clams; f
one air filter sample was not collected because of equipment malfunction and one was missed as a result of flooding; one water sample contained insufficient volume for iodine analysis; two water samples were not collected as a result of equipment malfunctions and the iodine fractions of two samples were lost during analysis.
Equipment malfunctions were f
corrected as quickly as possible so that subsequent samples could be collected as scheduled.
The missed samples and analyses are listed in the following table.
i N
L Table C-1 r
SEQUOYAH NUCLEAR PLANT Environmental Radiological Monitoring Program Exceptions Date Station Location Remarks 1/4/94 TRM 483.4 1.1 miles One surface water sample was not downstream collected because of a leaking valve.
The valve was replaced and subsequent samples collected.
1/5/94 &
Farm C 16.0 miles NE Milk had already been picked up by 2/2/94 the processor and there was no milk available for these two samples.
Both samples were scheduled for strontium analysis.
This is one of three control stations.
f 1/25/94 &
TRM 473.0 11.5 miles The fractions of two drinking 1
downstream water samples being analyzed for
[
I-131 were lost during analysis.
1/24/94 TRM 503.8 19.3 miles All other analyses were performed upstream on these samples.
2/16/94 Farm S 12 miles NNE Milk had already been picked up by 4/27/94 the processor and there was no milk 6/8/94 available for these five samples.
10/25/94 Two of the samples were scheduled 12/7/94 for strontium analysis.
This is one of three control stations.
3/15/94 TRM 503.8 19.3 miles The drinking water sample contained upstream insufficient volume of water for performing an analysis for I-131.
All other analyses were performed.
3/29/94 LM-2 0.8 miles N Air particulate and charcoal filter samples were not collected because the station was inaccessible due to flooding. Subsequent samples were collected as scheduled. - _ _
I Table C-1 SEQUOYAH NUCLEAR PLANT Environmental Radiological Monitoring Program Exceptions I
Date Station Location Remarks 5/4/94 &
Chickamauga SQN area Three clam samples not collected:
10/4/94 Reservoir scarcity of clams made them difficult to locate in sufficient I
quantities.
6/6/94 TRM-483.4 1.1 miles The surface water samples was I
not collected because of a blown fuse.
The fuse was replaced and subsequent samples collected.
7/5/94 Farm J 1.1 miles HNH The milk sample was spoiled, consequently the milk would not pass through the ion exchange I
column for the I-131 analysis.
All other analyses were performed.
I 9/6/94 PM-2 3.8 miles SH Air particulate and charcoal filter samples were not collected as a result of a malfunction in the sampling equipment.
The I
problem was repaired and all other samples were collected.
11/7/94 &
Farm J 1.1 miles HNH Two milk samples were not 11/21/94 collected because the cow was dry.
Sampling resumed on 12/5/94.
11/21/94 Farm H 5.3 miles NE Milk had already been picked up by the processor and there was no I
milk available for a sample.
Subsequent samples were collected as scheduled.
I --
I:
l lI lI I
1 E
1 I-1 APPENDIX D 1
ANALYTICAL PROCEDURES l
l i
)
I l
1 E
! ]
4 J
I L
APPENDIX D 4R Analytical Procedures Analyses of environmental samples are performed by the radioanalytical
,I 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 technigt'es and methodology follows.
I 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 planchet.
I 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.
I -
f
lf 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 i
concentrations can be determined.
Water samples are analyzed for tritium content by first distilling a portion of the sample and then counting by 11guld 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 HYPERHET.
The charcoal cartridges used to sample gaseous radiolodine were analyzed by gamma spectroscopy using a germanium detector.
All of the necessary efficiency values, weight-efficiency curves, and geometry tables are established and maintained on each detector and counting system. A series of daily and periodic quality control checks are performed to monitor counting instrumentation.
System logbooks and control charts are used to document the results of the quality control checks.
t
4 P
L
)
APPENDIX E l
NOMINAL LOWER LIMITS OF DETECTION (LLD) l 1
I Appendix E Nominal Lower Limits of Detection Sensitive radiation detection devices can give a signal or reading even when no radioactivity is present in a sample being analyzed.
This signal may come from trace amounts of radioactivity in the components of the device, from cosmic rays, from naturally Occurring radon gas, or from 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 readingLabove the critical level, additional statistical analysis of the background readings is required. The hypothetical activity calculated from this analysis is called the lower limit of detection (LLD). A listing of typical LLD values that a laboratory publishes is a guide to the sensitivity of the analytical measurements performed by the laboratory. _ _ _
L l
F 1
L f
Every time an activity is calculated from a sample, the background must L
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 LLD to determine if there is really activity present or if the number is an artifact of the way radioactivity is measured.
A number of factors influence the LLD, including sample size, count time, counting efficiency, chemical processes, radioactive decay factors, and interfering isotopes encountered in the sample. The most likely values for these factors have been evaluated for the various analyses performed in the environmental monitoring program.
The nominal LLDs calculated from these values, in accordance with the methodology prescribed in the 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 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 l
if a measured activity is greater than the LLD. - _ - _ - - - _ _
1I lll
)vr tld ni eoa eS/
l i
ddC 64 eno Saf 10 no i) ttae t w e
ga ek V/
i 000 tCeo 612 Wf 31 i
s v
e r
r d
u h
d sa se i/
ec Fi 93 uo C
00 l r o
aP
(
00 1
V l
E Da t c 1
e Lt L
l e
k/
b l e li a
ah iC 400 T
nc Mo i o i
022 mi od NaR 1
A rL e/
9 400 ti aC 10052 Wo 0
f 3
s,
re _
tl liim 14 F/
2 10 i
0 00 rC 0
00 io AI 0
00 90 89 a
1 - -
t 3mm e
1 uu Bm ii uett si n n n sti oo oidrr-rrott GTISS.
Table E-1 Nominal LLD Values B.
Gamma Analyses (GeLI)
Fish.
Air Charcoal Water Vegetation Wet Soil and Foods. Tomatoes Heat and Particulates Filters and Milk and Grain Vegetation Sediment Clam Flesh Potatoes, etc.
Poultry 2
oCi/m3 oCi/m oCi/L oC1/a. drv nCi/ka. wet oCi/a drv oCl/a. drv oCl/ko. wet nCi/ko. wei Ce-141 0.005
.02 10
.07 35
.10
.35 20 15 Ce-144
.01
.07 30
.15 115
.20
.85 60 50 Cr-51'
.02
.15 45
.30 200
.35 2.40 95 75 I-131
.005
.03 10
.20 60
.25 1.70 20 25 Ru-103
.005
.02 5
.03 25
.03
.25 25 15 l
Ru-106
.02
.12 40
.15 190
.20 1.25 190 60
{
Cs-134
.005
.02 5
.03 30
.03
.14 10 10 l
.005
.02 5
.03 25
.03
.15 10 10 Zr-95
.005
.03 10
.05 45
.05
.45 45 20 Nb-95
.005
.02 5
.25 30
.035
.25 10 10 M
Co-58
.005
.02 5
.03 20
.03
.25 10 10 02 Mn-54
.005
.02 5
.03 20
.03
.20 10 10 Zn-65
.005
.03 10
.05 45
.05
.40 45 20 Co-60
.005
.02 5
.03 20
.03
.20 10 10 K-40
.04
.30 100
.40 400
.75 3.50 250 200 Ba-140 0.015
.07 25
.30 130
.30 2.40 50 50 La-140 0.01
.04 10
.20 50
.20 1.40 25 30
{
i Fe-59
.005
.04 10
.08 40
.05
.45 25 20 Be-7
.02
.15 45
.25 200
.25 1.90 90 70 Pb-212
.005
.03 15
.04 40
.10
.30 40 20 t
Pb-214
.005
.07 20
.50 80
.15
.10 80 40
{
Bi-214
.005
.05 20
.10 55
.15
.50 40 25 j
Bi-212
.02
.20 50
.25 250
.45 2.00 130 90 1
T1-208
.002
.02 10
.03 30
.06
.25 30 30 Ra-224
.75 3.00 Ra-226
.15
.50 P
3m 50 3'.
0 8
4 40 4
35.b0 25 20 l
1 i
m
I I
Table E-2 Maximum Values for the Lower Limits of Detection (LLD) i Specified by the SQN Offsite Dose Calculation Manual Airb;:ne Particd ate Food Hater or Gases cish Hilk Products Sediment
- I l
Analysis DC1/L DC1/m,__
DC1/Ka.wot pC1/L pci/ko. wet pC1/KQ. dry gross beta 4
1 x 10-8 N.A.
N.A.
N.A.
N.A.
!I 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.
I 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.
I-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.
I If no drinking water pathway exists, a value of 3000pC1/L may be used.
If no drinking water pathway exists, a value of 15 pC1/L may be used.
t I
I I
l
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r k
(
APPENDIX F QUALITY ASSURANCE / QUALITY CONTROL PROGRAM i
1 4
i
E.
Appendix F y
Quality Assurance / Quality Control Program A thorough. quality assurance program is employed by the laboratory to ensure that the environmental monitoring data are reliable.
This program includes the use of written, approved procedures in performing the work, a.nonconformance and corrective action tracking system, systematic l
internal audits, a complete training and retraining system, audits by various external organizations, and a laboratory quality control program.
The quality control program employed by the radioanalytical laboratory is designed to ensure that the sampling and analysis process is working as intended. The program includes equipment checks and the analysis of
(
special samples along with routine samples.
Radiation detection devices are complex and can be tested in a number of There are two primary tests which are performed on all devices.
ways.
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 l
trace amounts.of radioactivity in the materials used to construct the j
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 <
I I
radioactive standard should be very reproducible.
These reproducibility checks are also monitored to ensure that they are neither higher nor 1
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.
V' 1
In addition to these two general checks, other quality control checks are
{
l performed on the variety of detectors used in the laboratory. The exact nature of these checks depends on the type of device and the method it uses to detect radiation or store the information obtained.
Quality control samples of a variety of types are used by the laboratory to verify the performance of different portions of the analytical process. These quality control samples may b'e 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 j
which schedules the collection of the routine samples.
For example, if the routine program calls for four milk samples every week, on a random
(
basis each farm might provide an additional sample several times a year. I
I 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 E
identical portions of material are analyzed side by side.
I Analytical knowns are another category of quality control sample.
A known amount of radioactivity is added to a sample medium by the quality control staff or by the analysts themselves.
The analysts are told the radioactive content of the sample. Whenever possible, the analytical knowns contain the same amount of radioactivity each time they are run.
(
In this way, the analysts have immediate knowledge of the quality of the measurement process. A portion of these samples are also blanks.
Blind spikes are samples containing radioactivity which are introduced into the analysis process disguised as ordinary environmental samples.
The analyst does not know they contain radioactivity. Since the bulk of
~
the ordinary workload of the environmental laboratory contains no I
measurable attivity or only naturally occurring radioisotopes, blind spikes can be used to test the detection capability of the icboratory 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 p'
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 aware they are being tested. Such samples test the best performance of I
the laboratory by determining if the analysts can find the "right answer." These samples provide information about the accuracy of the I
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
( L
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
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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 and Figure F-1.
For 1994, all but one EPA cross-check sample concentrations measured by TVA's laboratory were within 2 3-sigma of the EPA reported values.
TVA splits certain environmental samples with laboratories operated by i
the States of Alabama and Tennessee and the EPA Eastern Environmental Radiation Facility in Montgomery, Alabama.
When radioactivity has been present in the environment in measurable quantitles, such as following atmospheric nuclear weapons testing, following the Chernobyl incident, or as naturally occurring radionuclides, the split samples have provided TVA with yet another level of information about laboratory performance. ___
These samples demonstrate performance on actual environmental sample
)
matrices rather than on the constructed matrices used in cross-check 9
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programs.
[
All the quality control data are routinely collected, examined, and reported to laboratory supervisory personnel. They are checked for trends, problem areas, or other indications that a portion of the analytical process needs correction or improvement. The end result is a measurement process that provides reliable and verifiable data and is sensitive enough to measure the presence of radioactivity far below the levels which could be harmful to humans.
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M M
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Table F-1 RESULTS OBTAINED IN INTERLABORATORY COMPARISON PROGRAH A.
Air Filter (pCl/ Filter)
Gross Aloha Gross Beta S t ron ti um-90 Cesium-137 EPA Value TVA EPA Value TVA EPA Value TVA EPA Value TVA
[ late fr3 sioman Arg.
I 3 slamal Arg.
f23 siomal Ar.g.
f 3 siomal Arg.
8/94 35t46 31 56 17 58 2029 18 1529 15 B.
Radiochemical Analysis of Water (pCi/L)
__Grnis Beta Jtrontity -89
_ Strontium-90 Tritium Indine-131 Plutonium-239 EPA Value TVA EPA Valur TVA EPA Value TVA EPA Value TVA EPA Value TVA EPA Value TVA Date (13 siomal Arg.
[23 sigral Arg.
Im3 stomal arg.
f13 stomal Arg.
(23 sigmal arg.
fr3 siomal arg.
8 1/94 62217 66 2529 21 1529 15 d
2/94 119:21 121 1
3/94 49362856 4874 26:5 27 4/94*
20 9 19 1429 14 7/94 10s 9 2d*
3029 28 2029 18 104 8/94 9951:1723 9501 10/94*
2529 22 1529 15 10/94 23: 9 20 79214 74
1 o
M M-M-M M
WM M
M M
Table F-1 RESULTS OBTAINED IN INTERLABORATORY COMPARISON PROGRAM (Continued)
C.
Gama-Spectral Analysis of Water (pC1/L)
Barium-133 Cobalt-60 Zinc-65 Ruthentue-106_
Cesium-134 Cesiuo-137 l
EPA Value TVA EPA Value TVA EPA Value TVA EPA Value TVA EPA Value TVA EPA Value TVA DAlg fi3 simal Arg. f 3 slamal Arg. f 3 si nal arg. f 3 slamal Arg, f 23 simal Arg. f 3 siamal arg.
4/94*
2029 20 3429 33 2929 30 6/94 98217 89 5029 50 134223 134 252 43 227 40s9 36 49t9 52 10/94*
4039 39 2029 20 3929 41 11/94 73 12 73 5929 58 100:17 100 24 9 22 4929 51 D.
Hilk (pCl/L)
_itrontium-89 Strontium-90__
Iodine-131 Cesium-137 Potassium-40*_
EPA Value TVA EPA Value TVA EPA Value TVA EPA Value TVA EPA Value TVA h
Qaig im3 sianal Arg. fm3 siamal Arg, im3 si mal Arg. Im3 slamal Arg. Im3 slamal Arg.
9/94 2529 26 1529 17 75:14 80 5929 63 1715:149 1713 a.
Performance Evaluation Intercomparison Study.
b.
The Grand Average of non-outlier participants indicates that the Performance Evaluation Standard had a postative bias for Gross Beta. If the Grand Average of 14.91 pCl/ liter were used for the known. TVA's results would be 1.65 sigma from the known.
c.
Units are milligrams of total potassium per liter rather than picocuries of K-40 per liter.
M M FM W
WM M
M M
Chn M
M M
M EPA Crosscheck Summary for 1994 EPA Crosscheck Summary for 1994 gamma spectroscopy methods analytical chemistry methods (found -given)/ EPA Sigma (found - given) / EPA sigma
-2
-1 0
1 2
-2 0
2 4
l air filter Cs-137 air filter Gross Alpha milk Cs-137 -
air filter Gross Eeta milk M31 air filter Sr40 milk Total K milk Sr49 water Co40 milk Sr40 water Cs-134 water Sr49 water hs-137 ~
water Sr40 water Ba-133 water Grose Beta
)
water Co40 trater I-131
'D water Cs-134 weiter H-3 water Cs-137.
water Pu-23 water Ru-106 water Sr49 water Zn45 water Sr40 water Co40 water Sr49 water Cs-134 water Sr40 l
water Cs-137 water Gross Beta water Ba-133 water H4 water Co40 water M31 water Cs 134 water Sr49 water ca.137 :
water Sr40 water Zn45 water Gross Beta
~
l I
Laboratory objective: abs [(found - given)lEPA sigma } < 3
I ji EI
- I I
APPENDIX G I
LAND USE SURVEY I
k k
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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 1 using appropriate techniques such as door-to-door survey, mail survey, telephone survey, aerial survey, or information from local agricultural authorities or other reliable sources.
In order to identify the locations around SQN which have the greatest relative potential for 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 arm equivalent to the design basis source terms.
The calculat9d doses are relative in nature and do not reflect actual exposures recete d 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 2). - - - - -
I In response to the 1994 SQN land use survey, annual doses were calculated for air submersion, vegetable ingestion, and milk ingestion.
External doses due to radioactivity in air (air submersion) are calculated for the nearest resident in each sector, while doses from drinking milk or eating foods produced near the plant are calculated for the areas with milk producing animals and gardens, respectively.
I Air submersion doses were calculated for the same locations as in 1993, with the resulting values almost identical to those calculated in 1993.
Doses calculated for ingestion of home-grown foods and milk also were similar to those calculated in 1993.
I for milk ingestion, projected doses were consistent with those calculated in 1993.
Samples are being taken from the three farms with the highest projected doses and the highest X/Q values.
I Tables G-1 G-2, and G-3 show the comparative relative calculated doses for 1993 and 1994.
I I
I I
Table G-1 SEQUOYAH NUCLEAR PLANT Relative Projected Annual Air Submersion Dose to the Nearest Resident I
Within Five Miles of Plant (mrem / year / unit)
I 1993 Survey 1994 Survey Approximate Approximate I
Sector Distance (Miles)
Annual Dose Distance (Miles)
Annual Dose N
0.8 0.13 0.8 0.13 I
NNE 1.5 0.07 1.5 0.07 NE 1.5 0.07 1.5 0.07 ENE 1.3 0.03 1.3 0.03 E
1.0 0.02 1.0 0.02 I
ESE 1.0 0.03 1.0 0.03 SE 1.0 0.03 1.0 0.03 SSE 1.3 0.03 1.3 0.03 I
S 1.4 0.05 1.4 0.05 SSW 1.3 0.14 1.3 0.14 SW 1.4 0.06 1.4 0.06 WSW 0.7 0.08 0.7 0.08 I
W 0.6 0.07 0.6 0.07 WNW 1.1 0.02 1.1 0.02 NW 0.8 0.04 0.8 0.04 I
NNW 0.5 0.13 0.5 0.13 I
I I
l I
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Table G-2 I
l SEQUOYAH NUCLEAR PLANT lI Relative Projected Annual Dose to Child's Critical Organ from Ingestion of Home-Grown Foods L
(mrem / year / unit)
E 1993 Survey 1994 Survey p
Approximate Annual Dose Approximate Annual Dose L
Sector Distance (Miles)
(Bone)
Distance (Miles)
(Bone)
N 1.1 2.41 1.1 2.41 NNE 1.6 1.97 1.6 1.97 NE 2.5 0.99 2.7 0.89 ENE 1.6 0.77 1.6 0.77 E
3.1 0.17 3.1 0.17 ESE 1.0 0.80 1.3 0.57 SE 1.1 0.86 1.1 0.86 SSE 1.3 1.04 1.3 1.04
[
S 1.4 1.76 1.4 1.76 SSW l.7 3.23 1.7 3.23 SW 2.1 1.11 2.1 1.11
[
WSW 1.0 1.49 1.0 1.49 W
l.2 0.87 1.2 0.87 WNW l.1 0.73 1.1 0.73 NW 0.9 1.09 0.9 1.09 NNW 0.5 3.94 0.5 3.94 i
l l
1 c
e Table G-3
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1 SEQUOYAH NU: LEAR PLANT s
Relative Projected Annual Dose to Receptor Thyroid from Ingestion of Milk (mrem / year / unit) r Approximate Distance Annual Dose X/Q Location Sector (Miles)*
1993 1994 s/m' t
. Farm H***
NE 4.7 0.022 0.026 3.33 x 10-'
Farm HS*
E 4.6 0.004 0.005 7.94 x 10-*
Farm JH*
ESE 3.9 0.005 0.006 9.97'x 10-*
Farm J' HNH 1.3 0.024 0.024 4.72 x 10-'
Farm HW NH 1.3 0.029 0.029 5.19 x 10-'
8 j
i
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a.
Distances measured to nearest property line.
b.
Vegetation sampled at this location.
c.
Grade A dairy d.
Milk sampled at this location. ;
c L,
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k APPENDIX H L
DATA TABLES
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( - - _ _
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i (L
Table H-1 DIRECT RADIATION LEVELS Average External Radiation Levels at Various Distances from Sequoyah Nuclear Plant for Each Quarter - 1994
(..'
arem/ Quarter
- Average External Gamma Radiation Levels
- Distance 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter
-Miles (Feb-Apr 94)
(May-Jul 94)
(Aua-Oct 94)
(Nov 94-Jan 95) 0-1 15.4
- 2.4 16.0
- 2.2 16.1
- 1.9 16.1 2 1.5 1-2 12.3
- 2.2 13.5
- 2.0 13.5
- 1.6 13.7'* 1.8 2-4 12.8
- 1.8 13.2
- 1.9 13.0 2.1 13.3
- 1.6 4-6 12.8
- 1.4 13.6 2 1.7 13.2
- 1.6 13.6
- 1.4
>6 12.8
- 2.4 12.9 1.4 12.8 1.4 13.3
- 1.3 Average.
0-2 m1~1es (onsite) 14.0
- 2.8 14.8
- 2.4 14.9
- 2.2 15.0
- 2.0 Average
> 2 elles (offsite) 12.8
- 1.9 13.3
- 1.7 13.1
- 1.7 13.5 2 1.4 Data normalized to one quarter (2190 hours0.0253 days <br />0.608 hours <br />0.00362 weeks <br />8.33295e-4 months <br />).
a.
b.
Averages of the individual measurements in the set *1 standard deviation of the set.
i 1
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Table H - 2 DIRECT RADIATION LEVELS Sequoyah Nudeer Plert indMdusi Stenons l
EnhonmmteWedMmalmle mrem / Quarter l
Map TLD Approx. 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Annual r
, Location Station NRC Direc6on, Distance, February-May-August -
Nov.1994 -
- Exposure, l
Number Nurnber StelmNo* Degrees Miles 8ptt1994 Jubc1994 Oct._1994 JarL1995 mrem /.Yeat
[
i 49 N-1 3
0.6 14.7 12.4 14.6 16.3 58 0 50 N-2 4
2.1 13.3 12.4 13 5 14.0 512 f
51 N-3 358 5.2 10.9 10.5 11.4 11.8 44.6 52 N-4 355 10 13.4 12.8 13.4 14.1 53.7 5
NNE-1 13 1.8 15.7 14.7 15.3 15.7 61.4 53 NNW-2 31 4.5 12.1 11.8 12.0 13.2 49.1 m
54 NNE-3 32 12.1 12.1 11.7 12.6 13.0 49.4 7
12 NNE4 32 17.8 12.0 12.0 12.4 13.2 49.6 55 NE-1 38 2.4 12.6 12.6 13.2 13.3 51.7 t
4 NE-1A 11 50 1.5 13.8 13.8 14.2 14.8 56.6 56 NE-2 51 4.1 10.6 11.7 44.6 57 ENE-1 73 0.4 14.6 12.8 13.9 13.3 54.6 58 ENE-2 66 5.1 12.4 12.0 12.3 13.1 49.8 I
65 E-A 91 0.3 16.4 16.5 16.5 16.6 66.0 59 E-1 96 1.2 12.4 12.3 12.5 12.3 49.5 f
60 E-2 87 5.2 12.4 12.9 13.3 13.2 51.8 61 ESE-A 110 0.3 17.2 16.8 18.4 16.7 69.1 62 ESE-1 110 1.2 13.4 13.0 13.4 13.2 53.0 63 ESE-2 112 4.9 14.8 14.4 14.6 14.9 58.7 13 ESE-3 77 11.3 9.8 13.6 13_3 14.2 50.9 64 SE-A 132 0.4 9.8 13.3 14.5 14.0 51.6 66 SE-1 131 1.4 7.8 10.1 10.7 10.9 39.5 67 SE-2 129 1.9 10.5 12.6 12.9 12.9 48.9 68 SE-4 136 5.2 15.2 15.7 16.7 16.1 63.7 69 SSE-1 6
154 1.6 11.0 11.9 11.9 11.8 46.6 70 SSE-2 158 4.6 14.9 15.6 15.2 15.5 61.2 Locogons with TVA and NRC stations co4ocated.
" Sum of evadable quarterly date normstrea to 1 year for the annual exposure.
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Tetdo H -2 DIRECT RADIATION LEVELS Sequoyah Nuclear Plant Indrvidual Stations Envrgnmerdal P% 1 -d cremouarter Map TLD Approx. 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Annual Location Staten NRC Direction. Dietence. February-Mey-August -
Nov.1994 -
Exposure.
Number Number StehanNo.* Degrees Mise apr41994 AdyJ994 0d 3994 JanJ995 mremfYear 71 S-1 5
183 1.5 12.2 17.5 16.1 16.8 62.6 72 S-2 185 4.7 11.7 13.1 12.7 12 9 50.4 73 SSW-1 203 0.6 14.5 16.1 14.8 15.6 61.0 90 SSW-1B 192 1.5 14.8 15 8 15.3 15.4 61.3 3
SSW-1C 4
198 2
13.8 14.4 14.4 14.1 56.7 74 SSW-2 3
204 3
16 2 17.3 16 9 16.2 66.6 9
SSW-3 203 8.7 17.9 11.6 11.1 11.8 52.4 co 75 SW-1 228 0.9 20.0 17.8 17.0 17.2 72.0 y
7 SW-2 227 3.8 12.6 12 8 12.0 12.5 49.9 11 SW-3 228 16.7 15.4 16 4 16.1 16.2 64.1 76 WSW-1 241 0.9 16 0 17.2 16 4 16.7 66.3 77 WSW-2 238 2.5 10.2 -
10 9 10 0 11.3 42.4 10 WSW-2A 250 2.6 10 9 11.9 11.3 11.6 45.7 78 WSW-3 248 5.7 14 0 16.0 15.0 15.3 90.3 79 WSW-4 244 7.8 11.9 12.6 11.7 12.5 48.7 80 WSW-5 244 10.1 12.2 13.6 12 8 13.1 51.7 81 W-1 280 0.8 17.2 19.0 18.5 18.5 73.2 82 W-2 37 275 4.3 11.1 12.2 11.6 12.1 47.0 8
W4 35 280 5.6 13.9 15.2 14.1 14.9 58.1 83 WNW-1 292 0.4 13.5 14.8 14.1 14 8 57.2 84 WNW-2 295 5.3 11.4 13.8 13 5 13.4 52.1 14 WNW-3 299 18.9 10.2 12.0 11.9 11 8 45.9 85 NW-1 315 0.4 16 8 19.2 19.4 17.9 73.3 86 NW-2 318 5.2 12.8 14 6 13.4 13.5 54.3 87 NNW-1 344 0.6 13.7 15 9 14.5 15 3 59.4 88 NNW-2 342 1.7 11.6 13.0 12.5 13.0 50.1 89 NNW-3 334 5.3 11.3 12.4 12.2 12.4 48.3
- I W with TVA and NRC etehone colocated.
m a---__
TENNESSEE VOLLEY AUTHORITY ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUMECTATION WESTERN AREA RADIOLOGICAL LABORATORY RADICACTIVITY IN AIR FILTER PCI/M3 - 0.037 80/M3 J
t NAME OF FACILITY: SEQUOYAN NUCLEAR PLANT DOCKET No.:
50-327,328 LOCATION OF FACILITY: NAMILTON TENNESSEE REPORTING PERIOD: 1994 TYPE AND LOWER L:Mlf ALL CONTROL IRAISER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION WITH NIGMEST AssNUAL MEAN LOCATIONS NONROUTINE I
0F ANALYSIS DETECTION MEAN (F)
NAME MEAN (F)
MEAN (F)
REPORTED PERFORMED (LLD)
RANGE DISTANCE AND DIRECTIOel RANGE RANGE MEASUREMENTS SEE NOTE 1 SEE NOTE 2 SEE Is0TE 2 SEE IIOTE 2 GROSS BETA 634 2.00E-03 1.91E-02( 422/ 422) PN-8 NARRISON, TN 1.99E-02( 53/ 53) 1.94E-02( 212/ 212) 6.94E 3.57E-02 8.75 MILES SSW 7.63E 3.52E-02 7.75E 3. TIE-02 CApetA SCAN (GELI) 168 SE-7 2.00E-02 9.43E-02( 111/ 112) LM-4 SKULL ISLAND 1.00E-01( 14/ 14) 9.55E 02( 56/ 56) 6.25E 1.43E-01 1.5 MILES IIE 6.25E 1.31E-01 5.72E 1.39E-01 81-214 5.00E 1.27E-02( 12/ 112) PM-8 NARRISON, TN 3.89E-02(
1/ 14) 1.66E-02(
5/ 56) 5.30E 3.89E-02 8.75 MILES SSW 3.89E 3.89E-02 6.90E 03-4.93E-02 H
P8-214 5.00E-03 1.39E-02( 10/ 112) PM-8 NARRISON, TN 4.61E-02(
1/ 14) 1.96E-02(
4/ 56) e 5.80E 4.61E-02 8.75 MILES SSW 4.61E 4.61E-02 8.00E 5.14E-02 r
?
m NOTE:
IW NOTE:
- 2. MEAN AND RANGE SASED UPolf DETECTABLE MEASUREMENTS ONLY. FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS IIIDICATED IN PARENTIIESES (F).
l I
u___
TENNESSEE VALLEY AUTHORITY ENVIRONMENTAL RADIOLOGICAL MONITORING Ate INSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADICACTIVITY IN CNARCOAL FILTER PCI/M3 - 0.037 80/M3 NAME OF FACILITY: SEQUOYAN NUCLEAR PLANT DOCKET NO.:
50-327,328 LOCATIDst OF FACILITY: NAMILTON TENNESSEE REPORTING PERIOD: 1994 l
TYPE AND LOER LIMIT ALL CONTROL NtmeER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATICII WITN NIGNEST ANNUAL MEAN LOCATIONS NONROUTINE OF ANALYSIS DETECTIost MEAN (F)
NAME MEAll (F)
MEAN (F)
REPORTED' PERFORMED (LLD)
RANGE DISTANCE AIS DIRECTIG4 RANGE RANGE MEASUREMENTS SEE IIOTE 1 SEE IIOTE 2 SEE NOTE 2 SEE NOTE 2 i
CAMMA SCAN (GELI) 634 l
K-40 3.00E-01 3.23E-01(
2/ 422) PM-9 LARESIDE 3.43E-01(
1/ $3) 4.79E-01(
3/ 212) 1 3.02E 3.43E-01 2.7 MILES WSW 3.43E 3.43E-01 3.05E 5.88E-01 NOTE:
NOTE:
- 2. MEAN AND RAIIGE BASED UPOII DETECTA8LE MEASURE *CNTS ONLY. FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIOllS IS INDICATED IN PARENTHESES (F).
i
?.
v o
TENIIESSEE VALLEY AUTIIORITY ENVIRONME TAL RADIOLOGICAL MONITORIIIE AND INSTRUMEITATION WESTERIl AllEA RADIOLOGICAL LABORATORT RADICA.'.TIVITT IN MILE PCI/L - 0.037 to/L 4AiME OF FACILITY: SEQUOTAN NUCLEAR PLAlli DOCKET 110.
.50-327,328 LOCAil0N OF FACILITY: NAMILTON TENNESSEE REPORTIIIG PEltitme 1994 TYPE AND LOER LIMIT ALL CONTROL IR8WER OF TOTAL IRMBER OF IISICATOR LOCATIONS LOCATICII WITN IIIGIIEST AIINUAL MEAll LOCATICIls IIONROUTINE OF R
- LYSIS DETECTICII MEAN (F)
IIAM
. EAll (F)
EAll (F)
REPORTED PERFORMED (LLD)
RAIIGE DISTANCE AIS DIllECTION, RANGE RANGE M ASUREE NTS-SEE IIOTE 1 SEE NOTE 2 SEE IIOTE 2 SEE IIOTE 2 IODINE-131 144 4.00E-01 73 VALUES < LLD T1 VALUES < LLD GAleIA SCAll (GELI) 145 el-214 2.00E+01 74 VALUES
- LLD JONES FARM 24 VALUES < LLD 7.80E+01( 10/ 71) 1.25 MILES U 2.51E+01-1.57E+02 E-40 1.00E*02 1.28E+03( 74/ 74) NOLDER DAIRY 1.35E+03( 24/ 24) 1.31E+03( 71/ 71)
Ps-214 2.00E+01.
9.15E+02-1.50E+03 4.25 MILES IIE 1.25E+03-1.47E+03 6.36E+02-1.60E+03 74 VALUES < LLD JONES FAINI 24 VALUES < LLD '
9.18E+01(
8/ 71)
+4 1.25 MILES W 3.16E+01-1.48E+02 g
e SR 89 e
y 47 FI '
I l
2.00E+00 12 VALUES < LLD JONES FARM 4 VALUES < LLD 2.04E+00(
1/ 35) m 1.25 MILES U '
2.04E+00- 2.04E+00 I
l SR 90 47 I
2.00E+00 5.31E+00(
8/ 12) JONES FAllM 6.48E+00(
4/ 4) 3.54E+00(
2/ 35) 2.40E+00- 8.71E+00 1.25 MILES W 3.02E+00- 8.71E+00 2.21E+00- 4.87E+00 IIOTE:
NOTE:
- 2. MEAll AND RAIIGE BASED UP0li DETECTABLE MASLMEMNTS ONLY. FRACTION OF DETECTA8LE MEASUREMENTS AT SPECIFIED LOCATICIls IS IISICATED IN PARENTIIESES (F).
--n.,-.
TENNESSEE VALLEY CJTNORITY ENV!RONME;iAl RADIOLOGICAL MONITORING AND INST".IME::TATION WESTERN AREA RADIOLOGICAL LABORATORY RAct0 ACTIVITY IN VEGETATION PCl/KG - 0.037 90/KG (WET WEIGNT)
NAME OF FACILITY: SEQUDYAN NUCLEAR PLANT DOCKET NO.:
50-327,328 LOCATION OF FACILITY: NAfflLTON TENNESSEE REPORTING PERIOD: 1994 TYPE AND LOWER LIMIT ALL CONTROL NUMBER OF TOTAL NLMcER OF ANALYSIS OF INDICATOR LOCATIONS LOCATION WITN NIGNEST AINFJAL MEAN LOCATIONS WONROUTINE DETECTION MEAN (F)
NAME MEAN (F)
MEAN (F)
REPORTED PERFORMED (LLD)
RANGE DISTANCE A m DIRECTION RANGE RANGE MASUREMNTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 10 DINE-131 26 6.00E+00 13 VALUES < LLD 13 VALUES < LLD GAf544 SCAN (Gell) 26 sE-7 2.00E+02 2.91E+03( 12/ 13) EDGAR MALONE FARM 2.91E+03( 12/ 13) 1.82E+03( 11/ 13) 2.64E+02-1.00E+04 2.5 MILES N 2.64E+02-1.00E+04 2.53E+02-6.96E+03 81-214 5.50E+01 8.36E+01(
1/ 13) EDGAR MALONE FARM 8.36E+01(
1/ 13) 13 VALUES < LLD K-40 4.00E+02.-
8.36E+01-8.36E+01 2.5 MILES N 8.36E+01-8.36E+01 6.82E+03( 13/ 13) EDGAR MALONE FARM 6.82E+03( 13/ 13) 5.30E+03( 13/ 13) 4 i
9.80E+02-2.07E+04 2.5 MILES N 9.80E+02-2.07E+04 2.76E+03-7.66E+03 g
e SR 89 e
W 8
t'l 3.10E+01 4 VALUES < LLD 4 VALUES < LLD SR 90
- g 8
8 1.20E+01 4.13E+01(
4/ 4) EDGAR MALONE FARM 4.13E+01(
4/ 4) 1.25E+01(
1/ 4) 2.15E+01-6.35E+01 2.5 MILES N 2.15E+01-6.35E+01 1.25E+01-1.2SE+01 NOTE:
NOTE:
- 2. MEAN AND RAelGE BASED UPON DETECTA9tE MEASUREMENTS ONLY. FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTNESES (F).
I w
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--___.-_.-____--.__-__.._u.
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v TENNESSEE VALLET AUTHORITT ENVIRONME7.TAL RAD 10 LOCI 3L MONITORING AND INSTRUME%TATION WESTERN " DEA RADIOLOGICAL LA80RATORY RA010A'TIVITY IN Soll PCI/GM 0.037 80/G (DRY WEIGNT)
NAME OF FACILITY: SEQUOTAN NUCLEAR PLANT DOCKET NO.:
50-327,328 LOCAil0N OF FACILITY: NAMILTON TENNESSEE REPORTlWG PERIOD: 1994 TYPE Ale LOER LIMIT ALL CONTROL IR818ER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATICII WITN MIGNEST ANNUAL MEAII LOCATIONS NONROUTINE OF ANALYSIS DETECTION MEAN (F)
NAIE RAIIGE RAIIGE EASUREIENTS M AII (F)
MEAN (F)
REPORTED PERFORMED (LLD)
RANGE DISTAIICE AIS DIRECT 1011 SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GAIGE SCAN (GELI) 13 AC 228 2.50E-01 1.09E+00(
8/ 8) LM-5 WARE PotNT 1.55E+00(
1/ 1) 9.10E-01(
5/ 5) 8.53E 1.55E+00 1.7 MILES NME 1.55E+00- 1.55E+00 5.86E 1.58E+00 81-212 4.50E-01 1.08E+00(
8/ 8) LM-5 WARE PolNT 1.60E+00(
1/ 1) 9.42E-01(
4/ 5) 8.25E 1.60E+00 1.7 MILES NNE 1.60E+00- 1.60E+00 5.78E 1.50E+00 81-214 1.50E-01 7.97E-01(
8/ 8) LM-5 WARE PolNT 9.93E-01(
1/ 1) 7.27E-01(
5/ 5) 7.05E 9.93E 01 1.7 MILES NME 9.93E 9.93E-01 5.25E 1.07E+00 CS-137 3.00E-02.
2.29E-01(
7/ 8) LM-4 SKULL ISLAND 3.20E 01(
1/ 1) 2.82E-01(
4/ 5) 6.63E 3.20E-01 1.5 MILES NE 3.20E 3.20E-01 4.72E 5.51E-01 H
i K-40 7.50E-01 5.58E+00(
8/ 8) SIREN STATION 8 27 1.28E+01(
1/ 1) 6.53E+00(
5/ 53 e
3.26E+00- 1.28E+01 2.0 MILES SSW 1.28E+01-1.28E+01 2.35E+00- 1.43E+01 M
7 P8-212 1.00E-01 9.69E-01(
8/ 8) LM-5 uhAE POINT 1.43E+00(
1/ 13 8.61E-01(
5/ 5) tus 7.55E 1.43E+00 1.7 MILES NNE 1.43E+00- 1.43E+00 4.87E 1.49E+00 PO 214 1.50E-01 8.87E-01(
8/ 8) LM-5 WARE POINT 1.15E+00(
1/ 1) 7.62E-01(
5/ 5)
I" 7.63E 1.15E+00 1.7 MILES NME 1.15E+00- 1.15E+00 5.57E 1.13E+00 RA-224 7.50E-01 1.00E+00(
8/ 8) PM-8 NARRISON, TN 1.54E+00(
1/ 1) 1.47E+00(
2/ 5) 8.14E 1.54E+00 8.75 MILES SSW 1.54E+00- 1.54E+00 1.29E+00- 1.64E+00 RA-226 1.50E-01 7.97E-01C 8/ 8) LM-5 WARE POINT 9.93E-01(
1/ 1) 7.27E-01(
5/ 5) 7.05E 9.93E-01 1.7 MILES NNE 9.93E 9.93E-01 5.25E 1.07E+00 TL-208 6.00E-02 3.34E-01(
8/ 8) LM-5 WARE POINT 5.07E-01(
1/ 1) 2.98E-01C 5/ 5) 2.70E 5.07E-01 1.7 MILES NNE 5.07E 5.07E-01 1.62E 5.17E-01 SR 89 13 1.60E+00 8 VALUES < LLD 5 VALUES < LLD SR 90 13 4.00E-01 8 VALUES < LLD 5 VALUES < LLD t
IIOTE:
1.' IIONINAL LOWER LIMIT OF DETECTION (LLD) AS DESCRISED IN TABLE E-1.
NOTE:
- 2. MEAN AND RAIIGE BASED UPON DETECTABLE MEASUREMENTS ONLY. FRACTIOII OF MTECTA8tE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).
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U TENNESSEE VALLEY AUTNORITY ENVIRONME;TAL RA0!0 LOGICAL MONITORING AND INSTRtR E TATION WESTERN AREA RADIOLOGICAL LABORATORY RADI0 ACTIVITY IN APPLES PCI/KG - 0.037 80/KG (WET WT)
NAME OF FACILITY: SEQUOYAN NUCLEAR PLANT DOCKET No.:
50-327,328 LOCATION OF FACILITY: NAMILTON TENNESSEE REPORTING PERIOD: 1994 TYPE AND LOWER LIMIT ALL CONTROL NUMBER OF TOTAL NUN 8ER OF INDICATOR LOCATIONS LOCATION WITH NIGNEST ANNUAL MEAM LOCATIONS NONROUTINE OF ANALYSIS DETECTION MEAN (F)
NAME MEAN (F)
MEAN (F)
REPORTED PEAFORMED (LLD)
RANCE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GAMMA SCAN (GELI) 2 K-40 2.50E+02 9.26E+02(
1/ 1) LM-5 WARE POINT 9.26E+02(
1/ 1) 5.67E+02(
1/ 1) 9.26E+02-9.26E+02 1.7 MILES NME 9.26E+02-9.26E+02 5.67E+02-5.67E+02 1
NOTE:
NOTE:
- 2. MEAN AND RANGE BASED UPON DETECTA8LE MEASUREMENTS ONLT. FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTNESES (F).
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TENNESSEE VI.LLEY AUTHORITT ENVIRONME"TAL RADIOLOGICAL MONITORING AND INSTRtpqENTAll0N WESTERN AREA RADIOLOGICAL LA80RATORY RADI0 ACTIVITY IN COLLARD GREENS
.PCI/KG - 0.03T BQ/KG (WET WT)
NAME OF FACILITY: SEQUDYAN NUCLEAR PLANT DOCKET No.:
50-327,328 LOCATION OF FACILITY: NAMILTON TENNESSEE REPORIING PERIOD: 1996 TYPE AND LOWER LIMIT ALL CONTROL NtsteER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION WITN MIGNEST ANNUAL MEAN LOCATIONS NONROUTINE OF ANALYSIS DETECTION MEAN (F)
NAME MEAN (F)
MAN (F)
REPORTED PERFORMED (LLD)
RANGE DISTANCE AND DIRECTION RANGE RAIIGE MASUREMENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GAMMA SCAN (GELI) 2 E.40 2.50E+02 1.88E+03(
1/ 1) N WALKER FARM 1.88E+03(
1/ 1) 1.79E+03(
1/ 1) 1.88E+03-1.88E+03 1.25 MILES NW 1.88E+03-1.88E+03 1.79E+03-1.79E+03 NOTE:
NOTE:
- 2. MEAN AND RAhGE BASED UPON DETECTAstE MEASUREMENTS DIILT. FRACTION OF DETECTA0LE MEASUREMENTS AT SPECIFIED l
LOCATICItS IS INDICATED IN PARENTMESES (F).
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TENNESSEE VALLEY AUTNORITY ENVIRONMECTAL RADIOLOGICCL MONITORlWG AND INSTRUMENTATION
'{
WESTERN AREA RADIOLOGICAL LABORATORY
{
4 RADI0 ACTIVITY IN CORN PCI/KG - 0.037 BQ/KG (WET WT)
NAME OF FACILITY: SEQUOTAN NUCLEAR PLANT DOCKET No.:
50-327,328 LOCATION OF FACILITY: P.AMILTON TENNESSEE REPORTING PERIOD: 1994 TYPE AND LOWER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION WITH NIGNEST ANNUAL MEAN LOCATIONS NONROUTINE i
i 0F ANALYSIS DETECTION MEAN (F)
NAME MEAN (F)
MEAN (F)
REPORTED l
PERFORMED (LLD)
RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GAMMA SCAN (Gell) 2 K-40 2.50E+02 2.24E+03(
1/ 1) N WALKER FARM 2.24E+03(
1/ 1) 2.14E+03(
1/ 1) 2.24E+03-2.24E+03 1.25 MILES NW 2.24E+03-2.24E+03 2.14E+03-2.14E+03 NOTE:
NOTE:
- 2. MEAN AND RANGE BASED UPON DETECTASLE MEASUREMENTS ONLY. FRACTION OF DETECTA8tE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTNESES (F).
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TECNESSEE tfALLEV OUTMORITY ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRtP9ENTATl001 WESTERN AREA RADIOLOGICAL LABORATORY RADIOACTIVITY IN GREEN BEANS PCl/KG - 0.037 SQ/KG (WET WT)
NAME OF FACILITY: SEQUDYAN NUCLEAR PLANT DOCKET No.:
50-327,328 LOCATION OF FACILITY: NAMILTON TENNESSEE REPORTlWG PERIOD: 1994 TYPE AND LOWER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOEt LOCATIONS LOCATION WITH NIGNEST ANNUAL MEAN LOCATIONS NONR3JTINE OF ANALYSIS DETECTION MEAN (F)
NAME MEAN (F)
MEAN (F)
REPORTED PERFORtqED (LLD)
RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GAMMA SCAN (GELI) 2 K-40 2.50E+02 2.00E+03(
1/ 1) N WALKER FARM 2.00E+03(
1/ 1) 1.14E+03(
1/ 1) 2.00E+03-2.00E+03 1.25 MILES NW 2.00E+03-2.00E+03 1.14E+03-1.14E+03 NOTE:
NOTE:
- 2. MEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLT. (9 ACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTNESES (F).
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TEN::ESSEE VALLEY AUTHORITY ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUENTAfl04 l
WESTERN AREA RADIOLOGICAL LABOEATORY RADI0 ACTIVITY IN POTATOES PCI/KG - 0.037 BQ/KG (WET WT)
NAME OF FACILITY: SEQUOTAN NUCLEAR PLANT DOCKET No.:
50-327,328 LOCATION OF FACILITY: NAMILTON TENNESSEE REPORTING PERIOD: 1994 TYPE AND LOWER LIMIT ALL CONTROL IRMBER OF TOTAL NLMBER OF INDICATOR LOCATIONS LOCATION WITN NIGNEST ANNUAL MEAM LOCATIONS NONROUTINE l
OF ANALYSIS DETECTION MEAN (f)
NAME MCAN (F)-
MEAN (F)
REPORTED PERFORMED (LLD)
RANGE DISTANCE AND DIRECTION RANGE Rf.NGE MEASUREMENTS l
SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GAMMA SCAN (GELI) 3 K-40 2.50E+02 2.36E+03(
1/
- 1) Il WALKER FARM 2.36E+03(
1/ 1) 2.51E+03(
2/ 2) l 2.36E+03 2.36E+03 1.25 MILES WW 2.36E+03-2.36E+03 2.06E+03-2.97E+03 l
NOTE:
NOTE:
- 2. MEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY. FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTNESES (F).
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TENNESSEE VALLEY AUTHORITY ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUMENTATION WESTERN AREA RADIOLOGICAL LA80RATORY RADI0 ACTIVITY IN TOMATOES PCI/KG - 0.037 BC/KG (WET WT)
NAME OF FACILITY: SEQUDYAN NUCLEAR PLANT DOCKET No.:
50-327,328 LOCATION OF FACILITY: NAMILTON TENNES$CE REPORTING PERICD: 1994 f
TP*E AND LOWER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER OF IICICATOR LOCATIONS LOCATION WITN NIGNEST ANNUAL MEAM LOCATIONS WONROJTINE OF ANALYSIS DETECTION MEAN (F)
NAME MEAN (F)
MEAN (F)
REPORTED PERFORMED (LLD)
RANGE DISTANCE A80 DIRECTION RANGE RANCE PEASUREMENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GAM A SCAN (GELI) 2 i
K-40 2.50E+02 2.42E+03(
1/ 1) N WALKER FARM 2.42E+03(
1/ 1) 2.21E+03(
1/ 1) l 2.42E+03-2.42E+03 1.25 MILES WW 2.42E+03-2.42E+03 2.21E+03-2.21E+03 NOTE:
NOTE:
- 2. MEAN AND RANGE BASED UPON DETECTABLE MEASURENENTS ONLY. FRACitON OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).
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TENNESSEE VALLEV AUTHOITY ENVIRONMEOTAL RADIOLCSICAL M OITO IOG A W INSTRUMEOTATI O WESTERN AREA RADIOLOGICAL LABORATORY RADIDACTIVITY IN SURFACE WATER (Total)
PCI/L - 0.037 Bo/L NAME OF FACILITY: SEQUOYAN NUCLEAR PLANT DCCKET Wo.:
50-327,328 LOCATION OF FACILITY: MAMILTON TENNESSEE REPGtTING PERIOD: 1994 TTPE AND LOWER LIMIT ALL CCIITROL NLMSER OF l
TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONS NONROUTINE I
0F ANALTSIS.
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 GROSS BETA 37 1.90E+00 2.66E+00( 22/ 24) TRM 483.4 2.93E+00( 10/ 11) 2.71E+00( 11/ 13) 1.91E+00- 5.45E+00 1.91E+00- 5.45E+00 2.15E+00- 3.82E+00 GAMMA SCAN (GELI) 37 5.00E+00 24 VALUES < LLD 13 VALUES < LLD SR 89 5.00E+00 8 VALUES < LLD 4 VALUES < LLD SR 90 e
12 E
O 2.00E+00 8 VALUES < LLD 4 VALUES < LLD Y
TRITIUM i
12 e
3.00E+02 8 VALUES < LLD 4 VALJES < LLD NOTE:
NOTE:
- 2. MEAN AND RANGE BASED UPON DETECTA8tE MEASUREMENTS ONLY. FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).
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TENuESSEE VALB.EY AUTHORITT ENVIRouMECTAL RADIOLOGICAL MONITORING AND INSTRUMEDTATION WESTERN AREA RADIOLOGICAL LA90RATORT RADI0 ACTIVITY IN PUBLIC WATER (Total)
PCI/L - 0.037 sc/L MAME OF FACILITY: SEGUDYAN NUCLEAR PLANT DOCKET No.:
50-327,328 LOCAfl0N OF FACILITY: Nm!LTON TENNESSEE REPORilWG PERIOD: 1994 TYPE AND LOWER LIMIT ALL CONTROL NLMBER OF TOTAL NUMOER OF INDICATOR LOCAfl0NS LOCATION UITN NIGNEST ANNUAL MEAN LOCATIONS NONROUTINE OF ANALYSIS DETECTION MEAN (F)
NAME-MEAN (F)
MEAN (F)
REPORTED PERFORMED (LLD)
RANGE DISTANCE AND DIRECTION RANGE RANGE DEASUREMENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 I
GROSS BETA 65 1.90E+00 2.46E+00( 14/ 39) CF INDUSTRIES 2.59E+00(
6/ 13) 2.68E+00( 20/ 26) 1.97E+00- 3.35E+00 TRM 473.0 1.99E*M-3.35E+00 1.99E+00- 3.82E+00 10 DINE-131 23 4.00E-01 12 VALUES < iLD 11 VALUES < LLD GAMMA SCAN (GELI) i 65 I
81-214 2.00E+01 2.09E+01(
1/ 39) CHICKmAUGA D M 2.09E+01(
1/ 13) 26 VALUES < LLD 2.09E+01-2.09E+01 TRM 465.3 2.09E+01-2.09E+01 tss b
MM N
O 20 Y
$.00E+00 12 VALUES < LLD 8 VALUES < LLD SR 90 W.
20 2.00E+00 12 VALUES < LLD 8 VALUES < LLD TRITIUM 20 3.00E+02 12 VALUES < LLD 8 VALUES < LLD NOTE:
NOTE:
- 2. MEAN AND RANGE BASED UPON DETECTA8tE MEASUREMENTS ONLY. FRACTION OF DETECTABLE MEASURENENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).
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.P TENNESSEE VALLEY AUTHORITT ENVIRONMEOTAL RADIOLOGICAL MONITORING Ae INSTRUNE~TATION WESTERN AREA RADIOLOGICAL LA90RATORY RADIDACTIVITY IN WELL WATER (Total)
PCI/L - 0.037 BQ/t NAE OF FACILITY: SEQUOYAN NUCLEAR PLANT DOCKET NO.:
50-327,328 LOCATION OF FACILITY: MAMILTON 1ENNESSEE REPORTlWG PERIOD: 1994 TTPE AND LOER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION VITN MIGNEST ANNUAL MEAN LOCAfl0NS WONROUTINE 0F ANALYSIS DETECTION MEAN (F)
NAME MEAN (F)
MEAN (F)
REPORTED I
i PERFORMED (LLD)
RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GROSS DETA 8
1.90E+00 4 VALUES < LLD SON WELL M 4 VALUES < LLD 6.41E+00(
4/ 4)
ONSITE NNE 4.10E+00- 9.63E+00 8
BI-214 2.00E+01 4 VALUES < LLD SON WELL M 4 VALUES < LLD 2.65E+02(
4/ 4) l ONSITE NME 1.96E+02-3.03E+02 PS-214 2.fM+01 4 VALUES < LLD SON WELL M 4 VALUES < LLD 2.61E+02(
4/ 4)
H ONSITE NME 1.94E+02-3.11E+02 1
SR 89 o
8 y
l W
5.00E+00 4 VALUES < LLD 4 VALUES < LLD 3:
SR 90 I
1 8
e 2.00E+00 4 VALUES < LLD 4 VALUES < LLD TRITIUM l
8 3.00E+02 4 VALUES < LLD 4 VALUES < LLD NOTE:
NOTE:
- 2. MEAN AND RANGE BASED UPON DETECTABLE MEASURLMENTS ONLY. FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).
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TENNESSEE VALLEY AUTNORITY ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUMENTAil04 WESTERN AREA RADIOLOGICAL LABORATORT RADICACTIVITY IN CHANNEL CATFISM FLESN PCI/CM - 0.037 80/G (DRY WEIGHT)
NAME OF FACILITY: SEQUO"AN NUCLEAR PLANT DOCKET NO.:
50-327,328 LOCATION OF FACILITY: NAMILTON TENNESSEE REPORTING PERIOD: 1994 TYPE AND LOWER LIMIT ALL CONTROL NLDBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION WITN NIGNEST ANNUAL MEAN LOCATIONS NONROUTINE OF ANALTSIS DETECTION MEAN (F)
NAfE MEAN (F)
MEAN (F)
REPORTED PERFORMED (LLD)
RANGE DISTANCE AND DIRECTION RANGE RANGE IEASUREMENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GAMA SCAN (GELI) 6 CS-137 3.00E-02 4.42E-02(
1/ 4) CHICKAMauGA 'tES 4.42E-02(
1/ 2) 2 VALUES < LLD 4.42E 4.42E-02 TRM 471-530 4.42E 4.42E-02 K-40 4.00E-01 1.13E+01(
4/ 4) CHICKAMAUGA RES 1.21E+01(
2/ 2) 1.52E+01(
2/ 2) 9.42E+00- 1.48E+01 TRM 471-530 9.42E+00- 1.48E+01 1.31E+01-1.73E+01 H
NOTE:
h NOTE:
- 2. MEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY. FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED j
LOCAil0NS IS INDICATED IN PARENTNESES (f).
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.P TENNESSEE VALLEY AUTHORITY ENvlRONME!TAL RADIOLOGICAL MONITORING Am INSTRUME; Tail 0N WESTERN AREA RADIOLOGICAL LADORATORY RADIDACTIVITY IN CRAPPIE FLESN PCI/CM - 0.037 BC/G (DRf WEIGHT)
NAME OF FACILITY: SEQUOTAN NUCLEAR PLANT DOCKET NO.:
50-327,328 LOCATION OF FACILITY: NAMILTON TENNESSEE REPORTING PERIOD: 1994 TYPE AND LOWER LIMIT ALL CONTROL NUMBER OF l
TOTAL NUMBER OF INDICATOR LOCATIONS LOCAfl0N WITH MIGNEST ANNUAL MEAM LOCATIONS NONROUTINE i
0F ANALYSl3 DETECTION MEAN (F)
NAME EAN (F)
MEAN (F)
REPORTED 7ERFORMED (LLO)
RANGE DISTANCE AND DIRECil0N RANGE RANGE MEASUREMENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GAMMA SCAN (GELI) l 6
'CS-137 3.00E-02 7.23E-02(
3/ 4) CMICKAMAUGA RES 7.86E-02(
2/ 2) 9.20E-02(
2/ 2) 5.90E 8.91E-02 TRM 471 530 6.80E 8.91E-02 8.27E 1.01E-01 K-40 4.00E-01 1.74E+01(
4/ 4) hlCKAJACK RES 1.825 41( 2/ 2) 1.75E+01t 2/ 2) 1.59E+01-2.02E+01 TRM 425-471 1 ' '.
<01-2.02E+01 1.69E+01-1.81E+01 NOTE:
H NOTE:
- 2. MEAN AND RANGE BASED bPON DETECTABLE MEASUREMENTS ONLY. FRACTION OF DETECTAOLE MEASUREE NTS AT SPECIFIED b
h LOCATIONS IS INDICATED IN PARENTNESES (F).
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TENNESSEE VALLEY AUTNORITY ENVIRONMENTAL RA010 LOGICAL MONITORING AND INSTRUMENTATION WESTERN AREA RADIOLOGICAL LABORATORY RADIDACTIVITY IN SMALLMOUTN BUFFALO FLESN PCl/CM - 0.037 BQ/G (DRT WElGHT)
NAME OF FACILITY: SEQUDYAN NUCLEAR PLANT DOCKET NO.:
50-327,328 LOCATION OF FACILITY: NAMILTON TENNESSEE REPORTING PERIOD: 1994 TYPE AND LOWER LIMIT ALL CONTROL NUMBER OF T0TAL NUMBER OF INDICATOR LOCATIONS LOCATION WITM N1GNEST ANNUAL MEAN LOCATIONS NONROLITINE OF ANALYS15 DETECTION MEAN (F)
NAME MEAN (F)
MEAN (F)
REPORTED PERFORMED (LLD)
RANGE DISTANCE A W DIRECTION RANGE RANGE MEASUREMENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GAM 4A SCAN (GELI) 6 CS 137 3.00E 02 4.36E-02(
2/ 4) NICKAJACK RES 4.81E-02(
1/ 2) 4.39E-02(
2/ 2) 3.91E 4.81E-02 TRM 425-471 4.81E 4.81E-02 4.15E 4.64E 02 R-40 4.00E-01 1.02E+01(
4/ 4) CHICKAMAUGA RES 1.07E*01(
2/ 2) 1.27E+01C 2/ 21 6.72E+00- 1.25E+01 TRM 471-530 1.01E+01-1.13E+01 9.77E+00- 1.57E+01 SR 89 6
9.00E-02 4 VALUES < LLD 2 VALUES < LLD H
SR 90
,w 6
t*
O 3.00E-02 4 VALUES < LLD 2 VALUES < LLO M
8 I
NOTE:
NOTE:
- 2. MEAN AND RANCE BASED UPON DETECTABLE MEASUREMENTS ONLY. FRACil04 0F DETECTABLE MEASUREMENis.'? '#ECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).
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TENNESSEE VALLEY AUTHORITY ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRtMENTAil0N WESTERN AREA RADIOLOGICAL LABORATORY RADIDACTIVITY IN SMALLMOUTN BUFFALO WHOLE PCl/GM - 0.037 80/G (DRY WEIGHT)
NAME OF FACILITY: SEOLUTAN NUCLEAR PLANT 00CKET NO.:
50-327,328 LOCATION OF FACILITY: NAMfLTON TENNESSEE REPORTING PERIOD: 1994 TYPE AND LOWER LIMIT ALL CONTROL NUMBER Of TOTAL NUMBER OF INDICATOR LOCATIONS LOCAil04 WITN MIGNEST ANNttAL MEAN LOCAfl0NS NONRCUTINE 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 (Gell) 6
~CS 137 3.00E-02 3.17E 02(
1/ 4) NICKAJACK RES 3.17E-02(
11 21 2 VALUES < LLD 3.17E 3.17E 02 TRM 425 471 3.17E 3.17E 02 K-40 4.00E 01 6.09E+00(
4/ 4) WICKAJACK RES 6.11E+00(
2/ 2) 5.69E+00(
2/ 2) 5.38E+00- 6.84E+00 TRM 425 471 5.38E+00- 6.84E+00 4.59E+00- 6.79E+00
(
SR 89 f
6 9.00E-02 1.85E-01(
2/ 4) CMICKAMAUGA RES 2.13E-01(
1/ 2) 2 VALUES < LLD 1.56E-01 2.13E-01 TRM 471 530 2.13E 2.13E-01 b
b SR 90 O
6 E
7 3.00E-02 8.66E-02(
4/ 4) CMICKAnAUGA RES 8.76E-02(
2/ 2) 1.25E-01(
2/ 2)
?
l 6.52E-02 1.10E-01 TRM 471 530 6.52E 1.10E-01 1.18E 1.32E-01 I
wo NOTE:
I NOTE:
- 2. MEAN AND RANGE BASED UPON DETECTASLE MEASUREMENTS ONLY. FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED I
LOCATIONS IS INDICATED IN PARENTMESES (F).
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TENNESSEE VALLEY AUTMORITY ENVIRONMENTAL RADIOLOGICAL MONITORING AND INSTRUMEITAfl04
~
WESTERN AREA RADIOLOGICAL LABORATORY RADI0 ACTIVITY lu SEDIE NT PCI/GM - 0.037 00/G (DRY wlGMT) 3 NAME OF FACILITY: SEGUOTAN NUCLEAR PLANT 00CKET N0.:
50-327,328
)
LOCATION OF FACILITT: IWWIILTON TENNESSEE REPORTING PEtie s 1994 l
TYPE ANO LCE R LIMlf ALL Comit0L IRAGER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCAfl0N WITN NIGNEST ANNUAL MAN LOCAfl0NS WONROUTINE OF ANALYSIS DETECTION MEAN (F)
NAME MEAN (F)
MEAN (F)
REPORTED PERFORMED (LLO)
RANGE OBSTANCE AIS OIRECTION RANGE RANGE >
M ASUREM NTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GArmA SCAN (GELI) 8
.AC-228 2.50E-01 1.72E+00(
6/ 6) TAM 483.4 2.17E+00(
2/ 2) 1.25E*00(
2/ 2) 9.78E 3.35E+00 9.78E 3.35E+00 1.07E+00- 1.43E+00 BE-7 2.50E-01 1.60E+00(
5/ 6) T m 472.80 2.71E+00(
2/ 2) 8.31E-01(
2/ 2) 4.30E-01 4.93E+00 4.86E 4.93E+00 3.14E 1.35E+00 81-212 4.50E-01 1.72E+00(
6/ 6) TAM 483.4 2.32E+00(
2/ 2) 1.17E+00(
2/ 2) 9.AM 3.70E+00 9.43E 3.70E+00 1.02E+00- 1.32E+00 31-214 1.50E-01 9.32E-01(
6/ 6) TAM 483.4 1.17E+00(
2/ 2) 7.74E-01(
2/ 2) y 6.09E 1.74E 4 0 6.09E 1.74E*00 7.21E 8.27E-01 l
Co-58 3.00E-02 1.53E-01(
1/ 6) T m 480.82 1.53E-01(
1/ 2) 2 VALUES < LLO t*
as o
1.53E 1.53E-01 1.53E 1.5M-01 "8
l Co-60 3.00E-02 1.09E-01(
5/ 6) i m 480.82 1.36E-01(
2/ 2) ' 2 VALUES < LLO tu 3.42E 2.10E 01 6.33E 2.10E-01 1
CS.134 3.00E-02 4.80E-02(
1/ 6) i m 480.82 4.80E-02(
1/ 2) 2 VALUES < LLO
'N 4.80E 4.80E-02 4.80E 02-4.80E-02 CS-137 3.00E-02 5.89E-01(
6/ 6) T M 472.80 8.10E-01(
2/ 2) 5.00E-01(
2/ 2) 8.71E 1.21E+00 6.66E 01-9.53E-01 3.49E 8.12E-01 E-40 7.50E-01 1.28E 41( 6/ 6) tan 472.80 1.45E+01(
2/ 2) 1.37E+01(
2/ 21 7.74E+00- 1.72E+01 1.34E+01-1.55E+01 1.24E 41-1.50E+01 Ps-212 1.00E-01 1.52E+00(
6/ 6) TAM 483.4 2.00E+00( - 2/ 2) 1.16E+00(
2/ 2) 8.63E 01-3.31E+00 8.63E 3.31E+00 1.04E+00- 1.29E+00 P5-214 1.50E 01 1.02E+00(
6/ 6) tan 483.4 1.31E+00(
2/ 2) 8.12E-01(
2/ 2) 6.90E 01-1.93E+00 6.90E 1.93E+00 8.05E 8.18E-01 RA-224 7.50E-01 1.60E+00(
6/ 6) Tell 483.4 2.01E+00(
2/- 2) 1.49E+00(
1/ 2) 9.54E 3.07E+00 9.54E 3.07E+00 1.49E+00- 1.49E+00 RA-226 1.50E-01 9.32E 01( 6/ 6) TAM 483.4 1.17E+00(
2/ 2) 7.74E-01(
2/ 2) 6.09E 1.74E+00 6.09E 1.74E+00 7.21E 8.27C-01 TL-208 6.00E-02 5.17E-01(
6/ 6) TAM 483.4 7.15E-01(
2/ 2) 3.84E-01(
2/ 2) -
3.01E 1.13E+00 3.01E 1.13E+00 3.20E 01-4.4?E-01 NOTE:
- 1. NOMINAL LOWER LIMli 0F OETECTION (LLO) AS DESCRISEO IN TABLE E-1.
NOTE:
- 2. MEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY. FRACTION OF OETECTABLE MEASUREMENTS AT SPECIFIED-LOCATIONS IS IISICATED IN PARENTNESES (F).
}.
TENNESSEE VALLEY AUTHORITT ENylRONMENTAL RADIOLOGICAL MONITORING AND INSTRUMENTAfl0N UESTERN AREA RADIOLOGICAL LABORATORT RADIDACTIVITY IN $NORELINE SEDIMENT PCI/GM - 0.037 80/G (DRY UEIGHT)
NAME OF FACILITY: SEQUOTAN NUCLEAR PLANT DOCKET NO.:
50-327,328 LOCATION OF FACILITY: NAMILTON TENNESSEE REPORTING tYRIOD: 1994 TYPE AND LOWER LIMIT ALL CONTROL NU48ER OF TOTAL NUMRER OF INDICATOR LOCATIONS LOCATION WITN NIGMEST ANNUAL MEAN LOCATIONS NONROUTINE OF ANALYSIS DETECTION MEAN (F)
NAME MEAN (F)
MEAN (F)
REPORTF0 PERFORMED (LLD)
RANGE DISTANCE AND DIRECTION RANCE RANGE MASUREMENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GMe9A SCAN (Gell) 6 AC 228 2.50E-01 8.11E-01(
4/ 4) GOLD POINT 9.79E-01(
2/ 2) 2 VALUES < LLD 4.91E 1.44E+00 TRM 478 5.15E 1.44E+00 SE-7 2.50E-01 3.19E-01(
2/ 4) COLD PolNT 3.43E-01(
1/ 2) 2 VALUES < LLD 2.95E 3.43E-01 TRM 478 3.43E 3.43E-01 81-212 4.50E 01 8.40E-01(
4/ 4) 00LD POINT 9.97E-01(
2/ 2) 2 VALUES 4 LLD 4.51E 1.54E+00 TRM 478 4.51E 1.54E+00 81-214 1.50E-01 6.42E-01(
4/ 4) 00LD POINT 6.54E-01(
2/ 2) 2 VALUES < LLD H
3.00E 1.01E+00 TM 478 3.00E 1.01E+00 h
CS-137 3.00E-02 5.38E-02(
4/ 4) HARRISON FLATS 6.12E-02(
2/ 2) 2 VALUES < LLD t*
o 3.27E 6.67E-02 TRM 477 5.57E 6.67E-02 M
'8 K-40 7.50E-01 4.23E+00(
4/ 4) GOLD PolNT 5.14E+00(
2/ 2) 1.53E+00(
2/ 2) tu 2.17E+00- 8.10E+00 TRM 478 2.17E+00- 8.10E+00 1.43E+00- 1.62E+00 h
P8-212 1.00E-01 7.45E-01(
4/ 43 GOLD PolNT 8.75E-01(
2/ 2) 1.07E-01(
1/ 2) w 3.83E 1.37E+00 TRM 478 3.83E 1.37E+00 1.07E 1.07E-01 P8-214 1.50E 01 7.12E-01(
4/ 4) GOLD POINT 7.22E-01(
2/ 2) 2 VAlbES < LLD 3.49E 1.10E+00 T m 478 3.49E 1.10E+00 RA-224 7.50E 01 1.16E+00(
2/ 4) GOLD POINT 1.44E+00(
1/ 2) 2 VALUES < LLD 8.79E 01-1.44E+00 TRM 478 1.44E+00- 1.44E+00 RA-226 1.50E-01 6.42E-01(
4/ 4) GOLD PolNT 6.54E-01(
2/ 2) 2 VALUES < LLD 3.00E 1.01E+00 TRM 478 3.00E 1.01E+00 TL-208 6.00E-02 2.54E-01(
4/ 4) COLD PolNT 3.00E 01( 2/ 2) 2 VALUES < LLD 1.34E-01 4.66E-01 TRM 478 1.34E 01-4.66E 01 NOTE:
NOTE:
- 2. MEAN AND RANGE 8ASED UPON DETECTABLE MEASUREMENTS ONLY. FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F).
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f7........ _. R JUT O
p TENNESSEE VALLEY f!JTHORITT ENVIRONMEr.TAL RADIOLOGICAL MONITORING AW INSTRUMENTATION WESTERN AREA RADIOLOGICAL LA80RATORY RA010 ACTIVITY IN CLAM FLESN PCI/GM - 0.03T BC/G (DRY WEIGHT)
NAME OF FACILITY: SEQUOYAN NUCLEAR PLANT DOCKET Wo.:
50-327.328 LOCAil04 0F FACILITY: MAMILTON TENNESSEE REPortilleG PERIOD: 1994 TYPE AND LOWER LIMIT ALL CONTROL IRstBER OF f
TOTAL NUMBER OF INDICATOR LOCATIONS LOCAfl0N WITN NIGNEST ANNUAL MEAN LOCATIONS NONROUTINE 3
0F ANALYSIS DETECTION MEAN (F)
NAME MEAN (F)
MEA 81 (F)
REPORTED PERFORMED (LLD)
RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS SEE NOTE 1 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 GAMMA SCAN (Gell) 5 Ps-214 1.00E-01 2.0?E-01(
1/ 3) 2.07E-01(
1/ 1) 3.85E-01(
1/ 2) 2.07E 2.07E-01 Seu Donmetroen Statt 2.07E 2.07E-01 3.85E 3.85E 01 NOTE:
NOTE:
- 2. MEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY. FRACTION OF DEIECTAGLE MEASUREMENTS AT SPECIFIED LOCATIONS IS IW ICATED IN PARENTIIESES (F).
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' ' ' ' ' ' ' ' ' ' RR '''''''''''''''''''''''''''''''''''''''l'''''''
77 78 79 80 81 82 83 84 85 86 87 BR 89 90 91 92 93 94 initial plantoperation in July 1980.
Year A Off-Site l v On-Site Sequoyah Nuclear Plant) m e
e ee-*+=eee==me e
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Annual Average Gross Beta Activity Air Filters, pCi/ Cubic Meter 0.25 Initial plant operation in July 1980.
0.2 N
j 0.15 E
g Preoperational Average
[
0.1 3n.
0.05
-=A' 0
71 72 73 74 75 76 77 78 79 80p800 81 82 83 84 85 86 87 88 89 90 91 92 93 94 Year O Indicator mi Control lSeciuoy~ah_ hearPlantl Note: No measurements were made in 1974.
~ -
l mem sem mi uma
==
mas som man aim men' men - um um en som uma amm Annual Average: Sr-90 in Milk tr r. u:e m x n :.=== r :.u
_:x._.__:.ru-:;.a w.:m w==_--
- w 14 - - -- - -- - - - - - - - - - - - -
initial plant operation in July 1980.
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71 72 73 76 77 78 79 80p 800 81 82 83 84 85 86 87 88 89 90 91 92 93 94 Year v Indicator
-A Control
- Preoperational Average
.--,__._...._.__.-r-__._..__.__.-_._m__._....--
Sequoyah Nuclear Plant Note: No milk samples were coileded in 1974 and 1975.
vm-r m
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u sum sum um amm um sus mm men um aus
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l 3
2.5 Initial plant operation in July 1980.
2 E
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0 71 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 Year v Indicator
- Control
- Preoperational Average l
- - - - - = - -
.____t lSequoyah Nuclear Plant l Note: Detector system changed from Nel to Geu in 1977.
-r e-
M M WM M
M mM m' M M
M M
M M
M M
M Annual Ave ~ rage Gross Beta Activity
~
Surface Water, pCi/ Liter g
6 fk initial plant operation in July 1980.
5
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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 94 Year v Indicator A Control
- Preoperational Average l
.==_.._...!
-........ - -. -..... -......... ~.........,.........
(Seguoyah NucIsar Plant l
m Annual Average Gross Beta Activity Drinking Water, pCl/ Liter 6
Initial plant operation in July 1980.
5 I
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f..
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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 94 Year v Indicator
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- Preoperational Average
-==
sus num men as mm
==
a=
sem
==
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l l
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4 Annual Average Cs-137 in Channel Catfish
,_.......-x....
0.6 l
l 4
Initial plant operation in July 1980.
0.4 i
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-A Upstream
- Preoperational Average l
_m_____.-
Sequoyah Nuclear Plant Note: Detector system changed from Nel to Gell in 1978.
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l Annual Average Cs
._..-137 in Fish: Crappie 0.6 0.5 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 94 Year v Downstream
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initial plant operation in July 1980.
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0 71 72 73 74 75 76 77 78 79 80p800 81 82 83 84 85 86 87 88 89 90 91 92 93 94 Year v Downstream
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==
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0.6 A
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y n
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71 72 73 74 75 78 77 78 79 80p800 81 82 83 84 85 86 87 88 89 90 91 92 93 94 Year 4 Downstream
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Annual Average Cs-137 in Sediment 10 Initial plant operation in July 1980.
8 E
6 m
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2 3
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71 72 73 74 75 78 77 78 79 80p800 81 82 83 84 85 86 87 88 89 90 91 92 93 94 Year y Downstream
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== me
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initial plant operation in July 1980.
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- Upstream lSeqyoyahyyclear Plantj Note: Detector system changed from Nel to Gellin 1977.
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