ML12115A253

Annual Radiological Environmental Operating Report - 2011

ML12115A253
Person / Time
Site:	Sequoyah
Issue date:	04/23/2012
From:	James Shea Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML12115A253 (96)

Text

Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402-2801 April 23, 2012 10 CFR 50.4 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission 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 - 2011 Enclosed is the subject report for the period of January 1 to December 31, 2011. 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, each of which specifies that the report be submitted prior to May 1s" of each year.

If you have any questions concerning this matter, please telephone Rusty Proffitt at (423) 843-6651.

'Resp t Ily, W Shea Saager, Corporate Nuclear Licensing

Enclosure:

Annual Radiological Environmental Operating Report, Sequoyah Nuclear Plant, 2011 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 2011

Annual Radiological Environmental Operating Report Seq uoyah Nuclear Plant 2011

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SEQUOYAH NUCLEAR PLANT 2011 TENNESSEE VALLEY AUTHORITY April 2012

TABLE OF CONTENTS Table of Contents .............................................

Executive Summary ...........................................

Introduction .............................. .................. 3 Naturally Occurring and Background Radioactivity ................. 3 Electric Power Production ..................................... 5 Site/Plant Description .......................................... 7 Radiological Environmental Monitoring Program .................... 8 Direct Radiation M onitoring ..................................... 11 Measurement Techniques ...................................... 11 R esults .................................................... 12 Atmospheric M onitoring ....................................... 14 Sample Collection and Analysis ................................ 14 R esults .................................................... 15 Terrestrial M onitoring ......................................... 16 Sample Collection and Analysis ................................ 16 R esults .................................................... 17 Liquid Pathway Monitoring ..................................... 18 Sample Collection and Analysis ................................ 18 Results .................................................... 19 Assessment and Evaluation ..................................... 21 Results .................................................... 21 C onclusions ................................................ 22 References ................................................... 23 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 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

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TABLE OF CONTENTS (continued)

Appendix A Radiological Environmental Monitoring Program and Sam pling Locations .............................................. 27 Appendix B 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

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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

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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

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EXECUTIVE

SUMMARY

This report describes the radiological environmental monitoring program (REMP) conducted by TVA in the vicinity of the Sequoyah Nuclear Plant (SQN) in 2011. 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 analyses performed on SQN Radiological Environmental Monitoring Program (REMP) samples for the 2011 monitoring year did not detect any fission or activiation product radionuclides attributable to SQN plant operations. Except for the period between March 2011 and April 2011, the levels of naturally occurring radionuclides identified by these analyses were consistent with the normal background levels measured in previous monitoring years. During the period of March 2011 and April 2011, SQN REMP air filters, charcoal cartridge, and milk samples showed low levels of radioactivity both in the on-site (indicator) and the off-site (control) samples as a result of the incident with the Fukushima nuclear plant in Japan on March 11, 2011. As such, the atypical detection of these radionuclides in both indicator and control samples is credibly attributed to the trans-Pacific transport of airborne releases from Dai-ichi, Fukushima following the March 11, 2011 Tohoku earthquake and is not related to the SQN plant operations. The Environmental Protection Agency (EPA) and other U.S. nuclear facilities identified trace amounts of radioactive iodine, cesium, and tellurium in the environmental samples consistent with the Japenese nuclear incident. These levels are also consistent with the levels found by a Department of Energy monitoring program. Similar results were observed in the radiological environmental monitoring samples following the Chernobyl plant event in Ukraine in 1986. However, the concentrations detected in the REMP samples during 2011 are conservatively included in this report for completeness.

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 and fish. 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.

INTRODUCTION This report describes and summarizes the results of radioactivity measurements taken in the vicinity of SQN and laboratory analyses of samples collected in the area. The measurements are taken to comply with the requirements of the Code of Federal Regulations (CFR), 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:

Total body <3 mrem/year Any organ <10 mrem/year Gaseous Effluents Noble gases:

Gamma radiation < 10 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 of detection (LLD) for the SQN monitoring program with the regulatory limits for maximum annual average effluent concentrations released to unrestricted areas and levels requiring special reports to the NRC. It should be noted that the levels of radioactive materials measured in the environment are typically only slightly above the lower limit of detection. The data presented in this report indicate compliance with the regulations.

SITE/PLANT DESCRIPTION Sequoyah is located on a site near the geographical center of Hamilton County, Tennessee, on a peninsula on the western shore of Chickamauga Lake at Tennessee River Mile (TRM) 484.5.

Figure 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 I 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 the 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 2011.

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 is performed by a contract laboratory. Analyses are conducted in accordance with written and approved procedures and are based on accepted methods. A summary of the analysis techniques and methodology is presented in Appendix D. Data tables summarizing the sample analysisr'*esults are presented in Appendix H.

The radiation detection devices and analysis methods used to determine the radionuclide content of samples collected in the environment are very sensitive to small amounts of radioactivity. The sensitivity of the measurements process is defined in terms of the lower limit of detection. A description of the nominal LLDs for the radioanalytical laboratory is presented in Appendix E.

The ERM&I laboratory employs a comprehensive quality assurance/quality control program to monitor laboratory performance throughout the year. The program is intended to detect any problems in the measurement process as soon as possible so they can be corrected. This program includes equipment checks, to ensure that the radiation detection instruments are working

properly, and the analysis of quality control samples. The laboratory participated in a blind cross check program administrated by a vendor. This program provided an independent interlaboratory comparison program. A complete description of the laboratory's quality assurance/quality control program is presented in Appendix F.

DIRECT RADIATION MONITORING Direct radiation levels are measured at various monitoring points around the plant site.

These measurements include contributions from cosmic radiation, radioactivity in the ground, fallout from atmospheric nuclear weapons tests conducted in the past, and any radioactivity that may be present as a result of plant operations. Because of the relatively large variations in background radiation as compared to the small levels from the plant, contributions from the plant may be difficult to distinguish.

Measurement Techniques The Landauer InLight environmental dosimeter is used in the radiological environmental monitoring program for the measurement of direct radiation. This dosimeter contains four elements consisting of aluminum oxide detectors with open windows as well as plastic and copper filters. The dosimeter is processed using optically stimulated luminescence (OSL) technology to determine the amount of radiation exposure.

The dosimeters are placed approximately 1 meter above the ground, with two at each monitoring location. Sixteen monitoring points are located around the plant near the site boundary, one location in each of the 16 compass sectors. One monitoring point is also located in each of the 16 compass sectors at a distance of approximately four to five miles from the plant.

Dosimeters are also placed at additional monitoring locations out to approximately 32 miles from the site. The dosimeters are exchanged every 3 months. The dosimeters are sent to Landauer for processing and results reporting. The values are corrected for transit and shielded background exposure. An average of the two dosimeter results is calculated for each monitoring point. The system meets or exceeds the performance specifications outlined in American National Standards Institute (ANSI) N545-1975 and Health Physics Society (HPS) Draft Standard N13.29 for environmental applications of dosimeters.

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Results The results for environmental dosimeter measurements are normalized to a standard quarter (91.25 days or 2190 hours0.0253 days <br />0.608 hours <br />0.00362 weeks <br />8.33295e-4 months <br />). The monitoring locations are grouped according to the distance from the plant. The first group consists of the monitoring points within 2 miles of the plant. The second group is made up of the locations greater than 2 miles from the plant. Past data have shown that the average results from the locations more than 2 miles from the plant are essentially the same. Therefore, for purposes of this report, monitoring points 2 miles or less from the plant are identified as "onsite" stations and locations greater than 2 miles are considered "offsite."

The quarterly gamma radiation levels determined from the dosimeters deployed around SQN in 2011 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 2011, 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 (Pre-operational) 2011 1976-79 Onsite Stations 68 79 Offsite Stations 61 63 The data in Table H- 1 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 2011.

The Landauer InLight Optically Stimulated Luminescence (OSL) dosimeters were deployed since 2007 replacing the Panasonic UD-814 used during the previous years.

From January 2007 to December 2010 the REMP OSL dosimeter results reported in the annual reports for these years included the Tungsten shield dose contribution resulting in an over correction. This industry common issue was identified and discussed in a presentation at the June 30, 2011 REMP industry conference. The industry guidance reference to this new method to correct for the shield dose will be incorporated in the upcoming revision of ANSI N13.37, Dosimetry Processing, expected to be issued in 2012. The conclusion from the historical data analysis is that a shield dose contribution of 5.3 mR needs to be added to both the on-site and off-site quarterly results reported during 2007-2010. The corrected value is applied both to the on-site (indicator) and off-site (control or background) OSL dosimeter quarterly data, and therefore, has no effect on the net final results which is based on the difference between the on-site and off-site values. The correction to add a shield dose contribution of 5.3 mR to the results during 2007-2010 is included in the 2011 Annual REMP report.

The data in Table H-2 contains the results of the individual monitoring stations. The results reported in 2011 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 (cfln) 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.

Resulls The results from the analysis of air particulate samples are summarized in Table H-3. Gross beta activity in 2011 was consistent with levels reported in previous years. The average gross beta activity for air filter samples was 0.022 pCi/m 3. The annual average of the gross beta activity in air particulate filters at these stations for the years 1971-2011 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 Chemobyl 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.

During the period of March 2011 and April 2011 SQN REMP samples showed low levels of radioactivity both in the on-site (indicator) and the off-site (control) samples as a result of the incident with the Fukushima nuclear plant in Japan on March 11, 2011. Except for this period between March 2011 and April 2011, the levels of naturally occurring radionuclides identified by these analyses were consistent with the normal background levels measured in previous monitoring years. As such, the atypical detection of these radionuclides in both indicator and control samples is credibly attributed to the trans-Pacific transport of airborne releases from Dai-ichi, Fukushima following the March 11, 2011 Tohoku earthquake and is not related to the SQN plant operations. However, the concentrations detected in the REMP samples during 2011 are conservatively included in this report for completeness.

Only naturally occurring radionuclides were identified by the monthly gamma spectral analysis of the air particulate samples. No fission or activation products attributable to SQN plant operations were detected. As shown in Table H-4, no 1-131 attributable to SQN plant operations was detected in any of the charcoal cartridge samples collected in 2011.

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-12.

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 2011 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 this year 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. Samples of apples, cabbage, corn, green beans, potatoes, and tomatoes 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.

I 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 except for the period in April 2011 attributed to the Fukushima event. The results for the quarterly Sr-89 analysis were also less than the nominal LLD value of 3.5 pCi/liter. By far the predominant isotope reported in milk samples was the naturally..

occurring K-40. The average K-40 concentration was approximately 1,240 pCi/liter for milk samples analyzed in 2011.

The gamma analysis of soil samples detected trace levels of Cs-137. 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-12.

LIQUID PATHWAY MONITORING Potential exposures from the liquid pathway can occur from drinking water, ingestion of edible fish, or from direct radiation exposure from radioactive materials deposited in the river sediment.

The monitoring program includes the collection of samples of surface water, groundwater, drinking water supplies, fish, and shoreline sediment. Samples from the reservoir are collected both upstream and downstream from the plant.

Sample Collection and Analysis Samples of surface water are collected from the Tennessee River downstream and upstream of the plant using automatic sampling systems. A timer turns on the system at least once every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and the sample is collected into a composite jug. A 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 'f6rgross 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 concentration in samples collected from the downstream monitoring location were below the LLD of 270 pCi/liter. 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/liter and control location samples averaged 3.1 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 2011 is presented in Figure H-4. A summary table of the results is shown in Table H-13.

There were no fission or activation product radionuclides identified by the gamma analysis of drinking water samples. The tritium concentration for samples from the downstream location and from the upstream location were below the LLD of 270 pCi/liter. Average gross beta activity was 2.4 pCi/liter for the downstream stations and 3.1 pCi/liter at the control station. The results are shown in Table H-14 and a trend plot of the gross beta activity in drinking water from 1971 to 2011 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. The average gross beta concentrations in samples from the onsite well was 2.4 pCi/liter, and the average from the offsite

well was 10.5 pCi/liter. These gross beta levels are representative of the levels typically found in groundwater. The results from the analysis of groundwater samples are presented in Table H-15.

Cesium-137 was identified in one control fish sample. The maximum Cs-137 concentration in this control sample was 0.03 pCi/g, while no Cs-137 was detected for indicator location samples.

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-16 and H-17.

The gamma analysis of shoreline sediment samples detected Cs-137 in one sample of 0.06 pCi/g.

The Cs-137 concentration is consistent with preoperational levels typically present in the environment as the result of past nuclear weapon testing or other fallout effects. Results from the analysis of shoreline sediment samples are shown in Table H-18.

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 2011 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 and soil. The Cs-137 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 1 COMPARISON OF PROGRAM LOWER LIMITS OF DETECTION WITH THE REGULATORY LIMITS FOR MAXIMUM ANNUAL AVERAGE EFFLUENT CONCENTRATIONS RELEASED TO UNRESTRICTED AREAS AND REPORTING LEVELS Concentrations in Water, pCi/Liter Concentrations in Air, pCi/Cubic Meter Effluent Reporting Lower limit Effluent Reporting Lower limit3 Analysis Concentration' Level 2 of Detection3 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 xl0"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 CFR20 2 Source: SQN Offsite Dose Calculation Manual, Table 2.3-2 3 Source: Table E-1 of this report

t'3 Figure 2 ENVIRONMENTAL EXPOSURE PATHWAYS OF MAN DUE TO RELEASES OF RADIOACTIVE MATERIAL TO THE ATMOSPHERE AND LAKE.

We Airibrne Releases Plume Exposure Liquid Releases Diluted By Lake ELJIJL J1I MAN Consumed By Man Animals (MilkMeat) Shereline Exposure Consumed By Animals Drinkiug Water Fish Vegetation Uptake From Soil

APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM AND SAMPLING LOCATIONS

Table A- I SEQUOYAH NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM8 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 approximately 6-10 miles from the 90 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 3. WATERBORNE

a. Surface water TRM 5 0 3 .8 d Collected by automatic sequential- Gross beta and gamma scan on each TRM 483.4 type sampler'C with composite composite sample. Composite for samples collected over a period tritium analysis at least once per of less than or equal to 31 days. 92 days.

b.. Groundwater 1 sample adjacent to the plant (Well At least once per 31 days. Composited for gross beta, gamma No. 6). scan, and tritium at least once per 92 days.

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 samplerc 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.

1 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 50 3 .8 d). sampler' with composite sample 0i 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 PROGRAM' Exposure Pathway Number of Samples and Sampling and Type and Frequency

.and/or Sample Locationsb Collection Frequency of Analysis

4. INGESTION

a. Milk 1 sample from milk producing At least once per 15 days. Gamma isotopic and 1-1 31 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 available.

At least one sample from a control location

b. Fish 1 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 grown at greater than 10 miles distance from the plant.

d. Vegetation' 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 2010.

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 wlihen 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 I AP,CF,S 7 PM-2 SW 3.8 I 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

!1 RM-1 SW 16.7 C AP,CF,S 12 RM-2 NNE 17.8 C AP,CF,S 13 RM-3 ESE 11.3 I AP,CF,S 14 RM-4 NW 20.0 CI AP,CF,§S 19 Farm HW NW 1.2 CI MW-21 Farm HS E 4.6 I M 23 Farm EH ENE 9.5 M 24 Well No. 6 NNE 0.15 C W 25 Farm K NE 40.0 M 31 TRMe 473.0 10.7' I PW (East Side Utilities) 32 TRM 469.9 -- 13.8d I PW (E. I. DuPont) 33 TRM 465.3 -- 18.4d I PW (Chattanooga) 35 TRM 503.8 -- 20.Id C PWSW (Dayton) 37 TRM 485.0 -- 1.3d C SS 38 TRM 483.4 0.3d I SW 40 TRM 479.0 -- 4.7' I SS 44 TRM 480.0 -- 3.7d SS 46 Chickamauga Reservoir (TRM 471-530) 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 Number' Station Sector (miles) Offsite (OM 3 SSW-IC SSW 2.0 On 4 NE-IA NE 1.5 On 5 NNE-I NNE 1.8 On 7 SW-2 SW 3.8 Off 8 W-3 W 5.6 Off 9 SSW-3 SSW 8.7 Off 10 WSW-2A WSW 2.6 Off 11 SW-3 SW 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-1 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-1 SSE 1.6 On 70 SSE-2 SSE 4.6 Off 71 S-1 S 1.5 On 72 S-2 S 4.7 Off 73 SSW-I SSW 0.6 On 74 SSW-2 SSW 4.0 Off 75 SW-I SW 0.7 On 76 - WSW-! 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-I NNW 0.6 On 88 NNW-2 NNW 1.7 On 89 NNW-3 NNW 5.3 Off 90 SSW-IB SSW 1.5 On

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

b. Dosimeters designated "onsite" are located 2 miles or less from the plant; "offsite" are located more than 2 miles from the plant.

Figure A-1 Radiological Environmental Monitoring Locations Within 1 mile of the Plant 348.75 11.25 4 126.29 33.75 S6.25

.MENE 8* i .78.75 NNW NNE

- 101.25 75" 3\, 123.75

!13.75SS* *112 S 146.25 Scale 0 Mile

Figure A-2 Radiological Environmental Monitoring Locations Between 1 and 5 miles from the Plant 348.75 N 11.25 NE 78.75

-E 59 A.

SCALE MI1 2 WIES

Figure A-3 Radiological Environmental Monitoring Locations More than 5 miles from the Plant SCAL

APPENDIX B PROGRAM MODIFICATIONS

Appendix B Radiological Environmental Monitoring Program Modification No modifications were made to the SQN REMP during 2011.

APPENDIX C PROGRAM DEVIATIONS

Appendix C Program Deviations Problems with the sampling equipment prevented the collection of a limited number air monitoring samples. A review of the details of missed samples did not identify any adverse trend in equipment performance.

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

Table C-1 Radiological Environmental Monitoring Program Deviations Sample Date Station Location Type Description 02/08/11 TRM 483.4 TRM 483.4 Water The breaker was found tripped and there was no water in the composite container to pull for a sample.

PER # 322624.

05/02/11 LM-2 0.7 Miles N AF/CF Stations PM-2 and LM-2 lost power due to the April 27th PM-2 3.8 Miles SW AF/CF tornadoes. PER # 368693 05/03/11 Walker Farm 1.25 Miles NW Milk No milk was available from this single cow small farm through due to the cow being dry from pregnancy and nursing.

08/22/11 Since no milk was produced at the location, sampling for this period was not applicable and therefore, no PER was k) generated. PER not applicable.

05/09/11 PM-2 3.8 Miles SW AF/CF There were still power issues from the April 27th tornadoes.

The electric motor was replaced twice.

There were only 70 volts AC coming in from the transformer.

The electric power board was contacted and they fixed the problem. PER # 456308 3rd Qtr 2011 WNW-2 5.3 Miles Dosimeter Both dosimeters were missing at two stations at the time of the SSE-1 1.6 Miles Dosimeter quarterly change out; WNW-2 Soddy Daisy Fire Station and SSE-1 Harrison Bay Road E. New dosimeters were deployed immediately upon discovery. PER # 409214 4th Qtr 2011 N-4 10.0 miles Dosimeter During the quarterly change out, one dosimeter from station N-4, Railroad St., Sale Creek was missing. The replacement dosimeter was deployed immediately upon discovery. PER 491413

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- I Nominal LLD Values A. Radiochemical Procedures Sediment Air Filters Water Milk Wet Vegetation and Soil Analysis (Rci/m3) (_Ci/L) (p*i/1) (pCi/kg wet) (nCi/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 90

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.

Analysis pCi/R3 pCi/m 3 pcil pCi/g. dy pCi/kg. wet pCi/g, dry PU/ dry pCi/a. dry pCi/ka, wet Ce-I141 .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/ 3 g. wet _kpCi/L pi/kg, wet pCi/ka. 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 Ib 7 x 10"2 N.A. 1 60 N.A.

Cs-134 15 5 x10"2 130 15 60 150 Cs-137 18 6 x 10-2 150 18 80 180 Ba-140 60 N.A. N.A. 60 N.A. N.A.

La-140 15 N.A. N.A. 15 N.A. N.A.

a. If no drinking water pathway exists, a value of 3000 pCi/liter may be used.

b. 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, and cross-checks.

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

Duplicate samples are generated at random by the sample computer program which schedules the collection of the routine samples. For example, 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 determining if the lab can find the "right answer." These samples provide information about the accuracy of the measurement process. Further information is available about the variability of the process if multiple analyses are requested on the same sample. Like blind spikes or analytical knowns, these samples can also be spiked with

low levels of activity to test detection limits. The lab results for the internal quality control program samples met the program performance goals.

To provide for an independent verification of the laboratory's ability to make accurate..

measurements, the laboratory participated in an environmental level cross-check program available through Analytics, Inc., during 2011. The results of TVA's participation in this cross-check program are presented in Table F-1. All results were within the program agreement limits.

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 2011 External Cross Checks Results Test Period Samele Tvye / Analysis Known TVA Agreement First Quarter Water (pCi/L)

Gross BBeta 2.47E+02 2.23E+02 Yes First Quarter Water (pCi/L) 3H 4.53E+03 5.73E+03 Yes First Quarter Water (pCi/L) 131I 9.40E+'01 9OIE+401 Yes 13"Cr 1.96E+02 2.02E+02 Yes 4

13' CS 8.56E+01 7.94E+01 Yes

'7CS 1.35E+02 1.36E+02 Yes

'Co 7.44E+0lI 7.57E+01 Yes Mn 1.75E+02 1.79E+02 Yes 654 "9Fe 1.15E+i02 1.34E-*02 Yes

'Zn 1.7213i-02 1.72E+402 Yes

'CO 1. 3E+02 1.16E+02 Yes Second Quarter Synthetic Urine (pCi/L) 3H L.OOE+04 1.02E+04 Yes Third Quarter Milk (pCi/L) 1311 I.OIE-t02 1.03E+02 Yes Third Quarter Water (pCi/L) 3H 9.01E+03 9.41E+03 Yes Third Quarter Sand (pCi/gran)

", Ce Yes 1.59E-0 I 1.56E-01

"'Cr 5.39E-0 I 5.03E-01 Yes

'"Cs 3.05E-0 1 2.67E-01 Yes 137Cs Yes 2.7 1E-0 I 2.60E-01 "Co 2.32E-0 I 2.1513-01 Yes 4

5 Mn 3.59E-0 I 3.52E-01 Yes "Fe 1.31IE-01 1.23E-01 Yes 6"Zn 4.30E-01 4.31 E-01 Yes OCo 3.7413-01 3.6 1E-0 I Yes Third Quarter Air Filter (pCi/Filter)

Gross Beta 9.36E+01 8.91E+01 Yes Third Quarter Air Filter (pCi/Filter) 14'Ce 6.07E+'01 Yes 6.5 1E+O I

"'Cr 2.21E+02 2.03E-'02 Yes 134Cs 1.25E+02 1.04E+02 Yes

'"TCs Yes 1.11IE402 1.03E+02 "Co Yes 9.51E'-0 I 8.94E+01 54Mn 1.47E+'02 1.48E+02 Yes "Fe 5.35E+01 4.75E+01O Yes 6"Zn 1.76E+02 1.83E-+02 Yes 60Co 1.53E+02 1.44E+02 Yes Third Quarter Water (pCi/L)

Gross Beta 2.49E+02 2.41E+02 Yes Fourth Quarter Milk (pCi/L) 131 9.OOE+01 9.87E+0lI Yes "Sr 8.93E+01 8.23E+01 Yes 9°Sr 1.48E+01 Yes 1.48E+01

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 (8 km) 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 2011 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. The historical meterological data period was revised in the SQN ODCM. This revised historical data was used in the calculations performed for the 2010 land use survey. This change resulted in small changes in the projected doses for 2011 as compared to 2010.

There were no changes in the location of the nearest resident as identified in 2011 compared to 2010. The location of the nearest garden changed in eight sectors as identified in 2011.

For milk ingestion, there were no changes as compared to 2010.

Tables G-1, G-2, and G-3 show the comparative relative calculated doses for 2010 and 2011.

The distances in these tables were identified in 'meters' instead of 'miles'.

Table G- 1 SEQUOYAH NUCLEAR PLANT Relative Projected Annual Air Submersion Dose to the Nearest Resident Within Five Miles (8 km) of Plant mrem/year 2011 Survey 2010 Survey Approximate Approximate Distance Annual Distance Annual Sector Meters Dose Meters Dose N 1,295 0.14 1,295 0.12 NNE 2,400 0.08 2,400 0.07 NE 2,400 0.05 2,400 0.06 ENE 2,134 0.02 2,134 0.02 E 1,694 0.02 1,694 0.02 ESE 1,600 0.02 1,600 0.02 SE 1,753 0.03 1,753 0.02 SSE 2,134 0.04 2,134 0.03 S 1,786 0.12 1,786 0.11 SSW 2,134 0.14 2,134 0.15 SW 2,341 0.05 2,341 0.06 WSW 1,032 0.06 1,032 0.05 W 976 0.05 976 0.06 WNW 1,449 0.03 1,449 0.02 NW 1,372 0.04 1,372 0.04 NNW 841 0.14 841 0.14

Table G-2 SEQUOYAH NUCLEAR PLANT Relative Projected Annual Dose to Child's Bone from Ingestion of Home-Grown Foods mrem/year 2011 Survey 2010 Survey Approximate Approximate Distance Annual Distance Annual Sector Meters Dose Meters Dose N 3,970 0.84 1,829 2.25 NNE 4,380 1.00 3,703 1.25 NE 4,580 0.67 6,118 0.49 ENE 5,490 0.19 4,508 0.26 E 2,446 0.37 2,446 0.42 ESE 1,850 0.52 1,850 0.50 SE 3,380 0.31 3,220 0.30 SSE 4,470 0.38 2,254 0.92 S 4,100 1.15 3,864 1.12 SSW 3,220 2.50 3,220 2.74 SW 3,542 0.88 3,542 1.12 WSW 1,127 1.75 1,127 1.45 W 1,449 0.87 1,449 1.03 WNW 3,381 0.26 3,381 0.24 NW 1,372 1.39 1,372 1.26 NNW 2,490 0.86 1,932 1.23

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 (Meters 2010 2011 (units-s/m 3')

Farm HSb E 7,468 0.008 0.007 ..5.93 E-8 Farm HW NW 2,097 0.052 0.058 6.09 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 - 2011 mR / Quarter (a)

Average External Gamma Radiation Levels (b) 1st qtr 2nd qtr 3rd qtr 4thqtr mR/yr Average, 0 - 2 miles 18.1 16.9 17.0 15.5 68 (onsite)

Average,

> 2 miles 16.1 15.1 15.2 14.5 61 (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 / quarter Map Dosimeter Approx 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Annual Location Station Direction, Distance, Jan-Mar Apr-Jun Jul-Sep Oct-Dec Exposure Number Number degrees miles 2011 2011 2011 2011 mR/year 49 N-1 3 .6 18.4 14.9 19.2 18.5 71.0 50 N-2 4 2.1 16.6 15.7 15.7 16.3 64.3 51 N-3 358 5.2 16.6 13.1 15.2 14.2 59.1 52 N-4 355 10.0 13.6 15.3 14.7 13.1 56.7 5 NNE-1 13 1.8 20.2 1.9.2 22.7 19.0 81.1 53 NNE-2 31 5.3 16.0 14.4 16.7 18.5 65.6 12 NNE-4 32 17.8 13.9 18.4 15.0 16.0 63.3

!

55 NE-1 38 2.4 17.2 17.5 16.7 15.2 66.6 4 NE-1A 50 1.5 16.6 17.0 17.2 14.7 65.5 56 NE-2 51 4.1 10.6 13.6 15.2 12.0 51.4 57 ENE-1 73 .2 18.4 14.9 15.2 16.3 64.8 58 ENE-2 66 5.1 13.6 14.0 16.2 15.8 59.6 59 E-1 96 1.2 16.6 14.4 12.7 13.1 56.8 60 E-2 87 5.2 19.0 17.9 14.7 14.2 65.8 62 ESE-1 110 1.2 16.0 14.9 16.7 13.1 60.7 63 ESE-2 112 4.9 16.6 14.0 17.2 15.2 63.0 13 ESE-3 117 11.3 15.4 14.9 12.7 17.4 60.4 66 SE-1 131 1.4 13.0 14.4 11.7 14.2 53.3 67 SE-2 129 1.9 16.6 13.1 18.2 14.2 62.1 68 SE-4 136 5.2 21.4 17.9 19.7 18.5 77.5 69 SSE-1 154 1.6 14.2 (1) 15.7 10.4 53.7 70 SSE-2 158 4.6 19.0 17.0 22.7 17.4 76.1 (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 Dosimeter Approx 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Annual Location Station Direction, Distance, Jan-Mar Apr-Jun Jul-Sep Oct-Dec Exposure Number Number degree miles 2011 2011 2011 2011 mR/year 71 S-1 183 1.5 22.6 20.5 17.2 17.4 77.7 72 S-2 185 4.7 13.6 10.9 12.2 11.5 48.2 73 SSW-1 203 .6 19.0 16.6 17.7 16.8 70.1 90 SSW-lB 192 1.5 12.4 13.1 11.7 12.5 49.7 3 SSW-1C 198 2.0 15.4 14.9 14.2 14.2 58.7 74 SSW-2 204 4.0 19.6 19.6 21.2 16.8 77.2 9 SSW-3 203 8.7 16.6 16.6 17.7 14.7 65.6 75 SW-1 228 .7 20.8 17.5 17.2 16.3 71.8 7 SW-2 227 3.8 17.2 16.6 13.7 14.2 61.7 Y, 11 SW-3 228 16.7 20.2 17.9 20.7 18.5 77.3 76 WSW-1 241 .9 20.8 18.3 20.2 17.9 77.2 77 WSW-2 238 2.5 13.0 12.3 10.8 11.5 47.6 10 WSW-2A 250 2.6 13.6 13.6 13.2 13.1 53.5 78 WSW-3 248 5.7 18.4 17.5 14.7 15.8 66.4 79 WSW-4 244 7.8 16.6 14.4 12.7 10.9 54.6 81 W-1 260 .6 25.0 22.7 21.7 18.5 87.9 82 W-2 275 4.3 13.6 12.3 11.7 12.5 50.1 8 W-3 280 5.6 17.2 14.4 13.7 12.5 57.8 83 WNW-1 292 .4 20.8 15.7 18.7 15.8 71.0 84 WNW-2 295 5.3 16.6 (1) 13.2 12.0 55.7 85 NW-1 315 .4 22.0 23.6 19.7 12.0 77.3 86 NW-2 318 5.2 12.4 12.3 14.2 17.9 56.8 14 NW-3 320 20.0 16.0 11.8 11.7 15.2 54.7 87 NNW-1 344 .6 17.8 19.6 17.7 16.8 71.9

- 88 NNW-2 342 1.7 14.8 15.7 14.7 12.0 57.2 89 NNW-3 334 5.3 16.6 14.0 11.7 10.9 53.2 (1) Sum of available quarterly data normalized to I year for the annual exposure value.

Tennessee Valley Authority RADIOACTIVITY IN AIR FILTER pCi/mA3 = 0.037 Bqm^A3 Name of Facility: SEQUOYAH NUCLEAR PLANT Docket Number: 50-327,328 Location of Facility: HAMILTON, TENNESSEE Reporting Period: 2011 Number of Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Total Number of Detection Mean (F) Mean (F) Mean (F) Reported of Analysis (LLD) Range Location Description with Range Range Measurements Performed See Note 1 See Note 2 Distance and Direction See Note 2 See Note 2 See Note 3 GROSS BETA - 633 2.OOE-03 2.17E-02 (421 / 421) LM-2 NORTH 2.29E-02 (52 / 52) 2.20E-02 (212 / 212) 1.22E 3.75E-02 0.8 MILES NORTH 1.32E 3.60E-02 1.10E 3.60E-02 GAMMA SCAN (GELI) - 168 AC-228 I .OOE-02 1.29E-02 (2/112) LM-5 WARE POINT 1.58E-02 (1/14) 56 VALUES < LLD 1.00E 1.58E-02 1.8 MILES NNE 1.58E 1.58E-02 BE-7 2.OOE-02 1.06E-01 (112/112) LM-2 NORTH 1.17E-01 (14 /14) 1.08E-01 (55 / 56) 4.58E 1.57E-01 0.8 MILES NORTH 7.71E 1.57E-01 5.73E 1.51E-01 BI-214 5.OOE-03 2.66E-02 (99 / 112) LM-4 SKULL ISLAND 3.01E-02 (13/14) 3.80E-02 (49 / 56) 5.OOE 1.57E-01 1.5 MILES NE 6.20E 1.35E-01 5.40E 4.43E-01 p'

0%

0%

CS-134 5.OOE-03 112 VALUES < LLD PM-2 COUNTY PARK TN 14 VALUES < LLD 56 VALUES < LLD 0z:

3.8 MILES SW CS-137 5.OOE-03 112 VALUES < LLD PM-2 COUNTY PARK TN 14 VALUES < LLD 56 VALUES < LLD 3.8 MILES SW K-40 4.OOE-02 6.10E-02 (4/112) LM-5 WARE POINT 1.06E-01 (1 / 14) 4.78E-02 (1/56) 4.37E 1.06E-01 1.8 MILES NNE 1.06E 1.06E-01 4.78E 4.78E-02 PB-212 5.OOE-03 6.80E-03 (21112) LM-5 WARE POINT 8.00E-03 (1/14) 56 VALUES < LLD 5.60E 8.00E-03 1.8 MILES NNE 8.OOE 8.OOE-03 PB-214 5.00E-03 2.87E-02 (95 1112) PM-8 HARRISON TN 3.43E-02 (11 1 14) 4.41E-02 (46/56) 5.OOE 2.02E-01 8.7 MILES SSW 5.40E 2.02E-01 5.10E 5.31E-01 TL-208 2.OOE-03 3.50E-03 (1/112) PM-2 COUNTY PARK TN 3.50E-03 (1 /14) 56 VALUES < LLD 3.50E 3.50E-03 3.8 MILES SW 3.50E 3.50E-03 Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1

2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).

3. Blanks in this column indicate no nonrountine measurements

Tennessee Valley Authority RADIOACTIVITY IN CHARCOAL FILTER pCi/mA3 = 0.037 Bq/mA3 Name of Facility: SEQUOYAH NUCLEAR PLANT Docket Number: 50-327,328 Location of Facility: HAMILTON, TENNESSEE Reporting Period: 2011 Number of Type and Lower Limit Incdilcator Locations Location with Highest Annual Mean Control Locations Nonroutine Total Number of Detection Mean (F) Mean (F) Mean (F) Reported of Analysis (LLD) Range Location Description with Range Range Measurements Performed See Note 1 See Note 2 Distance and Direction See Note 2 See Note 2 See Note 3 GAMMA SCAN (GELI) -633 AC-228 7.00E-02 42 1 VALUES < LLD PM-8 HARRISON TN 53 VALUES < LLD 8.39E-02 (11 212) 8.7 MILES SSW 8.39E 8.39E-02 BI-212 2.OOE-01 42 1 VALUES < LLD LM-2 NORTH 52 VALUES < LLD 212 VALUES < LLD 0.8 MILES NORTH BI-214 5.00E-02 8.83E- 02 (89/421) PM-8 HARRISON TN 1.13E-01 (10/53) 1.06E-01 (48/212) 5.0 1E 2.75E-01 8.7 MILES SSW 5.22E 2.75E-01 5.12E-02 - 2.86E-01 1-131 3.OOE-02 6.50E-02 (16/421) LM-5 WARE POINT 7.25E-02 (2 / 53) 6.06E-02 (8 /212) 5.518E 8.51E-02 1.8 MILES NNE 5.99E 8.51E-02 4.87E-02 - 7.00E-02 K-40 3.OOE-01 3.94E- 01 (79/421) LM-5 WARE POINT 4.29E-01 (6 /53) 3.69E-01 (28 / 212)

-J 3.0'5E 6.63E-01 1.8 MILES NNE 3.50E 5.34E-01 3.01E-01 - 6.03E-01 H:

C" PB-212 3.OOE-02 42 1 VALUES < LLD PM-2 COUNTY PARK TN 51 VALUES < LLD 212 VALUES < LLD 0'

3.8 MILES SW 1.31E-01 (42/212)

PB-214 7.00E-02 1.15E- 01 (85/421) PM-8 HARRISON TN 1.39E-01 (12 /53) 7.0:2E 3.22E-01 8.7 MILES SSW 7.43E 2.96E-01 7.OOE 2.96E-01 TL-208 2.OOE-02 4.90E-02 (1 /421) LM-5 WARE POINT 4.90E-02 (1 /53) 212 VALUES < LLD 4.9'OE 4.90E-02 1.8 MILES NNE 4.90E 4.90E-02 Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1 2: Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).

3. Blanks in this column indicate no nonrountine measurements

Tennessee Valley Authority RADIOACTIVITY IN MILK pCi/L = 0.037 Bq/L Name of Facility:. SEQUOYAH NUCLEAR PLANT Docket Number: 50-327,328 Location of Facility: HAMILTON, TENNESSEE Reporting Period: 2011 Number of Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Total Number of Detection Mean (F) Mean (F) Mean (F) Reported of Analysis (LLD) Range Location Description with Range Range Measurements Performed See Note 1 See Note 2 Distance and Direction See Note 2 See Note 2 See Note 3 IODINE-131 - 95 4.OOE-01 4.38E+00 (4 /43) H WALKER FARM 4.68E+00 (2 / 17) 5.60E+00 (3 /52) 7.90E 8.16E+00 1.2 MILES NW 1.20E+00 - 8.16E+00 6.41E 1.09E+01 GAMMA SCAN (GELI) - 95 AC-228 2.00E+01 2.75E+01 (2/43) H. SMITH FARM 2.75E+01 (2/26) 2.37E+01 (1/ 52) 2.69E+01 - 2.81E+01 4.6 MILES E 2.69E+01 - 2.81E+01 2.37E+01 - 2.37E+01 BI-214 2.00E+01 3.36E+01 (6/43). H WALKER FARM 5.17E+01 (2/17) 4.97E+01 (13/52) 2.17E+01 - 8.06E+01 1.2 MILlfS NW 2.27E+01 - 8.06E+01 2.03E+01 - 2.93E+02 K-40 1.00E+02 1.24E+03 (43/43) H. SMITH FARM 1.36E+03 (26/26) 1.23E+03 (52 / 52) 5.25E+02 - 1.49E+03 4.6 MILES E 5.43E+02 - 1.49E+03 1.07E+03 - 1.48E+03 PB-212 1.50E+01 HWALKER FARM C" 40 43 VALUES < LLD 17 VALUES < LLD 52 VALUES < LLD 1.2 MILES NW 2.OOE+01 2.42E+01 (3 /43) 2.42E+01 (2 /17) 4.24E+01 (11/52) xi PB-214 H WALKER FARM 2.31E+01 - 2.54E+01 1.2 MILES NW 2.31E+01 - 2.54E+01 2.08E+01 - 1.79E+02 TL-208 1.OOE+01 43 VALUES < LLD H WALKER FARM 17. VALUES < LLD 52 VALUES < LLD 1.2 MILES NW SR 89 -14 3.50E+00 6 VALUES < LLD 8 VALUES < LLD SR 90 -14 2.OOE+00 6 VALUES < LLD 8 VALUES < LLD Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1

2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).

3. Blanks in this column indicate no nonrountine measurements

Tennessee Valley Authority RADIOACTIVITY IN SOIL pCi/g = 0.037 Bq/g (DRY WEIGHT)

Name of Facility: SEQUOYAH NUCLEAR PLANT Docket Number: 50-327,328 Location of Facility: HAMILTON, TENNESSEE Reporting Period: 2011 Number of Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Total Number of Detection Mean (F) Mean (F) Mean (F) Reported of Analysis (LLD) Range Location Description with Range Range Measurements Performed See Note 1 See Note 2 Distance and Direction See Note 2 See Note 2 See Note 3 GAMMA SCAN (GELI) -12 AC-228 2.50E-01 8.09E-01 (8/8) PM-3 DAISY TN 1.15E+00 (1 /1) 8.83E-01 (414) 4.74E-01 - 1.15E+00 5.6 MILES W 1.15E+00 - 1.15E+00 7.40E 1.11E+00 BE-7 2.50E-01 3.63E-01 (21 8) PM-3 DAISY TN 4.14E-01 (1 /1) 5.86E-01 (1 /4) 3.11E 4.14E-01 5.6 MILES W 4.14E 4.14E-01 5.86E-01 - 5.86E-01 BI-212 4.50E-01 8.69E-01 (8 / 8) PM-3 DAISY TN 1.25E+00 (1/ 1) 9.72E-01 (4 /4) 5.84E-01 " 1.25E+00 5.6 MILES W 1.25E+00 - 1.25E+00 7.09E 1.22E+00 BI-214 1.50E-01 6.83E-01 (8/8) PM-3 DAISY TN 1.06E+00 (1 / 1) 7.06E-01 (4 /4) 3.85E 1.06E+00 5.6 MILES W 1.06E+00 - 1.06E+00 5.04E-01 " 9.30E-01 CS-137 3.OOE-02 5.55E-01 (7 8) LM-2 NORTH 1.27E+00 (1 /1) 7.82E-01 (4 /4) 1.52E 1.27E+00 0.8 MILES NORTH 1.27E+00 - 1.27E+00 1.15E-01 - 1.67E+00

,%

K-40 7.50E-01 6.55E+00 (8 8) LM-2 NORTH 9.97E+00 (1 / 1) 6.47E+00 (4 / 4) 3.27E+00 - 9.97E+00 0.8 MILES NORTH 9.97E+00 - 9.97E+00 3.66E+00 - 9.55E+00 0~~

PB-212 1.00E-01 7.67E-01 (8 /8) PM-3 DAISY TN 1.13E+00 (1 / 1) 8.30E-01 (4 / 4) 5.30E 1.13E+00 5.6 MILES W 1.13E+00 - 1.13E+00 6.83E 1.06E+00 PB-214 1.50E-01 7.21E-01 (8/8) PM-3 DAISY TN 1.13E+00 (1 / 1) 7.60E-01 (4 /4) 3.91E 1.13E+00 5.6 MILES W 1.13E+00 - 1.13E+00 5.78E 9.74E-01 TL-208 6.OOE-02 2.61E-01 (8 /8) PM-3 DAISY TN 3.86E-01 (11/ 1) 2.65E-01 (4 /4) 1.69E 3.86E-01 5.6 MILES W 3.86E 3.86E-01 2.26E 3.40E-01 SR 89 - 12 1.60E+00 8 VALUES < LLD 4 VALUES < LLD SR 90 - 12 4.OOE-01 8 VALUES < LLD 4 VALUES < LLD Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1

2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).

3. Blanks in this column indicate no nonrountine measurements

Tennessee Valley Authority RADIOACTIVITY IN APPLES pCi/Kg = 0.037 Bq/Kg (WET WEIGHT)

Name of Facility: SEQUOYAH NUCLEAR PLANT Docket Number: 50-327.328 Location of Facility: HAMILTON, TENNESSEE Reporting Period: 2011 Number of Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Total Number of Detection Mean (F) Mean (F) Mean (F) Reported of Analysis (LLD) Range Location Description with Range Range Measurements See Note 1 See Note 2 Distance and Direction See Note 2 See Note 2 See Note 3 Performed GAMMA SCAN (GELI) -1 BI-214 4.OOE+01 7.84E+01 (1/1) 1 MILES NW 7.84E+01 (1 / 1) VALUES < LLD 7.84E+01 - 7.84E+01 7.84E+01 - 7.84E+01 K-40 2.50E+02 9.55E+02 (1 / 1) 1 MILES NW 9.55E+02 (I/1) VALUES < LLD 9.55E+02 - 9.55E+02 9.55E+02 - 9.55E+02 PB-214 8.OOE+01 1 VALUES < LLD 1 MILES NW 1 VALUES < LLD VALUES < LLD 0

-3 Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1

2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).

3. Blanks in this column indicate no nonrountine measurements

Tennessee Valley Authority RADIOACTIVITY IN CABBAGE pCi/Kg = 0.037 Bq/Kg (WET WEIGHT)

Name of Facility: SEQUOYAH NUCLEAR PLANT Docket Number: 50-327,328 Location of Facility: HAMILTON, TENNESSEE Reporting Period: 2011 Number of Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Total Number of Detection Mean (F) Mean (F) Mean (F) Reported of Analysis (LLD) Range Location Description with Range Range Measurements Performed See Note 1 See Note 2 Distance and Direction See Note 2 See Note 2 See Note 3 GAMMA SCAN (GELI) - 2 BI-214 4.OOE+01 4.51E+011 (11l1) 1 MILES NW 4.51E+01 (1/1) 4.03E+01 (1 /1) 4.51E+01 -4.51E+011 4.51E+01- 4.51E+01 4.03E+01 - 4.03E+01 K-40 2.50E+02 1.72E+03 (1/ 1) 1 MILES NW 1.72E+03 (1/ 1) 1.85E+03 (1 11) 1.72E+03 - 1.72E+03 1.72E+03- 1.72E+03 1.85E+03 - 1.85E+03 PB-212 4.OOE+01 1 VALUES < LLD 1 MILES NW 1 VALUES < LLD 1 VALUES < LLD PB-214 8.00E+01 I VALUES < LLD 1 MILES NW 1 VALUES < LLD 1 VALUES < LLD 0H C"

-J 00 Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1

2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).

3. Blanks in this column indicate no nonrountine measurements

Tennessee Valley Authority RADIOACTIVITY IN CORN pCi/Kg = 0.037 Bq/Kg (WET WEIGHT)

Name of Facility: SEQUOYAH NUCLEAR PLANT Docket Number: 50-327,328 Location of Facility: HAMILTON, TENNESSEE Reporting Period: 2011 Number of Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Total Number of Detection Mean (F) Mean (F) Mean (F) Reported of Analysis (LLD) Range Location Description with Range Range Measurements Performed See Note 1 See Note 2 Distance and Direction See Note 2 See Note 2 See Note 3 GAMMA SCAN (GELI) - 2 BI-214 4.OOE+01 5.90E+01 (111) LM-3 HARRISON BAY RD 5.90E+01 (1/1) 1 VALUES < LLD 5.90E+01 - 5.90E+01 2.0 MILES SSW 5.90E÷01- 5.90E+01 K-40 2.50E+02 2.02E+03 (1 1) LM-3 HARRISON BAY RD 2.02E+03 (1 1) 2.14E+03 (1 1) 2.02E+03 - 2.02E+03 2.0 MILES SSW 2.02E+03- 2.02E+03 2.14E+03 - 2.14E+03 PB-214 8.00E+01 1 VALUES < LLD LM-3 HARRISON BAY RD 1 VALUES < LLD 1 VALUES < LLD 2.0 MILES-SSW CH 0=

-4 t.J '.0 Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1

2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).

3. Blanks in this column indicate no nonrountine measurements

Tennessee Valley Authority RADIOACTIVITY IN GREEN BEANS pCi/Kg = 0.037 Bq/Kg (WET WEIGHT)

Name of Facility: SEQUOYAH NUCLEAR PLANT Docket Number: 50-327,328 Location of Facility- HAMILTON, TENNESSEE Reporting Period: 2011 Number of Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Total Number of Detection Mean (F) Mean (F) Mean (F) Reported of Analysis (LLD) Range Location Description with Range Range Measurements Performed See Note 1 See Note 2 Distance and Direction See Note 2 See Note 2 See Note 3 GAMMA SCAN (GELI) - 2 K-40 2.50E+02 1.91E+03 (1 1) LM-3 HARRISON BAY RD 1.91E+03 (1 1) 3.27E+03 (1 / 1) 1.91E+03- 1.91E+03 2.0 MILES SSW 1.91E+03 - 1.91E+03 3.27E+03 - 3.27E+03 PB-212 4.00E+01 1 VALUES < LLD LM-3 HARRISON BAY RD 1 VALUES < LLD 1 VALUES < LLD 2.0 MILES SSW 0

Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1

2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location Is indicated in parentheses (F).

3. Blanks in this column indicate no nonrountine measurements

Tennessee Valley Authority RADIOACTIVITY IN POTATOES pCi/Kg = 0.037 Bq/Kg (WET WEIGHT)

Name of Facility: SEQUOYAH NUCLEAR PLANT Docket Number: 50-327,328 Location of Facility: HAMILTON, TENNESSEE Reporting Period: 2011 Number of Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Total Number of Detection Mean (F) Mean (F) Mean (F) Reported of Analysis (LLD) Range Location Description with Range Range Measurements Performed See Note I See Note 2 Distance and Direction See Note 2 See Note 2 See Note 3 GAMMA SCAN (GELI) -1 BI-214 4.OOE+01 1 VALUES < LLD 1 MILES NW 1 VALUES < LLD VALUES < LLD K-40 2.50E+02 3.89E+03 (11I1) 1 MILES NW 3.89E+03 (1I 1) VALUES < LLD 3.89E+03 - 3.89E+03 3.89E+03 - 3.89E+03 PB-214 8.0012+011 1 VALUES < LLD 1 MILES NW 1 VALUES < LLD VALUES < LLD

-j Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1

2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).

3. Blanks in this column indicate no nonrountine measurements

Tennessee Valley Authority RADIOACTIVITY IN TOMATOES pCi/Kg = 0.037 Bq/Kg (WET WEIGHT)

Name of Facility: SEQUOYAH NUCLEAR PLANT Docket Number. 50-327,328 Location of Facility: HAMILTON, TENNESSEE Reporting Period: 2011 Number of Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Total Number of Detection Mean (F) Mean (F) Mean (F) Reported of Analysis (LLD) Range Location Description with Range Range Measurements Performed See Note 1 See Note 2 Distance and Direction See Note 2 See Note 2 See Note 3 GAMMA SCAN (GELI) - 2 BI-214 4.00E+01 1 VALUES < LLD LM-3 HARRISON BAY RD 1 VALUES < LLD 1 VALUES < LLD 2.0 MILES SSW K-40 2.50E+02 1.86E+03 (1/l1) LM-3 HARRISON BAY RD 1.86E+03 (1 11) 2.14E+03 (1/ 1) 1.86E+03 - 1.86E+03 2.0 MILES SSW 1.86E+03 - 1.86E+03 2.14E+03 - 2.14E+03 PB-214 8.OOE+01 1 VALUES < LLD LM-3 HARRISON BAY RD 1 VALUES < LLD 1 VALUES < LLD 2.0 MILES SSW 0~

Cs 1'J Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1

2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).

3. Blanks in this column indicate no nonrountine measurements

Tennessee Valley Authority 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: 2011 Number of Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Total Number of Detection Mean (F) Mean (F) Mean (F) Reported of Analysis (LLD) Range Location Description with Range Range Measurements Performed See Note 1 See Note 2 Distance and Direction See Note 2 See Note 2 See Note 3 GROSS BETA - 25 1.90E+00 2.23E+00 (12/ 12) TRM 483.4 2.23E+00 (12 112) 3.07E+00 (10 /13) 1.92E+00 - 2.94E+00 1.92E+00 - 2.94E+00 1.96E+00 - 4.97E+00 GAMMA SCAN (GELI) - 25 AC-228 2.0012+01 12 VALUES < LLD TRM 483.4 12 VALUES < LLD 13 VALUES < LLD BI-214 2.00E+01 2.39E+01 (1 / 12) TRM 483.4 2.39E+01 (1 / 12) . 4.02E+01 (1 13) 2.39E+01 - 2.39E+01 2.39E+01- 2.39E+01 4.02E+01 - 4.02E+01 K-40 1.OOE+02 12 VALUES < LLD TRM 483.4 12 VALUES < LLD 13 VALUES < LLD H"

432 PB-212 1.50E+01 12 VALUES < LLD TRM 483.4 12 VALUES < LLD 13 VALUES < LLD

?I PB-214 2.OOE+01 12 VALUES < LLD TRM 483.4 12 VALUES < LLD 3.54E+01 (1 /13) 3.54E+01 - 3.54E+01 TL-208 1 .012+01 12 VALUES < LLD TRM 483.4 12 VALUES < LLD 13 VALUES < LLD TRITIUM - 21 2.70E+02 4 VALUES < LLD 17 VALUES < LLD Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1

2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).

3. Blanks in this column indicate no nonrountine measurements

Tennessee Valley Authority 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: 2011 Number of Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Total Number of Detection Mean (F) Mean (F) Mean (F) Reported of Analysis (LLD) Range Location Description with Range Range Measurements Performed See Note 1 See Note 2 Distance and Direction See Note 2 See Note 2 See Note 3 GROSS BETA - 52 1.90E+00 2.44E+00 (17/39) E.I. DUPONT 2.62E+00 (1 13) 3.07E+00 (10 /13) 1.92E+00 - 3.44E+00 TRM 470.5 2.62E+00- 2.62E+00 1.96E+00 - 4.97E+00 GAMMA SCAN (GELI) - 52 AC-228 2.0012+01 39 VALUES < LLD E.I. DUPONT 13 VALUES < LLD 13 VALUES < LLD TRM 470.5 BI-214 2.OOE+01 2.66E+01 (8 39) CHATTANOOGA 2.82E+01 (2 /13) 4.02E+01 (1/ 13) 2.01E+01 - 3.89E+01 TRM 465.3 2.74E+01 - 2.89E+01 4.02E+01 - 4.02E+01 K-40 1.OOE+02 39 VALUES < LLD CHATTANOOGA 13 VALUES < LLD 13 VALUES < LLD TRM 465.3 o-

-J PB-212 1.50E+01 39 VALUES < LLD E.I. DUPONT 13 VALUES < LLD 13 VALUES < LLD ,'

-J TRM 470.5 PB-214 2.00E+01 2.69E+01 (5/39) E.I. DUPONT 2.83E+01 (3 / 13) 3.54E+01 (1 / 13) 2.18E+01 - 3.73E+01 TRM 470.5 2.18E+01 - 3.73E+01 3.54E+01 - 3.54E+01 TL-208 1.OOE+01 39 VALUES < LLD CHATTANOOGA 13 VALUES < LLD 13 VALUES < LLD TRM 465.3 TRITIUM - 42 2.70E+02 25 VALUES < LLD 17 VALUES < LLD Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1

2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).

3. Blanks in this column indicate no nonrountine measurements

Tennessee Valley Authority RADIOACTIVITY IN WELL WATER(Total) pCi/I = 0.037 Bq/L Name of Facility: SEQUOYAH NUCLEAR PLANT Docket Number: 50-327,328 Location of Facility: HAMILTON. TENNESSEE Reporting Period: 2011 Number of Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Total Number of Detection Mean (F) Mean (F) Mean (F) Reported of Analysis (LLD) Range Location Description with Range Range Measurements Performed See Note 1 See Note 2 Distance and Direction See Note 2 Sea Note 2 See Note 3 GROSS BETA - 9 1.90E+00 2.41E+00 (4 15) SQN WELL #6 2.41E+00 (415) 1.05E+01 (4/4) 2.05E+00- 2.73E+00 ONSITE NNE 2.05E+00 - 2.73E+00 3.27E+00 - 1.46E+01 GAMMA SCAN (GELI) - 18 AC-228 2.OOE+01 14 VALUES < LLD SQN WELL #6 14 VALUES < LLD 4 VALUES < LLD ONSITE NNE BI-214 2.00E+011 2.74E+01 (7 /14) SQN WELL #6 2.74E+01 (7 / 14) 2.64E+02 (4 / 4) 2.12E+01 - 4.32E+01 ONSITE NNE 2.12E+01 - 4.32E+01 1.89E+02 - 3.40E+02 K-40 1 .00E+02 14 VALUES < LLD SON WELL #6 14 VALUES < LLD 4 VALUES < LLD ONSITE NNE 00 PB-212 1.50E+01 14 VALUES < LLD SON WELL #6 14 VALUES < LLD 4 VALUES < LLD ONSITE NNE PB-214 2.00E+011 2.57E+01 (4 /14) SON WELL #6 2.57E+01 (4 / 14) 2.72E+02 (4 /4) 2.22E+01 3.30E+01 ONSITE NNE 2.22E+01 - 3.30E+01 1.91E+02 - 3.60E+02 TL-208 11.00E+011 14 VALUES < LLD SON WELL #6 14 VALUES < LLD 2.39E+01 (1 /4)

ONSITE NNE 2.39E+01 - 2.39E+01 TRITIUM - 18 2.70E+02 14 VALUES < LLD 4 VALUES < LLD Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1

2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).

3. Blanks in this column indicate no nonrountine measurements

Tennessee Valley Authority RADIOACTIVITY IN COMMERCIAL FISH pCi/g = 0.037 Bq/g (DRY WEIGHT)

Name of Facility: SEQUOYAH NUCLEAR PLANT Docket Number: 50-327,328 Location of Facility: HAMILTON, TENNESSEE Reporting Period: 2011 Number of Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Total Number of Detection Mean (F) Mean (F) Mean (F) Reported of Analysis (LLD) Range Location Description with Range Range Measurements Performed See Note I See Note 2 Distance and Direction See Note 2 See Note 2 See Note 3 GAMMA SCAN (GELI) - 4 BI-214 1.00E-01 2 VALUES < LLD CHICKAMAUGA RES 2 VALUES < LLD 6.67E-01 (212)

TRM 471-530 1.70E-01 - 1.16E+00 K-40 4.OOE-01 1.29E+01 (2 /2) CHICKAMAUGA RES 1.29E+01 (2 2) 1.41E+01 (2/2) 1.20E+01 - 1.38E+01 TRM 471-530 1.20E+01 - 1.38E+01 1.27E+01 - 1.56E+01 PB-212 4.OOE-02 2 VALUES < LLD CHICKAMAUGA RES 2 VALUES < LLD 2 VALUES < LLD TRM 471-530 2 VALUES < LLD CHICKAMAUGA RES 5.84E-01 (11/2)

PB-214 5.0012-01 2 VALUES < LLD TRM 471-530 5.84E-01 - 5.84E-01 a-]

TL-208 3.OOE-02 2 VALUES < LLD CHICKAMAUGA RES 2 VALUES < LLD 2 VALUES c LLD TRM 471-530 C"

-!4

'10

,=~

Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1

2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).

3. Blanks in this column indicate no nonrountine measurements

Tennessee Valley Authority RADIOACTIVITY IN GAME FISH pCi/g = 0.037 Bq/g (DRY WEIGHT)

Name of Facility: SEEQUOYAH NUCLEAR PLANT Docket Number: 50-327,328 Location of Facility: HA,MILTON, TENNESSEE Reporting Period: 2011 Number of Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Total Number of Detection Mean (F) Mean (F) Mean (F) Reported of Analysis (LLD) Range Location Description with Range Range Measurements Performed See Note 1 See Note 2 Distance and Direction See Note 2 See Note 2 See Note 3 GAMMA SCAN (GELI) - 4 BI-214 1.OOE-01 1.18E-01 (1 /2) CHICKAMAUGA RES 1.18E-01 (1/2) 1.45E-01 (112) 1.18E 1.18E-01 TRM 471-530 1.18E 1.18E-01 1.45E 1.45E-01 CS-137 3.00E-02 2 VALUES < LLD CHICKAMAUGA RES 2 VALUES < LLD 3.11E-02 (1 2)

TRM 471-530 3.11E 3.11E-02 K-40 4.00E-01 1.43E+01 (2 /2) CHICKAMAUGA RES 1.43E+01 (2/2) 1.34E+01 (2 /2) 1.41E+01 - 1.46E+01 TRM 471-530 1.41E+01 - 1.46E+01 1.24E+01 - 1.44E+01 PB-212 4.OOE-02 2 VALUES < LLD CHICKAMAUGA RES 2 VALUES < LLD 2 VALUES < LLD TRM 471-530 PB-214 5.OOE-01 2 VALUES < LLD CHICKAMAUGA RES 2 VALUES < LLD CH 2 VALUES < LLD 00 TRM 471-530 ,=

Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1

2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is Indicated In parentheses (F).

3. Blanks in this column indicate no nonrountine measurements

Tennessee Valley Authority RADIOACTIVITY IN SHORELINE SEDIMENT pCi/g = 0.037 Bq/g (DRY WEIGHT)

Name of Facility: SE-QUOYAH NUCLEAR PLANT Docket Number: 50-327,328 Location of Facility: HAMILTON, TENNESSEE Reporting Period: 2011 Number of Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Total Number of Detection Mean (F) Mean (F) Mean (F) Reported of Analysis (LLD) Range Location Description with Range Range Measurements Performed See Note 1 See Note 2 Distance and Direction See Note 2 See Note 2 See Note 3 GAMMA SCAN (GELI) -6 AC-228 2.50E-01 1.04E+00 (4/.4) TRM 479.0 1.39E+00 (2 12), 4.OOE-01 (1/ 2) 3.57E 1.40E+00 TRM 479:0 1.39E+00 - 1.40E+00 4.OOE 4.OOE-01 BE-7 2.50E-01 4.40E-01 (2 /4) TRM 480.0 5.14E-01 (1 /2) 3.25E-01 (212) 3.66E:01 - 5.14E-01 TRM 480.0 5.14E 5.14E-01 3.01E-01 - 3.49E-01 BI-212 4.50E-01 1.39E+00 (3 4) TRM 479.0 1.56E+00 (2 2), 2 VALUES < LLD 1.06E+00- 1.56E+00 TRM 479.0 1.55E+00 - 1.56E+00 BI-214 1.50E-01 7.48E-01 (4 /4) TRM 479.0 9.85E-01 (2 / 2) 3.01E-01 (2/2) 2.67E 1.16E+00 TRM 479.0 8.09E 1.16E+00 2.12E-01 - 3.90E-01 CS-137 3.OOE-02 5.90E-02 (1/ 4) TRM 479.0 5.90E-02 (1 / 2) 2 VALUES < LLD 5.90E 5.90E-02 TRM 479.0 5.90E 5.90E-02 00 K-40 7.50E-01 7.19E+00 (3 14) TRM 479.0 9.68E+00 (2 / 2) 2.32E+00 (2 / 2) 2.20E+00 - 1.13E+01 TRM 479.0 8.09E+00 - 1.13E+01 1.15E+00 - 3.50E+00 PB-212 1.00E-01 9.68E-01 (4/4) TRM 479.0 1.34E+00 (2 / 2) 2.81E-01 (2/2) 00 2.82E 1.36E+00 TRM 479.0 1.32E+00- 1.36E+00 1.72E-01 - 3.91E-01 PB-214 1.50E-01 7.49E-01 (4 / 4) TRM 479.0 1.11E+00 (2/2,) 3.14E-01 (2/2) 3.30E 1.30E+00 TRM 479.0 9.15E 1.30E+00 2.14E-01 - 4.15E-01 TL-208, 6.OOE-02 3.39E-01 (4 14) TRM 479.0 4.45E-01 (2 2) 1.05E-01 (2/2) 1.06E 4.52E-01 TRM 479.0 4.39E 4.52E-01 6.34E-02 - 1.46E-01 Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1

2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).

3. Blanks in this column indicate no nonrountine measurements

Figure H- I Direct Radiation Direct Radiation Levels Sequoyah Nuclear Plant Four Quarter Moving Average 25 Initial SQNP operation inJuly, InLight Dosimeter Deployment in S1980 1 January, 2007

--20Af.A. AA IA 0

C.

x 0 a

!10 II

>* --- On-Site

- Off-Site 1970 1975 1980 1985 1990 1995 2000 2005 2010 2015 Calendar Year Dosimeters are processed quarterly. This chart shows trends in the average measurement for all dosimeters grouped as "on-site" or "off-site". The data from preoperational phase, prior to 1980, show the same trend of "on-site" measurements higher than "off-site" measurements that is observed in current data indicating that the slightly higher "on-site" direct radiation levels are not related to plant operations.

Figure H-2 Radioactivity in Air Filters Annual Average Gross Beta Activity in Air Filters Sequoyah Nuclear Plant 0.25 E 0.20 Initial SONP Operation in

a. --- Indicator

- Control

, 0.15 t 0.10 I - - - ---------

I -I Q I y S0.05 0.00 1965 1970 1975 1980 1985 1990 1995 2000 2005 2010 2015 Note: no gross beta measurements Calendar Year were made in 1974 As can be seen in the trend plot of gross beta activity, the gross beta levels in air particulates have remained relatively constant with the exception of years when the beta activity was elevated due to fallout from nuclear weapons testing. The data also shows that there is no difference in the gross beta activity levels for sampling conducted at the indicator stations as compared to the control stations.

a W ý

Figure H-3 Cs-137 in Soil Annual Average Activity of Cs-137 in Soil Sequoyah Nuclear Plant 3.0 2.5 2.0 Initial SQNP Operation in

-. July, 198(q 1.5 41"0 Pmoperatio 0.5 0.0 0.0 1970 1975 1980 1985 1990 1995 2000 2005 2010 2015 Calendar Year Cesium-137 was produced by past nuclear weapons testing and is present in almost every environmental soil sample exposed to the atmosphere. The "control" and "indicator" locations have generally trended downward with year-to-year variation, since the end of atmospheric nuclear weapons testing in 1980.

Figure H-4 Gross Beta Activity in Surface Water Average Annual Gross Beta Activity in Surface Water Sequoyah Nuclear Plant 6

Preoperational Average 1'4 (3

EuInitial SQNP

• 2 Operation July, 1980 in:

-A- Indicator 1,--0-- Control 0

1970 1975 1980 1985 1990 1995 2000 2005 2010 2015 Calendar Year As shown in the graph, the gross beta activity in samples from the downstream indicator locations has been essentially the same as the activity in samples from the upstream control locations. The average gross beta activity in these samples has been trending down since the early 1980's.

Figure H-5 Gross Beta Activity in Drinking Water Annual Average Gross Beta Activity in Drinking Water Sequoyah Nuclear Plant 6.0 5.0 2.0 2.0 Initial SQNP Operation in 1.0 July, 1980 0.0 1970 1975 1980 1985 1990 1995 2000 2005 2010 2015 Calendar Year The average gross beta activity in drinking water samples from the upstream control locations has typically been slightly higher than activity level measured in samples from the downstream indicator locations. The annual average gross beta activity has been relatively constant since the start of plant operations in 1980 and is slightly lower than preoperational levels.

Figure H-6 Radioactivity in Fish Annual Average Activity Cs-137 in Game Fish Sequoyah Nuclear Plant 0.60 0.50 [ -- Indicator

--0-- Control o' 0.40 Initial SQNP 0.40

._0.30 Preoperational

-- ---------------------- -----------------------------------------------

0.20 0

1E0.10 0.00 1970 1975 1980 1985 1990 1995 2000 2005 2010 2015 Calendar Year The concentrations of Cs- 137 found in fish are consistent with levels present in the Tennessee River due to past atmospheric nuclear weapons testing and operation of other nuclear facilities in the upper reaches of the Tennessee River Watershed. As shown in the graph, the levels of Cs-137 have been decreasing consistent with the overall levels of Cs-137 in the environment.

(f

Figure H-7 Radioactivity in Shoreline Sediment Annual Average Activity Cs-137 in Shoreline Sediment Sequoyah Nuclear Plant 0.35 0.30 -h- Downstreai

[ ~-0--- Upstream B.0.25 0.20 Note: Initial SQNP

.. Operation in July, 1980 i0.15 There was no 0.10 0.05 0.00 1970 1975 1980 1985 1990 1995 2000 2(105 2010 2015 Calendar Year The Cs- 137 present in the shoreline sediments of the Tennessee River system was produced both by past atmospheric testing of nuclear weapons and the operation of other nuclear facilities in the upper reaches of the Tennessee River Watershed. The abnormally high value for the 2009 data from the downstream locations resulted from a problem with one sample collected in April, 2009. The sample was collected during a period of high water levels and was actually surface soil and not the normal shoreline sediment material. This sample contained Cs-137 at a level typical for environmental soil but was much higher than levels normally found in shoreline sediment. This issue was discussed in the 2009 SQN report.