ML17130A850
| ML17130A850 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 05/08/2017 |
| From: | Anthony Williams Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML17130A850 (93) | |
Text
Tennessee Valley Authority, Post OfficeBox 2000, Soddy Daisy,Tennessee 37384-2000 May 8, 2017 10CFR50.4 ATTN:
Document Control Desk U.S. Nuclear Regulatory Commission Washington, D. C. 20555-0001 Sequoyah Nuclear Plant, Units 1 and 2 Renewed Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327, 50-328,72-034
Subject:
Annual Radiological Environmental Operating Report Enclosed is the Annual Radiological Environmental Operating Report for the period of January 1 to December 31, 2016. This report is being submitted as required by the respective Sequoyah Nuclear Plant (SQN), Units 1 and 2, Technical Specification 5.6.1 and SQN's Offsite Dose Calculation Manual Administrative Control Section 5.1, each of which specifies that the report be submitted prior to May 15th of each year.
There are no new regulatory commitments contained in this letter. If you have any questions concerning this matter, please contact Mike McBrearty at (423) 843-7170.
Chthony L. Williams Site Vice President Sequoyah Nuclear Plant
Enclosure:
Annual Radiological Environmental Operating Report, Sequoyah Nuclear Plant, 2016 cc (Enclosure):
NRC Regional Administrator-Region II NRC Resident Inspector-Sequoyah Nuclear Plant
ENCLOSURE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SEQUOYAH NUCLEAR PLANT 2016
Annual Radiological Environmental Operating Report Sequoyah Nuclear Plant 2016
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SEQ UOY AH NUCLEAR PLANT 2016 TENNESSEE VALLEY AUTHORITY April 2017
TABLE OF CONTENTS Table of Contents.............................................
1 Executive Summary...........................................
1 Introduction.................................................
2 Naturally Occurring and Background Radioactivity.................
2 Electric Power Production.....................................
4 Site/Plant Description..........................................
6 Radiological Environmental Monitoring Program....................
7 Direct Radiation Monitoring.....................................
10 Measurement Techniques......................................
10 Results....................................................
11 Atmospheric Monitoring.......................................
13 Sample Collection and Analysis................................
13 Results....................................................
14 Terrestrial Monitoring.........................................
15 Sample Collection and Analysis................................
15 Results....................................................
16 Liquid Pathway Monitoring.....................................
17 Sample Collection and Analysis................................
17 Results....................................................
18 Assessment and Evaluation.....................................
20 Results....................................................
20 Conclusions................................................
21 References...................................................
22 Table 1 Comparison of Program Lower Limits of Detection with Regulatory Limits for Maximum Annual Average Effluent Concentrations Released to Unrestricted Areas and Reporting Levels.........
23 Figure 1 Tennessee Valley Region................................
24 Figure 2 Environmental Exposure Pathways of Man Due to Releases of Radioactive Materials to the Atmosphere and Lake............
25
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TABLE OF CONTENTS (continued)
Appendix A Radiological Environmental Monitoring Program and Sampling Locations..............................................
26 Appendix B Program Modifications...................................
37 Appendix C Program Deviations.....................................
39 Appendix D Analytical Procedures..................................
42 Appendix E Nominal Lower Limits of Detection (LLD)..................
45 Appendix F Quality Assurance/Quality Control Program.................
50 Appendix G Land Use Survey......................................
55 Appendix H Data Tables and Figures.................................
60
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EXECUTIVE
SUMMARY
This report describes the Radiological Environmental Monitoring Program (REMP) conducted by TV A in the vicinity of the Sequoyah Nuclear Plant (SQN) during the monitoring period of 2016. The program is conducted in accordance with regulatory requirements to monitor the environment per 10 CFR 20 and 10 CFR 50, and in accordance with TV A procedures. The REMP includes the collection and subsequent determination of radioactive material content in environmental samples. Various types of samples are collected within the vicinity of the plant, including air, water, milk, food crops, soil, fish, shoreline sediment, and the measurement of direct radiation levels. The radiation levels of these samples are measured and then compared with results at control stations located outside the plant's vicinity and data collected at SQN prior to operation (preoperational data). This report contains an evaluation of the potential impact of SQN operation on the environment and general public.
The vast majority of radioactivity measured in environmental samples from the SQN program can be contributed to naturally occurring radioactive materials. Trace quantities of cesium-137 (Cs-137) were measured in soil, shoreline sediment and fish. The concentrations were typical of the levels expected to be present in the ~nvironment from past nuclear weapons testing or operation of other nuclear facilities in the region. The fallout from accidents at the Chernobyl plant in the Ukraine in 1986 and the Fukushima plant in Japan in 2011 may have also contributed to the low levels of Cs-13 7 measured in environmental samples. Tritium at concentrations slightly above the analytical detection limit was detected in water samples collected from Chickamauga Reservoir and in samples of groundwater collected from the onsite REMP well.
These levels of radioactive elements detected do not represent a significant contribution to the radiation exposure to members of the public.
INTRODUCTION This report describes and summarizes the results of radioactivity measurements taken in the vicinity of SQN and laboratory analyses of samples collected in the area. The measurements are taken to comply with the requirements of the Code of Federal Regulations (CFR), IO CFR 50, Appendix A, Criterion 64 and IO CFR 50, Appendix I, Sections IV.B.2, IV.B.3 and IV.C, and to determine potential effects on public health and safety. This report satisfies the annual reporting requirements of SQN Plant Technical Specification (TS) 5.6.1 and Offsite Dose Calculation Manual (ODCM) Administrative Control 5.1. The data presented in this report include results from the prescribed program and other information to help correlate the significance of results measured by this monitoring program to the levels of environmental radiation resulting from naturally occurring radioactive materials.
Naturally Occurring and Background Radioactivity Many materials in our world contain trace amounts of naturally occurring radioactivity. For example, approximately 0.01 percent bf all potassium is radioactive potassium-40 (K-40) which has a half-life of 1.3 billion years. An individual weighing 150 pounds contains about 140 grams of potassium (Reference 1 ). Other examples of naturally occurring radioactive materials are beryllium (Be)-7, bismuth (Bi)-212 and 214, lead (Pb)-212 and 214, thallium (Tl)-208, actinium (Ac)-228, uranium (U)-238 and 235, thorium (Th)-234, radium (Ra)-226, radon (Rn)-222 and 220, carbon (C)-14, and hydrogen (H)-3 (generally called tritium). These naturally occurring radioactive materials are in the soil, our food, our drinking water, and our bodies. The remainder of the natural background radiation is produced by cosmic rays. The relative hazard of different types ofradiation sources can be compared by evaluating the amount ofradiation the U.S.
population receives from each type of radiation source as displayed in the following table. This table was adapted from References 2 and 3.
U.S. GENERAL POPULATION AVERAGE DOSE EQUIVALENT ESTIMATES Source Natural background dose equivalent Cosmic Terrestrial In the body Radon Total Medical (exposure)
Nuclear energy Consumer products Total I. One-thousandth of a Roentgen equivalent man (rem)
Millirem /Year Per Person 33 21 29 228 311 300 0.28 13 624 (approximately)
As can be seen from the table, natural background radiation dose equivalent to the U.S.
population normally exceeds that from nuclear plants by several hundred times. The 0.28 mrem attributable to nuclear plant operations results in a population radiation dose equivalent that is insignificant as compared to the dose from natural background radiation.
Electric Power Production Nuclear power plants are similar in many respects to conventional coal burning (or other fossil fuel) electric generating plants. The basic process behind electrical power production in power plants is that fuel is used to heat water to produce steam which provides the force to turn turbines and generators. In a nuclear power plant, the fuel is uranium and the heat is produced in the reactor through the fission of the uranium. Fission of uranium results in fission and activation products such as tritium, cobalt-60 and cesium-137. Nuclear plants include many complex systems to control the nuclear fission process and to safeguard against the possibility of reactor malfunction. The nuclear reactions produce radionuclides commonly referred to as fission and activation products. 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 may be released to the environment.
The pathways through which radioactivity is released are monitored. Liquid and gaseous effluent monitors record the radiation levels for each release. These monitors provide alarm mechanisms to prompt termination of release above limits.
Releases are monitored at the onsite points of release and through the environmental monitoring program which measures the environmental radiation in areas around the plant. In this way, not only is the release of radioactive materials from the plant tightly controlled, but measurements are made in surrounding areas to verify that the population is not being exposed to significant levels of radiation or radioactive materials.
The SQN ODCM, which is required by the plant technical specifications, prescribes limits for the release of radioactive effluents, as well as limits for doses to the general public from the release of these effluents.
The dose to a member of the general public from radioactive materials released to unrestricted areas, as given in Nuclear Regulatory Commission (NRC) guidelines and the ODCM, is limited as follows:
Liquid Effluents Gaseous Effluents Total body Any organ Noble gases:
Gamma radiation Beta radiation Particulates:
Any organ
- =:3 mrem/year
- 10 mrem/year
- 10 mrad/year
- 20 mrad/year
- =:15 mrem/year The Environmental Protection Agency (EPA) limits for the total dose to the public in the vicinity of a nuclear power plant, established in the Environmental Dose Standard of 40 CFR 190, are as follows:
Total body Thyroid Any other organ
- =:25 mrem/year
- =:75 mrem/year
- =:25 mrem/year Appendix B to 10 CFR 20 presents annual average limits for the concentrations of radioactive materials released in gaseous and liquid effluents at the boundary of the unrestricted areas.
Table 1 of this report compares the nominal lower limits of detection (LLD) for the SQN monitoring program with the regulatory limits for maximum annual average effluent concentrations released to unrestricted areas and levels requiring special reports to the NRC. It should be noted that the levels of radioactive materials measured in the environment are typically only slightly above the lower limit of detection. The data presented in this report indicate compliance with the regulations.
SITE/PLANT DESCRIPTION Sequoyah is located on a site near the geographical center of Hamilton County, Tennessee, on a peninsula on the western shore of Chickamauga Lake at Tennessee River Mile (TRM) 484.5.
Figure I show:s the site in relation to other TV A 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 TV A's Watts Bar Nuclear Plant (WBN) site.
Population is distributed unevenly within I 0 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. Residential subdivision growth has continued within the IO-mile radius of the plant. There is also some small-scale farming located within 5 miles of the plant.
Chickamauga Reservoir is one of a series of highly controlled multiple-use reservoirs located on the Tennessee River whose primary uses are flood control, navigation, and the generation of electric power. Secondary uses include industrial and public water supply and waste disposal, commercial fishing, and recreation. Public access areas, boat docks, and residential subdivisions have been developed along the reservoir shoreline.
SQN consists of two pressurized water reactors. Fuel was loaded in Unit I on March I, 1980, and the unit achieved criticality on July 5, 1980. Fuel was loaded in Unit 2 in July 1981, and the unit achieved initial criticality on November 5, 1981.
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Most of the radiation and radioactivity generated in a nuclear power reactor is contained within the reactor itself or one of the other plant systems. Plant effluent monitors are designed to detect the small amounts of radioactive material released to the environment. Environmental monitoring provides a final verification that the systems are performing as planned. The monitoring program is designed to monitor the pathways between the plant and the general public in the immediate vicinity. Sample types are chosen so that the potential for detection of radioactivity in the environment will be maximized. The radiological environmental monitoring program is outlined in Appendix A.
There are two primary pathways by which radioactivity can move through the environment to humans: air and water (see Figure 2). The air pathway can be separated into two components:
the direct (airborne) pathway and the indirect (ground or terrestrial) pathway. The direct airborne pathway consists of direct radiation and inhalation by humans. In the terrestrial pathway, radioactive materials may be deposited on the ground or on plants and subsequently be ingested by animals and/or humans. Human exposure through the liquid pathway may result from drinking water, eating fish, or by direct exposure at the shoreline. The types of samples collected in this program are designed to monitor these pathways.
A number of factors were considered in determining the locations for collecting environmental samples. The locations for the atmospheric monitoring stations were determined from a critical pathway analysis based on weather patterns, dose projections, population distribution, and land use. Terrestrial sampling stations were selected after reviewing such factors as the locations of dairy animals and gardens in conjunction with the air pathway analysis. Liquid pathway stations were selected based on dose projections, water use information, and availability of media such as fish and sediment. Table A-2 (Appendix A, Table 2: This identification system is used for the tables and figures in the appendices.) lists the sampling stations and the types of samples collected. Modifications made to the SQN monitoring program in 2016 are described in Appendix B. Deviations from the sampling and analysis schedule are presented in Appendix C.
To determine the amount of radioactivity in the environment prior to the operation of SQN, a preoperational radiological environmental monitoring 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 knowledge of pre-existing radionuclide patterns in the environment permits a determination, through comparison and trending analyses, of any impact on the environment due to the operation of SQN.
The determination of impact from the plant during the operating phase also utilizes the data from control stations that have been established in the monitoring program. 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.
Samples are analyzed by TV A's Environmental Radiological Monitoring and Instrumentation (ERM&I) group located at the Western Area Radiological Laboratory (W ARL) in Muscle Shoals, Alabama, with the exception of the strontium (Sr )-89, 90 analysis of soil samples which is performed by a contract laboratory. 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 radiation detection devices and analysis methods used to determine the radionuclide content of samples collected in the environment are very sensitive to small amounts of radioactivity. The sensitivity of the measurements process is defined in terms of the lower limit of detection. A description of the nominal LLDs for the radioanalytical laboratory is presented in Appendix E.
The ERM&I laboratory employs a comprehensive quality assurance/quality control program to monitor laboratory performance throughout the year. The program is intended to detect any problems in the measurement process as soon as possible so they can be corrected. This program includes equipment checks, to ensure that the radiation detection instruments are working properly, and the analysis of quality control samples. The laboratory participated in a blind cross check program administrated by a vendor. This program provided an independent interlaboratory comparison program. A complete description of the laboratory's quality assurance/quality control program is presented in Appendix F.
DIRECT RADIATION MONITORING Direct radiation levels are measured at various monitoring points around the plant site.
These measurements include contributions from cosmic radiation, radioactivity in the ground, fallout from atmospheric nuclear weapons tests conducted in the past, and any radioactivity that may be present as a result of plant operations. Because of the relatively large variations in background radiation as compared to the small levels from the plant, contributions from the plant may be difficult to distinguish.
Measurement Techniques The Landauer InLight environmental dosimeter is used in the radiological environmental monitoring program for the measurement of direct radiation. This dosimeter contains four elements consisting of aluminum oxide detectors with open windows as well as plastic and copper filters. The dosimeter is processed using optically stimulated luminescence (OSL) technology to determine the amount of radiation exposure.
The dosimeters are placed approximately 1 meter above the ground, with two at each monitoring location. Sixteen monitoring points are located around the plant near the site boundary, one location in each of the 16 compass sectors. One monitoring point is also located in each of the 16 compass sectors at a distance of approximately four to five miles from the plant.
Dosimeters are also placed at additional monitoring locations out to approximately 32 miles from the site. The dosimeters are exchanged every 3 months. The dosimeters are sent to Landauer for processing and results reporting. The values are corrected for transit and shielded background exposure. An average of the two dosimeter results is calculated for each monitoring point. The system meets or exceeds the performance specifications outlined in American National Standards Institute (ANSI) N545-1975 and Health Physics Society (HPS) Draft Standard N13.29 for environmental applications of dosimeters.
Results The results for environmental dosimeter measurements are normalized to a standard quarter (91.25 days or 2190 hours0.0253 days <br />0.608 hours <br />0.00362 weeks <br />8.33295e-4 months <br />). The monitoring locations are grouped according to the distance from the plant. The first group consists of the monitoring points within 2 miles of the plant. The second group is made up of the locations greater than 2 miles from the plant. Past data have shown that the average results from the locations more than 2 miles from the plant are essentially the same. Therefore, for purposes of this report, monitoring points 2 miles or less from the plant are identified as "onsite" stations and locations greater than 2 miles are considered "offsite."
The quarterly gamma radiation levels determined from the dosimeters deployed around SQN in 2016 are summarized in Table H-1. The exposures are measured in milliroentgens (mR). For purposes of this report, one milliroentgen, one millirem (mrem) and one millirad (mrad) are assumed to be numerically equivalent.
The rounded average annual exposures, as measured in 2016, are shown below. For comparison purposes, the average direct radiation measurements made in the preoperational phase of the monitoring program are also shown.
Onsite Stations Offsite Stations Annual SQN Average Direct Radiation Levels mR/Year (Pre-operational) 2016 1976-79 63 56 79 63 The data in Table H-1 indicate that the average quarterly direct radiation levels at the SQN onsite stations are approximately 1.6 mR/quarter higher than levels at the offsite stations. This equates to 6.2 mR/year detected at the onsite locations. This value falls below the BP A limit of 25 mrem/year total body. The difference in onsite and off site averages is consistent with levels measured for the preoperational and construction phases of TV A nuclear power plant sites where the average levels onsite were slightly higher than levels offsite. Figure H-1 compares plots of the data from the onsite stations with those from the off site stations over the period from 1976 through 2016. The Landauer InLight Optically Stimulated Luminescence (OSL) dosimeters were deployed since 2007 replacing the Panasonic UD-814 used during the prev10us years.
The data in Table H-2 contains the results of the individual monitoring stations. The results reported in 2016 are consistent with direct radiation levels identified at locations which are not influenced ~y the operation of SQN. There is no indication that SQN activities increased the background radiation levels normally. observed in the areas surrounding the plant.
ATMOSPHERIC MONITORING The atmospheric monitoring network is divided into three groups identified as local, perimeter, and remote. Four local air monitoring stations are located on or adjacent to the plant site in the general directions of greatest wind frequency. Four perimeter air monitoring stations are located in communities out to about 10 miles from the plant, and four air monitors are located between 10-20 miles. These four stations are used as control or baseline stations. The monitoring program and the locations of monitoring stations are identified in the tables and figures of Appendix A.
Sample Collection and Analysis Air particulates are collected by continuous sampling of air at a flow rate of approximately 2 cubic feet per minute (cfm) through a 2-inch glass fiber filter. The sampling system consists of a pump, magnehelic gauge for measuring the drop in pressure across the system, and a dry gas meter to measure the volume of air sampled. This sampling system is housed in a metal building. The filter is contained in a sampling head mounted on the outside of the monitor building. The filter is replaced weekly. Each filter is analyzed for gross beta activity about 3 days after collection to allow time for the radon daughters to decay. Every 4 weeks composites of the filters from each location are analyzed by gamma spectroscopy.
The presence of gaseous radioiodine is monitored using a commercially available cartridge containing TEDA (triethylene di-amine) impregnated charcoal. This system is designed to collect iodine (I) 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 gamma spectroscopy analysis.
Results The results from the analysis of air particulate samples are summarized in Table H-3. Gross beta activity in 2016 was consistent with levels reported in previous years. The annual average gross beta activity for air filter samples was 0.021 pCi/m3* The annual average of the gross beta activity in air particulate filters at these stations for the years 1971-2016 are presented in Figure H-2. Increased levels due to fallout from atmospheric nuclear weapons testing are evident, especially in 1971, 1977, 1978, and 1981. Evidence of a small increase resulting from the Chernobyl accident can also be seen in 1986. These patterns are consistent with data from monitoring programs conducted during the preoperational and construction phases at other TV A nuclear plant sites.
Only naturally occurring radionuclides were identified by the monthly gamma spectral analysis of the air particulate samples. As shown in Table H-4, no 1-131 was detected in any of the charcoal cartridge samples collected in 2016.
TERRESTRIAL MONITORING Terrestrial monitoring is accomplished by collecting samples of environmental media that may transport radioactive material from the atmosphere to humans. For example, radioactive material may be deposited on a vegetable garden and be ingested along with the vegetables or it may be deposited on pasture grass where dairy cattle are grazing. When the cow ingests the radioactive material, some of it may be transferred to the milk and consumed by humans who drink the milk.
Therefore, samples of milk, soil, 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 gardens within a 5-mile radius of the plant. The only location identified where milk could be produced for human consumption was a small farm located approximately 1.2 miles northwest of the plant. The location was sampled in accordance with the SQN sampling program. The results of the 2016 land use survey are presented in Appendix G.
Sample Collection and Analysis Milk samples are collected every 2 weeks from the indicator location and from at least one control dairy. A radiochemical separation analysis for 1-131 and a gamma spectroscopy analysis are performed on each sample and Sr-89, 90 analysis is performed quarterly.
The monitoring program includes provision for sampling of vegetation from locations where milk is being produced when milk sampling cannot be conducted. Walker Farm did not milk their cows routinely during 2016 so vegetation was collected and analyzed in lieu of the milk sample when milk was unavailable.
Soil samples are collected annually from the air monitoring locations. The samples are collected with either a "cookie cutter" or an auger type sampler. After drying and grinding, the sample is analyzed by gamma spectroscopy and for Sr-89, 90.
Samples representative of food crops raised in the area near the plant are obtained from individual gardens. Types of foods may vary from year to year as a result of changes in the local vegetable gardens. Samples of cabbage, com, green beans, pears, potatoes, and tomatoes were collected in 2016 from local gardens. Samples of these same food crops were purchased from area produce markets or private gardens to serve as control samples. The edible portion of each sample is analyzed by gamma spectroscopy.
Results The results from the analysis of milk and vegetation samples are presented in Table H-5 and H-6.
The iodine-131 results were less than the established nominal LLD of0.4 pCi/liter. The results for the quarterly Sr-89, 90 analysis were less than the nominal LLD value of 3.5 pCi/liter and 2.0 pCi/liter respectively. Only naturally occurring isotopes were identified in the gamma analysis of the milk samples.
Vegetation was collected in lieu of milk throughout 2016. The iodine-131 results were less than the established nominal LLD of 6.0 pCi/kg. Only naturally occurring radionuclides were identified by the gamma spectral analysis of the vegetation samples.
The gamma analysis of soil samples detected trace levels of Cs-13 7. The concentrations of Cs-13 7 are consistent with levels previously reported from fallout. All other* radionuclides reported were naturally occurring isotopes. The soil analysis data are provided in Table H-7.
A plot of the annual average Cs-137 concentrations in soil is presented in Figure H-3. The concentrations of Cs-13 7 in soil are steadily decreasing as a result of the cessation of weapons testing in the atmosphere, the 3 0-year half-life of Cs-13 7 and transport through the environment.
Radionuclides reported in food samples were all naturally occurring. Analysis of these samples indicated no contribution from plant activities. The results are reported in Tables H-8 through H-13.
LIQUID PATHWAY MONITORING Potential exposures from the liquid pathway can occur from drinking water, ingestion of edible fish, or from direct radiation exposure from radioactive materials deposited in the river sediment.
The monitoring program includes the collection of samples of surface water, groundwater, drinking water supplies, fish, and shoreline sediment. Samples from the reservoir are collected both upstream and downstream from the plant.
Sample Collection and Analysis Samples of surface water are collected from the Tennessee River downstream and upstream of the plant using automatic sampling systems. A timer turns on the system at least once every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and the sample is collected into a composite jug. A I-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 gross beta activity. A quarterly composite sample is analyzed for tritium.
Samples are collected by an automatic sampling system at the first downstream drinking water intake and at the water intake for the city of Dayton located approximately 20 miles upstream.
At other selected locations, grab samples are collected from drinking water systems which use the Tennessee River as their source. The drinking water samples are analyzed every 4 weeks by gamma spectroscopy and for gross beta activity. A quarterly composite sample from each station is analyzed for tritium. Additional tritium analyses are performed on samples from two of the locations that are shared with the Watts Bar monitoring program. The sample collected at the water intake for the city of Dayton also serves as control sample for surface water.
Groundwater is sampled from an onsite well using an automatic composite sampler and a grab sample is collected quarterly from a private well in an area unaffected by SQN. Gamma spectroscopy and tritium analyses are performed monthly on samples from the onsite well and gross beta analysis is performed on a quarterly composite sample. The samples from the offsite well are analyzed by gamma spectroscopy and for tritium and gross beta activity.
Samples of commercial and game fish species are collected semiannually from each of two reservoirs: the reservoir on which the plant is located (Chickamauga Reservoir) and the upstream reservoir (Watts Bar Reservoir). The samples are collected using a combination of netting techniques and electrofishing. Samples are prepared from filleted fish. After drying and grinding, the samples are analyzed by gamma spectroscopy.
Samples of shoreline sediment are collected from two downstream recreational use areas and one upstream location. The samples are dried and ground and analyzed by gamma spectroscopy.
Results There were no fission or activation product radionuclides identified from the gamma spectroscopy analyses performed on surface water samples. Tritium activity above the nominal LLD value was measured in.samples of surface water. The tritium concentrations in samples from the indicator location averaged 646 pCi/liter and samples from the control location averaged 591 pCi/liter. This tritium concentration represented only a small fraction of the EPA drinking water limit of 20,000 pCi/liter. The values were consistent with previously reported values. Gross beta activity above the nominal LLD value was measured in approximately one third of the surface water samples. The gross beta concentrations in samples from the indicator and control locations averaged 2.1 pCi/liter. The values were consistent with previously reported levels. A trend plot of the annual average gross beta activity in surface water samples from 1971 through 2016 is presented in Figure H-4. A summary table of the results is shown in Table H-14.
There were no fission or activation product radionuclides identified by the gamma analysis of drinking water samples. Tritium activity above the nominal LLD value was measured in drinking water samples. The tritium concentrations in samples from the indicator location averaged 566 pCi/liter and samples from the control location averaged 591 pCi/liter. These tritium levels represented only a small fraction of the EPA drinking water limit of20,000 pCi/liter. The values were consistent with previously reported values. Average gross beta activity was 2.3 pCi/liter for the downstream stations and 2.1 pCi/liter for the upstream station.
The values were consistent with previously reported values. The results are shown in Table H-
-18~
15 and a trend plot of the annual average gross beta activity in drinking water from 1971 through 2016 is presented in Figure H-5.
No fission or activation products were detected by the gamma analyses performed on ground-water samples from the REMP monitoring locations. Tritium above the nominal LLD value of 270 pCi/liter was detected in samples collected from the onsite monitoring well. The average tritium concentration was 436 pCi/liter. No gross beta activity was detected for indicator location samples. The average gross beta concentration in samples from the offsite well was 9.6 pCi/liter. These gross beta levels are representative of the levels typically found in groundwater.
The results from the analysis of groundwater samples are presented in Table H-16.
Cesium-137 was identified in one fish sample collected from the control location. The Cs-137 concentration in this sample was 0.03 pCi/g. No Cs-137 was detected for indicator location samples. All other radionuclides reported were naturally occurring isotopes. The results are summarized in Tables H-17 and H-18. A plot of the annual average Cs-137 concentration in samples of game fish is presented in Figure H-6.
Cesium-137 was identified in one shoreline sediment sample collected from the indicator location. The Cs-137 concentration in the indicator sample was 0.06 pCi/g. All other radionuclides reported were naturally occurring isotopes. Results from the analysis of shoreline sediment samples are shown in Table H-19. Figure H-7 presents a plot of the annual average Cs-137 concentrations measured in shoreline sediment since 1980.
ASSESSMENT AND EVALUATION Potential doses to the public are estimated from measured effluents using computer models.
These models were developed by TV A 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 results of the effluent dose calculations are reported in the Annual Radioactive Effluent Release Report. The doses calculated are a representation of the dose to a "maximum exposed individual." Some of the factors used in these calculations (such as ingestion rates) are maximum expected values which will tend to overestimate the dose to this "hypothetical" person. The calculated maximum doses due to plant effluents are small fractions of the applicable regulatory limits. In reality, the expected dose to actual individuals is significantly lower.
Based on the very low concentrations of radionuclides actually present in the plant effluents, radioactivity levels measured in the environment as a result of plant operations are expected to be negligible. The results for the radiological environmental monitoring conducted for the SQN 2016 operations confirm this expectation.
Results As stated earlier in this report, the estimated increase in radiation dose equivalent to the general public resulting from the operation of SQN is negligible when compared to the dose from natural background radiation. The results from environmental samples are compared with the concentrations from the corresponding control stations as well as appropriate preoperational and background data to determine influences from the plant. Measurable levels of Cs-13 7 were detected in fish, shoreline sediment, and soil. The Cs-13 7 concentrations are consistent with levels identified previously that are the result of fallout from past atmospheric nuclear weapons testing. The low levels of tritium measured in water samples from Chickamauga Reservoir and from the onsite well represented concentrations that were significantly lower than the EPA drinking water limit.
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 plant operations is negligible. The radioactivity reported herein is primarily the result of fallout or natural background radiation. Any activity which may be present as a result of plant operations does not represent a significant contribution to the radiation exposure to members of the public.
REFERENCES
- 1. Merril Eisenbud, Environmental Radioactivity, Academic Press, Inc., New York, NY, 1987.
- 2. National Council on Radiation Protection and Measurements, Report No. 160, "Ionizing Radiation Exposure of the Population of the United States," March 2009.
- 3. United States Nuclear Regulatory Commission, Regulatory Guide 8.29, "Instruction Concerning Risks from Occupational Radiation Exposure," February 1996.
Table 1 COMPARISON OF PROGRAM LOWER LIMITS OF DETECTION WITH THE REGULATORY LIMITS FOR MAXIMUM ANNUAL AVERAGE EFFLUENT CONCENTRATIONS RELEASED TO UNRESTRICTED AREAS AND REPORTING LEVELS Concentrations in Water, nCi/Liter Concentrations in Air, nCi/Cubic Meter Effluent Reporting Lower limit Effluent Reporting Lower limit Analysis Concentration 1 Level2 of Detection3 Concentration 1 LeveI2 of Detection3 H-3 1,000,000 20,000 270 100,000 Cr-51 500,000 45 30,000 0.02 Mn-54 30,000 1,000 5
1,000 0.005 Co-58 20,000 1,000 5
1,000 0.005 Co-60 3,000 300 5
50 0.005 Zn-65 5,000 300 IO 400 0.005 Sr-89 8,000 1,000 Sr-90 500 6
Nb-95 30,000 400 5
2,000 0.005 Zr-95 20,000 400 IO 400 0.005 Ru-103 30,000 5
900 0.005 Ru-106 3,000 40 20 0.02 1-131 1,000 2
0.4 200 0.9 0.03 Cs-134 900 30 5
200 IO 0.005 Cs-137 1,000 50 5
200 20 0.005 Ce-144 3,000 30 40 0.01 Ba-140 8,000 200 25 2,000 0.015 La-140 9,000 200 IO 2,000 0.01 Note: 1pCi=3.7 xI0*2 Bq.
Note: For those reporting levels and lower limits of detection that are blank, no value is given in the reference.
1 Source: Table 2 of Appendix B to 10 CFR 20 2 Source: SQN Offsite Dose Calculation Manual, Table 2.3-2 3 Source: Table E-1 of this report
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APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM AND SAMPLING LOCATIONS Exposure Pathway and/or Sample
- 1. AIRBORNE
- a. Particulates
- b. Radioiodine
- c. Soil Table A-1 SEQUOYAH NUCLEAR PLANT RADIOLOGICAL ENVIRONMENT AL MONITORING PROGRAM" Number of Samples and Sampling and Locationsb Collection Frequency 4 samples from locations (in different Continuous sampler operation with sectors) at or near the site boundary sample collection once per 7 days (LM-2, LM-3, LM-4, and LM-5).
(more frequently ifrequired by dust loading).
4 samples from communities approximately 6-10 miles from the Plant (PM-2, PM-3, PM-8, and PM-9).
4 samples from control locations greater than 10 miles from the plant (RM-1 RM-2, RM-3 and RM-4).
Same locations as air particulates.
Continuous sampler operation with charcoal canister collected at same time as particulate filters at least once per 7 days.
Samples from same locations as air Once per year.
particulates Type and Frequency of Analysis Analyze for gross beta radioactivity greater than 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. Perform gamma isotopic analysis on each sample when gross beta is greater than 10 times yearly mean of control samples. Composite at least once per 31 days (by location) for gamma scan.
1-131 by gamma scan on each sample.
Each sample is analyzed by gamma isotopic and for Sr-89 and Sr-90.
Exposure Pathway and/or Saml!k
- 2. DIRECT RADIATION
- 3. WATERBORNE
- a. Surface water
- b. Groundwater Table A-1 (continued)
SEQUOYAH NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM8 Number of Samples and Sampling and Type and Frequency Locationsb Collection Freguency of Analvsis 2 or more dosimeters placed at At least once per 92 days.
Gamma dose at least once per 92 locations at or near the site boundary days.
in each of the 16 sectors.
2 or more dosimeters placed at stations located approximately 4 to 5 Miles from the plant in each of the 16 sectors.
2 or more dosimeters in other locations of special interest.
TRM 503.8d Collected by automatic sequential-Gross beta and gamma scan on each TRM483.4 type sampler c with composite composite sample. Composite for samples collected over a period tritium analysis at least once per of less than or equal to 31 days.
92 days.
1 sample adjacent to the plant (Well At least once per 31 days.
Composited for gross beta, gamma No. 6).
scan, and tritium at least once per 92 days.
1 sample from groundwater source At least once per 92 days.
Gross beta, gamma scan, and up gradient (Farm HW).
tritium at least once per 92 days.
Exposure Pathway and/or Sample
- c. Drinking Water
- d. Shoreline sediment Table A-1 (continued)
SEQUOYAH NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMa Number of Samples and Location sh 1 sample at the first potable water supply downstream from the plant (TRM 473.0).
1 sample at the next 2 downstream potable water systems (greater than 10 miles downstream) (TRM 469.9 and TRM 465.3).
1 sample at the upstream control location (TRM 503.8d).
TRM485
- TRM480 TRM479 Sampling and Collection Freauencv Collected by automatic sequential-type sampler0 with composite sample collected over a period of less than or equal to 31 days.
Grab sample once per 31 days.
Samples collected by sequential-type sampler0 with composite sample collected over a period of less than or equal to 31 days.
At least once per 184 days. Type and Frequency of Analysis Gross beta and gamma scan on each composite sample. Composite for tritium at least once per 92 days.
Gamma scan of each sample.
Exposure Pathway and/or Sample
- 4. INGESTION
- a. Milk
- b. Fish Table A-1 (continued)
SEQUOYAH NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM8 Number of Samples and Locationsb Sampling and Collection Frequency 1 sample from milk producing At least once per 15 days.
animals in each of 1-3 areas indicated by the cow census where doses are calculated to be 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 in milk from other sectors or by sampling vegetation where milk is not available.
At least 1 sample from a control location 1 sample each from Chickamauga and Watts Bar Reservoirs.
At least once per 184 days.
1 sample representing a commercially important species and 1 sample representing a recreationally important species. Type and Frequency of Analvsis Gamma isotopic and 1-131 analysis of each sample. Sr-89 and Sr-90 once per quarter.
Gamma scan on edible portion.
Exposure Pathway and/or Sample Table A-1 (continued)
SEQUOYAH NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Number of Samples and Locationsb Sampling and Collection Frequency Type and Frequency of Analysis
- c. Food Products 1 sample each of principal food products grown at private gardens and/or farms in the immediate vicinity of the plant.
At least once per 365 days at time of harvest. The types of foods available for sampling will vary. Following is a list of typical foods which may be available:
Gamma scan on edible portion.
- d. Vegetatione 1 sample of each of the same foods grown at greater than 10 miles distance from the plant.
Samples from farms producing milk but not providing a milk sample.
Control sample from 1 control dairy farm when sampling is performed at an indicator location.
Cabbage, lettuce, or greens Com Green Beans Potatoes Tomatoes At least once per 31 days.
- a. The sampling program outlined in this table is that which was in effect at the end of 2016.
- b. Sample locations, sector and distance from plant, are described in Table A-2 and A-3 and shown in Figures A-1, A-2, and A-3.
- c. Composite samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
- d. The sample collected at this location shall be considered a control for the drinking water and surface water.
1-131 and gamma scan at least once per 31 days.
- e. Vegetation sampling is applicable only for farms that meet the criteria for milk sampling and when implementation of milk sampling is not possible.
Map Location Number" 2
3 4
5 7
8 9
10 11 12 13 14 19 91 24 31 32 33 35 37 38 40 44 46 47 Table A-2 SEQUOYAH NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS Approximate Indicator (I)
Distance or Station Sector (Miles}
Control (C}
LM-2 N
0.7 I
LM-3 SSW 2.0 I
LM-4 NE 1.5 I
LM-5 NNE 1.8 I
PM-2 SW 3.8 I
PM-3 w
5.6 I
PM-8 SSW 8.7 I
PM-9 WSW 2.6 I
RM-1 SW 16.7 c
RM-2 NNE 17.8 c
RM-3 ESE 11.3 c
RM-4 NW 20.0 c
FarmHW NW 1.2 I
Farm BB ENE 12.0 c
Well No. 6 NNE 0.15 I
TRM0 473.0 10.7d I
(East Side Utilities)
TRM469.9 13.8d (E. I. DuPont)
TRM 465.3 18.4d (Chattanooga)
TRM 503.8 20.ld c
(Dayton)
TRM485.0 1.3d c
TRM483.4 0.3d I
TRM479.0 4.7d I
TRM480.0 3.7d I
Chickamauga Reservoir (TRM 471-530)
I Watts Bar Reservoir (TRM 530-602) c
- a. See Figures A-1, A-2, and A-3
- b. Sample codes:
Samples Collectedb AP,CF,S AP,CF,S AP,CF,S AP,CF,S AP,CF,S AP,CF,S AP,CF,S AP,CF,S AP,CF,S AP,CF,S AP,CF,S AP,CF,S M,wc M
w PW PW PW PW,SW SS SW SS SS F
F AP = Air particulate filter PW = Public Water SS = Shoreline Sediment CF = Charcoal filter s
=
Soil SW = Surface water F
=Fish w
= Well water M =Milk
- c. A control for well water.
- d. Distance from plant discharge (TRM 483.7).
- e. TRM = Tennessee River Mile TableA-3 SEQ UOY AH NUCLEAR PLANT ENVIRONMENT AL DOSIMETER LOCATIONS Map Approximate Onsite (On)b Location Distance or Number" Station Sector (miles)
Offsite (OID 3
SSW-IC SSW 2.0 On 4
NE-IA NE 1.5 On 5
NNE-I NNE 1.8 On 7
SW-2 SW 3.8 Off 8
W-3 w
5.6 Off 9
SSW-3 SSW 8.7 Off 10 WSW-2A WSW 2.6 Off 11 SW-3 SW I6.7 Off I2 NNE-4 NNE I7.8 Off 13 ESE-3 ESE I 1.3 Off I4 NW-3 NW 20.0 Off 49 N-I 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 5.3 Off 55 NE-I NE 2.4 Off 56 NE-2 NE 4.I Off 57 ENE-I ENE 0.2 On 58 ENE-2 ENE 5.1 Off 59 E-I E
1.2 On 60 E-2 E
5.2 Off 62 ESE-I ESE 1.2 On 63 ESE-2 ESE 4.9 Off 66 SE-I SE 1.4 On 67 SE-2 SE 1.9 On 68 SE-4 SE 5.2 Off 69 SSE-I SSE 1.6 On 70 SSE-2 SSE 4.6 Off 7I S-I s
1.5 On 72 S-2 s
4.7 Off 73 SSW-I SSW 0.6 On 74 SSW-2 SSW 4.0 Off 75 SW-I SW 0.7 On 76 WSW-I WSW 0.9 On 77 WSW-2 WSW 2.5 Off 78 WSW-3 WSW 5.7 Off 79 WSW-4 WSW 7.8 Off 8I W-I w
0.6 On 82 W-2 w
4.3 Off 83 WNW-I WNW 0.4 On 84 WNW-2 WNW 5.3 Off 85 NW-I NW 0.4 On 86 NW-2 NW 5.2 Off 87 NNW-I NNW 0.6 On 88 NNW-2 NNW 1.7 On 89 NNW-3 NNW 5.3 Off 90 SSW-IB SSW 1.5 On
- a. See Figures A-I, A-2, and A-3.
- b. Dosimeters designated "onsite" are located 2 miles or less from the plant; "offsite" are located more than 2 miles from the plant Figure A-1 Radiological Environmental Monitoring Locations Within 1 mile of the Plant 78.75 E
101.25 191.25 s 168.75 Scale 0
Mile 1
Figure A-2 Radiological Environmental Monitoring Locations Between 1 and 5 miles from the Plant 348.75 N
191.25 s 11.25 168.75 0
SCALE 1
MILES 2
Figure A-3 Radiological Environmental Monitoring Locations More than 5 miles from the Plant 191.25 I
188.75 SCALE o=-=-r-16 18 *- ~~
MILES APPENDIXB PROGRAM MODIFICATIONS Appendix B Radiological Environmental Monitoring Program Modification The farm identified as Farm K closed its operation in 2015 and was replaced by Bacon Farm.
However, it was not removed from the REMP collection schedule until January of2016. Farm K was a control milk location. The change is reflected in the Tables and Figures of Appendix A of this report. There were no other modifications to the SQN REMP program during 2016.
APPENDIXC PROGRAM DEVIATIONS Appendix C Program Deviations During 2016, issues with sampling equipment resulted in missed air samples at two of twelve sampling stations during two separate sampling periods. In addition, excess loading resulted in missed air samples at one location.
During the 4th quarter, an abnormal value was reported from the vendor resulting in the loss of data from one of two paired dosimeters for that location.
Table C-1 provides additional details on the missed samples.
Table C-1 Radiological Environmental Monitoring Program Deviations Date Station Location Sample Type Description 03/14/2016 PM-3 5.6 Miles W AF/CF Maintenance was being performed that caused a loss of power to the station resulting in insufficient volume. This problem was documented in CR 1150251.
11/21/2016 PM-3 5.6 Miles W AF/CF The delta pressure had an abnormal reading from the filter being dirtier than usual. The excess was believed to be caused by the forest fires happening during this sampling period. Due to the abnormal delta pressure, the sample had an insufficient volume. This problem was documented in CR 1235586.
12/19/2016 LM-5 1.8 Miles NNE AF/CF During the weekly change out, station 2225 (LM-5) was found out of service. Emergency Preparedness Field Support personnel were contacted. After troubleshooting, the breaker was reset. This issue was documented in CR 1243992.
4th QTR2016 40-SQ-SSE-1 1.6 Miles SSE Dosimeter The A dosimeter for this location read abnormally high as compared to the paired B dosimeter. The questionable result was also compared to the previous 3 quarters data for this location. The questionable result was excluded.
This issue was documented in CR 1273019.
APPENOIXD ANALYTICAL PROCEDURES Appendix D Analytical Procedures Analyses of environmental samples, except for the Sr-89, 90 analysis of soil samples, are performed by the radioanalytical laboratory located at the Western Area Radiological Laboratory facility in Muscle Shoals, Alabama. The analysis procedures are based on accepted methods. A summary of the analysis techniques and methodology follows. The Sr-89, 90 analyses for soil samples are performed by a commercial laboratory.
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 sample to near dryness, transferring to a stainless steel planchet and completing the evaporation process. Air particulate filters are counted directly in a shallow planchet.
The specific analysis ofl-131 in milk is performed by first isolating and purifying the iodine by radiochemical separation and then counting the final precipitate on a beta-gamma coincidence counting system. The normal count time is 50 minutes. With the beta-gamma coincidence counting system, background counts are virtually eliminated and extremely low levels of activity can be detected.
After a radiochemical separation, milk samples analyzed for Sr-89, 90 are counted on a low background beta counting system. The sample is counted a second time after minimum ingrowth period of six days. From the two counts, the Sr-89 and Sr-90 concentrations can be determined.
Water samples are analyzed for tritium content by first distilling a portion of the sample and then counting by liquid scintillation. A commercially available scintillation cocktail is used.
Gamma analyses are performed in various counting geometries depending on the sample type and volume. All gamma counts are obtained with germanium type detectors interfaced with a computer based multichannel analyzer system.
The charcoal cartridges used to sample gaseous radioiodine are analyzed by gamma spectroscopy using a high resolution gamma spectroscopy system with germanium detectors.
The necessary 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.
APPENDIXE NOMINAL LOWER LIMITS OF DETECTION (LLD)
Appendix E Nominal Lower Limits of Detection A number of factors influence the Lower Limit of Detection (LLD) for a specific analysis method, including sample size, count time, counting efficiency, chemical processes, radioactive decay factors, and interfering isotopes encountered in the sample. The most probable values for these factors have been evaluated for the various analyses performed in the environmental monitoring program. The nominal LLDs are calculated from these values, in accordance with the methodology prescribed in the ODCM. The current nominal LLD values achieved by the ERM&I radioanalytical lab are listed in Table E-1. For comparison, the maximum values for the lower limits of detection specified in the ODCM are given in Table E-2.
The nominal LLDs are also presented in the data tables in Appendix H. For analyses for which LLDs have not been established, an LLD of zero is assumed in determining if a measured activity is greater than the nominal LLD. In these cases, the LLD value will appear as -1.00E+OO in the data tables in Appendix H.
Analysis Gross Beta Tritium Iodine-131 Strontium-89 Strontium-90 Air
{pCi/m3) 0.002 Water
{pCi/L) 1.9 270.0 0.4 Table E-1 Nominal LLD Values A. Radiochemical Procedures Milk (pCi/Ll 0.4 3.5 2.0.
Wet Vegetation
{pCi/kg wet) 6.0 Sediment and Soil
{pCi/g dry) 1.6 0.4
Table E-1 (continued)
Nominal LLD Values B. Gamma Analyses Foods Air Charcoal Water Wet Soil and Tomatoes Particulates Filter and Milk Vegetation Sediment Fish Potatoes, etc.
Analysis pCi/m3 pCi/m3 pCi/L pCi/kg, wet pCi/g, dry pCi/g. dry pCi/kg, wet Ce-141
.005 0.02 10 35
.10
.07 20 Ce-144
.01 0.07 30 115
.20
.15 60 Cr-51
.02 0.15 45 200
.35
.30 95 1-131
.005 0.03 10 60
.25
.20 20 Ru-103
.005 0.02 5
25
.03
.03 25 Ru-106
.02 0.12 40 190
.20
.15 90 Cs-134
.005 0.02 5
30
.03
.03 10 Cs-137
.005 0.02 5
25
.03
.03 10 Zr-95
.005 0.03 10 45
.05
.05 45 Nb-95
.005 0.02 5
30
.04
.25 10 Co-58
.005 0.02 5
20
.03
.03 10 Mn-54
.005 0.02 5
20
.03
.03 10 Zn-65
.005 0.03 10 45
.05
.05 45 Co-60
.005 0.02 5
20
.03
.03 10 K-40
.04 0.30 100 400
.75
.40 250 Ba-140
.015 0.07 25 130
.30
.30 50 La-140
.01 0.04 10 50
.20
.20 25 Fe-59
.005 0.04 10 40
.05
.08 25 Be-7
.02 0.15 45 200
.25
.25 90 Pb-212
.005 0.03 15 40
.10
.04 40 Pb-214
.005 0.07 20 80
.15
.10 80 Bi-214
.005 0.05 20 55
.15
.10 40 Bi-212
.02 0.20 50 250
.45
.25 130 Tl-208
.002 0.02 10 30
.06
.03 30 Ra-224
.75 Ra-226
.15 Ac-228
.01 0.07 20 70
.25
.10 50 Pa-234m 800 4.0 Table E-2 Maximum Values for the Lower Limits of Detection (LLD)
Specified by the SQN Offsite Dose Calculation Manual Airborne Particulate Food Water or Gases Fish Mille Products Sediment Analysis pCi/L pCi/m3 pCi/kg. wet pCi/L pCi/kg. wet pCi/kg. dry Gross Beta 4
1x10*2 N.A.
N.A.
N.A.
N.A.
H-3 20008 N.A.
N.A.
N.A.
N.A.
N.A.
Mn-54 15 N.A.
130 N.A.
N.A.
N.A.
Fe-59 30 N.A.
260 N.A.
N.A.
N.A.
Co-58,60 15 N.A.
130 N.A.
N.A.
N.A.
Zn-65 30 N.A.
260 N.A.
N.A.
N.A.
Zr-95 30 N.A.
N.A.
N.A.
N.A.
N.A.
Nb-95 15 N.A.
N.A.
N.A.
N.A.
N.A.
1-131 lb 7 x 10*2 N.A.
60 N.A.
Cs-134 15 5 x10*2 130 15 60 150 Cs-137 18 6 x 10*2 150 18 80 180 Ba-140 60 N.A.
N.A.
60 N.A.
N.A.
La-140 15 N.A.
N.A.
15 N.A.
N.A.
- a. If no drinking water pathway exists, a value of 3000 pCi/liter may be used.
- b.
lfno drinking water pathway exists, a value of 15 pCi/liter may be used.
APPENDIXF QUALITY ASSURANCE/QUALITY CONTROL PROGRAM AppendixF Quality Assurance/Quality Control Program A 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, provisions for staff training and certification, internal self assessments of program performance, audits by various external organizations, and a laboratory quality control program.
The quality control program empfoyed 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 quality control samples along with routine samples. Instrument quality control checks include background count rate and counts reproducibility. In addition to these two general checks, other quality control checks are performed on the variety of detectors used in the laboratory. The exact nature of these checks depends on the type of device and the method it uses to detect radiation or store the information obtained.
Quality control samples of a variety of types are used by the laboratory to verify the performance of different portions of the analytical process. These quality control samples include blanks, replicate samples, blind samples, and cross-checks.
Blanks are samples which contain no measurable radioactivity or no activity of the type being measured. Such samples are analyzed to determine whether there is any contamination of equipment or commercial laboratory chemicals, cross-contamination in the chemical process, or interference from isotopes other than the one being measured.
Duplicate samples are generated at random by the sample computer program which schedules the collection of the routine samples. For example, ifthe routine program calls for four milk samples every week, on a random basis each farm might provide an additional sample several times a year. These duplicate samples are analyzed along with 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 staff can split it into two portions. Such a sample provides information about the variability of the analytical process since two identical portions of material are analyzed side by side.
Analytical knowns are another category of quality control sample. A known amount of radioactivity is added to a sample medium. The lab staff knows 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, analytical knowns provide immediate data on the quality of the measurement process.
Blind spikes are samples containing radioactivity which are introduced into the analysis process disguised as ordinary environmental samples. The lab staff does not know the sample contains radioactivity. Since the bulk of the ordinary workload of the environmental laboratory contains no measurable activity or only naturally occurring radioisotopes, blind spikes can be used to test the detection capability of the laboratory or can be used to test the data review process. If an analysis routinely generates numerous zeroes for a particular isotope, the presence of the isotope is brought to the attention of the lead chemist in the daily review process.
Blind spikes test this process since the blind spikes contain radioactivity at levels high enough to be detected. Furthermore, the activity can be put into such samples at the extreme limit of detection (near the LLD) to verify that the laboratory can detect very low levels of activity.
Another category of quality control samples is the internal cross-checks. These samples have a known amount of radioactivity added and are presented to the lab staff labeled as cross-check samples. This means that the quality control staff knows the radioactive content or "right answer" but the lab personnel performing the analysis do not. Such samples test the best performance of the laboratory by determining if the lab can find the "right answer." These samples provide information about the accuracy of the measurement process. Further information is available about the variability of the process if multiple analyses are requested on the same sample. Like blind spikes or analytical knowns, these samples can also be spiked with low levels of activity to test detection limits. The lab results for the internal quality control program samples met the program performance goals.
To provide for an independent verification of the laboratory's ability to make accurate measurements, the laboratory participated in an environmental level cross-check program available through Eckert and Ziegler Analytics, during 2016. The results for these cross-check
- samples, as shown in Table F-1, were all within the program agreement limits with the exception of the Tritium in Synthetic Urine result for the first quarter cross-checks and the Sr-89,90 in Milk result for the third quarter cross-checks. The investigation for the Tritium in Synthetic Urine determined the wrong volume was used in the analysis for the cross-check. The disagreement was documented in CR 1187094. The cross-check was reordered and analyzed in the second quarter and results were within agreement. The disagreement for Sr-89,90 in Milk was documented in CR 1241797. A replacement sample was ordered and reanalyzed. At the time of this report the results have not been received.
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.
Table F-1 Results For 2016 External Cross Checks
&mil!
Test Period Sami!le T~~ l &m!x1i1 K!!!!M!
!YA
~
First Quarter Water (pCi/L)
Gross Beta 2.SIE+o2 2.SSE+o2 1.02 First Quarter Water (pCi/L) 3H 4.63E+o3 4.S7E+o3 0.99 First Quarter Water (pCi/L)
"'1 8.89E+ol 8.90E+ol 1.00 "er 2.93E+o2 2.90E+02 0.99 134Cs l.S7E+o2 l.46E+02 0.93 137Cs l.94E+02 l.94E+o2 1.00
- co l.4IE+o2 l.39E+o2 0.99 "Mn l.40E+o2 1.48E+o2 1.06 09Fe l.S7E+02 l.49E+o2 0.9S "Zn 2.1SE+02 2.20E+o2 1.02
'°Co 2.93E+o2 3.03E+o2 1.03
,.,Ce 1.18E+o2 l.13E+o2 0.96 First Quarter Synthetic Urine (pCi/L) 3H 1.34E+o4 6.67E+o3 o.so First Quarter Milk(pCi/L) 1311 9.20E+ol 9.31E+ol 1.01 89Sr 7.83E+ol 7.39E+ol 0.94 90Sr l.03E+ol l.OSE+Ol 1.02 First Quarter Air Filter (pCi/Filter)
Gross Beta 7.72E+ol 7.70E+Ol 1.00 Second Quarter.
Synthetic Urine (pCi/L) 3H l.34E+o4 l.40E+o4 I.OS Third Quarter Water (pCi/L) 3H l.35E+o4 l.35E+o4 1.00 Third Quarter Sand (pCi/gram)
,.,Ce l.83E-Ol l.76E-01 0.96 "er 4.61E-01 4.44E-01 0.96 134Cs 2.66E-01 2.64E-01 0.99 137Cs 2.32E-01 2.16E-Ol 0.93
- co l.91E-01 1.78E-01 0.93 "Mn 2.98E-01 3.13E-01 I.OS 09Fe l.78E-01 l.71E-01 0.96
"'Zn 3.SOE-01 3.64E-01 1.04
'°Co 2.64E-01 2.S7E-01 0.91 Third Quarter Air Filter (pCi/Filter)
Gross Beta S.60E+ol 4.81E+ol 0.86 Third Quarter Air Filter (pCi/Filter) 141Ce 7.27E+ol 7.41E+ol 1.02 "er 1.84E+02 1.8SE+o2 1.01 134Cs l.06E+o2 9.16E+ol 0.86 137Cs 9.25E+Ol 9.43E+Ol 1.02
'"co 7.60E+Ol 7.42E+ol 0.98 "Mn 1.19E+o2 l.28E+o2 1.08 09Fe 7.07E+ol 7.23E+ol 1.02
"'Zn 1.39E+o2 1.6IE+o2 1.16 60Co 1.0SE+o2 1.12E+o2 1.07 Third Quarter Synthetic Urine (pCi/L) 3H l.32E+o4 l.36E+o4 1.03 Third Quarter Milk (pCi/L) 1311 8.lSE+ol 8.29E+ol 1.02 89Sr 8.97E+ol S.04E+ol O.S6 90Sr l.3SE+ol 9.06E+o0 0.67 APPENDIXG LAND USE SURVEY Appendix G Land Use Survey A land use survey is conducted annually to identify the location of the nearest milk producing 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 (8,047 meters) 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.
Using survey data, relative radiation doses are projected for individuals living near the plant.
These projections use the data obtained in the survey and historical meteorological data. They also assume that releases are equivalent to the design basis source terms. The calculated doses are relative in nature and do not reflect actual exposures received by individuals living near SQN. Calculated doses to individuals based on measured effluents from the plant are well below applicable dose limits.
Using the locations identified in the 2016 SQN land use survey, annual dose projections 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.
There were no changes in the location of the nearest resident as identified in 2016 compared to 2015. The location of the nearest garden changed in a total of four sectors. The survey of milk producing locations performed in 2016 did not identify any new locations.
Tables G-1, G-2, and G-3 show the comparative relative calculated doses for 2016 and 2015.
Sector N
NNE NE ENE E
WNW NW NNW Table G-1 SEQUOYAH NUCLEAR PLANT Relative Projected Annual Air Submersion Dose to the Nearest Resident Within Five Miles (8,047 meters) of Plant mrem/year 2015 Survey 2016 Survey Approximate Approximate Distance Annual Distance Meters Dose Meters 1,389 0.13 1,389 2,456 0.07 2,456 2,361 0.06 2,361 2,127 0.02 2,127 1,685 0.02 1,685 1,693 0.02 1,693 1,721 0.03 1,721 2,073 0.04 2,073 1,764 0.13 1,764 2,129 0.14 2,129 2,502 0.04 2,502 1,036 0.06 1,036 982 0.05 982 1,331 0.03 1,331 1,316 0.05 1,316 864 0.13 864 Annual Dose 0.13 0.07 0.06 0.02 0.02 0.02 0.03 0.04 0.13 0.14 0.04 0.06 0.05 0.03 0.05 0.13
Table G-2 SEQ UOY AH NUCLEAR PLANT Relative Projected Annual Dose to Child's Bone from Ingestion of Home-Grown Foods mrem/year 2015 Survey 2016 Survey Approximate Approximate Distance Annual Distance Annual Sector Meters Dose Meters Dose N
4,329 0.74 4,329 0.74 NNE 3,770 1.24 3,770 1.24 NE 4,551 0.68 1,400 3.87 ENE 5,220 0.21 5,220 0.21 E
4,332 0.16 5,933 0.10 ESE 1,861 0.51 1,861 0.51 SE 3,406 0.30 3,406 0.30 SSE 8,046 0.17 6,969 0.20 s
4,137 1.14 4,137 1.14 SSW 4,532 1.55 4,532 1.55 SW 4,440 0.64 4,440 0.64 WSW 1,152 1.69 1,152 1.69 w
1,419 0.89 1,393 0.92 WNW 5,363 0.14 5,363 0.14 NW 1,316 1.48 1,316 1.48 NNW 635 6.56 635 6.56 Location FarmHW NW Table G-3 SEQ UOY AH NUCLEAR PLANT Relative Projected Annual Dose to Receptor Thyroid from Ingestion of Mille mrem/year Annual Dose Approximate Distance (Meterst 2015 2016 2,074 0.064 0.064
- a.
Distances measured to nearest property line. X/Q (units-s/m3) 6.18 E-07
APPENDIXH DATA TABLES AND FIGURES
- Average, 0-2 miles (onsite)
- Average,
> 2 miles (offsite)
Table H -1 DIRECT RADIATION LEVELS Average External Gamma Radiation Levels Onsite and Offsite Sequoyah Nuclear Plant for Each Quarter-2016 mR I Quarter (a)
Average External Gamma Radiation Levels (b) 1st qtr 2nd qtr 3rd qtr 4th qtr 15.1 14.9 17.0 15.6 13.7 13.3 15.2 14.2 mR/yr (c) 63 56 (a)
Field periods normalized to one standard quarter (2190 hours0.0253 days <br />0.608 hours <br />0.00362 weeks <br />8.33295e-4 months <br />)
(b)
Average of the individual measurements in the set (c)
The 6.2 mrem/yr for onsite locations falls below the 25 mrem total body limit in 10 CFR 190.
TABLE H-2 DIRECT RADIATION LEVELS Individual Stations at Sequoyah Nuclear Plant Environmental Radiation Levels mR I quarter Map Dosimeter Approx 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Annual Location Station Direction,
- Distance, Jan-Mar Apr-Jun Jul-Sep Oct-Dec Exposure Number Number degrees miles 2016 2016 2016 2016 mR/:tear 49 N-1 3
.6 17.1 14.4 18.2 19.1 68.8 50 N-2 4
2.1 12.8 13.4 19.1 16.5 61.8 51 N-3 358 5.2 12.8 13.0 13.6 14.4 53.8 52 N-4 355 10.0 13.8 15.6 22.8 15.4 67.6 5
NNE-1 13 1.8 13.8 17.8 20.5 20.0 72.1 53 NNE-2 31 5.3 13.3 13.4 15.4 14.9 57.0 12 NNE-4 32 17.8 15.1 11.5 14.6 14.6 55.8 55 NE-1 38 2.4 14.7 14.5 20.0 17.5 66.7 4
NE-1A 50 1.5 14.2 14.0 19.1 16.5 63.8 56 NE-2 51 4.1 10.9 10.7 11.3 8.3 41.2 57 ENE-1 73
.2 15.3 11.8 15.4 13.3 55.8 58 ENE-2 66 5.1 14.2 15.1 13.1 12.4 54.8 59 E-1 96 1.2 13.8 12.4 12.7 13.4 52.3 60 E-2 87 5.2 15.2 13.4 14.1 14.4 57.1 62 ESE-1 110 1.2 14.2 14.5 15.9 13.4 58.0 63 ESE-2 112 4.9 14.2 14.5 15.4 14.9 59.0 13 ESE-3 117 11.3 11.9 13.4 13.6 13.4 52.3 66 SE-1 131 1.4
- 11.9 10.7 11.8 12.9 47.3 67 SE-2 129 1.9 12.8 12.4 15.9 13.4 54.5 68 SE-4 136 5.2 15.6 16.7 18.7 15.9 66.9 69 SSE-1 154 1.6 11.9 12.9 15.9 10.4 51.1 70 SSE-2 158 4.6 13.3 15.6 18.7 18.0 65.6 (1)
Sum of available quarterly data normalized to 1 year for the annual exposure value.
TABLE H -2 continued DIRECT RADIATION LEVELS Individual Stations at Sequoyah Nuclear Plant Environmental Radiation Levels mR I quarter Map Dosimeter Approx 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Annual Location Station Direction,
- Distance, Jan-Mar Apr-Jun Jul-Sep Oct-Dec Exposure Number Number degrees miles 2016 2016 2016 2016 mR/xear 71 S-1 183 1.5 16.6 17.8 19.1 19.0 72.5 72 S-2 185 4.7 13.3 12.9 11.8 11.4 49.4 73 SSW-1 203
.6 17.2 15.6 20.0 14.8 67.6 90 SSW-18 192 1.5 11.9 10.7 10.4 11.4 44.4 3
SSW-1C 198 2.0 13.3 11.8 14.5 12.9 52.5 74 SSW-2 204 4.0 17.5 21.1 21.0 17.0 76.6 9
SSW-3 203 8.7 14.2 16.7 14.5 15.9 61.3 75 SW-1 228
.7 17.5 16.7 18.7 18.5 71.4 7
SW-2 227 3.8 15.1 10.7 16.0 14.3 56.1 11 SW-3 228 16.7 16.5 15.2 19.9 17.6 69.2 76 WSW-1 241
.9 17.1 18.9 17.3 18.5 71.8 77 WSW-2 238 2.5 11.8 8.6 10.8 10.4 41.6 10 WSW-2A 250 2.6 12.7 12.4 14.1 13.4 52.6 78 WSW-3 248 5.7 16.9 15.6 18.3 15.8 66.6 79 WSW-4 244 7.8 13.7 10.2 12.7 11.8 48.4 81 W-1 260
.6 19.7 24.9 22.4 23.6 90.6 82 W-2 275 4.3 12.4 10.2 11.8 13.9 48.3 8
W-3 280 5.6 11.9 10.2 11.3 12.4 45.8 83 WNW-1 292
.4 16.5 16.7 17.7 15.4 66.3 84 WNW-2 295 5.3 11.4 12.4 13.1 12.9 49.8 85 NW-1 315
.4 16.6 15.0 19.6 15.9 67.1 86 NW-2 318 5.2 12.8 10.7 14.1 12.9 50.5 14 NW-3 320 20.0 14.2 10.7 9.4 13.5 47.8 87 NNW-1 344
.6 15.6 17.1 21.4 15.6 69.7 88 NNW-2 342 1.7 14.2 12.4 13.6 14.4 54.6 89 NNW-3 334 5.3 12.4 13.4 16.4 13.9 56.1 (1)
Sum of available quarterly data normalized to 1 year for the annual exposure value.
Name of Facility: SEQUOYAH NUCLEAR PLANT Location of Facility: HAMIL TON, TENNESSEE Type and Total Number of Analysis Performed GROSS BETA - 633 GAMMA SCAN (GELi) - 168 AC-228 BE-7 Bl-214
°' K-40
.i:.
I PB-212 PB-214 TL-208 Lower Limit of Detection (LLD)
See Note 1 2.00E-03 1.00E-02 2.00E-02 5.00E-03 4.00E-02 5.00E-03 5.00E-03 2.00E-03 Indicator Locations Mean (F)
Range See Note 2 2.04E-02 (421 / 421) 2.58E 4.24E-02 2.21 E-02 (1 / 112) 2.21 E 2.21 E-02 1.18E-O 1 ( 112 / 112) 6.23E 1.79E-01 2.49E-02 (110 / 112) 5.40E 1.73E-01 4.29E-02 (2 / 112) 4.16E 4.42E-02 1.10E-02 (6 / 112) 9.20E 1.44E-02 2.43E-02 (109 / 112) 5.1 OE 1.81 E-01 3.92E-03 (5 / 112) 2.00E 6.30E-03 Tennessee Valley Authority RADIOACTIVITY IN AIR FILTER pCi/m113 = 0.037 Bq/m113 Docket Number:
50-327,328 Reporting Period:
2016 Location with Highest Annual Mean Mean (F)
Location Description with Range Distance and Direction See Note 2 PM-8 HARRISON TN 2.09E-02 (53 I 53) 8.7 MILES SSW 3.95E 4.01 E-02 PM-3 DAISY TN 2.21E-02 (1/14) 5.6 MILESW 2.21 E 2.21 E-02 PM-8 HARRISON TN 1.24E-01 (14/14) 8.7 MILES SSW 8.05E 1.65E-01 LM-5 WARE POINT 3.75E"02 (13114) 1.8 MILES NNE 5.60E 1.73E-01 PM-2 COUNTY PARK TN 4.29E-02 (2 / 14) 3.8MILESSW 4.16E 4.42E-02 PM-3 DAISY TN 1.44E-02 (1/14) 5.6MILESW 1.44E 1.44E-02 LM-5 WARE POINT 3.73E-02 (13 / 14) 1.8 MILES NNE 5.20E 1.81 E-01 LM-5 WARE POINT 4.70E-03 (1 / 14) 1.8 MILES NNE 4.70E 4.70E-03 Control Locations Mean (F)
Range See Note 2 2.06E-02 (212 I 212) 3.30E 7.07E-02 56 VALUES < LLD 1.16E-01 (56 I 56) 6.47E 1.74E-01 2.71 E-02 (55 / 56) 5.40E 1.89E-01 56 VALUES < LLD 1.02E-02 (3 I 56) 6.80E 1.19E-02 2.59E-02 (54 I 56) 5.20E 1.75E-01 6.90E-03 (1 I 56) 6.90E 6.90E-03 Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1
- 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F):
- 3. Blanks in this column indicate no nonrountine measurements Number of Nonroutine Reported Measurements See Note 3
~
~ -
(1)
- c:
I w
Name of Facility: SEQUOYAH NUCLEAR PLANT Location of Facility: HAMIL TON, TENNESSEE Type and Total Number of Analysis Performed GAMMA SCAN (GELi) - 633 AC-228 81-214 1-131 K-40 PB-212 I 0\\
V'PB-214 TL-208 Lower Limit of Detection (LLD)
See Note 1 7.00E-02 5.00E-02 3.00E-02 3.00E-01 3.00E-02 7.00E-02 2.00E-02 Indicator Locations Mean (F)
Range See Note 2 421 VALUES < LLD 9.36E-02 (182 / 421) 5.03E 3.63E-01 SEE NOTE4 3.60E-01 (79 I 421) 3.01 E 5.94E-01 421 VALUES < LLD 1.24E-01 (104 I 421) 7.00E 4.14E-01 421 VALUES < LLD Tennessee Valley Authority RADIOACTIVITY IN CHARCOAL FILTER pCi/m"3 = 0.037 Bq/m"3 Docket Number:
50-327,328 Reporting Period:
2016 Location with Highest Annual Mean Mean (F)
Location Description with Range Distance and Direction See Note 2 LM-5 WARE POINT 1.8 MILES NNE PM-8 HARRISON TN 8.7 MILES SSW LM-5 WARE POINT 1.8 MILES NNE PM-2 COUNTY PARK TN 3.8MILESSW PM-8 HARRISON TN 8.7 MILES SSW PM-3 DAISY TN 5.6MILESW 52 VALUES < LLD 1.05E-01 (31 / 53) 5.07E 3.06E-01 3.85E-01 (9 I 52) 3.54E 4.64E-01 53 VALUES< LLD 1.46E-01 (18 I 53) 7.00E 4.14E-01 51 VALUES< LLD Control Locations Mean (F)
Range See Note2 212 VALUES< LLD 9.87E-02 (91 / 212) 5.04E 3.14E-01 3.56E-01 (40 I 212) 3.01 E 5.38E-01 212 VALUES< LLD 1.28E-01 (50 I 212) 7.22E 3.13E-01 212 VALUES< LLD Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1
- 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).
- 3. Blanks in this column indicate no nonrountine measurements Number of Nonroutine Reported Measurements See Note 3
- 4. The analysis of Charcoal Filters was performed by Gamma Spectroscopy. No 1-131 was detected. The LLD for 1-131 by Gamma Spectroscopy was 0.03 pCi/cubic meter.
1-1
~ -
0
- c:
I
~
Name of Facility: SEQUOYAH NUCLEAR PLANT Location of Facility: HAMIL TON, TENNESSEE Type and Total Number of Analysis Performed IODINE-131 -40 GAMMA SCAN (GELi) - 40 AC-228 Bl-214 K-40 6'PB-212
°'
I PB-214 TL-208 SR 89 -6 SR 90 -6 Lower Limit of Detection (LLD)
See Note 1 4.00E-01 2.00E+01 2.00E+01 1.00E+02 1.50E+01 2.00E+01 1.00E+01 3.50E+OO 2.00E+OO Indicator Locations Mean (F)
Range See Note 2 14 VALUES < LLD 3.57E+01 (1 / 14) 3.57E+01 -
3.57E+01 3.73E+01 (6 / 14) 2.09E+01 -
5.40E+01 8.61 E+02 (14 / 14) 2.11 E+02 -
1.26E+03 2.18E+01 (1/14) 2.18E+01 -
2.18E+01 3.93E+01 (2 / 14) 3.47E+01 - 4.39E+01 14 VALUES < LLD 2 VALUES < LLD 2 VALUES < LLD Tennessee Valley Authority RADIOACTIVITY IN MILK pCi/L = 0.037 Bq/L Docket Number:
50-327,328 Reporting Period:
2016 Location with Highest Annual Mean Mean (F)
Location Description with Range Distance and Direction See Note 2 H WALKER FARM 1.2 MILES NW H WALKER FARM 1.2 MILES NW H WALKER FARM 1.2 MILES NW H WALKER FARM 1.2 MILES NW H WALKER FARM 1.2 MILES NW H WALKER FARM 1.2 MILES NW 3.57E+01 (1 / 14) 3.57E+01 -
3.57E+01 3.73E+01 (6 / 14) 2.09E+01 -
5.40E+01 8.61E+02 (14 / 14) 2.11 E+02 -
1.26E+03 2.18E+01 (1 / 14) 2.18E+01 -
2.18E+01 3.93E+01 (2 / 14) 3.47E+01 -
4.39E+01 14 VALUES < LLD Control Locations Mean (F)
Range See Note2 26 VALUES< LLD 2.03E+01 (1 I 26) 2.03E+01 - 2.03E+01 3.93E+01 (13 / 26) 2.13E+01 - 1.05E+02 1.31 E+03 (26 / 26) 1.18E+03 - 1.48E+03 26 VALUES< LLD 4.20E+01 (7 I 26) 2.29E+01 - 8.27E+01 26 VALUES< LLD 4 VALUES < LLD 4 VALUES < LLD Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1
- 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).
- 3. Blanks in this column indicate no nonrountine measurements Number of Nonroutine Reported Measurements See Note 3
~
~ -
tD
- z::
I UI
Name of Facility: SEQUOYAH NUCLEAR PLANT Location of Facility: HAMIL TON, TENNESSEE
.Type and Total Number of Analysis Performed IODINE-131 - 18 GAMMA SCAN (GELi) - 18 AC-228 BE-7 Bl-214
°'K-40
....:i I
PB-212 PB-214 TL-208 Lower Limit of Detection (LLD)
See Note 1 6.00E+OO 7.00E+01 2.00E+02 5.50E+01 4.00E+02 4.00E+01 8.00E+01 3.00E+01 Indicator Locations Mean (F)
Range See Note2 12 VALUES< LLD 8.49E+01 (1 / 12) 8.49E+01 -
8.49E+01 1.84E+03 (12 / 12) 2.96E+02 - 4.28E+03 1.48E+02 (10 / 12) 5.65E+01 - 2.49E+02 4.78E+03 (12 / 12) 1.67E+03 - 8.56E+03 4.03E+01 (1 / 12) 4.03E+01 - 4.03E+01 1.46E+02 (9 / 12) 8.91 E+01 -
2.32E+02 12 VALUES< LLD Tennessee Valley Authority RADIOACTIVITY IN VEGETATION pCi/Kg = 0.037 Bq/Kg (WET WEIGHT)
Docket Number:
50-327,328 Reporting Period:
2016 Location with Highest Annual Mean Mean (F)
Location Description with R1[mge Distance and Direction See Note 2 H WALKER FARM 8.49E+01 (1 / 12) 1.2 MILES NW 8.49E+01 -
8.49E+01 H WALKER FARM 1.84E+03 (12 / 12) 1.2 MILES NW 2.96E+02 -
4.28E+03 H WALKER FARM 1.48E+02 (10/12) 1.2 MILES NW 5.65E+01 -
2.49E+02 H WALKER FARM 4.78E+03 (12 / 12) 1.2 MILES NW 1.67E+03 -
8.56E+03 H WALKER FARM 4.03E+01 (1 / 12) 1.2 MILES NW 4.03E+01 -
4.03E+01 H WALKER FARM 1.46E+02 (9 / 12) 1.2MILES NW 8.91 E+01 -
2.32E+02 H WALKER FARM 12 VALUES< LLD 1.2MILES NW Control Locations Mean (F)
Range See Note 2 6 VALUES < LLD 6 VALUES < LLD 9.32E+02 (6 / 6) 2.79E+02 - 3.46E+03 1.23E+02 (3 I 6) 1.01 E+02 - 1.37E+02 4.74E+03 (6 / 6) 2.70E+03 - 6.38E+03 5.96E+01 (1 / 6) 5.96E+01 - 5.96E+01 1.16E+02 (3 / 6) 9.27E+01 - 1.39E+02 6 VALUES < LLD Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1
- 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).
- 3. Blanks in this column indicate no nonrountine measurements Number of Nonroutine Reported Measurements See Note 3 i-3
~
n
- .c:
I
°'
Name of Facility: SEQUOYAH NUCLEAR PLANT Location of Facility: HAMIL TON, TENNESSEE Type and Total Number of Analysis Performed GAMMA SCAN (GELi) - 12 AC-228 BE-7 81-212 Bl-214 CS-137 I °'
c:ioK-40 PA-234M PB-212 PB-214 RA-226 TL-208 SR89 -12 SR 90 -12 Lower Limit of Detection (LLD)
See Note 1 2.50E-01 2.50E-01 4.50E-01 1.50E-01 3.00E-02 7.50E-01 4.00E+OO 1.00E-01 1.50E-01 1.50E-01 6.00E-02 1.60E+OO 4.00E-01 Indicator Locations Mean (F)
Range See Note2 9.36E-01 (8 I 8) 4.64E 1.65E+OO
- 2. 78E-01 (1 I 8) 2.78E 2.78E-01 1.01 E+OO (8 I 8)
- 4. 78E 1.88E+OO 8.26E-01 (8 I 8) 4.37E 1.28E+OO 2.62E-01 (4 / 8) 1.25E 4.57E-01
- 5. 79E+OO (8 I 8) 3.08E+OO -
1.08E+01 8 VALUES < LLD 9.35E-01 (8 I 8) 4.61 E 1.66E+OO 8.97E-01 (8 I 8) 5.15E 1.38E+OO 8.26E-01 (8 I 8) 4.37E 1.28E+OO 3.05E-01 (8 I 8) 1.56E 5.48E-01 8 VALUES< LLD 8 VALUES< LLD Tennessee Valley Authority RADIOACTIVITY IN SOIL pCi/g = 0.037 Bq/g (DRY WEIGHT)
Docket Number:
50-327,328 Reporting Period:
2016 Location with Highest Annual Mean Mean (F)
Location Description with Range Distance and Direction See Note 2 LM-5 WARE POINT 1.65E+OO (1 / 1) 1.8 MILES NNE 1.65E+OO -
1.65E+OO PM-3 DAISY TN
- 2. 78E-01 (1 / 1) 5.6MILESW 2.78E 2.78E-01 LM-5 WARE POINT 1.88E+OO (1 / 1) 1.8 MILES NNE 1.88E+OO -
1.88E+OO PM-8 HARRISON TN 1.28E+OO (1 / 1) 8.7 MILES SSW 1.28E+OO -
1.28E+OO LM-4 SKULL ISLAND 4.57E-01 (1 / 1) 1.5MILES NE 4.57E 4.57E-01 LM-2 NORTH 1.08E+01 (1 / 1) 0.8 MILES NORTH 1.08E+01 -
1.08E+01 LM-5 WARE POINT 1 VALUES < LLD 1.8 MILES NNE LM-5 WARE POINT 1.66E+OO (1 / 1) 1.8 MILES NNE 1.66E+OO -
1.66E+OO PM-8 HARRISON TN 1.38E+OO (1 / 1) 8.7 MILES SSW 1.38E+OO -
1.38E+OO PM-8 HARRISON TN 1.28E+OO (1 / 1) 8.7 MILES SSW 1.28E+OO -
1.28E+OO LM-5 WARE POINT 5.48E-01 (1 / 1) 1.8 MILES NNE 5.48E 5.48E-01 Control Locations Mean (F)
Range See Note 2 9.51 E-01 (4 I 4) 5.71E 1.33E+OO 6.06E-01 (2 / 4) 4.26E 7.86E-01 1.00E+OO (4 / 4) 5.54E 1.48E+OO 7.85E-01 (4 / 4) 6.10E 9.99E-01 1.32E-01 (3 I 4) 3.73E 2.48E-01 8.31 E+OO (4 / 4) 4.48E+OO - 1.89E+01 4 VALUES < LLD 9.61E-01 (4 / 4) 5.71E 1.33E+OO 8.51 E-01 (4 / 4) 6.24E 1.08E+OO 7.85E-01 (4 / 4) 6.1 OE 9.99E-01 3.14E-01 (4 / 4) 1.93E 4.44E-01 4 VALUES< LLD 4 VALUES < LLD Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1
- 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).
- 3. Blanks in this column indicate no nonrountine measurements Number of Nonroutine Reported Measurements See Note 3 t-3 g..
tr
- i=
-...J
Name of Facility: SEQUOYAH NUCLEAR PLANT Location of Facility: HAMIL TON, TENNESSEE Type and Total Number of Analysis Performed GAMMA SCAN {GELi) - 3 Bl-214
°'
'P K-40 PB-214 Lower Limit of Detection
{LLD)
See Note 1 4.00E+01 2.50E+02 8.00E+01 Indicator Locations Mean {F)
Range See Note2 1.41E+02 {1/1) 1.41E+02 -
1.41E+02 1.59E+03 (1 / 1) 1.59E+03 -
1.59E+03 1 VALUES < LLD Tennessee Valley Authority RADIOACTIVITY IN CABBAGE pCi/Kg = 0.037 Bq/Kg (WET WEIGHT)
Docket Number:
50-327,328 Reporting Period:
2016 Location with Highest Annual Mean Mean {F)
Location Description with Range Distance and Direction See Note 2 1 MILES NW 1 MILES NW 1 MILES NW 1.41E+02 (1/1) 1.41E+02 -
1.41E+02 1.59E+03 (1 / 1) 1.59E+03 -
1.59E+03 1 VALUES< LLD Control Locations Mean {F)
Range See Note 2 2 VALUES < LLD 2.32E+03 (2 I 2) 2.07E+03 - 2.57E+03 2 VALUES < LLD Notes: 1. Nominal Lower Level of Detection {LLD) as described in Table E - 1
- 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).
- 3. Blanks in this column indicate no nonrountine measurements Number of Nonroutine Reported Measurements See Note 3
~
~
n
- t=
00
Name of Facility: SEQUOYAH NUCLEAR PLANT Location of Facility: HAMIL TON, TENNESSEE Type and Total Number of Analysis Performed GAMMA SCAN (GELi) - 2 Bl-214
.!.:i er K-40 PB-214 Lower Limit of Detection (LLD)
See Note 1 4.00E+01 2.50E+02 8.00E+01 Indicator Locations Mean (F)
Range See Note 2 1 VALUES< LLD 1.95E+03 (1 / 1) 1.95E+03 -
1.95E+03 1 VALUES < LLD Tennessee Valley Authority RADIOACTIVITY IN CORN pCi/Kg = 0.037 Bq/Kg (WET WEIGHT)
Docket Number:
50-327,328 Reporting Period:
2016 Location with Highest Annual Mean Mean (F)
Location Description with Range Distance and Direction See Note 2 1 MILES NW 1 MILES NW 1 MILES NW 1 VALUES < LLD 1.95E+03 (1 / 1) 1.95E+03 -
1.95E+03 1 VALUES< LLD Control Locations Mean (F)
Range See Note2 1 VALUES< LLD 2.16E+03 (1/1) 2.16E+03 - 2.16E+03 1 VALUES< LLD Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1
- 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).
- 3. Blanks in this column indicate no nonrountine measurements Number of Non routine Reported Measurements See Note 3
~
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- c:
I
"°
Name of Facility: SEQUOYAH NUCLEAR PLANT Location of Facility: HAMIL TON, TENNESSEE Type and Total Number of Analysis Performed GAMMA SCAN (GELi) - 2 Bl-214 K-40 PB-214 I
-...I -
I Lower Limit of Detection (LLD)
See Note 1 4.00E+01 2.50E+02 8.00E+01 Indicator Locations Mean (F)
Range See Note 2 1.67E+02 (1 / 1) 1.67E+02 -
1.67E+02 4.13E+03 (1/1) 4.13E+03 - 4.13E+03 1.80E+02 (1 / 1) 1.80E+02 -
1.80E+02 Tennessee Valley Authority RADIOACTIVITY IN GREEN BEANS pCi/Kg = 0.037 Bq/Kg (WET WEIGHT)
Docket Number:
50-327,328 Reporting Period:
2016 Location with Highest Annual Mean Mean (F)
Location Description with Range Distance and Direction See Note 2 1 MILES NW 1.67E+02 (1 / 1) 1.67E+02 -
1.67E+02 1 MILES NW 4.13E+03 (1/1) 4.13E+03 -
4.13E+03 1 MILES NW 1.80E+02 (1 / 1) 1.80E+02 -
1.80E+02 Control Locations Mean (F)
Range See Note 2 5.53E+01 (1 / 1) 5.53E+01 - 5.53E+01 3.70E+03 (1 / 1) 3.70E+03 - 3.70E+03 1 VALUES < LLD Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1
- 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).
- 3. Blanks in this column indicate no nonrountine measurements Number of Nonroutine Reported Measurements See Note 3
- g.
0
- p 0
Name of Facility: SEQUOYAH NUCLEAR PLANT Location of Facility: HAMIL TON, TENNESSEE Type and Total Number of Analysis Performed GAMMA SCAN {GELi) - 2 81-214 I
-..J t;->
K-40 PB-212 PB-214 Lower Limit of Detection
{LLD)
See Note 1 4.00E+01 2.50E+02 4.00E+01 8.00E+01 Indicator Locations Mean {F)
Range See Note 2 6.17E+01 (1 / 1) 6.17E+01 - 6.17E+01 9.84E+02 (1 / 1) 9.84E+02 -
9.84E+02 1 VALUES < LLD 1 VALUES < LLD Tennessee Valley Authority RADIOACTIVITY IN PEARS pCi/Kg = 0.037 Bq/Kg (WET WEIGHT)
Docket Number:
50-327,328 Reporting Period:
2016 Location with Highest Annual Mean Mean {F)
Location Description with Range Distance and Direction See Note 2 SQNP 6.17E+01 (1 / 1) 1.1 MILES WNW 6.17E+01 -
6.17E+01 SQNP 9.84E+02 (1 / 1) 1.1 MILES WNW 9.84E+02 -
9.84E+02 SQNP 1 VALUES < LLD 1.1 MILES WNW SQNP 1 VALUES< LLD 1.1 MILES WNW Control Locations Mean {F)
Range See Note 2 6.53E+01 (1 / 1) 6.53E+01 - 6.53E+01 7.79E+02 {1/1) 7.79E+02 - 7.79E+02 1 VALUES < LLD 1 VALUES< LLD Notes: 1. Nominal Lower Level of Detection {LLD) as described in Table E - 1
- 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses {F).
- 3. Blanks in this column indicate no nonrountine measurements*
Number of Non routine Reported Measurements See Note 3
~
~ -
0
- c:
I --
Name of Facility: SEQUOYAH NUCLEAR PLANT Location of Facility: HAMIL TON, TENNESSEE Type and Total Number of Analysis Performed GAMMA SCAN (GELi) - 2 Bl-214 I
....;i w
I K-40 PB-212 PB-214 TL-208 Lower Limit of Detection (LLD)
See Note 1 4.00E+01 2.50E+02 4.00E+01 8.00E+01 3.00E+01 Indicator Locations Mean (F)
Range See Note 2 5.15E+01 (1 / 1) 5.15E+01 -
5.15E+01 3.39E+03 (1 / 1) 3.39E+03 -
3.39E+03 1 VALUES < LLD 1 VALUES < LLD 1 VALUES < LLD Tennessee Valley Authority RADIOACTIVITY IN POTATOES pCi/Kg = 0.037 Bq/Kg (WET WEIGHT)
Docket Number:
50-327,328 Reporting Period:
2016 Location with Highest Annual Mean Mean (F)
Location Description with Range Distance and Direction See Note 2 1 MILES NW 5.15E+01 (1 / 1) 5.15E+01 -
5.15E+01 1 MILES NW 3.39E+03 (1/1) 3.39E+03 -
3.39E+03 1 MILES NW 1 VALUES < LLD 1 MILES NW 1 VALUES < LLD 1 MILES NW 1 VALUES< LLD Control Locations Mean (F)
Range See Note 2 7.16E+01 (1 / 1) 7.16E+01 - 7.16E+01 3.75E+03 (1/1) 3.75E+03 - 3.75E+03 1 VALUES < LLD 1 VALUES < LLD 1 VALUES < LLD Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1
- 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).
- 3. Blanks in this column indicate no nonrountine measurements Number of Nonroutine Reported Measurements See Note 3
'"""3
§.. -
0
- c:
I -
N
Name of Facility: SEQUOYAH NUCLEAR PLANT Location of Facility: HAMIL TON, TENNESSEE Type and Total Number of Analysis Performed GAMMA SCAN (GELi) - 2 Bl-214 K-40 PB-214
~
I Lower Limit of Detection (LLD)
See Note 1 4.00E+01 2.50E+02 8.00E+01 Indicator Locations Mean (F)
Range See Note 2 4.32E+01 (1 / 1) 4.32E+01 - 4.32E+01 1.79E+03 (1/1) 1.79E+03 -
1.79E+03 1 VALUES < LLD Tennessee Valley Authority RADIOACTIVITY IN TOMATOES pCi/Kg = 0.037 Bq/Kg (WET WEIGHT)
Docket Number:
50-327,328 Reporting Period:
2016 Location with Highest Annual Mean Mean (F)
Location Description with Range Distance and Direction See Note 2 1 MILES NW 1 MILES NW 1 MILES NW 4.32E+01 (1 / 1) 4.32E+01 -
4.32E+01 1.79E+03 (1 / 1) 1.79E+03 -
1.79E+03 1 VALUES < LLD Control Locations Mean (F)
Range See Note 2 4.05E+01 (1 / 1) 4.05E+01 - 4.05E+01 1.90E+03 (1 / 1) 1.90E+03 - 1.90E+03 1 VALUES < LLD Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1
- 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).
- 3. Blanks in this column indicate no nonrountine measurements Number of Non routine Reported Measurements See Note 3
~
~
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- c:
I -
w
Name of Facility: SEQUOYAH NUCLEAR PLANT Location of Facility: HAMIL TON, TENNESSEE Type and Total Number of Analysis Performed GROSS BETA - 26 GAMMA SCAN (GELi) - 26 AC-228 Bl-214 K-40
.!.:i PB-212 VI I
PB-214 TL-208 TRITIUM -21 Lower Limit of Detection (LLD)
See Note 1 1.90E+OO 2.00E+01 2.00E+01 1.00E+02 1.50E+01 2.00E+01 1.00E+01 2.70E+02 Indicator Locations Mean (F)
Range See Note 2 2.08E+OO (4 / 13) 1.92E+OO -
2.24E+OO 13 VALUES< LLD 4.00E+01 (8 / 13) 2.00E+01 -
9.82E+01 13 VALUES< LLD 13 VALUES< LLD 4.79E+01 (4 / 13) 2.63E+01 -
8.64E+01 13 VALUES< LLD 6.46E+02 (2 I 4) 3.96E+02 - 8.97E+02 Tennessee Valley Authority RADIOACTIVITY IN SURFACE WATER (Total) pCi/L = 0.037 Bq/L Docket Number:
50-327,328 Reporting Period:
2016 Location with Highest Annual Mean Mean (F)
Location Description with Range Distance and Direction See Note 2 TRM483.4 TRM483.4 TRM 483.4 TRM483.4 TRM483.4 TRM483.4 TRM483.4 TRM 483.4 2.08E+OO (4 / 13) 1.92E+OO -
2.24E+OO 13 VALUES< LLD 4.00E+01 (8 / 13) 2.00E+01 -
9.82E+01 13 VALUES< LLD 13 VALUES < LLD 4.79E+01 (4 / 13) 2.63E+01 -
8.64E+01 13 VALUES< LLD 6.46E+02 (2 I 4) 3.96E+02 -
8.97E+02 Control Locations Mean (F)
Range See Note 2 2.12E+OO (4/13) 2.07E+OO - 2.20E+OO 8.05E+01 (2 / 13) 3.69E+01 - 1.24E+02 3.77E+01 (5 / 13) 2.80E+01 - 6.05E+01 13 VALUES< LLD 13 VALUES< LLD 3.20E+01 (4 / 13) 2.07E+01 - 5.42E+01 13 VALUES< LLD 5.91 E+02 (7 / 17) 3.50E+02 - 9.85E+02 Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1
- 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).
- 3. Blanks in this column indicate no nonrountine measurements Number of Nonroutine Reported Measurements See Note 3
'""'1
~ -
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- c:
I -
~
Tennessee Valley Authority RADIOACTIVITY IN PUBLIC (DRINKING) WATER (Total) pCi/L = 0.037 Bq/L Name of Facility: SEQUOYAH NUCLEAR PLANT Location of Facility: HAMIL TON, TENNESSEE Docket Number:
50-327,328 Reporting Period:
2016 Type and Lower Limit Total Number of Detection of Analysis (LLD)
Performed See Note 1 GROSS BETA - 52 1.90E+OO GAMMA SCAN (GELi) - 52 AC-228 2.00E+01 Bl-212 5.00E+01 Bl-214 2.00E+01
.!J K-40 1.00E+02
°'
I PB-212 1.50E+01 PB-214 2.00E+01 TL-208 1.00E+01 TRITIUM -42 2.70E+02 Indicator Locations Mean (F)
Range See Note 2 2.32E+OO (13 I 39) 1.94E+OO -
3.32E+OO 3.13E+01 (3 / 39) 2.28E+01 -
3.78E+01 39 VALUES < LLD 4.17E+01 (19 I 39) 2.05E+01 -
1.12E+02 39 VALUES < LLD 39 VALUES < LLD 4.76E+01 (12 / 39) 2.23E+01 -
1.12E+02 39 VALUES < LLD 5.66E+02 (10 / 25) 2.82E+02 -
1.01 E+03 Location with Highest Annual Mean Mean (F)
Location Description with Range Distance and Direction See Note 2 CF INDUSTRIES TRM473.0 CF INDUSTRIES TRM473.0 CHATTANOOGA TRM465.3 E.I. DUPONT TRM470.5 CHATTANOOGA TRM465.3 CHATTANOOGA TRM465.3 E.I. DUPONT TRM470.5 CHATTANOOGA TRM465.3 CHATTANOOGA TRM465.3 2.39E+OO (6 / 13) 2.06E+OO -
3.32E+OO 3.56E+01 (2 / 13) 3.34E+01 -
3.78E+01 13 VALUES< LLD 4.84E+01 (8 / 13) 2.29E+01 -
1.12E+02 13 VALUES< LLD 13 VALUES< LLD 5.85E+01 (5 / 13) 2.32E+01 -
1.12E+02 13 VALUES< LLD 6.26E+02 (1 / 4) 6.26E+02 -
6.26E+02 Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1 Control Locations Mean (F)
Range See Note 2 2.12E+OO (4/13) 2.07E+OO - 2.20E+OO 8.05E+01 (2 / 13) 3.69E+01 - 1.24E+02 13 VALUES< LLD 3.77E+01 (5 / 13) 2.80E+01 - 6.05E+01 13 VALUES< LLD 13 VALUES< LLD 3.20E+01 (4 / 13) 2.07E+01 - 5.42E+01 13 VALUES< LLD 5.91 E+02 (7 / 17) 3.50E+02 - 9.85E+02
- 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).
- 3. Blanks in this column indicate no nonrountine measurements Number of Nonroutine Reported Measurements See Note 3 1-:3 g.. -
CD
- I::
I -
VI
Tennessee Valley Authority RADIOACTIVITY IN WELL (GROUND) WATER (Total) pCi/L = 0.037 Bq/L Name of Facility: SEQUOYAH NUCLEAR PLANT Location of Facility: HAMIL TON, TENNESSEE Docket Number:
50-327,328 Reporting Period:
2016 Type and Total Number of Analysis Performed GROSS BETA - 9 GAMMA SCAN (GELi) - 18 AC-228 Bl-214 K-40
.!.:iPB-212
-.J I
PB-214 TL-208 TRITIUM -18 Lower Limit of Detection (LLD)
See Note 1 1.90E+OO 2.00E+01 2.00E+01 1.00E+02 1.50E+01 2.00E+01 1.00E+01 2.70E+02 Indicator Locations Mean (F)
Range See Note2 5 VALUES < LLD 14 VALUES< LLD 1.05E+02 (10/14) 2.10E+01 - 7.87E+02 14 VALUES< LLD 4.97E+01 (1 / 14) 4.97E+01 - 4.97E+01 1.32E+02 (7 / 14) 2.08E+01 -
- 7. 73E+02 1.61E+01 (1/14) 1.61 E+01 -
1.61 E+01 4.36E+02 (12 / 14) 2.83E+02 -
1.37E+03 Location with Highest Annual Mean Mean (F)
Location Description with Range Distance and Direction See Note 2 SQN WELL#6 ONSITE NNE SQN WELL#6 ONSITE NNE SQN WELL#6 ONSITENNE SQN WELL#6 ONSITE NNE SQN WELL#6 ONSITE NNE SQN WELL#6 ONSITE NNE SQN WELL#6 ONSITE NNE SQN WELL#6 ONSITENNE 14 VALUES< LLD 1.05E+02 (10 / 14) 2.10E+01 -
7.87E+02 14 VALUES < LLD 4.97E+01 (1 / 14) 4.97E+01 -
4.97E+01 1.32E+02 (7 / 14) 2.08E+01 -
7.73E+02 1.61 E+01 (1 / 14) 1.61 E+01 -
1.61 E+01 4.36E+02 (12 / 14) 2.83E+02 -
1.37E+03 Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1 Control Locations Mean (F)
Range See Note 2 9.59E+OO (3 / 4) 4.78E+OO - 1.42E+01 4 VALUES < LLD 3.38E+02 (4 / 4) 1.65E+02 - 4.97E+02 4 VALUES < LLD 4 VALUES < LLD 3.49E+02 (4 / 4) 1.63E+02 - 5.33E+02 4 VALUES< LLD 4 VALUES < LLD
- 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).
- 3. Blanks in this column indicate no nonrountine measurements Number of Nonroutine Reported Measurements See Note 3
~
~
0
- t= -°'
Name of Facility: SEQUOYAH NUCLEAR PLANT Location of Facility: HAMIL TON, TENNESSEE Type and Total Number of Analysis Performed GAMMA SCAN (GELi) - 4 81-214
.!J 00 I
K-40 PB-212 PB-214 TL-208 Lower Limit of Detection (LLD)
See Note 1 1.00E-01 4.00E-01 4.00E-02 1.00E-01 3.00E-02 Indicator Locations Mean (F)
Range See Note 2 2 VALUES < LLD 8.09E+OO (2 I 2) 6.57E+OO -
9.61 E+OO 2 VALUES < LLD 2 VALUES< LLD 2 VALUES < LLD Tennessee Valley Authority RADIOACTIVITY IN COMMERCIAL FISH pCi/g = 0.037 Bq/g (DRY WEIGHT)
Docket Number:
50-327,328 Reporting Period:
2016 Location with Highest Annual Mean Mean (F)
Location Description with Range Distance and Direction See Note 2 CHICKAMAUGA RES 2 VALUES< LLD TRM 471-530 CHICKAMAUGA RES 8.09E+OO (2 I 2)
TRM 471-530 6.57E+OO -
9.61E+OO CHICKAMAUGA RES 2 VALUES < LLD TRM 471-530 CHICKAMAUGA RES 2 VALUES< LLD TRM 471-530 CHICKAMAUGA RES 2 VALUES< LLD TRM 471-530 Control Locations Mean (F)
Range See Note 2 1.19E-01 (1/2) 1.19E 1.19E-01 1.21 E+01 (2 / 2) 1.1 OE+01 - 1.32E+01 2 VALUES < LLD 1.16E-01 (1 / 2) 1.16E 1.16E-01 2 VALUES < LLD Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1
- 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).
- 3. Blanks in this column indicate no nonrountine measurements Number of Nonroutine Reported Measurements See Note 3
~
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- c:
I.....
....;i
Name of Facility: SEQUOYAH NUCLEAR PLANT Location of Facility: HAMIL TON, TENNESSEE Type and Total Number of Analysis Performed GAMMA SCAN (GELi) - 4 81-214 CS-137 K-40 PB-212 PB-214 I
'P Lower Limit of Detection (LLD)
See Note 1 1.00E-01 3.00E-02 4.00E-01 4.00E-02 1.00E-01 Indicator Locations Mean (F)
Range See Note 2 1.18E-01 (1/2) 1.18E 1.18E-01 2 VALUES < LLD 1.25E+01 (2 I 2) 1.23E+01 -
1.28E+01 2 VALUES < LLD 2 VALUES < LLD Tennessee Valley Authority RADIOACTIVITY IN GAME FISH pCi/g = 0.037 Bq/g (DRY WEIGHT)
Docket Number:
50-327,328 Reporting Period:
2016 Location with Highest Annual Mean Mean (F)
Location Description with Range Distance and Direction See Note 2 CHICKAMAUGA RES 1.18E-01 (1/2)
TRM471-530 1.18E 1.18E-01 CHICKAMAUGA RES 2 VALUES < LLD TRM 471-530 CHICKAMAUGA RES 1.25E+01 (2 I 2)
TRM 471-530 1.23E+01 -
1.28E+01 CHICKAMAUGA RES 2 VALUES < LLD TRM 471-530 CHICKAMAUGA RES 2 VALUES < LLD TRM 471-530 Control Locations Mean (F)
Range See Note 2 1.03E-01 (1 I 2) 1.03E 1.03E-01 3.23E-02 (1 I 2) 3.23E 3.23E-02 1.31 E+01 (2 / 2) 1.28E+01 - 1.34E+01 2 VALUES < LLD 2 VALUES < LLD Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1
- 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).
- 3. Blanks in this column indicate no nonrountine measurements Number of Nonroutine Reported Measurements See Note 3 t-3
~ -
0
- c:
I -
oc
Name of Facility: SEQUOYAH NUCLEAR PLANT Location of Facility: HAMIL TON, TENNESSEE Type and Total Number of Analysis Performed GAMMA SCAN (GELi) - 6 AC-228 I 00 BE-7 81-212 81-214 CS-137 cp K-40 PA-234M PB-212 PB-214 RA-226 TL-208 Lower Limit of Detection (LLD)
See Note 1 2.50E-01 2.50E-01 4.50E-01 1.50E-01 3.00E-02 7.50E-01 4.00E+OO 1.00E-01 1.50E-01 1.50E-01 6.00E-02 Indicator Locations Mean (F)
Range See Note 2 1.18E+OO (4/4) 7.75E 1.64E+OO 2.74E-01 (1 / 4) 2.74E 2.74E-01 1.28E+OO (4 / 4) 9.42E 1.61 E+OO 7.56E-01 (4 / 4) 4.45E 1.03E+OO 6.39E-02 (1 I 4) 6.39E 6.39E-02 7.76E+OO (4 / 4) 2.69E+OO -
1.57E+01 4 VALUES < LLD 1.10E+OO (4 / 4) 7.94E 1.50E+OO 8.12E-01 (4 I 4) 4.82E 1.10E+OO 7.56E-01 (4 / 4) 4.45E 1.03E+OO
- 3. 78E-01 (4 / 4) 2.64E 5.01 E-01 Tennessee Valley Authority RADIOACTIVITY IN SHORELINE SEDIMENT pCi/g = 0.037 Bq/g (DRY WEIGHT)
Docket Number:
50-327,328 Reporting Period:
2016 Location with Highest Annual Mean Mean (F)
Location Description with Range Distance and Direction See Note 2 TRM479.0 1.26E+OO (2 I 2)
TRM479.0 8.76E 1.64E+OO TRM480.0 2.74E-01 (1 / 2)
TRM480.0 2.74E 2.74E-01 TRM479.0 1.28E+OO (2 I 2)
TRM479.0 9.42E 1.61 E+OO TRM479.0 8.36E-01 (2 I 2)
TRM479.0 6.41E 1.03E+OO TRM480.0 6.39E-02 (1 I 2)
TRM480.0 6.39E 6.39E-02 TRM480.0 9.18E+OO (2 I 2)
TRM480.0 2.69E+OO -
1.57E+01 TRM479.0 2 VALUES< LLD TRM479.0 TRM479.0 1.15E+OO (2 I 2)
TRM479.0 7.94E 1.50E+OO TRM479.0 8.90E-01 (2 / 2)
TRM479.0 6.82E 1.1 OE+OO TRM479.0 8.36E-01 (2 I 2)
TRM479.0 6.41 E 1.03E+OO TRM479.0 3.88E-01 (2 I 2)
TRM479.0 2.75E 5.01E-01 Control Locations Mean (F)
Range See Note 2 4.28E-01 (2 I 2) 2.67E 5.90E-01 2 VALUES< LLD 6.36E-01 (1 I 2) 6.36E 6.36E-01 3.26E-01 (2 I 2) 2.27E 4.24E-01 2 VALUES < LLD
- 2. 11 E+OO (2 I 2) 1.44E+OO - 2. 77E+OO 2 VALUES< LLD 4.06E-01 (2 I 2) 2.52E 5.60E-01 3.51 E-01 (2 I 2) 2.24E 4.78E-01 3.26E-01 (2 I 2) 2.27E 4.24E-01 1.42E-01 (2 I 2) 9.03E 1.94E-01 Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1
- 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).
- 3. Blanks in this column indicate no nonrountine measurements Number of Nonroutine Reported Measurements See Note 3
~ -
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- r:
I -
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Figure H-1 Direct Radiation Direct Radiation Levels Sequoyah Nuclear Plant Four Quarter Moving Average 25 20 15 10 5
1975 Initial SQNP operation in July,, 1980 1980 1985
-.-on-Site Off-Site 1990 1995 Calendar Year lnlight Dosimeter Deployment in January, 2007 i 2000 2005 2010 2015 Dosimeters are processed quarterly. This chart shows trends in the average measurement for all dosimeters grouped as "on-site" or "off-site". The data from preoperational phase, prior to 1980, show the same trend of "on-site" measurements higher than "off-site" measurements that is observed in current data indicating that the slightly higher "on-site" direct radiation levels are not related to plant operations. 2020
0.25 0.20 M
E 0.15 u
CL
~ 0.10
~
~
fo I!
0.05
~
0.00 1970 Figure H-2 Radioactivity in Air Filters Annual Average Gross Beta Activity in Air Filters Note:
No gross beta measurements were made in 1974 Sequoyah Nuclear Plant Initial SQNP Operation in July, 1980 Preoperational Average 1975 1980 1985 1990 1995 2000 Calendar Year
--.- Indicator Control 2005 2010 2015 As can be seen in the trend plot of gross beta activity, the gross beta levels in air particulates have remained relatively constant with the exception of years when the beta activity was elevated due to fallout from nuclear weapons testing. The data also shows that there is no difference in the gross beta activity levels for sampling conducted at the indicator stations as compared to the control stations.
Figure H-3 Cs-137 in Soil Annual Average Activity of Cs-137 in Soil Sequoyah Nuclear Plant 3.0 2.5 Initial SQNP
~ 2.0
~
0 1.5
- a.
I f
~ 1.0
~
GI 0.5
~
0.0 1970 1975 Operation in July, 1980 1980 Preoperational Average 1985 1990 1995 2000 2005 2010 2015 Calendar Year I _,.._Indicator -o-- Contro1J Cesiurn-13 7 was produced by past nuclear weapons testing and is present in almost every environmental soil sample exposed to the atmosphere. The fallout from accidents at the Chernobyl plant in the Ukraine in 1986 and Fukushima plant in Japan in 2011 may have also contributed to the low levels of Cs-13 7 measured in environmental samples.
...... u 6.00 5.00 4.00
- a. 3.00 I
f
~ 2.00
&'o I!
~ 1.00 0.00 1970 1975 Figure H-4 Gross Beta Activity in Surface Water Average Annual Gross Beta Activity in Surface Water Sequoyah Nuclear Plant Preoperational Average 1980 Initial SQNP Operation in July, 1980 1985 1990 1995 2000 Calendar Year
--+--Indicator -o-Control I 2005 2010 2015 As shown in the graph, the gross beta activity in samples from the downstream indicator locations has been essentially the same as the activity in samples from the upstream control locations. The average gross beta activity in these samples has been trending down since the early 1980's.
..J -
0 CL Figure H-5 Gross Beta Activity in Drinking Water Annual Average Gross Beta Activity in Drinking Water Sequoyah Nuclear Plant 6.0 r...........................................................................................................................................................................................................................................................................................................................................................,
5.0 4.0 3.0 2.0 1.0 Initial SQNP Operation in July, 1980 Preoperational Average 0.0 ~--~--~--~~--~---'---~---~--~--~-
1970 1975 1980 1985 1990 1995 2000 2005 2010 2015 Calendar Year --- Indicator Control The average gross beta activity in drinking water samples from the upstream control locations has typically been slightly higher than activity level measured in samples from the downstream indicator locations. The annual average gross beta activity has been relatively constant since the start of plant operations in 1980 and is slightly lower than preoperational levels.
Figure H-6 Radioactivity in Fish Annual Average Activity Cs-137 in Game Fish Sequoyah Nuclear Plant 0.60 0.50
- **************************.............. ---.......... -*******************-*-**- -...... -- -1
~ 0.40
~
DI -
~ 0.30 f !
0.20 t
CD
~ 0.10 Initial SQNP Operation in July, 1980 Preoperational Average 0.00 '--------'--------'-----'-----'----.l....-------'------'---A---'---A-i..-c..Jf-Qa,**
.1970 1975 1980 1985 1990 1995 2000 2005 2010 2015 Calendar Year
---.- indicator
-o-- Control The concentrations ofCs-137 found in fish are consistent with levels present in the Tennessee River due to past atmospheric nuclear weapons testing and operation of other nuclear facilities in the upper reaches of the Tennessee River Watershed. As shown in the graph, the levels of Cs-137 have been decreasing consistent with the overall levels of Cs-137 in the environment.
~
Cll -
0 a.
I
~ j Ill Cll l! t oil(
Figure H-7 Radioactivity in Shoreline Sediment Annual Average Activity Cs-137 in Shoreline Sediment Sequoyah Nuclear Plant 0.35 0.30 Note: Initial 0.25 SQNP Operation in July, 1980.
There was no 0.20 preoperational sampling of shoreline 0.15 sediment 0.10 0.05 0.00 1970 1975 1980 1985 1990 1995 Calendar Year
~Indicator (Downstream)
--<>- Control (Upstream) 2000 2005 2010 2015 The Cs-137 present in the shoreline sediments of the Tennessee River system was produced both by past atmospheric testing of nuclear weapons and the operation of other nuclear facilities in the upper reaches of the Tennessee River Watershed. The abnormally high value for the 2009 data from the downstream locations resulted from a problem with one sample collected in April, 2009. The sample was collected during a period of high water levels and was actually surface soil and not the normal shoreline sediment material. This sample contained Cs-13 7 _at a level typical for environmental soil but was much higher than levels normally found in shoreline sediment. This issue was discussed in the 2009 SQN report.