ML101240920

Submittal of Annual Radiological Environmental Operating Report 2009

ML101240920
Person / Time
Site:	Sequoyah
Issue date:	04/28/2010
From:	Krich R Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML101240920 (94)

Text

Tennessee Valley Authority 1101 Market Street, LP 3R Chattanooga, Tennessee 37402-2801 R. M. Krich Vice President Nuclear Licensing April 28, 2010 10 CFR 50.4 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Units 1 and 2 Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327 and 50-328

Subject:

Annual Radiological Environmental Operating Report - 2009 Enclosed is the subject report for the period of January 1 to December 31, 2009. This report is being submitted as required by the respective Sequoyah Nuclear Plant (SQN),

Units 1 and 2, Technical Specification 6.9.1.6 and SQN's Offsite Dose Calculation Manual Administrative Control Section 5.1.

If you have any questions concerning this matter, please telephone Beth A. Wetzel at (423) 843-7170.

Respectfully, R. M. Krich

Enclosure:

Annual Radiological Environmental Operating Report, Sequoyah Nuclear Plant, 2009 cc (Enclosure):

NRC Regional Administrator - Region II NRC Resident Inspector - Sequoyah Nuclear Plant printed on recycled paper

ENCLOSURE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SEQUOYAH NUCLEAR PLANT 2009

Annual Radiological Environmental Operating Report Sequoyah Nuclear Plant 2009

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SEQUOYAH NUCLEAR PLANT 2009 TENNESSEE VALLEY AUTHORITY April 2010

TABLE OF CONTENTS Table of Contents ............................................. ii Executive Summary...........................................I Introduction .................................................. 2 Naturally Occurring and Background Radioactivity ................. 2 Electric Power Production ..................................... 4 Site/Plant Description .......................................... 6 Radiological Environmental Monitoring Program .................... 7 Direct Radiation M onitoring ..................................... 10 Measurement Techniques ...................................... 10 R esults .................................................... 11 Atmospheric M onitoring ....................................... 13 Sample Collection and Analysis ................................ 13 Results .................................................... 14 Terrestrial M onitoring ......................................... 15 Sample Collection and Analysis ................................ 15 Results .................................................... 16 Liquid Pathway M onitoring ..................................... 18 Sample Collection and Analysis .........................  ; ...... 18 Results .................................................... 19 Assessment and Evaluation ..................................... 21 Results .................................................... 21 Conclusions ................................................ 22 R eferences ................................................... 23

-ii-

Appendix A Radiological Environmental Monitoring Program and Sam pling Locations .............................................. 27 Appendix B 2009 Program Modifications ........................... 38 Appendix C Program Deviations .................................. 40 Appendix D Analytical Procedures ................................ 43 Appendix E Nominal Lower Limits of Detection (LLD) ................ 46 Appendix F Quality Assurance/Quality Control Program ............... 51 Appendix G Land Use Survey ..................................... 56 Appendix H Data Tables and Figures .............................. 62

-III-.

LIST OF TABLES 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 ............. 24

-iv-

LIST OF FIGURES Figure 1 Tennessee Valley Region ................................. 25 Figure 2 Environmental Exposure Pathways of Man Due to Releases of Radioactive Materials to the Atmosphere and Lake .................................... 26

EXECUTIVE

SUMMARY

This report describes the radiological environmental monitoring program (REMP) conducted by TVA in the vicinity of the Sequoyah Nuclear Plant (SQN) in 2009. The program includes the collection of samples from the environment and the determination of the concentrations of radioactive materials in the samples. Samples were collected from locations in the general area of the plant and from areas that would not be influenced by plant operations. Monitoring includes the sampling of air, water, milk, foods, soil, fish, shoreline sediment and the measurement of direct radiation levels. Results from stations near the plant are compared with data from control stations and with preoperational measurements to determine potential impacts of site operations.

The vast majority of radioactivity measured in environmental samples from the SQN program resulted from naturally occurring radioactive materials. Trace quantities of cesium-137 (Cs-137) were measured in soil, shoreline sediment, and fish. Strontium-90 (Sr-90) at very low levels was detected in milk samples. The concentrations were typical of the levels expected to be present in the environment from past nuclear weapons testing or operation of other nuclear facilities in the region. Tritium at concentrations slightly above the analytical detection limit was detected in a limited number of water samples collected from Chickamauga Reservoir. These levels would not represent a significant contribution to the radiation exposure to Members of the Public.

NTRODUCTION This report describes and summarizes the results of radioactivity measurements made in the vicinity of SQN and laboratory analyses of samples collected in the area. The measurements are made to comply with the requirements of the Code of Federal Regulations (CFR), 10 CFR 50, Appendix A, Criterion 64 and 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3 and IV.C, and to determine potential effects on public health and safety. This report satisfies the annual reporting requirements of SQN Plant Technical Specification (TS) 6.9.1.6 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 of 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). This is equivalent to approximately 100,000 picoCuries (pCi) of K-40 which delivers a dose of 15 to 20 mrem per year to the bone and soft tissue of the body.

Other examples of naturally occurring radioactive materials are beryllium (Be)-7, bismuth (Bi)-

212 and 214, lead (Pb)-212 and 214, thallium (TI)-208, actinium (Ac)-228, uranium (U)-238 and 235, thorium (Th)-234, radium (Ra)-226, radon (Rn)-222, carbon (C)-14, and hydrogen (H)-3 (generally called tritium). These naturally occurring radioactive materials are in the soil, our food, our drinking water, and our bodies. The radiation from these materials makes up a part of the low level natural background radiation. The remainder of the natural background radiation is produced by cosmic rays. The relative hazard of different types of radiation sources can be compared by evaluating the amount of radiation 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 Millirem/Year Per Person Natural background dose equivalent Cosmic 27 Cosmogenic 1 Terrestrial 28 In the body 39 Radon 200 Total 295 Release of radioactive material in natural gas, mining, ore processing, etc. 5 Medical (effective dose equivalent) 53 Nuclear weapons fallout less than 1 Nuclear energy 0.28 Consumer products 0.03 Total 355 (approximately)

As can be seen from the table, natural background radiation dose equivalent to the U.S.

population normally exceeds that from nuclear plants by several hundred times. The 0.28 mrem attributable to nuclear plant operations results in a population radiation dose equivalent which is insignificant compared to that which results 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 both types of 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. 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 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 Total body <3 mrem/year Any organ <10 mrem/year Gaseous Effluents Noble gases:

Gamma radiation <I 0 mrad/year Beta radiation <20 mrad/year Particulates:

Any organ <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 <_25 mrem/year Thyroid <75 mrem/year Any other organ <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 (LLD) of detection for the SQN monitoring program with the regulatory limits for maximum annual average effluent concentrations released to unrestricted areas and levels requiring special reports to the NRC. It should be noted that the levels of radioactive materials measured in the environment are typically 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 1 shows the site in relation to other TVA projects. The SQN site, containing approximately 525 acres, is approximately 7.5 miles northeast of the nearest city limit of Chattanooga, Tennessee, 14 miles west-northwest of Cleveland, Tennessee, and approximately 31 miles south-southwest of TVA's Watts Bar Nuclear Plant (WBN) site.

Population is distributed unevenly within 10 miles of the SQN site. Approximately 60 percent of the population is in the general area between 5 and 10 miles from the plant in the sectors ranging from the south, clockwise, to the northwest sector. This concentration is a reflection of suburban Chattanooga and the town of Soddy-Daisy. This area is characterized by considerable vacant land with scattered residential subdivisions. Residential subdivision growth has continued within a 10-mile radius of the plant. There is also some small-scale farming and at least one dairy farm 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 1 on March 1, 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 all tables and figures in the appendices.) lists the sampling stations and the types of samples collected. There were no modifications made to the SQN monitoring program in 2009.

Appendix B, "Program Modifications," is included in this report as a place keeper. 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 TVA's Environmental Radiological Monitoring and Instrumentation (ERM&I) group located at the Western Area Radiological Laboratory (WARL) in Muscle Shoals, Alabama, with the exception of the Sr-89, 90 analysis of soil samples which was 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. In 2009, 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 Techniqlues 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 varying plastic and copper filtrations to provide qualitative information about conditions during the 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 N 13.29 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 all monitoring points within 2 miles of the plant. The second group is made up of all 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 2009 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 2009, are shown below. For comparison purposes, the average direct radiation measurements made in the preoperational phase of the monitoring program are also shown.

Annual SQN Average Direct Radiation Levels mR/Year 2009 1976-79 Onsite Stations 45 79 Offsite Stations 38 63 The data in Table H-I indicate that the average quarterly direct radiation levels at the SQN onsite stations are approximately 1.8 mR/quarter higher than levels at the offsite stations. This difference is consistent with levels measured for the preoperation and construction phases of TVA 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 offsite stations over the period from 1976 through 2009.

The results from the Landauer InLight Optically Stimulated Luminescence (OSL) dosimeters are lower across all locations when compared to the results previously obtained using the Panasonic UD-814 dosimeters. This difference is most likely due to the manner in how background badge data was applied for the in house processing of Panasonic dosimeters as compared to the method used by the vendor.

The data in Table H-2 contains the results of the individual monitoring stations. The results reported in 2009 are consistent with direct radiation levels identified at locations which are not influenced by the operation of SQN. There is no indication that SQN activities increased the background radiation levels normally observed in the areas surrounding the plant.

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 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 1-131 by gamma spectroscopy analysis.

Results The results from the analysis of air particulate samples are summarized in Table H-3. Gross beta activity in 2009 was consistent with levels reported in previous years. The average gross beta activity for air filter samples was 0.021 pCi/m 3. The annual average of the gross beta activity in air particulate filters at these stations for the years 1971-2009 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 preoperation and construction phases at other TVA nuclear plant sites.

Only naturally occurring radionuclides were identified by the monthly gamma spectral analysis of the air particulate samples. No fission or activation products were detected. As shown in Table H-4, 1-131 was not detected in any of the charcoal cartridge samples collected in 2009.

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-10.

A land use survey is conducted annually to locate milk producing animals and gardens within a 5-mile radius of the plant. One dairy farm was located on the east side of the river between 4 and 5 miles from the plant and one small farm with a milk cow is located approximately 1.5 miles northwest of the plant. These two locations were sampled in accordance with the SQN sampling program. The results of the 2009 land use survey are presented in Appendix G.

Sample Collection and Analysis Milk samples are collected every 2 weeks from the indicator locations 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. There were no periods during 2009 when vegetation sampling was necessary.

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. In 2009 samples of cabbage, corn, green beans, and potatoes were collected from local gardens. Samples of these same food crops were purchased from area produce markets to serve as control samples. The edible portion of each sample is analyzed by gamma spectroscopy.

Results The results from the analysis of milk samples are presented in Table H-5. No radioactivity attributable to SQN operations was identified. The 1-131 results were less than the established nominal LLD of 0.4 pCi/liter. The results for the quarterly Sr-89 analysis were also less than the nominal LLD value of 3.5 pCi/liter. Four of the samples of milk did contain low levels of Sr-90. The Sr-90 concentration measured in these samples averaged 3.6 pCi/liter. The presence of low levels of Sr-90 in milk samples is consistent with levels in the environment resulting from past nuclear weapons testing. By far the predominant isotope reported in milk samples was the naturally occurring K-40. The average K-40 concentration was approximately 1325 pCi/liter for milk samples analyzed in 2009.

The gamma analysis of soil samples detected trace levels of Cs-137 with the maximum concentration being 0.82 pCi/g in a control location sample. The concentrations of Cs-137 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-6.

A plot of the annual average Cs-137 concentrations in soil is presented in Figure H-3. The concentrations of Cs- 137 in soil are steadily decreasing as a result of the cessation of weapons testing in the atmosphere, the 30-year half-life of Cs-137 and transport through the environment.

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-7 through H-10.

LIOUID 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 1-gallon sample is removed from the composite jug at 4-week intervals and the remaining water in the jug is discarded. The composite sample is analyzed for gamma emitting radionuclides and 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 and from a private well in an area unaffected by SQN. Gamma spectroscopy analysis is performed monthly on a composite sample from the onsite well and quarterly on samples from an offsite well. Analyses are also performed for gross beta activity and tritium.

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. The tritium analysis of surface water samples detected tritium in one sample from the upstream control location at concentration of 280 pCi/L. This level of tritium represented only a small fraction of the EPA drinking water limit of 20,000 pCi/L. Gross beta activity above the nominal LLD value was measured in most surface water samples. The gross beta concentrations in samples from the indicator locations averaged 2.2 pCi/L and control location samples averaged 2.9 pCi/liter. The values were consistent with previously reported levels. A trend plot of the gross beta activity in surface water samples from 1971 through 2009 is presented in Figure H-4. A summary table of the results is shown in Table H-11.

There were no fission or activation product radionuclides identified by the gamma analysis of drinking water samples. Tritium was detected at low levels in samples collected during periods of low river flow rates. The highest tritium concentration was 363 pCi/L which is significantly below the EPA drinking water limit for tritium. Average gross beta activity was 2.5 pCi/liter for the downstream stations and 2.9 pCi/liter at the control station. The results are shown in Table H-12 and a trend plot of the gross beta activity in drinking water from 1971 to the present is presented in Figure H-5.

No fission or activation products were detected by the gamma analyses performed on ground-water samples from the two REMP monitoring locations. The results for tritium analysis of samples from these locations were all less than the nominal LLD. Gross beta concentrations in samples from the onsite well were all below the nominal LLD, while the average from the offsite well was 11.0 pCi/liter. The results from the analysis of groundwater samples are presented in Table H- 13.

Cesium-137 was identified in a total of five fish samples. The maximum Cs-137 concentration for indicator samples was 0.04 pCi/g, while the maximum Cs-137 concentration for control location samples was 0.08 pCi/g. A plot of the annual Cs-137 concentration in samples of game fish is presented in Figure H-6. The results are summarized in Tables H-14 and H-15.

Cesium-137 was detected in four shoreline sediment samples. The concentrations of Cs-137 measured in one downstream location sample and two control location samples were consistent with previously identified levels. The Cs-137 concentration measured in one of the downstream samples was 0.5 pCi/gm. This level of Cs-137 is higher than concentrations typically found in shoreline sediment but is consistent with the Cs-137 concentrations found in environmental soil samples. This sample was collected in April 2009 during a period of high water levels. The high water level resulted in collection of a sample that contained surface soil instead of typical shoreline sediment which resulted in the higher Cs-137 concentration. Results from the analysis of shoreline sediment samples are shown in Table H-16.

Figure H-7 presents a plot of the 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 TVA and are based on methodology provided by the NRC in Regulatory Guide 1.109 for determining the potential dose to individuals and populations living in the vicinity of a nuclear power plant. The 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 2009 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-137 were detected in fish, soil, and shoreline sediment and Sr-90 was detected in milk. The Cs-1 37 and Sr-90 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 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. 93, "Ionizing Radiation Exposure of the Population of the United States," September 1987.

3. United States Nuclear Regulatory Commission, Regulatory Guide 8.29, "Instruction Concerning Risks from Occupational Radiation Exposure," July 1981.

Table I COMPARISON OF PROGRAM LOWER LIMITS OF DETECTION WITH THE REGULATORY LIMITS FOR MAXIMUM ANNUAL AVERAGE EFFLUENT CONCENTRATIONS RELEASED TO UNRESTRICTED AREAS AND REPORTING LEVELS Concent rations in Water. DCi/Liter Concentrations in Air, pCi/Cubic Meter Effluent Reporting Lower limit3 Effluent Reporting Lower limit3 Concentration' Level 2 of Detection Concentration' Level 2 of Detection 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 10 400 0.005 Sr-89 8,000 5 1,000 0.0011 Sr-90 500 2 6 0.0004 Nb-95 30,000 400 5 2,000 0.005 Zr-95 20,000 400 10 400 0.005 Ru- 103 30,000 5 900 0.005 Ru- 106 3,000 40 20 0.02 1-131 1,000 2 0.4 200 0.9 0.03 Cs- 134 900 30 5 200 10 0.005 Cs-137 1,000 50 5 200 20 0.005 Ce- 144 3,000 30 40 0.01 Ba-140 8,000 200 25 2,000 0.015 La- 140 9,000 200 10 2,000 0.01 Note: I pCi = 3.7 x10 2 Bq.

Note: For those reporting levels that are blank, no value is given in the reference.

I Source: Table 2 of Appendix B to 10 CFR 20 2 Source: SQN Offsite Dose Calculation Manual, Table 2.3-2 3 Source: Table E-I of this report TENNESSEE VALLEY REGIOI (TVA NUCLEAR PLANT SITES)

W V A.

C K Y M

2i t'3 JACKSON#

S C A R.

FIfJtiP.

M I S S. IIS -WATTS BAR NUCLEAR PLANT G EO RG I A - SEQUOYAH NUCLEAR PLANT

- BELLEFONITE NUCLEAR PLANT

- BROWNS FERRY NUCLEAR PLANT

Figure 2 ENVIRONMENTAL EXPOSURE PATHWAYS OF MAN DUE TO RELEASES OF RADIOACTIVE MATERIAL TO THE ATMOSMP1HERE AND LAKE.

oere Airborne Releases Plume Exposure ML].

Liquid Releases Diluted By Lake ILJIIJLJ MAN Animals Consumed By Nian (Milk,Meat) Shoreline Exposure Consumed By Animals E

Drinking Water IFish Vegetation Uptake From Soil [

APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM AND SAMPLING LOCATIONS Table A-I SEQUOYAH NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM' Exposure Pathway Number of Samples and Sampling and Type and Frequency and/or Sample Locationsb Collection Frequency of Analysis

1. AIRBORNE

a. Particulates 4 samples from locations (in different Continuous sampler operation with Analyze for gross beta radioactivity sectors) at or near the site boundary sample collection once per 7 days 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 /> (LM-2, LM-3, LM-4, and LM-5). (more frequently if required by dust following filter change. Perform loading). 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.

4 samples from communities 00 approximately 6-10 miles from the Plant (PM-2, 3, 8, and 9).

4 samples from control locations greater than 10 miles from the plant (RM-I RM-2, RM-3and RM-4).

b. Radioiodine Same locations as air particulates. Continuous sampler operation with 1-131 by gamma scan on each sample.

charcoal canister collected at same time as particulate filters at least once per 7 days.

c. Soil Samples from same locations as air Once per year. Each sample is analyzed by gamma particulates isotopic and for Sr-89 and Sr-90.

Table A-I (continued)

SEQUOYAH NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMa Exposure Pathway Number of Samples and Sampling and Type and Frequency and/or Sample Locationsb Collection Frequency of Analysis

2. DIRECT RADIATION 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.

t!J 3. WATERBORNE 11P

a. Surface water TRM 50 3 .8 d Collected by automatic sequential- Gross beta and gamma scan on each TRM 483.4 type sampler' 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.

b. Groundwater I 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.

I sample from groundwater source At least once per 92 days. Gross beta, gamma scan, and upgradient (Farm HW). tritium at least once per 92 days.

Table A-I (continued)

SEQUOYAH NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMa Exposure Pathway Number of Samples and Sampling and Type and Frequency and/or Sample Locationsb Collection Frequency of Analysis

c. Drinking Water I sample at the first potable Collected by automatic sequential- Gross beta and gamma scan on each Water supply downstream from the type sampler' with composite sample composite sample. Composite for Plant (TRM 473.0). collected over a period of less than tritium at least once per 92 days.

or equal to 31 days.

I sample at the next 2 downstream Grab sample once per 31 days.

potable water systems (greater than 10 miles downstream) (TRM 469.9 and TRM 465.3).

1 sample at the upstream control Samples collected by sequential-type location (TRM 5 0 3 .8d). sampler' with composite sample 0 collected over a period of less than or equal to 31 days.

d. Shoreline sediment TRM 485 At least once per 184 days. Gamma scan of each sample.

TRM 480 TRM 479

Table A-I (continued)

SEQUOYAH NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMa Exposure Pathway Number of Samples and Sampling and Type and Frequency and/or Sample Locationsb Collection Frequency of Analysis

4. INGESTION

a. Milk I sample from milk producing At least once per 15 days. Gamma isotopic and 1-131 analysis of animals in each of 1-3 areas indicated each sample. Sr-89 and Sr-90 once by the cow census where doses are per quarter.

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 U.)

available.

At least one sample from a control location

b. Fish I sample each from Chickamauga and At least once per 184 days. One Gamma scan on edible portion.

Watts Bar Reservoirs. sample representing a commercially important species and one sample representing a recreationally important species.

Table A-I (continued)

SEQUOYAH NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples and Sampling and Type and Frequency and/or Sample Locationsb Collection Frequency of Analysis

c. Food Products I sample each of principal food At least once per 365 days at time of Gamma scan on edible portion.

products grown at private gardens harvest. The types of foods available and/or farms in the immediate for sampling will vary. Following is vicinity of the plant. a list of typical foods which may be available:

Cabbage, lettuce, or greens Corn Green Beans Potatoes Tomatoes One sample of each of the same foods

(.kj t'j grown at greater than 10 miles distance from the plant.

d. Vegetatione Samples from farms producing milk At least once per 31 days. 1-131 and gamma scan at least once but not providing a milk sample. per 31 days.

Control sample from one control dairy farm when sampling is performed at an indicator location.

a. The sampling program outlined in this table is that which was in effect at the end of 2009.

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.

e. Vegetation sampling is applicable only for farms that meet the criteria for milk sampling and when implementation of milk sampling is not possible.

Table A-2 SEQUOYAH NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS Map Approximate Indicator (I)

Location Distance or Samples Number' Station Sector (Miles) Control (C) Collectedb 2 LM-2 N 0.7 I AP,CF,S 3 LM-3 SSW 2.0 I AP,CF,S 4 LM-4 NE 1.5 I AP,CF,S 5 LM-5 NNE 1.8 AP,CF,S 7 PM-2 SW 3.8 AP,CF,S 8 PM-3 W 5.6 AP,CF,S 9 PM-8 SSW 8.7 AP,CF,S 10 PM-9 WSW 2.6 AP,CF,S 11 RM-! SW 16.7 CI AP,CF,S 12 RM-2 NNE 17.8 I AP,CF,S 13 RM-3 ESE 11.3 C AP,CF,S 14 RM-4 NW 20.0 C AP,CF,S 19 Farm HW NW 1.2 CI MWC 21 Farm HS E 4.6 C M C

23 Farm EH ENE 9.5 I M 24 Well No. 6 NNE 0.15 W 25 Farm K NE 40.0 M 31 TRMO 473.0 -- 10.7' PW (East Side Utilities) 32 TRM 469.9 -- PW (E. I. DuPont) I 33 TRM 465.3 --

PW (Chattanooga) 35 TRM 503.8 -- 20.1' C PWSW (Dayton) 37 TRM 485.0 -- 1.3d C SS 38 TRM 483.4 0.3d SW 40 TRM 479.0 -- 4.7d SS 44 TRM 480.0 -- 3.7d SS 46 Chickamauga Reservoir (TRM 471-530) I F 47 Watts Bar Reservoir (TRM 530-602) C F

a. See Figures A-I, A-2, and A-3

b. Sample codes:

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 Table A-3 SEQUOYAH NUCLEAR PLANT ENVIRONMENTAL DOSIMETER LOCATIONS Map Approximate Onsite (On)b Location Distance or Number3 Station Sector Offsite MOY 3 SSW-1C 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 II SW-3 SW 16.7 Off 12 NNE-4 NNE 17.8 Off 13 ESE-3 ESE 11.3 Off 14 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 4.5 Off 55 NE-I NE 2.4 Off 56 NE-2 NE 4.1 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 71 S-1 S 1.5 On 72 S-2 S 4.7 Off 73 SSW-1 SSW 0.6 'On 74 SSW-2 SSW 4.0 Off 75 SW-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 81 W-1 W 0.6 On 82 W-2 W 4.3 Off 83 WNW-1 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-1 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 348.75 N 11.25 NNW NNE337 "57.25 33.75

- 4.,, EQ"*U OY AH 41 Eo1.25 Scale Mile Figure A-2 Radiological Environmental Monitoring Locations Between 1 and 5 miles from the Plant N

SCALE 0 1 2 MILES Figure A-3 Radiological Environmental Monitoring Locations More than 5 miles from the Plant SCAL.E J0 l fa 12 WIIEB APPENDIX B 2009 PROGRAM MODIFICATIONS Appendix B Radiological Environmental Monitoring Program Modification No modifications were made to the SQN REMP during 2009.

APPENDIX C PROGRAM DEVIATIONS Appendix C Program Deviations A problem with the sampling equipment prevented the collection of air monitoring samples from one of the twelve sampling locations during two sampling periods. A milk sample was not available from the small farm located 1.2 miles NW for one biweekly sampling period.

Problems with the sampling pump on the onsite Well No. 6 prevented collection of the groundwater composite sample during the last sampling period of the year.

Table C-1 provides additional details on these missed samples.

Table C- I Radiological Environmental Monitoring Program Deviations Date Station Location Remarks 02/10/09 Farm HW 1.2 miles NW The milk sample was not available at this small farm location. The cow that was being milked went dry andmilk was not available from a second cow until the following sampling period. A PER was not generated for the missed sample. Since no milk was produced at the location, sampling for the period was not applicable.

04/13/09 LM-2 0.7 miles N The total sample volume for air filter and charcoal cartridge samples was not adequate due to a failure of the sampling pump. The problem was a failure of the pump. The pump was replaced and the system returned to normal operation. The missed samples were documented with PER 169007.

.L.

06/01/09 PM-2 3.8 miles SW The sampling system was not running at the time of weekly sample collection. The problem was loss of power. The utility company supplying power to the locations was contacted and power was restored in time for samples to be collected during the next sampling cycle. The missed samples were documented with PER 173059.

12/22/09 Well 6 0.15 miles NNE The starter relay for sampling pump failed and the composite sample did not contain an adequate sample volume. A replacement part was ordered.

The missed sample and equipment problem was documented with PER 212325.

APPENDIX D 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 of 1-131 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. Spectral data reduction is performed by the computer program HYPERMET.

The charcoal cartridges used to sample gaseous radioiodine are analyzed by gamma spectroscopy using a high resolution gamma spectroscopy system with germanium detectors.

The necessary 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.

APPENDIX E 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.

Table E- 1 Nominal LLD Values A. Radiochemical Procedures Sediment Air Filters Water Milk Wet Vegetation and Soil (pCi/mr) (PCY/L (pCi/L) (pCi/kg wet) (pCi/g dry)

Gross Beta 0.002 1.9 Tritium 270 Iodine- 131 0.4 0.4 6.0 Strontium-89 5.0 3.5 31.0 1.6 Strontium-90 2.0 2.0 12.0 0.4

,00

Table E- I (continued)

Nominal LLD Values B. Gamma Analyses Foods Air Charcoal Water Vegetation Wet Soil and Tomatoes Particulates Filter and Milk and Grain Vegetation Sediment Fish Clam Flesh Potatoes, etc.

__pCim 3 pCi/m 3 PC L pCig, dry pCi/kg, wet pCi/g, dry pCilg, dry pCi/g, dry pCi/kg, wet Ce-141 .005 .02 10 .07 35 .10 .07 .35 20 Ce-144 .01 .07 30 .15 115 .20 .15 .85 60 Cr-51 .02 0.15 45 .30 200 .35 .30 2.4 95 1-131 .005 0.03 10 .20 60 .25 .20 1.7 20 Ru-103 .005 0.02 5 .03 25 .03 .03 .25 25 Ru-106 .02 0.12 40 .15 190 .20 .15 1.25 90 Cs-134 .005 0.02 5 .03 30 .03 .03 .14 10 Cs-137 .005 0.02 5 .03 25 .03 .03 .15 10 Zr-95 .005 0.03 10 .05 45 .05 .05 .45 45 Nb-95 .005 0.02 5 .25 30 .04 .25 .25 10 Co-58 .005 0.02 5 .03 20 .03 .03 .25 10 Mn-54 .005 0.02 5 .03 20 .03 .03 .20 10 Zn-65 .005 0.03 10 .05 45 .05 .05 .40 45 Co-60 .005 0.02 5 .03 20 .03 .03 .20 10 K-40 .04 0.30 100 .40 400 .75 .40 3.50 250 Ba-140 .015 0.07 25 .30 130 .30 .30 2.4 50 La-140 .01 0.04 10 .20 50 .20 .20 1.4 25 Fe-59 .005 0.04 10 .08 40 .05 .08 .45 25 Be-7 .02 0.15 45 .25 200 .25 .25 1.9 90 Pb-212 .005 0.03 15 .04 40 .10 .04 .30 40 Pb-214 .005 0.07 20 .50 80 .15 .50 .10 80 Bi-214 .005 0.05 20 .10 55 .15 .10 .50 40 Bi-212 .02 0.20 50 .25 250 .45 .25 2.0 130 TI-208 .002 0.02 10 .03 30 .06 .03 .25 30 Ra-224 -- -- -- -- .75 -- -- --

Ra-226 -- -- -- -- .15 -- -- --

Ac-228 .01 0.07 20 .10 70 .25 .10 .75 50

Table E-2 Maximum Values for the Lower Limits of Detection (LLD)

Specified by the SQN Offsite Dose Calculation Manual Airborne Particulate Food Water or Gases Fish Milk Products Sediment Analysis pCi/L _pCi/mr3 aCi/k wet pCi/L pCi/kg, wet pCi/kg, dry gross beta 4 1 x 10-2 N.A. N.A. N.A. N.A.

H-3 2000a 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 1b 7 x 10. 2 N.A. 1 60 N.A.

Cs-134 15 5 xl0"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. If no drinking water pathway exists, a value of 15 pCi/liter may be used.

APPENDIX F QUALITY ASSURANCE/QUALITY CONTROL PROGRAM Appendix F 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 employed by the radioanalytical laboratory is designed to ensure that the sampling and analysis process is working as intended. The program includes equipment checks and the analysis of 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, or cross-checks.

Blanks are samples which contain no measurable radioactivity or no activity of the type being measured. Such samples are analyzed to determine whether there is any contamination of equipment or commercial laboratory chemicals, cross-contamination in the chemical process, or interference from isotopes other than the one being measured.

Duplicate samples are generated at random by the sample computer program which schedules the collection of the routine samples. For example, if the 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 laboratory supervisor in the daily review process.

Blind spikes test this process since the blind spikes contain radioactivity at levels high enough to be detected. Furthermore, the activity can be put into such samples at the extreme limit of detection (near the LLD) to 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 deterniining 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. During 2009, all analysis results for internal cross-check samples were within agreement limits when compared to the known value.

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 2009. The results of TVA's participation in this cross-check program are presented in Table F-1. As shown in Table F-i, the result for the Cs- 134 reported for the third quarter gamma in air filter cross check was too low. A review of the lab results of other gamma cross checks containing Cs-134 analyzed during 2009 verified that all other Cs-134 results for QC samples were within the applicable agreement limits. This data included two cross checks analyzed after the sample with the low result. Corrective action program problem evaluation report (PER) 222670 was initiated to document the investigation of this Cs-134 measurement.

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-I Results For 2009 External Cross Checks Results Test Period Sample Type / Analysis Known TVA First Quarter Water (pCi/L)

Gross Beta 2.35E+02 2.37E+02 1.01 Water (pCi/Filter) 34 4.48E+03 5.78E+03 1.29 First Quarter Water (pCi/L) 6.90E+01 6.91E+01 1.00 1.20E+02 1.18E+02 0.98 3.87E+02 3.91E+02 1.01 1.19E+02 1.1OE+02 0.92 131cS 1.41E+02 1.45E+02 1.03 58 CO 1.51E+02 1.50E+02 0.99 54 Mn 1.62E+02 1.69E+02 1.04 5917e 1.27E+02 1.22E+02 0.96 65 Zn 1.97E+02 2.06E+02 1.05 "CO 1.80E+02 1.89E+02 1.05 First Quarter Milk (pCi/L) 13311 0.99 7.95E+01 7.91E+01 9 1.06 8 Sr 8.35E+01 8.84E+01 9'Sr 1.3313+01 1.52E+01 1.14 Third Quarter Water (pCi/L) 3 H 1.41E+04 1.44E+04 1.02 Third Quarter Sand (pCi/gram) 0.640 0.613 0.96 0.515 0.513 1.00

' 34cS 0.287 0.269 0.94 137Cs 0.431 0.442 1.03 58 Co 0.232 0.233 1.00 54MN 0.480 0.502 1.05 59 Fe 0.343 0.350 1.02 65 0.503 1.06 Zn 0.474 60CO 0.373 0.389 1.04 Third Quarter Air Filter (pCi/filter)

Gross Beta 80.1 69.3 0.87 Third Quarter Air Filter (pCi/filter) 14 Ce 228.0 198.0 0.87 183.0 168.0 0.92 134 Cs 102.0 78.7. 0.77

'37Cs 153.0 139.0 0.91 SSCo 0.98 82.3 80.9 IMn 171.0 167.0 0.98 59 Fe 122.0 121.0 0.99 65 Zn 169.0 170.0 1.01 60Co 133.0 120.0 0.90 APPENDIX G 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 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.

In response to the 2009 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 2009 compared to 2008. The location of the nearest garden changed in eight sectors as identified in 2009.

For milk ingestion, there were no changes as compared to 2008.

Tables G-1, G-2, and G-3 show the comparative relative calculated doses for 2008 and 2009.

Table G- 1 SEQUOYAH NUCLEAR PLANT Relative Projected Annual Air Submersion Dose to the Nearest Resident Within Five Miles of Plant mrem/year 2008 Survey 2009 Survey Approximate Approximate Distance Annual Distance Annual Sector Miles Dose Miles Dose N 0.8 0.12 0.8 0.12 NNE 1.5 0.07 1.5 0.07 NE 1.5 0.06 1.5 0.06 ENE 1.3 0.02 1.3 0.02 E 1.0 0.02 1.0 0.02 ESE 1.0 0.02 1.0 0.02 SE 1.1 0.02 1.1 0.02 SSE 1.3 0.03 1.3 0.03 S 1.1 0.11 1.1 0.11 SSW 1.3 0.15 1.3 0.15 SW 1.4 0.06 1.4 0.06 WSW 0.6 0.05 0.6 0.05 W 0.6 0.06 0.6 0.06 WNW 1.1 0.02 0.9 0.02 NW 0.8 0.04 0.8 0.04 NNW 0.5 0.14 0.5 0.14 Table G-2 SEQUOYAH NUCLEAR PLANT Relative Projected Annual Dose to Child's Bone from Ingestion of Home-Grown Foods mrem/year IfiOR f5q1rev 2009 Survey

......... I Approximate Approximate Distance Annual Distance Annual Miles Dose, Miles Dose Sector 1.1 2.25 1.1 2.25 N

2.5 1.13 2.5 1.13 NNE NE 2.9 0.74 3.8 0.49 2.8 0.26 2.8 0.26 ENE 1.5 0.42 1.5 0.42 E

1.1 0.50 1.1 0.50 ESE 2.0 0.30 2.1 0.28 SE 2.8 0.34 1.3 1.03 SSE 1.3 2.72 2.6 1.00 S

2.8 1.70 2.8 1.70 SSW 2.2 1.01 2.2 1.12 SW 2.3 0.27 0.7 1.45 WSW 0.9 1.03 0.9 1.03 W

1.1 0.62 1.1 0.62 WNW 0.9 1.26 0.9 1.16 NW 1.5 0.87 1.2 1.23 NNW C

Table G-3 SEQUOYAH NUCLEAR PLANT Relative Projected Annual Dose to Receptor Thyroid from Ingestion of Milk mrem/year Approximate Distance Annual Dose X/Q Location Sector (MilesW 2008 2009 (units-s/m 3 )

Farm HSb E 4.6 0.008 0.008 6.74 E-8 Farm HW NW 1.2 0.052 0.052 5.48 E-7

a. Distances measured to nearest property line.

b. Grade A dairy.

APPENDIX H DATA TABLES AND FIGURES Table H - 1 DIRECT RADIATION LEVELS Average External Gamma Radiation Levels Onsite and Offsite Sequoyah Nuclear Plant for Each Quarter - 2009 mR / Quarter (a)

Average External Gamma Radiation Levels (b) 1st qtr 2nd qtr 3rd qtr 4th qtr mRlyr Average, 0 - 2 miles 10.3 11.8 12.3 10.6 45 (onsite)

Average,

> 2 miles 8.7 9.7 10.6 8.7 38 (offsite)

(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 TABLE H - 2 DIRECT RADIATION LEVELS Individual Stations at Sequoyah Nuclear Plant Environmental Radiation Levels mR I quarter Map TLD 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 2009 2009 2009 2009 mR/year 49 N-1 3 .6 12.4 12.9 14.8 12.7 52.8 50 N-2 4 2.1 10.1 8.3 13.8 9.6 41.8 51 N-3 358 5.2 13.5 9.2 11.4 8.1 42.2 52 N4 355 10.0 9.0 8.7 11.8 10.6 40.1 5 NNE-1 13 1.8 11.3 15.2 15.7 14.2 56.4 53 NNE-2 31 4.5 7.9 7.8 7.5 7.1 30.3 12 NNE-4 32 17.8 7.6 8.6 12.5 5.2 33.9 55 NE-1 38 2.4 7.9 9.7 12.3 10.1 40.0 4 NE-1A 50 1.5 10.1 (1) 12.8 11.2 45.5 56 NE-2 51 4.1 1.1 5.9 6.5 4.6 18.1 57 ENE-1 73 .2 9.0 11.1 10.9 8.1 39.1 58 ENE-2 66 5.1 6.2 11.1 9.9 9.6 36.8 59 E-1 96 1.2 6.8 7.3 8.0 6.6 28.7 60 E-2 87 5.2 10.7 8.7 10.9 8.6 38.9 62 ESE-1 110 1.2 9.6 10.1 10.4 6.6 36.7 63 ESE-2 112 4.9 8.4 12.0 10.9 9.1 40.4 13 ESE-3 117 11.3 8.4 12.0 10.9 6.1 37.4 66 SE-1 131 1.4 7.9 6.4 7.0 8.6 29.9 67 SE-2 129 1.9 10.7 10.1 11.8 11.7 44.3 68 SEA 136 5.2 11.8 14.3 14.8 9.1 50.0 69 SSE-1 154 1.6 8.4 8.3 10.9 7.6 35.2 70 SSE-2 158 4.6 11.3 14.3 15.7 14.2 55.5 note (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 / quarter Map TLD 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 2009 2009 2009 2009 mR/year 71 S-1 183 1.5 10.7 13.4 13.8 12.7 50.6 72 S-2 185 4.7 4.5 5.5 7.0 8.1 25.1 73 SSW-1 203 .6 14.1 12.5 (1) 11.7 51.1 90 SSW-lB 192 1.5 3.9 6.4 8.0 5.6 23.9 3 SSW-1C 198 2.0 8.4 (1) 9.9 9.1 36.5 74 SSW-2 204 4.0 12.4 14.8 14.8 13.2 55.2 9 SSW-3 203 8.7 7.9 10.1 12.8 10.6 41.4 75 SW-1 228 .7 14.1 15.2 14.3 15.7 59.3

& 7 SW-2 227 3.8 9.0 10.6 11.8 8.1 39.5

! 11 SW-3 228 16.7 11.3 12.5 12.8 13.7 50.3 76 WSW-1 241 .9 16.3 17.6 12.8 11.2 57.9 77 WSW-2 238 2.5 7.9 4.1 6.5 6.6 25.1 10 WSW-2A 250 2.6 7.3 6.9 6.5 6.1 26.8 78 WSW-3 248 *5.7 11.3 12.5 15.2 12.2 51.2 79 WSW-4 244 7.8 10.7 9.7 8.4 6.1 34.9 81 W-1 260 .6 10.7 13.9 20.6 13.2 58.4 82 W-2 275 4.3 7.9 7.8 *7.5 4.6 27.8 8 W-3 280 5.6 7.9 8.3 8.9 8.1 33.2 83 WNW-1 292 .4 6.8 13.9 14.8 13.7 49.2 84 WNW-2 295 5.3 7.9 (1) 12.3 10.6 41.1 85 NW-1 315 .4 16.3 14.8 14.8 16.7 62.6 86 NW-2 318 5.2 9.0 8.7 8.4 8.6 34.7 14 NW-3 320 20.0 7.3 10.1 6.5 6.6 30.5 87 NNW-1 344 .6 11.8 11.5 11-.4 8.1 42.8 88 NNW-2 342 1.7 6.2 11.5 11.8 8.1 37.6 89 NNW-3 334 5.3 7.3 11.1 9.4 8.1 35.9 note (1) Sum of available quarterly data normalized to 1 year for the annual exposure value

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory RADIOACTIVITY IN AIR FILTER PCI/M3 - 0.037 BQ/M3 Name of Facility: SEQUOYAH NUCLEAR PLANT Docket Number: 50-327,328 Location of Facility: HAMILTON TENNESSEE Reporting Period: 2009 Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Detection Mean (F) Name Mean (F) Mean (F) Nonroutine of Analysis (LLD) Range Distance and Direction Range Range Reported Performed See Note 1 See Note 2 See Note 2 See Note 2 Measurements GROSS BETA 622 2.OOE-03 2.03E-02 (414 /414) PM-2 COUNTY PARK TN 2.09E-02 (51/ 51) 2.07E-02 (208 / 208) 9.53E 3.61E-02 3.8 MILES SW 1.20E 3.32E-02 1.07E 3.34E-02 GAMMA SCAN (GELI) 156 AC-228 1.OOE-02 104 VALUES < LLD PM-9 LAKESIDE 13 VALUES < LLD 52 VALUES < LLD 2.6 MILES WSW BE-7 2.OOE-02 1.15E-01 (104/104) PM-2 COUNTY PARK TN 1.23E-01 (13/13) 1.16E-01 (52/52) 6.42E 1.83E-01 3.8 MILES SW 8.06E 1.83E-01 7.79E 1.82E-01 81-212 2.OOE-02 9.92E-02 (1 / 104) LM-2 NORTH 9.92E-02 (1 13) 52 VALUES < LLD 9.92E 9.92E-02 0.8 MILES NORTH 9.92E 9.92E-02 81-214 5.00E-03 1.77E-02 (101 I 104) PM-3 DAISY TN 2.13E-02 (13/13) 1.69E-02 (51 / 52)

CD C'

5.30E 9.83E-02 5.6 MILES W 5.40E 9.83E-02 5.60E 4.59E-02 K-40 4.OOE-02 104 VALUES < LLD LM-3 HARRISON BAY RD 13 VALUES < LLD 4.15E-02 (1 / 52) 2.0 MILES SSW 4.15E 4.15E-02 PB-212 5.OOE-03 104 VALUES < LLD PM-9 LAKESIDE 13 VALUES < LLD 52 VALUES < LLD 2.6 MILES WSW PB-214 5.OOE-03 1.72E-02 (99 / 104) PM-2 COUNTY PARK TN 2.03E-02 (12/13) 1.60E-02 (51 /52) 5.10E 9.40E-02 3.8 MILES SW 7.OOE 4.44E-02 5.70E-03 - 4.68E-02 TL-208 2.OOE-03 104 VALUES < LLD PM-9 LAKESIDE 13 VALUES < LLD 52 VALUES < LLD 2.6 MILES WSW Note: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1 Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory RADIOACTIVITY IN CHARCOAL FILTER PCI/M3 - 0.037 BQ/M3 Name of Facility: SEQUOYAH NUCLEAR PLANT Docket Number: 50-327,328 Location of Facility: HAMILTON TENNESSEE Reporting Period: 2009 Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Detection Mean (F) Name Mean (F) Mean (F) Nonroutine of Analysis (LLD) Range Distance and Direction Range Range Reported Performed See Note 1 See Note 2 See Note 2 See Note 2 Measurements GAMMA SCAN (GELI) 622 BI-214 5.00E-02 8.30E-02 (132 /414) PM-8 HARRISON TN 9.85E-02 (171 52) 7.74E-02 (461 208) 5.03E 2.62E-01 8.7 MILES SSW 5.56E 2.32E-01 5.09E 1.72E-01 1-131 3.OOE-02 SEE NOTE 3 K-40 3.OOE-01 3.77E-01 (100/414) PM-2 COUNTY PARK TN 4.15E-01 (27/51) .3.93E-01 (34 1208) 3.OOE 6.25E-01 3.8 MILES SW 3.04E 5.96E-01 3.06E 6.03E-01 PB-212 3.OOE-02 414 VALUES < LLD PM-8 HARRISON TN 52 VALUES < LLD 208 VALUES < LLD 8.7 MILES SSW PB-214 7.OOE-02 1.06E-01 (66/414) PM-9 LAKESIDE 1.24E-01 (1 152) 1.05E-01 (26 / 208) H 7.05E 3.02E-01 2.6 MILES WSW 1.24E 1.24E-01 7.02E 2.77E-01 0~

Note: 1. Nominal Lower Level of Detection (LLD) as described in Table E ' 1 Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).

Note: 3. 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.

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory RADIOACTIVITY IN MILK PCI/IL - 0.037 BQ/L Name of Facility: SEQUOYAH NUCLEAR PLANT Docket Number: 50-327,328 Location of Facility: HAMILTON TENNESSEE Reporting Period: 2009 Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Detection Mean (F) Name Mean (F) Mean (F) Nonroutine of Analysis (LLD) Range Distance and Direction Range Range Reported Performed See Note 1 See Note 2 See Note 2 See Note 2 Measurements IODINE-131 103 4.00E.01 51 VALUES < LLD 52 VALUES < LLD GAMMA SCAN (GELI) 103 AC-228 2.00E+01 3.75E+01 (1 /51) H. SMITH FARM 3.75E+01 (1 /26) 1.92E+02 (2 /52) 3.75E+01 - 3.75E+01 4.6 MILES E 3.75E+01- 3.75E+01 2.61E+01 - 3.58E+02 BI-214 2.OOE+01 3.27E+01 (23/51) H WALKER FARM 3.67E+01 (12 /25) 3.31E+01 (21/52) 2.09E+01 - 4.98E+01 1.2 MILES NW 2.23E+01 - 4.98E+01 2.08E+01 - 6.82E+01 K-40 1.00E+02 1.35E+03 (51 /51) H. SMITH FARM 1.47E+03 (26126) 1.30E+03 (52 / 52) 9.84E+02 - 2.37E+03 4.6 MILES E 1.20E+03 - 2.37E+03 1.07E+03 - 1.44E+03 PB-212 1.50E+01 51 VALUES < LLD H WALKER FARM 25 VALUES < LLD 52 VALUES < LLD 00 1.2 MILES NW PB-214 2.00E+01 2.86E+01 (16/51) H WALKER FARM 2.94E+01 (13/25) 2.94E+01 (13/52) U' 2.09E+01 - 4.07E+01 1.2 MILES NW 2.09E+01 - 4.07E+01 2.02E+01 - 5.67E+01 TL-208 1.00E+01 51 VALUES < LLD H. SMITH FARM 26 VALUES < LLD 52 VALUES < LLD 4.6 MILES E SR 89 15 3.50E+00 8 VALUES < LLD 7 VALUES < LLD SR 90 15 2.00E+00 3.59E+00 (4/8) H WALKER FARM 3.59E+00 (4 / 4) 7 VALUES < LLD 2.25E+00 - 5.14E+00 1.2 MILES NW 2.25E+00 - 5.14E+00 Note: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1 Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory RADIOACTIVITY IN SOIL PCI/GM - 0.037 BQ/G (DRY WEIGHT)

Name of Facility: SEQUOYAH NUCLEAR PLANT Docket Number: 50-327,328 Location of Facility: HAMILTON TENNESSEE Reporting Period: 2009 Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Detection Mean (F) Name Mean (F) Mean (F) Nonroutine of Analysis (LLD) Range Distance and Direction Range Range Reported Performed See Note I See Note 2 See Note 2 See Note 2 Measurements GAMMA SCAN (GELI) 12 AC-228 2.50E-01 1.05E+00 (8 18) PM-2 COUNTY PARK TN 1.56E+00 (/I 1) 9.52E-01 (4/4) 5.19E 1.56E+00 3.8 MILES SW 1.56E+00- 1.56E+00 7.23E 1.23E+00 BE-7 2.50E-01 3.47E-01 (2 8) PM-3 DAISY TN 3.53E-01 (1/ 1) 4.54E-01 (2/4) 3.41 E 3.53E-01 5.6 MILES W 3.53E 3.53E-01 4.28E 4.80E-01 BI-212 4.50E-01 1.15E+00 (8/8) PM-2 COUNTY PARK TN 1.73E+00 (1 /1) 1.12E+00 (4/4) 5.79E 1.73E+00 3.8 MILES SW 1.73E+00- 1.73E+00 7.35E 1.58E+00 BI-214 1.50E-01 9.42E-01 (8 /8) LM-4 SKULL ISLAND 1.09E+00 (1/ 1) 7.94E-01 (4 /4) 6.60E 1.09E+00 1.5 MILES NE 1.09E+00- 1.09E+00 6.54E 8.85E-01 CS-137 3.OOE-02 3.65E-01 (8 I 8) LM-4 SKULL ISLAND 5.31E-01 (1 /1) 3.03E-01 (4 4) 1.01E 5.31E-01 1.5 MILES NE 5.31E 5.31E-01 9.32E 8.22E-01 S K-40 7.50E-01 7.48E+00 (8 /8) LM-2 NORTH 1.12E+01 (0 1) 7.93E+00 (4/4) 3.42E+00- 1.12E+01 0.8 MILES NORTH 1.12E+01- 1.12E+01 4.30E+00 - 1.32E+01 PA-234M 4.OOE+00 8 VALUES < LLD PM-3 DAISY TN 1 VALUES < LLD 4 VALUES < LLD 5.6 MILES W PB-212 1.00E-01 1.05E+00 (8 /8) PM-2 COUNTY PARK TN 1.52E+00 (1/1) 9.21E-01 (4/4) 5.22E 1.52E+00 3.8 MILES SW 1.52E+00 - 1.52E+00 6.87E 1.21E+00 PB-214 1.50E-01 1.04E+00 (8/8) PM-2 COUNTY PARK TN 1.22E+00 (1/1) 8.18E-01 (414).

7.35E 1.22E+00 3.8 MILES SW 1.22E+00- 1.22E+00 6.80E 9.13E-01 RA-226 1.50E-01 9.42E-01 (8 /8) LM-4 SKULL ISLAND 1.09E+00 (1/ 1) 7.94E-01 (4 /4) 6.60E-01 - 1.09E+00 1.5 MILES NE 1.09E+00- 1.09E+00 6.54E 8.85E-01 TL-208 6.00E-02 3.51E-01 (8/8) LM-5 WARE POINT 4.72E-01 (1/ 1) 3.11E-01 (4/4) 1.77E 4.72E-01 1.8 MILES NNE 4.72E 4.72E-01 2.24E 4.32E-01 SR 89 12 1.60E+00 8 VALUES < LLD 4 VALUES < LLD SR 90 12 4.00E-01 8 VALUES < LLD 4 VALUES < LLD Note: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1 Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory RADIOACTIVITY IN CABBAGE PCI/KG - 0.037 BQ/KG (WET WT)

Name of Facility: SEQUOYAH NUCLEAR PLANT Docket Number: 50-327,328 Location of Facility: HAMILTON TENNESSEE Reporting Period: 2009 Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Detection Mean (F) Name Mean (F) Mean (F) Nonroutine of Analysis (LLD) Range Distance and Direction Range Range Reported Performed See Note 1 See Note 2 See Note 2 See Note 2 Measurements GAMMA SCAN (GELI) 2 BI-214 4.OOE+01 8.05E+01 (1 1) SQNP 8.05E+01 (1/1) 6.38E+01 (11 1) 8.05E+01 - 8.05E+01 1.1 MILES WNW 8.05E+01- 8.05E+01 6.38E+01 - 6.38E+01 K-40 2.50E+02 1.63E+03 (1/1) SQNP 1.63E+03 (11/ 1) 2.12E+03 (1 1) 1.63E+03 - 1.63E+03 1.1 MILES WNW 1.63E+03 - 1.63E+03 2.12E+03 - 2.12E+03 PB-212 4.OOE+01 1 VALUES < LLD SQNP 1 VALUES < LLD 1 VALUES < LLD 1.1 MILES WNW PB-214 8.OOE+01 1 VALUES < LLD SQNP 1 VALUES < LLD 1 VALUES < LLD 1.1 MILES WNW

-! CD 0P

,=

Note: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1 Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory RADIOACTIVITY INCORN PCI/KG - 0.037 BQ/KG (WET WT)

Name of Facility: SEQUOYAH NUCLEAR PLANT Docket Number: 50-327,328 Location of Facility: HAMILTON TENNESSEE Reporting Period: 2009 Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Detection Mean (F) Name Mean (F) Mean (F) Nonroutine of Analysis (LLD) Range Distance and Direction Range Range Reported Performed See Note 1 See Note 2 See Note 2 See Note 2 Measurements GAMMA SCAN (GELI) 2 BI-214 4.OOE+01 8.36E+01 (1 1) SQNP 8.36E+01 (1 /1) 7.72E+01 (1l1) 8.36E+01 -8.36E+01 1.1 MILES WNW 8.36E+01 -8.36E+01 7.72E+01 -7.72E+01 K-40 2.50E+02 2.10E+03 (1l1) SQNP 2.1 OE.03 (1l1) 2.08E+03 (Il11) 2.10E+03 -2.10E+03 1.1 MILES WNW 2.10E+03 -2.10E+03 2.08E+03 - 2.08E+03 PB-214 8.OOE+01 8.04E+01 (11/1) SQNP 8.04E+01 (1l1) 8.62E+01 (1/.1) 8.04E.Oi 8.04E+01 1.1 MILES WNW 8.04E+01 -8.04E+01 8.62E+01 - 8.62E+01 00 Note: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1 Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory RADIOACTIVITY IN GREEN BEANS PCI/KG - 0.037 BQ/KG (WET WT)

Name of Facility: SEQUOYAH NUCLEAR PLANT Docket Number: 50-327,328 Location of Facility: HAMILTON TENNESSEE Reporting Period: 2009 Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Detection Mean (F) Name Mean (F) Mean (F) Nonroutine of Analysis (LLD) Range Distance and Direction Range Range Reported Performed See Note 1 See Note 2 See Note 2 See Note 2 Measurements GAMMA SCAN (GELI) 2 AC-228 5.00E+01 1 VALUES < LLD SQNP I VALUES < LLD 1 VALUES < LLD 1.1 MILES WNW BI-214 4.OOE+01 8.61 E+01 (1/1) SQNP 8.61 E+01 (1/1) 6.58E+01 (1 /1) 8.61E+01 -8.61E+01 1.1 MILES WNW 8.61E+01 -8.61E+01 6.58E+01 - 6.58E+01 K-40 2.50E+02 2.25E+03 (1/1) SQNP 2.25E+03 (11/1) 1.58E+03 (11/1) 2.25E+03 -2.25E+03 1.1 MILES WNW 2.25E+03 - 2.25E+03 1.58E+03 - 1.58E+03 PB-214 8.OOE+01 8.28E+01 (1l1) SQNP 8.28E+01 (1/1) 1 VALUES < LLD 8.28E+01 -8.28E+01 1.1 MILES WNW 8.28E+01 -8.28E+01 t-J ,=

Note: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1 Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory RADIOACTIVITY IN POTATOES PCI/KG - 0.037 BQ/KG (WET WT)

Name of Facility: SEQUOYAH NUCLEAR PLANT Docket Number: 50-327,328 Location of Facility: HAMILTON TENNESSEE Reporting Period: 2009 Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Detection Mean (F) Name Mean (F) Mean (F) Nonroutine of Analysis (LLD) Range Distance and Direction Range Range Reported Performed See Note 1 See Note 2 See Note 2 See Note 2 Measurements GAMMA SCAN (GELI) 2 BI-214 4.OOE+01 6.66E+01 (1 /1) SQNP 6.66E+01 (1 /1) 1.03E+02 (1 1) 6.66E+01 - 6.66E+01 1.1 MILES WNW 6.66E+01- 6.66E+01 1.03E+02 - 1.03E+02 K-40 2.50E+02 3.33E+03 (1 /1) SQNP 3.33E+03 (1 /1) 3.60E+03 (1/1) 3.33E+03 - 3.33E+03 1.1 MILES WNW 3.33E+03- 3.33E+03 3.60E+03 - 3.60E+03 PB-212 4.00E+01 1 VALUES < LLD SQNP 1 VALUES < LLD 1 VALUES < LLD 1.1 MILES WNW PB-214 8.00E+01 1 VALUES < LLD SQNP 1 VALUES < LLD 9.37E+01 (11 1) 1.1 MILES WNW 9.37E+01 - 9.37E+01 TL-208 3.OOE+01 1 VALUES < LLD SQNP 1 VALUES < LLD 1 VALUES < LLD ,H 1.1 MILES WNW L,3

!i o" Note: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1 Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory RADIOACTIVITY IN SURFACE WATER(Total)

PCI/L - 0.037 BQ/L Name of Facility: SEQUOYAH NUCLEAR PLANT Docket Number: 50-327,328 Location of Facility: HAMILTON TENNESSEE Reporting Period: 2009 Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Detection Mean (F) Name Mean (F) Mean (F) Nonroutine of Analysis (LLD) Range Distance and Direction Range Range Reported Performed See Note 1 See Note 2 See Note 2 See Note 2 Measurements GROSS BETA 26 1.90E+00 2.24E+00 (4 /13) TRM 483.4 2.24E+00 (4 /13) 2.88E+00 (10 /13) 2.05E+00 - 2.54E÷00 2.05E+00- 2.54E+00 1.93E+00 - 4.24E+00 GAMMA SCAN (GELI) 26 AC-228 2.OOE+01 13 VALUES < LLD TRM 483.4 13 VALUES < LLD 13 VALUES < LLD BI-214 2.OOE+01 2.99E+01 (6/13) TRM 483.4 2.99E+01 (6/13) 3.06E+01 (8 /13) 2.07E+01 - 4.14E+01 2.07E+01 - 4.14E+01 2.03E+01 - 4.27E+01 K-40 1.OOE.02 13 VALUES < LLD TRM 483.4 13 VALUES < LLD 13 VALUES < LLD

-3 PB-212 I .50E+011 13 VALUES < LLD TRM 483.4 13 VALUES < LLD 13 VALUES < LLD PB-214 2.OOE+01 2.18E+01 (3 /13) TRM 483.4 2.18E+01 (3/13) 2.82E+01 (5/13) 2.02E+01 - 2.37E+01 2.02E+01 - 2.37E+01 2.15E+01 - 3.54E+01 TL-208 1.0OE+01 13 VALUES < LLD TRM 483.4 13 VALUES < LLD 13 VALUES < LLD TRITIUM 21 2.70EI-02 4 VALUES < LLD TRM 483.4 2.80E+02 (1 / 17) 2.80E+02 - 2.80E+02 Note: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1 Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory RADIOACTIVITY IN PUBLIC WATER(Total)

PCI/L - 0.037 BQ/L Name of Facility: SEQUOYAH NUCLEAR PLANT Docket Number: 50-327,328 Location of Facility: HAMILTON TENNESSEE Reporting Period: 2009 Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Detection Mean (F) Name Mean (F) Mean (F) Nonroutine of Analysis (LLD) Range Distance and Direction Range Range Reported Performed See Note 1 See Note 2 See Note 2 See Note 2 Measurements GROSS BETA 52 1.90E+00 2.50E+00 (16/39) CHATTANOOGA 2.63E+00 (7 / 13) 2.88E+00 (10/13) 1.98E+00 - 3.67E+00 TRM 465.3 2.OOE+00 - 3.67E+00 1.93E+00 - 4.24E+00 GAMMA SCAN (GELI) 52 AC-228 2.00E+011 2.OOE+01 (1/ 39) E.1. DUPONT 2.00E+01 (1/13) 13 VALUES < LLD 2.OOE+01 - 2.00E+01 TRM 470.5 2.00E+01 - 2.OOE+01 B1-214 2.OOE+01 3.16E+01 (28139) CF INDUSTRIES 3.50E+01 (8/13) 3.06E+01 (8 / 13) 2.11E+01 - 5.37E+01 TRM 473.0 2.24E+01 - 5.16E+01 2.03E+01 - 4.27E+01 K-40 11.00E+02 39 VALUES < LLD CF INDUSTRIES 13 VALUES < LLD 13 VALUES < LLD TRM 473.0 9-PB-212 1.50E+01 39 VALUES < LLD CHATTANOOGA 13 VALUES < LLD 13 VALUES < LLD 0~

-'I Y, TRM 465.3 PB-214 2.OOE+01 2.83E+01 (16/39) CF INDUSTRIES 3.17E+01 (5/13) 2.82E+01 (5 13) 2.01E+01 - 4.91E+01 TRM 473.0 2.01E+01 - 4.91E+01 2.15E+01 - 3.54E+01 TH-234 -1.00E+00 1.83E+01 (1 39) CHATTANOOGA 1.83E+01 (1/ 13) 9.03E+00 (11/ 13) 1.83E+01 - 1.83E+01 TRM 465.3 1.83E+01- 1.83E+01 9.03E+00 - 9.03E+00 TL-208 1.OOE+01 39 VALUES < LLD E.I. DUPONT 13 VALUES < LLD 13 VALUES < LLD TRM 470.5 TRITIUM 42 2.70E+02 3.17E+02 (4/25) CF INDUSTRIES 3.17E+02 (4/17) 2.80E+02 (1 / 17) 2.70E+02 - 3.63E+02 TRM 473.0 2.70E+02- 3.63E+02 2.80E+02 - 2.80E+02 Note: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1 Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory RADIOACTIVITY IN WELL WATER(Total)

PCIIL - 0.037 BQ/L Name of Facility: SEQUOYAH NUCLEAR PLANT Docket Number: 50-327,328 Location of Facility: HAMILTON TENNESSEE Reporting Period: 2009 Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Detection Mean (F) Name Mean (F) Mean (F) Nonroutine of Analysis (LLD) Range Distance and Direction Range Range Reported Performed See Note 1 See Note 2 See Note 2 See Note 2 Measurements GROSS BETA 8 1.90E+00 4 VALUES < LLD SON WELL #6 1.10E+01 (4/4)

ONSITE NNE 4.50E+00 - 1.47E+01 GAMMA SCAN (GELI) 16 AC-228 2.OOE+01 12 VALUES < LLD SON WELL #6 12 VALUES < LLD 4 VALUES < LLD ONSITE NNE BI-214 2.00E+011 3.44E+01 (8/12) SQN WELL #6 3.44E+01 (8/12) 4.07E+02 (4 / 4) 2.03E+01 - 6.48E+01 ONSITE NNE 2.03E+01 - 6.48E+01 2.57E+02 - .5.87E+02 K-40 1.OOE+02 12 VALUES < LLD SON WELL #6 12 VALUES < LLD 4 VALUES < LLD ONSITE NNE H 9-41 PB-212 1.50E+01 12 VALUES < LLD SON WELL #6 12 VALUES < LLD 4 VALUES < LLD ONSITE NNE PB-214 2.OOE+01 3.21E+01 (7/12) SON WELL #6 3.21E+01 (7/12) 3.95E+02 (4 /4) 2.27E+01 - 4.07E+01 ONSITE NNE 2.27E+01 - 4.07E+01 2.61E+02 - 5.77E+02 TRITIUM 16 2.70E+02 12 VALUES < LLD 4 VALUES < LLD Note: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1 Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated In parentheses (F).

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory RADIOACTIVITY IN COMMERCIAL FISH PCI/GM - 0.037 BQJG (DRY WEIGHT)

Name of Facility: SEQUOYAH NUCLEAR PLANT Docket Number: 50-327,328 Location of Facility: HAMILTON TENNESSEE Reporting Period: 2009 Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Detection Mean (F) Name Mean (F) Mean (F) Nonroutine of Analysis (LLD) Range Distance and Direction Range Range Reported Performed See Note 1 See Note 2 See Note 2 See Note 2 Measurements GAMMA SCAN (GELI) 4 AC-228 1.00E-01 1.28E-01 (1 /2) CHICKAMAUGA RES 1.28E-01 (1 2) 2 VALUES < LLD 1.28E 1.28E-01 TRM 471-530 1.28E 1.28E-01 BI-214 1.00E-01 1;83E-01 (212) CHICKAMAUGA RES 1.83E-01 (2/2) 1.63E-01 (1 /2) 1.04E 2.62E-01 TRM 471-530 1.04E 2.62E-01 1.63E 1.63E-01 CS-137 3.OOE-02 2 VALUES < LLD CHICKAMAUGA RES 2 VALUES < LLD 5.80E-02 (2 / 2)

TRM 471-530 4.29E 7.31E-02 K-40 4.OOE-01 1.34E+01 (2 /2) CHICKAMAUGA RES 1.34E+01 (2 / 2) 1.28E+01 (2 / 2) 1.32E+01 - 1.37E+01 TRM 471-530 1.32E+01 - 1.37E+01 1.24E+01 - 1.32E+01 PB-212 4.OOE-02 9.10E-02 (1/2) CHICKAMAUGA RES 9.10E-02 (1 /2) 2 VALUES < LLD 9.10E 9.10E-02 TRM 471-530 9.10E 9.10E-02 ,H

, PB-214 5.00E-01 2 VALUES < LLD CHICKAMAUGA RES 2 VALUES < LLD 2 VALUES < LLD 40=

TRM 471-530 TL-208 3.00E-02 4.70E-02 (1 / 2) CHICKAMAUGA RES 4.70E-02 (1/2) 2 VALUES < LLD 4.70E 4.70E-02 TRM 471-530 4.70E 4.70E-02 Note: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1 Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory RADIOACTIVITY IN GAME FISH PCI/GM - 0.037 BQ/G (DRY WEIGHT)

Name of Facility: SEQUOYAH NUCLEAR PLANT Docket Number: 50-327,328 Location of Facility: HAMILTON TENNESSEE Reporting Period: 2009 Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Detection Mean (F) Name Mean (F) Mean (F) Nonroutine of Analysis (LLD) Range Distance and Direction Range Range Reported Performed See Note 1 See Note 2 See Note 2 See Note 2 Measurements GAMMA SCAN (GELI) 4 BI-214 1.OOE-01 3.19E-01 (2/2) CHICKAMAUGA RES 3.19E-01 (2/2) 2.04E-01 (2 / 2) 3.05E 3.33E-01 TRM 471-530 3.05E 3.33E-01 1.45E 2.63E-01 CS-137 3.OOE-02 3.74E-02 (1 /2) CHICKAMAUGA RES 3.74E-02 (11/2) 5.95E-02 (2 /2) 3.74E 3.74E-02 TRM 471-530 3.74E 3.74E-02 3.58E 8.32E-02 K-40 4.OOE-01 1.53E+01 (2 / 2) CHICKAMAUGA RES 1.53E+01 (2 / 2) 1.63E+01 (2 /2) 1.47E+01 - 1.58E+01 TRM 471-530 1.47E+01 - 1.58E+01 1.47E+01 - 1.79E+01 PB-214 5.00E-01 2 VALUES < LLD CHICKAMAUGA RES 2 VALUES < LLD 2 VALUES < LLD TRM 471-530

,00 Note: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1 Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory RADIOACTIVITY IN SHORELINE SEDIMENT PCI/GM - 0.037 BQ/G (DRY WEIGHT)

Name of Facility: SEQUOYAH NUCLEAR PLANT Docket Number: 50-327,328 Location of Facility: HAMILTON TENNESSEE Reporting Period: 2009 Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Number of Total Number of Detection Mean (F) Name Mean (F) Mean (F) Nonroutine of Analysis (LLD) Range Distance and Direction Range Range Reported Performed See Note I See Note 2 See Note 2 See Note 2 Measurements GAMMA SCAN (GELI) 6 AC-228 2.50E-01 1.07E+00 (4 /4) TRM 479.0 1.22E+00 (2 / 2) 1.15E+00 (2/2) 7.85E 1.47E+00 TRM 479.0 9.59E 1.47E+00 1.08E+00 - 1.23E+00 BE-7 2.50E-01 5.23E-01 (4 /4) TRM 480.0 6.29E-01 (2 12) 2 VALUES < LLD 3185E-01 - 8.73E-01 TRM 480.0 3.85E 8.73E-01 BI-212 4.50E-01 1.35E+00 (4 4) TRM 479.0 1.58E+00 (2/2) 1.24E+00 (2 2) 1.06E+00- 1.73E+00 TRM 479.0 1.42E+00 - 1.73E+00 1.15E+00 - 1.32E+00 BI-214 1.50E-01 1.03E+00 (4 /4) TRM 479.0 1.24E+00 (2 / 2) 9.68E-01 (2 /2) 8.09E 1.33E+00 TRM 479.0 1.16E+00 - 1.33E+00 9.49E 9.88E-01 GS-137 3.OOE-02 2.86E-01 (2 /4) TRM 480.0 5.01E-01 (1/2) 7.07E-02 (2 /2) 7.08E 5.01E-01 TRM 480.0 5.01E 5.01E-01 3.37E 1.08E-01 K-40 7.50E-01 9.35E+00 (4 4) TRM 480.0 1.25E+01 (2 / 2) 5.35E+00 (2 2) 0ý 2.14E+00 - 2.28E+01 TRM 480.0 2.14E+00 - 2.28E+01 4.41E+00 - 6.28E+00 PB-212 1.0OE-01 1.06E+00 (4 /4) TRM 479.0 1.17E+00 (2/2) 1.10E+00 (2 12) 7.32E 1.46E+00 TRM 479.0 8.82E 1.46E+00 1.04E+00 - 1.16E+00 PB-214 1.50E-01 1.011E+00 (4/4) TRM 479.0 1.19E+00 (2/2) 1.02E+00 (2 /2) 7.94E 1.32E+00 TRM 479.0 1.05E+00- 1.32E+00 1.00E+00 - 1.04E+00 RA-224 7.50E-01 1.45E+00 (11 4) TRM 480.0 1.45E+00 (1 / 2) 2 VALUES < LLD 1.45E+00- 1.45E+00 TRM 480.0 1.45E+00- 1.45E+00 RA-226 1.50E-01 1.03E+00 (4 /4) TRM 479.0 1.24E+00 (212) 9.68E-01 (2 /2) 8.09E 1.33E+00 TRM 479.0 1.16E+00 - 1.33E+00 9.49E 9.88E-01 TL-208 6.00E-02 3.58E-01 (4/4) TRM 479.0 3.91E-01 (212) 3.84E-01 (2/2) 2.61E 4.80E-01 TRM 479.0 3.02E 4.80E-01 3.53E 4.15E-01 Note: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1 Note: 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).

Direct Radiation Levels Sequoyah Nuclear Plant Four Quarter Moving Average 25 . ................. ..... ..... . .. ........ ... .

Initial SQNP operation in July, 1980 InLight OSL deployment in Jan 2007 20

a. 15

< o CLL 10ru

-A- On-Sae Off-Site 5

1970 1975 1980 1985 1990 1995 2000 2005 2010 2015 Calendar Year

Annual Average Gross Beta Activity in Air Filters Sequoyah Nuclear Plant 0.25 0.20 F E Initial SQNP Operation in July, 1980 [Indictr LzzCntrliý Ir1 CL 0.15 F 00 Z-0.10 -

PReoperational Average 0.05 I 0.00 1965 1970 1975 1980 1985 1990 1995 2000 2005 2010 Calendar Year Note: no gross beta measurements were made in 1974

Annual Average Activity of Cs-137 in Soil Sequoyah Nuclear Plant 3.0 - - - - - - - - ------------ * - - - ~ - - * - - - - - ..-

. -. 1.......

- bIndicator 2.5 Initial SQNP Operation in July, 1980 -- o-Control E

00 E 2.0 Preoperational Average w.

S1.5 E 1.0 - - .... . .--.......-......------------

14 0.5 0.0 1970 1975 1980 1985 1990 1995 2000 2005 2010 Calendar Year

Average.Annual Gross Beta Activity in Surface Water Sequoyah Nuclear Plant 6

5 ITI R'eoperational Average

ý0 4 -----------------------------------------------------------

1;1 I-a.

3 "0

>U 0

Initial SQNP 2 Operation in July, 1980 Idicator

--0-- Control 1

0 1970 1975 1980 1985 1990 1995 2000 2005 2010 Calendar Year

Annual Average Gross Beta Activity in Drinking Water Sequoyah Nuclear Plant 5.0.

. 4.0 Preoperational Average

'=*3.0 06

---

---- 1

• 2.0 SInitial SQNP Id ao Operation in July, --- Indicator 1980 -- Control 1.0 0.0 1970 1975 1980 1985 1990 1995 2000 2005 2010 Calendar Year

Annual Average Activity Cs-137 in Game Fish Sequoyah Nuclear Plant 0.60 - *----*-.****. - --- . --.. --..

-s-Dovmteam Upstream 0.50 Initial SQNP Operation in EJuly, 1980 0 0.40

> 0.30 Preoperational Average U

0.20 0.10 0.00 1970 1975 1980 1985 1990 1995 2000 2005 2010 Calendar Year

Annual Average Activity Cs-137 in Shoreline Sediment Sequoyah Nuclear Plant 0.35 0.30

-0o- Up~stream _

Dotmaslrem 2

2 0.25 0T 40 '3

a. Note: Iitial SQNP Operation in 0.20 July, 1980. There was no preoperational sampling of 0

4 0.15 shoreline sediment 1!

0 4 0.10 0.05 0.00 L 1970 1975 1980 1985 1990 1995 2000 2005 2010 Calendar Year