ML091200458

Annual Radiological Environmental Operating Report - 2008

ML091200458
Person / Time
Site:	Sequoyah
Issue date:	04/28/2009
From:	Cleary T Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML091200458 (97)

Text

Timothy P. Cleary Site Vice President Sequoyah Nuclear Plant April 28, 2009 Tennessee Valley Authority Post Office Box 2000 Soddy Daisy, Tennessee 37384-2000 U.S. Nuclear Regulatory Commission ATTN:

Document Control Desk Washington, D.C. 20555 Gentlemen:

In the Matter of Tennessee Valley Authority (TVA)

Docket Nos.

50-327 50-328 SEQUOYAH NUCLEAR PLANT (SQN) - ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2008 Enclosed is the subject report for the period of January 1 to December 31, 2008.

This report is being submitted as required by SQN Technical Specification 6.9.1.6 and SQN's Offsite Dose Calculation Manual Administrative Control Section 5.1.

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

Sincerely, Timothy P. Cleary Enclosure printed on recycled paper

U.S. Nuclear Regulatory Commission Page 2 April 28, 2009 cc (Enclosure):

Mr. Tracy J. Orf, Project Manager U.S. Nuclear Regulatory Commission Mail Stop 08G-9a One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2739

U.S. Nuclear Regulatory Commission Page 2 April 28, 2009 BAW:JWP:SKD cc (Enclosure):

Mr. Tracy J. Orf, Project Manager U.S. Nuclear Regulatory Commission Mail Stop 08G-9a One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2739 cc (w/o Enclosure):

G.Arent, EQB1B-WBN T. J. Bradshaw (NSRB Support), LP 4K-C C. R. Church, POB 2B-SQN D. E. Jernigan, LP 3R-C K. R. Jones, OPS 4A-SQN R. M. Kerwin, OPS 4A-SQN M. J. Lorek, LP 3R-C L. E. Nicholson, LP 3R-C M. A. Purcell, LP 4K-C P. D. Swafford, LP 3R-C L. E. Thibault, LP 3R-C S. A. Vance, ET 10A-K E. J. Vigluicci, ET10A-K WBN Site Licensing Files, ADM 1L-WBN EDMS, WT CA-K l:License/Annual Reports/2008/2008 AREOR

ENCLOSURE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SEQUOYAH NUCLEAR PLANT 2008

Annual Radiological Environmental Operating Report Sequoyah Nuclear Plant 2008

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SEQUOYAH NUCLEAR PLANT 2008 TENNESSEE VALLEY AUTHORITY April 2009

TABLE OF CONTENTS Table of Contents ii Executive Summary 1

Introduction 2

Naturally Occurring and Background Radioactivity 2

Electric Power Production 4

Site/Plant Description 6

Radiological Environmental Monitoring Program 7

Direct Radiation Monitoring 10 Measurement Techniques 10 Results 11 Atmospheric Monitoring 13 Sample Collection and Analysis 13 Results 14 Terrestrial Monitoring 15 Sample Collection and Analysis 15 Results 16 Liquid Pathway Monitoring 18 Sample Collection and Analysis 18 Results 19 Assessment and Evaluation 21 Results 21 Conclusions 22 References 23

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Appendix A Radiological Environmental Monitoring Program and Sampling Locations 27 Appendix B 2008 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

-in-

LIST OF TABLES Table 1 Comparison of Program Lower Limits of Detection with Regulatory Limits for Maximum Annual Average Effluent Concentrations Released to Unrestricted Areas and Reporting Levels 24

-IV-

LIST OF FIGURES Figure 1

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

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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 2008.

The program includes the collection of samples from the environment and the determination of the concentrations of radioactive materials in the samples.

Samples were collected from locations in the general area of the plant and from areas that would not be influenced by plant operations.

Monitoring includes the sampling of air, water, milk, foods, soil, fish, shoreline sediment and the measurement of direct radiation levels.

Results from stations near the plant are compared with data from control stations and with preoperational measurements to determine potential impacts of site operations.

The vast majority of radioactivity measured in environmental samples from the SQN program resulted from naturally occurring radioactive materials.

Trace quantities of cesium-137 (Cs-137) were measured in soil, shoreline sediment, and fish.

Strontium-90 (Sr-90) at very low levels was detected in milk samples. The concentrations were typical of the levels expected to be present in the environment from past nuclear weapons testing or operation of other nuclear facilities in the region.

Tritium at concentrations slightly above the analytical detection limit was detected in a limited number of water samples collected from Chickamauga Reservoir.

These levels would not represent a significant contribution to the radiation exposure to Members of the Public.

INTRODUCTION This report describes and summarizes the results of radioactivity measurements made in the vicinity of SQN and laboratory analyses of samples collected in the area.

The measurements are made to comply with the requirements of the Code of Federal Regulations (CFR), 10 CFR 50, Appendix A, Criterion 64 and 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3 and IV.C, and to determine potential effects on public health and safety.

This report satisfies the annual reporting requirements of SQN Plant Technical Specification (TS) 6.9.1.6 and Offsite Dose Calculation Manual (ODCM) Administrative Control 5.1.

The data presented in this report include results from the prescribed program and other information to help correlate the significance of results measured by this monitoring program to the levels of environmental radiation resulting from naturally occurring radioactive materials.

Naturally Occurring and Background Radioactivity Many materials in our world contain trace amounts of naturally occurring radioactivity.

For example, approximately 0.01 percent of all potassium is radioactive potassium-40 (K-40) which has a half-life of 1.3 billion years.

An individual weighing 150 pounds contains about 140 grams of potassium (Reference 1).

This is equivalent to approximately 100,000 picoCuries (pCi) of K-40 which delivers a dose of 15 to 20 mrem per year to the bone and soft tissue of the body.

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

212 and 214, lead (Pb)-212 and 214, thallium (TI)-208, actinium (Ac)-228, uranium (U)-238 and 235, thorium (Th)-234, radium (Ra)-226, radon (Rn)-222, carbon (C)-14, and hydrogen (H)-3 (generally called tritium).

These naturally occurring radioactive materials are in the soil, our food, our drinking water, and our bodies.

The radiation from these materials makes up a part of the low level natural background radiation.

The remainder of the natural background radiation is produced by cosmic rays.

The relative hazard of different types of radiation sources can be compared by evaluating the amount of radiation the U.S. population receives from each type of radiation source as displayed in the following table.

This table was adapted from References 2 and 3.

U.S. GENERAL POPULATION AVERAGE DOSE EQUIVALENT ESTIMATES Source Millirem/Year Per Person Natural background dose equivalent Cosmic 27 Cosmogenic 1

Terrestrial 28 In the body 39 Radon 200 Total 295 Release of radioactive material in natural gas, mining, ore processing, etc.

5 Medical (effective dose equivalent) 53 Nuclear weapons fallout less than 1

Nuclear energy 0.28 Consumer products 0.03 Total 355 (approximately)

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

population normally exceeds that from nuclear plants by several hundred times.

The 0.28 mrem attributable to nuclear plant operations results in a population radiation dose equivalent which is insignificant compared to that which results from natural background radiation.

Electric Power Production Nuclear power plants are similar in many respects to conventional coal burning (or other fossil fuel) electric generating plants.

The basic process behind electrical power production in both types of plants is that fuel is used to heat water to produce steam which provides the force to turn turbines and generators.

In a nuclear power plant, the fuel is uranium and the heat is produced in the reactor through the fission of the uranium.

Nuclear plants include many complex systems to control the nuclear fission process and to safeguard against the possibility of reactor malfunction.

The nuclear reactions produce radionuclides commonly referred to as fission and activation products.

Very small amounts of these fission and activation products are released into the plant systems.

This radioactive material can be transported throughout plant systems and some of it released to the environment.

The pathways through which radioactivity is released are monitored.

Liquid and gaseous effluent monitors record the radiation levels for each release.

These monitors provide alarm mechanisms to prompt termination of release above limits.

Releases are monitored at the onsite points of release and through the environmental monitoring program which measures the environmental radiation in areas around the plant.

In this way, not only is the release of radioactive materials from the plant tightly controlled, but measurements are made in surrounding areas to verify that the population is not being exposed to significant levels of radiation or radioactive materials.

The SQN ODCM, which is required by the plant Technical Specifications, prescribes limits for the release of radioactive effluents, as well as limits for doses to the general public from the release of these effluents.

The dose to a member of the general public from radioactive materials released to unrestricted areas, as given in Nuclear Regulatory Commission (NRC) guidelines and the ODCM, is limited as follows:

Liquid Effluents Total body

<3 mrem/year Any organ

<10 mrem/year Gaseous Effluents Noble gases:

Gamma radiation

<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 (LLD) of detection for the SQN monitoring program with the regulatory limits for maximum annual average effluent concentrations released to unrestricted areas and levels requiring special reports to the NRC.

It should be noted that the levels of radioactive materials measured in the environment are typically only slightly above the lower limit of detection.

The data presented in this report indicate compliance with the regulations.

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

Figure 1 shows the site in relation to other TVA projects.

The SQN site, containing approximately 525 acres, is approximately 7.5 miles northeast of the nearest city limit of Chattanooga, Tennessee, 14 miles west-northwest of Cleveland, Tennessee, and approximately 31 miles south-southwest of TVAfs Watts Bar Nuclear Plant (WBN) site.

Population is distributed unevenly within 10 miles of the SQN site.

Approximately 60 percent of the population is in the general area between 5 and 10 miles from the plant in the sectors ranging from the south, clockwise, to the northwest sector.

This concentration is a reflection of suburban Chattanooga and the town of Soddy-Daisy.

This area is characterized by considerable vacant land with scattered residential subdivisions.

Residential subdivision growth has continued within a 10-mile radius of the plant.

There is also some small-scale farming and at least one dairy farm located within 5 miles of the plant.

Chickamauga Reservoir is one of a series of highly controlled multiple-use reservoirs located on the Tennessee River whose primary uses are flood control, navigation, and the generation of electric power.

Secondary uses include industrial and public water supply and waste disposal, commercial fishing, and recreation.

Public access areas, boat docks, and residential subdivisions have been developed along the reservoir shoreline.

SQN consists of two pressurized water reactors.

Fuel was loaded in Unit 1 on March 1, 1980, and the unit achieved criticality on July 5, 1980.

Fuel was loaded in Unit 2 in July 1981, and the unit achieved initial criticality on November 5,1981.

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Most of the radiation and radioactivity generated in a nuclear power reactor is contained within the reactor itself or one of the other plant systems.

Plant effluent monitors are designed to detect the small amounts of radioactive material released to the environment.

Environmental monitoring provides a final verification that the systems are performing as planned.

The monitoring program is designed to monitor the pathways between the plant and the general public in the immediate vicinity.

Sample types are chosen so that the potential for detection of radioactivity in the environment will be maximized.

The radiological environmental monitoring program is outlined in Appendix A.

There are two primary pathways by which radioactivity can move through the environment to humans:

air and water (see Figure 2).

The air pathway can be separated into two components:

the direct (airborne) pathway and the indirect (ground or terrestrial) pathway.

The direct airborne pathway consists of direct radiation and inhalation by humans.

In the terrestrial pathway, radioactive materials may be deposited on the ground or on plants and subsequently be ingested by animals and/or humans.

Human exposure through the liquid pathway may result from drinking water, eating fish, or by direct exposure at the shoreline.

The types of samples collected in this program are designed to monitor these pathways.

A number of factors were considered in determining the locations for collecting environmental samples.

The locations for the atmospheric monitoring stations were determined from a critical pathway analysis based on weather patterns, dose projections, population distribution, and land use.

Terrestrial sampling stations were selected after reviewing such factors as the locations of dairy animals and gardens in conjunction with the air pathway analysis.

Liquid pathway stations were selected based on dose projections, water use information, and availability of media such as fish and sediment.

Table A-2 (Appendix A, Table 2:

This identification system is used for all tables and figures in the appendices.) lists the sampling stations and the types of samples collected.

Modifications made to the SQN monitoring program in 2008 are described in Appendix B.

Deviations from the sampling and analysis schedule are presented in Appendix C.

To determine the amount of radioactivity in the environment prior to the operation of SQN, a preoperational radiological environmental monitoring program was initiated in 1971 and operated until the plant began operation in 1980.

Measurements of the same types of radioactive materials that are measured currently were assessed during the preoperational phase to establish normal background levels for various radionuclides in the environment.

The knowledge of pre existing radionuclide patterns in the environment permits a determination, through comparison and trending analyses, of any impact on the environment due to the operation of SQN.

The determination of impact from the plant during the operating phase also utilizes the data from control stations that have been established in the monitoring program.

Results of environmental samples taken at control stations (far from the plant) are compared with those from indicator stations (near the plant) to establish the extent of SQN influence.

Samples are analyzed by TVA's Environmental Radiological Monitoring and Instrumentation (ERM&I) group located at the Western Area Radiological Laboratory (WARL) in Muscle Shoals, Alabama, with the exception of the Sr-89, 90 analysis of soil samples which was performed by a contract laboratory.

Analyses are conducted in accordance with written and approved procedures and are based on accepted methods. A summary of the analysis techniques and methodology is presented in Appendix D.

Data tables summarizing the sample analysis results are presented in Appendix H.

The radiation detection devices and analysis methods used to determine the radionuclide content of samples collected in the environment are very sensitive to small amounts of radioactivity.

The sensitivity of the measurements process is defined in terms of the lower limit of detection. A description of the nominal LLDs for the radioanalytical laboratory is presented in Appendix E.

The ERM&I laboratory employs a comprehensive quality assurance/quality control program to monitor laboratory performance throughout the year.

The program is intended to detect any problems in the measurement process as soon as possible so they can be corrected.

This program includes equipment checks, to ensure that the radiation detection instruments are working properly, and the analysis of quality control samples.

In 2008, 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 varying plastic and copper filtrations to provide qualitative information about conditions during the exposure.

The dosimeters are placed approximately 1 meter above the ground, with two at each monitoring location.

Sixteen monitoring points are located around the plant near the site boundary, one location in each of the 16 compass sectors.

One monitoring point is also located in each of the 16 compass sectors at a distance of approximately four to five miles from the plant.

Dosimeters are also placed at additional monitoring locations out to approximately 32 miles from the site. The dosimeters are exchanged every 3 months.

The dosimeters are sent to Landauer for processing and results reporting.

The values are corrected for transit and shielded background exposure.

An average of the two dosimeter results is calculated for each monitoring point.

The system meets or exceeds the performance specifications outlined in American National Standard Institute (ANSI) Standard N545-1975 and Health Physics Society (HPS) Draft Standard N13.29 for environmental applications of dosimeters.

Results The results for environmental dosimeter measurements are normalized to a standard quarter (91.25 days or 2190 hours0.0253 days <br />0.608 hours <br />0.00362 weeks <br />8.33295e-4 months <br />).

The monitoring locations are grouped according to the distance from the plant.

The first group consists of all monitoring points within 2 miles of the plant.

The second group is made up of all locations greater than 2 miles from the plant.

Past data have shown that the average results from the locations more than 2 miles from the plant are essentially the same.

Therefore, for purposes of this report, monitoring points 2 miles or less from the plant are identified as "onsite" stations and locations greater than 2 miles are considered "offsite."

The quarterly gamma radiation levels determined from the dosimeters deployed around SQN in 2008 are summarized in Table H-l. 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 2008, 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 2008 1976-79 Onsite Stations 39 79 Offsite Stations 34 63 The data in Table H-l indicate that the average quarterly direct radiation levels at the SQN onsite stations are approximately 1.3 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-l compares plots of the data from the onsite stations with those from the offsite stations over the period from 1976 through 2008.

The results from the Landauer InLight dosimeters are lower across all locations when compared to the results previously obtained using the Panasonic UD-814 dosimeters.

This difference is most likely due to the manner in how background badge data was applied for the in house processing of Panasonic dosimeters as compared to the method used by the vendor.

The data in Table H-2 contains the results of the individual monitoring stations.

The results reported in 2008 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 remote air monitors are located out to approximately 20 miles.

The monitoring program and the locations of monitoring stations are identified in the tables and figures of Appendix A.

The remote stations are used as control or baseline stations.

Sample Collection and Analysis Air particulates are collected by continuous sampling of air at a flow rate of approximately 2 cubic feet per minute (cfrn) 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 I-131 by gamma spectroscopy analysis.

Results The results from the analysis of air particulate samples are summarized in Table H-3.

Gross beta activity in 2008 was consistent with levels reported in previous years.

The average gross beta activity for air filter samples was 0.022 pCi/m3. The annual average of the gross beta activity in air particulate filters at these stations for the years 1971-2008 are presented in Figure H-2.

Increased levels due to fallout from atmospheric nuclear weapons testing are evident, especially in 1971, 1977, 1978, and 1981.

Evidence of a small increase resulting from the Chernobyl accident can also be seen in 1986.

These patterns are consistent with data from monitoring programs conducted during the preoperation and construction phases at other TVA nuclear plant sites.

Only naturally occurring radionuclides were identified by the monthly gamma spectral analysis of the air particulate samples.

No fission or activation products were detected.

As shown in Table H-4,1-131 was not detected in any of the charcoal cartridge samples collected in 2008.

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-l 1.

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 2008 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 2008 when vegetation sampling was necessary.

Soil samples are collected annually from the air monitoring locations.

The samples are collected with either a "cookie cutter" or an auger type sampler.

After drying and grinding, the sample is analyzed by gamma spectroscopy and for Sr-89, 90.

Samples representative of food crops raised in the area near the plant are obtained from individual gardens.

Types of foods may vary from year to year as a result of changes in the local vegetable gardens.

In 2008 samples of apples, cabbage, corn, green beans, 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.

Results The results from the analysis of milk samples are presented in Table H-5.

No radioactivity attributable to SQN operations was identified.

The 1-131 results were less than the established nominal LLD of 0.4 pCi/liter.

The results for the quarterly Sr-89 analysis were also less than the nominal LLD value of 3.5 pCi/liter.

Three of the samples of milk did contain low levels of Sr-90.

The Sr-90 concentration measured in these samples averaged 2.8 pCi/liter.

The presence of low levels of Sr-90 in milk samples is consistent with levels in the environment resulting from past nuclear weapons testing.

By far the predominant isotope reported in milk samples was the naturally occurring K-40.

The average K-40 concentration was approximately 1310 pCi/liter for milk samples analyzed in 2008.

The gamma analysis of soil samples detected trace levels of Cs-137 with the maximum concentration being 0.57 pCi/g.

These concentrations 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-ll.

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 for gross beta activity and tritium.

Samples of commercial and game fish species are collected semiannually from each of two reservoirs:

the reservoir on which the plant is located (Chickamauga Reservoir) and the upstream reservoir (Watts Bar Reservoir).

The samples are collected using a combination of netting techniques and electrofishing.

Samples are prepared from filleted fish.

After drying and grinding, the samples are analyzed by gamma spectroscopy.

Samples of shoreline sediment are collected from two downstream recreational use areas and one upstream location.

The samples are dried and ground and analyzed by gamma spectroscopy.

Results There were no fission or activation product radionuclides identified from the gamma spectroscopy analyses performed on surface water samples.

The tritium analysis of surface water samples detected tritium in a total of five samples collected during a period of low river flow rates.

The highest tritium concentration detected in these samples was 622 pCi/L.

This level of tritium represented only a small fraction of the EPA drinking water limit of 20,000 pCi/L.

Gross beta activity above the nominal LLD value was measured in most surface water samples.

The gross beta concentrations in samples from the indicator locations and control location samples averaged 2.7 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 2008 is presented in Figure H-4. A summary table of the results is shown in Table H-12.

There were no fission or activation product radionuclides identified by the gamma analysis of drinking water samples.

Similar to the results reported above for surface water, the tritium was detected at low levels in samples collected during periods of low river flow rates.

The highest tritium concentration was 631 pCi/L which is significantly below the EPA drinking water limit for tritium.

Average gross beta activity was 3.1 pCi/liter for the downstream stations and 2.7 pCi/liter at the control station.

The results are shown in Table H-13 and a trend plot of the gross beta activity in drinking water from 1971 to the present is presented in Figure H-5.

No fission or activation products were detected by the gamma analyses performed on ground-water samples from the two REMP monitoring locations.

The results for tritium analysis of samples from these locations were all less than the nominal LLD.

Gross beta concentrations in samples from the onsite well averaged 2.8 pCi/liter, while the average from the offsite well was 8.2 pCi/liter.

The results from the analysis of groundwater samples are presented in Table H-14.

Cesium-137 was identified in a total of five fish samples.

The maximum Cs-137 concentration for indicator samples was 0.03 pCi/g, while the maximum Cs-137 concentration for control location samples was 0.07 pCi/g. A plot of the annual Cs-137 concentration in samples of game fish is presented in Figure H-6.

The results are summarized in Tables H-15 and H-16.

Cesium-137 was detected in two shoreline sediment samples.

The concentration of Cs-137 in sediment was consistent with previously identified levels.

Results from the analysis of shoreline sediment samples are shown in Table H-17.

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 2008 operations confirm this expectation.

Results As stated earlier in this report, the estimated increase in radiation dose equivalent to the general public resulting from the operation of SQN is negligible when compared to the dose from natural background radiation.

The results from environmental samples are compared with the concentrations from the corresponding control stations as well as appropriate preoperational and background data to determine influences from the plant.

Measurable levels of Cs-137 were detected in fish, soil, and shoreline sediment and Sr-90 was detected in milk.

The Cs-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 Effluent Reporting Lower limit Concentration1 Level2 of Detection3 270 45 5

5 5

10 5

2 5

10 5

40 0.4 5

5 30 25 10 H-3 Cr-51 Mn-54 Co-58 Co-60 Zn-65 Sr-89 Sr-90 Nb-95 Zr-95 Ru-103 Ru-106 1-131 Cs-134 Cs-137 Ce-144 Ba-140 La-140 1,000,000 500,000 30,000 20,000 3,000 5,000 8,000 500 30,000 20,000 30,000 3,000 1,000 900 1,000 3,000 8,000 9,000 20,00C 1,000 1,000 300 300 400 400 2

30 50 200 200 Concentrations in Air, pCi/Cubic Meter Effluent Reporting Lower limit Concentration1 Level2 of Detection3 100,000 30,000 1,000 1,000 50 400 1,000 6

2,000 400 900 20 200 200 200 40 2,000 2,000 0.9 10 20 0.02 0.005 0.005 0.005 0.005 0.0011 0.0004 0.005 0.005 0.005 0.02 0.03 0.005 0.005 0.01 0.015 0.01 Note:

lpCi = 3.7xlO"2Bq.

Note:

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

1 Source:

Table 2 of Appendix B to 10 CFR 20 2

Source:

SQN Offsite Dose Calculation Manual, Table 2.3-2 3

Source:

Table E-l of this report V

LOUISVILLE J

TENNESSEE VALLEY REGION \\

(TVA NUCLEAR PLANT SITES)

V W

V A.

ALABAMA M

-WATTS BAR NUCLEAR PLANT

-SEQUOYAH NUCLEAR PLANT

- BELLEFONTE NUCLEAR PLANT

- BROWNS FERRY NUCLEAR PLANT

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

Diluted By Atmosphere Airborne Releases Plume Exposure Animals (Milk.Meat)

Consumed By Animals Vegetation Uptake From Soil Liquid Releases Diluted By Lake MAN o

Consumed By Man Shoreline Exposure 1 Drinking Fish APPENDDCA RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM AND SAMPLING LOCATIONS Table A-1 SEQUOYAH NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM3 Exposure Pathway and/or Sample 1.

AIRBORNE a.

Particulates to oo b.

Radioiodine c.

Soil Number of Samples and Locationsb 4 samples from locations (in different sectors) at or near the site boundary (LM-2, LM-3, LM-4, and LM-5).

4 samples from communities approximately 6-10 miles from the Plant(PM-2,3,8,and9).

4 samples from control locations greater than 10 miles from the plant (RM-1 RM-2, RM-3and RM-4).

Same locations as air particulates.

Samples from same locations as air particulates Sampling and Collection Frequency Continuous sampler operation with sample collection once per 7 days (more frequently if required by dust loading).

Continuous sampler operation with charcoal canister collected at same time as particulate filters at least once per 7 days.

Once per year.

Type and Frequency of Analysis Analyze for gross beta radioactivity greater than or equal to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following filter change.

Perform gamma isotopic analysis on each sample when gross beta is greater than 10 times yearly mean of control samples.

Composite at least once per 31 days (by location) for gamma scan.

1-131 by gamma scan on each sample.

Each sample is analyzed by gamma isotopic and for Sr-89 and Sr-90.

Table A-l SEQUOYAH NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM3 to Exposure Pathway and/or Sample Number of Samples and Locationsb 2.

DIRECT RADIATION 2 or more dosimeters placed at locations at or near the site boundary 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.

3.

WATERBORNE a.

Surface water b.

Groundwater TRM 503.8d TRM 483.4 1 sample adjacent to the plant (Well No. 6).

1 sample from groundwater source upgradient (Farm HW).

Sampling and Collection Frequency At least once per 92 days.

Collected by automatic sequential-type sampler0 with composite samples collected over a period of less than or equal to 31 days.

At least once per 31 days.

At least once per 92 days.

Type and Frequency of Analysis Gamma dose at least once per 92 days.

Gross beta and gamma scan on each composite sample.

Composite for tritium analysis at least once per 92 days.

Composited for gross beta, gamma scan, and tritium at least once per 92 days.

Gross beta, gamma scan, and tritium at least once per 92 days.

Table A-l SEQUOYAH NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM3 Exposure Pathway and/or Sample c.

Drinking Water 9

Number of Samples and Locationsb 1 sample at the first potable Water supply downstream from the Plant (TRM 473.0).

1 sample at the next 2 downstream potable water systems (greater than 10 miles downstream) (TRM 469.9 and TRM 465.3).

1 sample at the upstream control location (TRM 503.8d).

Sampling and Collection Frequency Collected by automatic sequential-type sampler0 with composite sample collected over a period of less than or equal to 31 days.

Grab sample once per 31 days.

Samples collected by sequential-type sampler0 with composite sample collected over a period of less than or equal to 31 days.

Type and Frequency of Analysis Gross beta and gamma scan on each composite sample.

Composite for tritium at least once per 92 days.

d.

Shoreline sediment TRM 485 TRM 480 TRM 479 At least once per 184 days.

Gamma scan of each sample.

Table A-l SEQUOYAH NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM" Exposure Pathway and/or Sample 4.

INGESTION a.

Milk b.

Fish Number of Samples and Locationsb 1 sample from milk producing animals in each of 1-3 areas indicated by the cow census where doses are calculated to be highest.

If samples are not available from a milk animal location, doses to that area will be estimated by projecting the doses from concentrations detected in milk from other sectors or by sampling vegetation where milk is not available.

At least one sample from a control location 1 sample each from Chickamauga and Watts Bar Reservoirs.

Sampling and Collection Frequency At least once per 15 days.

Type and Frequency of Analysis Gamma isotopic and 1-131 analysis of each sample.

Sr-89 and Sr-90 once per quarter.

At least once per 184 days.

One sample representing a commercially important species and one sample representing a recreationally important species.

Gamma scan on edible portion.

Table A-1 SEQUOYAH NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway and/or Sample c.

Food Products Number of Samples and Locations1*

1 sample each of principal food products grown at private gardens and/or farms in the immediate vicinity of the plant.

Sampling and Collection Frequency At least once per 365 days at time of harvest.

The types of foods available for sampling will vary.

Following is a list of typical foods which may be available:

Cabbage, lettuce, or greens Corn Green Beans Potatoes Tomatoes Type and Frequency of Analysis Gamma scan on edible portion.

to d.

Vegetation6 One sample of each of the same foods grown at greater than 10 miles distance from the plant.

Samples from farms producing milk but not providing a milk sample.

At least once per 31 days.

1-131 and gamma scan at least once 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 2008.

b.

Sample locations, sector and distance from plant, are described in Table A-2 and A-3 and shown in Figures A-l, A-2, and A-3.

c.

Composite samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

d.

The sample collected at this location shall be considered a control for the drinking water and surface water.

e.

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

Table A-2 SEQUOYAH NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS Map Location Number3 2

3 4

5 7

8 9

10 11 12 13 14 19 21 23 24 25 31 32 33 35 37 38 40 44 46 47 a.

See Figures A-1 b.

Sample codes:

Station LM-2 LM-3 LM-4 LM-5 PM-2 PM-3 PM-8 PM-9 RM-1 RM-2 RM-3 RM-4 FarmHW FarmHS Farm EH Well No. 6 FarmK TRMe 473.0 (East Side Utilities)

TRM 469.9 (E. I. DuPont)

TRM 465.3 (Chattanooga)

TRM 503.8 (Dayton)

TRM 485.0 TRM 483.4 TRM 479.0 TRM 480.0 Sector N

ssw NE NNE sw w

ssw wsw sw NNE ESE NW NW E

ENE NNE NE

Chickamauga Reservoir (TRM 471-530)

Watts Bar Reservoir (TRM 530-602)

, A-2, and A-3 AP

=

Air particulate filter CF =

Charcoal filter F

=

Fish M

=

Milk PW

=

Public Water S

=

Soil Approximate Distance (Miles) 0.7 2.0 1.5 1.8 3.8 5.6 8.7 2.6 16.7 17.8 11.3 20.0 1.2 4.6 9.5 0.15 40.0 10.7d 13.8d 18.4d

20. ld 1.3d 0.3d 4.7d 3.7d

Indicator (I) or Control (C)

]

]

C C

c c

I I

c I

c I

I I

c c

I I

I I

c Samples Collected6 AP,CF,S AP,CF,S AP,CF,S AP,CF,S AP,CF,S AP,CF,S AP,CF,S AP,CF,S AP,CF,S AP,CF,S AP,CF,S AP,CF,S M,W° M

M W

M PW PW PW PW,SW SS sw SS SS F

F SS

=

Shoreline Sediment SW

=

Surface water W

=

Well water 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 Location Number3 3

4 5

7 8

9 10 11 12 13 14 49 50 51 52 53 55 56 57 58 59 60 62 63 66 67 68 69 70 71 72 73 74 75 76 77 78 79 81 82 83 84 85 86 87 88 89 90 Station SSW-1C NE-1A NNE-1 SW-2 W-3 SSW-3 WSW-2A SW-3 NNE-4 ESE-3 NW-3 N-l N-2 N-3 N-4 NNE-2 NE-1 NE-2 ENE-i ENE-2 E-l E-2 ESE-1 ESE-2 SE-1 SE-2 SE-4 SSE-1 SSE-2 S-l S-2 SSW-1 SSW-2 SW-1 WSW-l WSW-2 WSW-3 WSW-4 W-l W-2 WNW-1 WNW-2 NW-1 NW-2 NNW-1 NNW-2 NNW-3 SSW-1 B Sector SSW NE NNE SW w

SSW wsw SW NNE ESE NW N

N N

N NNE NE NE ENE ENE E

E ESE ESE SE SE SE SSE SSE S

S ssw SSW SW WSW WSW WSW WSW w

w WNW WNW NW NW NNW NNW NNW SSW Approximate Distance (miles) 2.0 1.5 1.8 3.8 5.6 8.7 2.6 16.7 17.8 11.3 20.0 0.6 2.1 5.2 10.0 4.5 2.4 4.1 0.2 5.1 1.2 5.2 1.2 4.9 1.4 1.9 5.2 1.6 4.6 1.5 4.7 0.6 4.0 0.7 0.9 2.5 5.7 7.8 0.6 4.3 0.4 5.3 0.4 5.2 0.6 1.7 5.3 1.5 Onsite (On)b or Offsite (Off*

On On On Off Off Off Off Off Off Off Off On Off Off Off Off Off Off On Off On Off On Off On On Off On Off On Off On Off On On Off Off Off On Off On Off On Off On On Off On a.

See Figures A-l,A-2, and A-3.

b.

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

Figure A-1 Radiological Environmental Monitoring Locations Within 1

mile of the Plant 348.75 N

11.25 NNW

^===M====^L NNE 326.25 33.75 NE 56.25 ENE 281.25 EQUOYAH NUCLEAR PLANT 78.75 258.75 101.25 SE 213.75 146.25 ssw 191.25 e

168.75 SSE Scale Mile Figure A-2 Radiological Environmental Monitoring Locations Between 1 and 5 miles from the Plant NW 303.75 56.25 WNW ENE 281.25 w-258.75 WSW 348.75 N

11.25 78.75 101.25 ESE 236.25 123.75 SW SE 213.75 146.25 SSW 191.25 SSE 168.75 SCALE 0

1 2

MILES Figure A-3 Radiological Environmental Monitoring Locations More than 5 miles from the Plant 326.25 303.75 281.25 258.7!

wsw 326.2 213.75 33.75 56.25 78.75 101.25 123.75 146.25 191.25 168.75 APPENDIX B 2008 PROGRAM MODIFICATIONS

Appendix B Radiological Environmental Monitoring Program Modification No modifications were made to the SQN REMP during 2008, APPENDIX C PROGRAM DEVIATIONS Appendix C Program Deviations A problem with the sampling equipment prevented the collection of air monitoring samples from one of the twelve sampling locations for one sampling period. A milk sample was not available from one of the two control locations for one biweekly sampling period.

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

Table C-l Radiological Environmental Monitoring Program Deviations Date Station Location Remarks 04/08/08 Farm EH 9.5 miles ENE The milk sample was not available at this control farm location.

The farmer was changing out his holding tank and was not saving any milk. A sample was collected from the other farm used as a control location meeting the requirement for at least one control sample.

09/30/08 RM-4 20.0 miles NW The total sample volume for air filter and charcoal cartridge samples was not adequate due to a failure of the sampling pump.

The problem was a failure of the drive motor.

The motor was replaced and the system returned to normal operation.

The missed samples were documented in the Corrective Action Program with Problem Evaluation Report (PER) 153800.

to

APPENDIX D ANALYTICAL PROCEDURES Appendix D Analytical Procedures Analyses of environmental 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 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, 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-l.

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-l Gross Beta Tritium Iodine-131 Strontium-89 Strontium-90 Air Filters (pCi/m3) 0.002 A.

Water fpCi/L) 1.9 270 0.4 5.0 2.0 Nominal LLD Values Radiochemical Procedures Milk (pCi/L) 0.4 3.5 2.0 Wet Vegetation fpCi/Ke wet) 6.0 31.0 12.0 Sediment and Soil fpCi/e dry) 1.6 0.4

Ce-141 Ce-144 Cr-51 1-131 Ru-103 Ru-106 Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Mn-54 Zn-65 Co-60 K-40 Ba-140 La-140 Fe-59 Be-7 Pb-212 Pb-214 Bi-214 Bi-212 Tl-208 Ra-224 Ra-226 Ac-228 Air Particulates DCi/m3

.005

.01

.02

.005

.005

.02

.005

.005

.005

.005

.005

.005

.005

.005

.04

.015

.01

.005

.02

.005

.005

.005

.02

.002

.01 Charcoal Filter pCi/m3

.02

.07 0.15 0,03 0:02 0.12 0.02 0.02 0.03 0.02 0.02 0.02 0.03 0.02 0.30 0.07 0.04 0.04 0.15 0.03 0.07 0.05 0.20 0.02

0.07 Water and Milk pCi/L 10 30 45 10 5

40 5

5 10 5

5 5

10 5

100 25 10 10 45 15 20 20 50 10

~

20 Table E-l Nominal LLD Values B.

Gamma Vegetatior and Grain pCi/p, drv

.07

.15

.30

.20

.03

.15

.03

.03

.05

.25

.03

.03

.05

.03

.40

.30

.20

.08

.25

.04

.50

.10

.25

.03

.10 Analyses i

Wet Vegetation pCi/kg, wet 35 115 200 60 25 190 30 25 45 30 20 20 45 20 400 130 50 40 200 40 80 55 250 30

70 Soil and Sediment pCi/g, drv

.10

.20

.35

.25

.03

.20

.03

.03

.05

.04

.03

.03

.05

.03

.75

.30

.20

.05

.25

.10

.15

.15

.45

.06

.75

.15

.25 Fish pCi/g, drv

.07

.15

.30

.20

.03

.15

.03

.03

.05

.25

.03

.03

.05

.03

.40

.30

.20

.08

.25

.04

.50

.10

.25

.03

.10 Clam Flesh pCi/g, drv

.35

.85 2.4 1.7

.25 1.25

.14

.15

.45

.25

.25

.20

.40

.20 3.50 2.4 1.4

.45 1.9

.30

.10

.50 2.0

.25

.75 Foods Tomatoes Potatoes, etc pCi/kg, wet 20 60 95 20 25 90 10 10 45 10 10 10 45 10 250 50 25 25 90 40 80 40 130 30

~

~

50

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

Specified by the SQN Offsite Dose Calculation Manual Analysis gross beta H-3 Mn-54 Fe-59 Co-58,60 Zn-65 Zr-95 Nb-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Water pCi/L 4

2000a 15 30 15 30 30 15 lb 15 18 60 15 Airborne Particulate or Gases j>Ci/m3 1 x 10-2 N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

7 x 10"2 5 xlO"2 6xlO"2 N.A.

N.A.

Fish pCi/kg. wet N.A.

N.A.

130 260 130 260 N.A.

N.A.

N.A.

130 150 N.A.

N.A.

Milk pCi/L N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

1 15 18 60 15 Food Products pCi/kg. wet N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

60 60 80 N.A.

N.A.

Sediment pCi/kg. dry N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

150 180 N.A.

N.A.

a.

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

b.

If no drinking water pathway exists, a value of 15 pCi/liter may be used.

APPENDIX F QUALITY ASSURANCE/QUALITY CONTROL PROGRAM Appendix F Quality Assurance/Quality Control Program A quality assurance program is employed by the laboratory to ensure that the environmental monitoring data are reliable.

This program includes the use of written, approved procedures in performing the work, provisions for staff training and certification, internal self assessments of program performance, audits by various external organizations, and a laboratory quality control program.

The quality control program employed by the radioanalytical laboratory is designed to ensure that the sampling and analysis process is working as intended.

The program includes equipment checks and the analysis of quality control samples along with routine samples.

Instrument quality control checks include background count rate and counts reproducibility.

In addition to these two general checks, other quality control checks are performed on the variety of detectors used in the laboratory.

The exact nature of these checks depends on the type of device and the method it uses to detect radiation or store the information obtained.

Quality control samples of a variety of types are used by the laboratory to verify the performance of different portions of the analytical process.

These quality control samples include blanks, replicate samples, blind samples, or cross-checks.

Blanks are samples which contain no measurable radioactivity or no activity of the type being measured.

Such samples are analyzed to determine whether there is any contamination of equipment or commercial laboratory chemicals, cross-contamination in the chemical process, or interference from isotopes other than the one being measured.

Duplicate samples are generated at random by the sample computer program which schedules the collection of the routine samples.

For example, if the routine program calls for four milk samples every week, on a random basis each farm might provide an additional sample several times a year.

These duplicate samples are analyzed along with other routine samples.

They provide information about the variability of radioactive content in the various sample media.

If enough sample is available for a particular analysis, the laboratory staff can split it into two portions.

Such a sample provides information about the variability of the analytical process since two identical portions of material are analyzed side by side.

Analytical knowns are another category of quality control sample.

A known amount of radioactivity is added to a sample medium.

The lab staff knows the radioactive content of the sample.

Whenever possible, the analytical knowns contain the same amount of radioactivity each time they are run.

In this way, analytical knowns provide immediate data on the quality of the measurement process.

Blind spikes are samples containing radioactivity which are introduced into the analysis process disguised as ordinary environmental samples.

The lab staff does not know the sample contains radioactivity.

Since the bulk of the ordinary workload of the environmental laboratory contains no measurable activity or only naturally occurring radioisotopes, blind spikes can be used to test the detection capability of the laboratory or can be used to test the data review process.

If an analysis routinely generates numerous zeroes for a particular isotope, the presence of the isotope is brought to the attention of the laboratory supervisor in the daily review process.

Blind spikes test this process since the blind spikes contain radioactivity at levels high enough to be detected.

Furthermore, the activity can be put into such samples at the extreme limit of detection (near the LLD) to verify that the laboratory-can detect very low levels of activity.

Another category of quality control samples is the internal cross-checks.

These samples have a known amount of radioactivity added and are presented to the lab staff labeled as cross-check samples.

This means that the quality control staff knows the radioactive content or "right answer" but the lab personnel performing the analysis do not.

Such samples test the best performance of the laboratory by 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.

During 2008, all analysis results for internal cross check samples were within agreement limits when compared to the known value.

To provide for an independent verification of the laboratory's ability to make accurate measurements, the laboratory participated in an environmental level cross-check program Eckert & Ziegler Analytics (formerly Analytics, Inc.), during 2008.

The results of TVA's participation in this cross-check program are presented in Table F-l.

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-l Results For 2008 External Cross Checks Test Period First Quarter First Quarter First Quarter Third Quarter Third Quarter Third Quarter Third Quarter Sample Tvpe / Analysis Water (pCi/L)

Gross Beta Water (pCi/Filter) 3H Water (pCi/L) hi, l41Ce 51Cr 134Cs l37Cs 58Co 54Mn 59Fe 65Zn 60Co Milk (pCi/L) mI 89Sr 90Sr Water (pCi/L) 3H Sand (pCi/gram) l41Ce 51Cr l34Cs 137Cs 58Co 54Mn 59Fe 65Zn 60Co Air Filter (pCi/filter)

Gross Beta Air Filter (pCi/filter) 14lCe 5lCr I34Cs 137Cs 58Co 54Mn 59Fe 65Zn 60Co Results Known 2.30E+02 4.01E+03 7.04E+01 1.98E+02 2.86E+02 9.97E+01 1.16E+02 5.64E+01 7.50E+01 8.14E+01 1.09E+02 1.88E+02 7.29E+01 9.89E+01 1.33E+01 1.14E+04 0.341 0.890 0.491 0.343 0.377 0.351 0.305 0.675 0.496 56.0 104.0 272.0 150.0 105.0 115.0 107.0 93.3 206.0 151.0 TVA 2.16E+02 4.10E+03 7.14E+01 1.80E+02 2.94E+02 9.41E+01 1.19E+02 5.65E+01 8.28E+01 7.58E+01 1.09E+02 1.92E+02 7.58E+01 9.85E+01 1.10E+01 1.16E+04 0.321 0.862 0.439 0.329 0.373 0.374 0.294 0.676 0.495 52.5 99.9 269.0 127.0 101.0 113.0 114.0 89.2 203.0 142.0 Agreement 0.94 1.02 1.01 0.91 1.03 0.94 1.03 1.00 1.10 0.93 1.00 1.02 1.04 1.00 0.83 1.02 0.94 0.97 0.89 0.96 0.99 1.07 0.96 1.00 1.00 0.94 0.96 0.99 0.85 0.96 0.98 1.07 0.96 0.99 0.94 APPENDIX G LAND USE SURVEY Appendix G Land Use Survey A land use survey is conducted annually to identify the location of the nearest milk producing animal, the nearest residence, and the nearest garden of greater than 500 square feet producing fresh leafy vegetables in each of 16 meteorological sectors within a distance of 5 miles from the plant.

The land use survey is conducted between April 1 and October 1 using appropriate techniques such as door-to-door survey, mail survey, telephone survey, aerial survey, or information from local agricultural authorities or other reliable sources.

Using survey data, relative radiation doses are projected for individuals living near the plant.

These projections use the data obtained in the survey and historical meteorological data.

They also assume that releases are equivalent to the design basis source terms.

The calculated doses are relative in nature and do not reflect actual exposures received by individuals living near SQN.

Calculated doses to individuals based on measured effluents from the plant are well below applicable dose limits.

In response to the 2008 SQN land use survey, annual dose projections were calculated for air submersion, vegetable ingestion, and milk ingestion.

External doses due to radioactivity in air (air submersion) are calculated for the nearest resident in each sector, while doses from drinking milk or eating foods produced near the plant are calculated for the areas with milk producing animals and gardens, respectively.

There were no changes in the location of the nearest resident as identified in 2008 compared to 2007.

There were two changes in the location for nearest gardens as identified in 2008.

For milk ingestion, there were no changes as compared to 2007.

Tables G-1, G-2, and G-3 show the comparative relative calculated doses for 2007 and 2008.

Table G-l SEQUOYAH NUCLEAR PLANT Relative Projected Annual Air Submersion Dose to the Nearest Resident Within Five Miles of Plant mrem/year Sector N

NNE NE ENE E

ESE SE SSE S

SSW sw wsw w

WNW NW NNW 2007 Survev Approximate Distance Miles 0.8 1.5 1.5 1.3 1.0 1.0 1.1 1.3 1.1 1.3 1.4 0.6 0.6 1.1 0.8 0.5 Annual Dose 0.12 0.07 0.06 0.02 0.02 0.02 0.02 0.03 0.11 0.15 0.06 0.05 0.06 0.02 0.04 0.14 2008 Survev Approximate Distance Miles 0.8 1.5 1.5 1.3 1.0 1.0 1.1 1.3 1.1 1.3 1.4 0.6 0.6 0.9 0.8 0.5 Annual Dose 0.12 0.07 0.06 0.02 0.02 0.02 0.02 0.03 0.11 0.15 0.06 0.05 0.06 0.02 0.04 0.14 Table G-2 SEQUOYAH NUCLEAR PLANT Relative Projected Annual Dose to Child's Bone from Ingestion of Home-Grown Foods mrem/year Sector N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW 2007 Survey Approximate Distance Miles 1.1 3.3 2.9 2.8 1.5 1.1 2.0 1.3 1.3 2.8 2.2 2.3 0.9 1.1 0.9 1.5 Annual Dose 2.25 0.74 0.74 0.26 0.42 0.50 0.30 1.00 2.72 1.70 1.01 0.27 1.03 0.62 1.26 0.87 2008 Survey Approximate Distance Miles 1.1 2.5 2.9 2.8 1.5 1.1 2.0 2.8 1.3 2.8 2.2 2.3 0.9 1.1 0.9 1.5 Annual Dose 2.25 1.13 0.74 0.26 0.42 0.50 0.30 0.34 2.72 1.70 1.01 0.27 1.03 0.62 1.26 0.87 Table G-3 SEQUOYAH NUCLEAR PLANT Relative Projected Annual Dose to Receptor Thyroid from Ingestion of Milk mrem/year r

Location FarmHSb FarmHW Sector E

NW Approximate Distance (Miles)*

4.6 1.2 2007 0.008 0.052 Annual Dose 2008 0.008 0.052 X/Q funits-s/m3) 6.74 E-8 5.48 E-7 a.

Distances measured to nearest property line.

b.

Grade A dairy.

APPENDIX H DATA TABLES AND FIGURES 1 st qtr

Average, 0 - 2 miles 8.4 (onsite)

Average,

> 2 miles 7.4 (offsite)

Table H -1 DIRECT RADIATION LEVELS Average External Gamma Radiation Levels Onsite and Offsite Sequoyah Nuclear Plant for Each Quarter - 2008 mR / Quarter (a)

Average External Gamma Radiation Levels (b) 2nd qtr 3rd qtr 8.5 6.8 11.2 9.9 4th qtr 11.2 10.2 (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 mR/yr 39 34 TABLE H -2 continued DIRECT RADIATION LEVELS Individual Stations at Sequoyah Nuclear Plant Map Location Number 71 72 73 90 3

74 9

75 7

11 76 77 10 78 79 81 82 8

83 84 85 86 14 87 88 89 TLD Station Number S-1 S-2 SSW-1 SSW-1B SSW-1 C SSW-2 SSW-3 SW-1 SW-2 SW-3 WSW-1 WSW-2 WSW-2A WSW-3 WSW-4 W-1 W-2 W-3 WNW-1 WNW-2 NW-1 NW-2 NW-3 NNW-1 NNW-2 NNW-3 Direction, decrees 183 185 203 192 198 204 203 228 227 228 241 238 250 248 244 260 275 280 292 295 315 318 320 344 342 334 I

Approx

Distance, miles 1.5 4.7

.6 1.5 2.0 4.0 8.7

.7 3.8 16.7

.9 2.5 2.6 5.7 7.8

.6 4.3 5.6

.4 5.3

.4 5.2 20.0

.6 1.7 5.3 Environmental Radiation Levels 1st Qtr Jan-Mar 2008 13.4 5.9 6.4 3.2 7.0 9.7 8.6 10.7 7.5 11.3 12.3 3.2 5.9 7.5 10.2 14.5 7.0 7.5 10.7 7.0 7.0 12.3 8.6 7.5 7.0 7.0 mR / quarter 2nd Qtr Apr-Jun 2008 9.9 3.4 6.2 3.8 6.2 12.2 7.6 10.4 8.0 10.4 13.2 3.4 7.6 11.8 5.7 12.2 2.4 6.6 12.2 7.6 8.0 14.5 4.3 10.8 6.2 5.2 3rd Qtr Jul-Sep 2008 15.9 1.8 11.5 6.7 10.6 15.9 13.0 15.4 13.5 12.0 15.4 5.2 7.2 14.0 9.6 15.9 3.8 9.6 8.6 9.6 4.2 15.9 7.2 14.0 6.2 9.1 4th Qtr Oct-Dec 2008 14.3 6.3 9.7 6.8 8.6 MA 12.5 14.8 11.4 12.5 16.0 6.8 7.4 12.0 10.8 12.5 8.6 8.6 10.3 8.6 7.4 14.3 8.0 13.1 12.0 8.6 I

Annual Exposure mR/vear 53.5 17.4 33.8 20.5 32.4 54.9 41.7 51.3 40.4 46.2 56.9 18.6 28.1 45.3 36.3 55.1 21.8 32.3 41.8 32.8 26.6 57.0 28.1 45.4 31.4 29.9

TABLE H-2 DIRECT RADIATION LEVELS Individual Stations at Sequoyah Nuclear Plant Map Location Number 49 50 51 52 5

53 12 55 4

56 57 58 59 60 62 63 13 66 67 68 69 70 TLD Station Number N-1 N-2 N-3 N-4 NNE-1 NNE-2 NNE-4 NE-1 NE-1A NE-2 ENE-1 ENE-2 E-1 E-2 ESE-1 ESE-2 ESE-3 SE-1 SE-2 SE-4 SSE-1 SSE-2 Direction, deqrees 3

4 358 355 13 31 32 38 50 51 73 66 96 87 110 112 117 131 129 136 154 158 Approx

Distance, miles

.6 2.1 5.2 10.0 1.8 4.5 17.8 2.4 1.5 4.1

.2 5.1 1.2 5.2 1.2 4.9 11.3 1.4 1.9 5.2 1.6 4.6 l

Environmental Radiation Levels 1stQtr Jan-Mar 2008 7.5 9.1 3.2 5.9 9.7 8.1 5.9 9.7 8.6 3.2 5.9 8.1 6.4 5.9 8.1 6.4 6.4 3.8 4.3 10.2 8.6 10.2 mR / quarter 2nd Qtr Apr-Jun 2008 8.5 8.5 6.2 5.7 14.1 8.0 5.2 9.9 6.6 1.5 8.0 5.7 5.2 5.7 8.0 4.8 5.2 3.8 4.3 9.4 5.7 9.0 3rd Qtr Jul-Sep 2008 10.6 13.0 10.1 10.1 14.9 9.1 9.7 14.0 11.0 7.2 8.1 6.2 10.6 12.5 8.6 13.0 8.1 7.2 11.5 15.4 6.2 12.5 4th Qtr Oct-Dec 2008 13.1 9.7 8.0 11.4 14.3 8.6 7.5 13.7 10.8 10.8 10.3 11.4 7.4 10.3 8.6 13.1 8.0 8.0 9.7 12.5 9.1 14.3 I

Annual Exposure mR/vear 39.7 40.3 27.5 33.1 53.0 33.8 28.3 47.3 37.0 22.7 32.3 31.4 29.6 34.4 33.3 37.3 27.7 22.8 29.8 47.5 29.6 46.0

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory Name of Facility:

SEQUOYAH NUCLEAR PLANT Location of Facility:

HAMILTON TENNESSEE Type and Total Number of Analysis Performed Lower Limit of Detection (LLD)

See Note 1 Indicator Locations Mean (F)

Range See Note 2 RADIOACTIVITY IN AIR FILTER PCI/M3 - 0.037 BQ/M3 Location with Highest Name Distance and Direction Docket Number:

50-327,328 Reporting Period: 2008 Annual Mean Control Locations Number of Mean (F)

Mean (F)

Nonroutine Range Range Reported See Note 2 See Note 2 Measurements GROSS BETA 623 On ON BE-7 BI-214 K-40 PB-212 PB-214 TL-208 2.00E-03 2.18E-02 (416/416) 1.03E-02 3.55E-02 GAMMA SCAN (GELI) 156 AC-228 1.00E-02 104 VALUES < LLD 2.00E-02 1.17E-01 (104/104) 7.25E-02 1.76E-01 5.00E-03 1.94E-02 (98/104) 5.80E-03 6.91 E-02 4.00E-02 4.07E-02 (1/104) 4.07E-02 4.07E-02 5.00E-03 104 VALUES < LLD 5.00E-03 1.95E-02 (97/104) 5.10E-03 6.80E-02 2.00E-03 104 VALUES < LLD PM-8 HARRISON TN 8.7 MILES SSW PM-3 DAISY TN 5.6 MILES W PM-2 COUNTY PARK TN 3.8 MILES SW PM-8 HARRISON TN 8.7 MILES SSW LM-3 HARRISON BAY RD 2.0 MILES SSW LM-5 WARE POINT 1.8 MILES NNE PM-8 HARRISON TN 8.7 MILES SSW PM-2 COUNTY PARK TN 3.8 MILES SW 2.22E-02 (52/52) 1.14E-02 3.53E-02 13 VALUES < LLD 1.24E-01 (13/13) 9.64E-02 1.76E-01 2.54E-02 (12/13) 6.40E-03 6.56E-02 4.07E-02 (1/13) 4.07E-02 4.07E-02 13 VALUES < LLD 2.43E-02 (12/13) 7.90E-03 6.55E-02 13 VALUES < LLD 2.22E-02 (207/207) 1.09E-02 4.52E-02 52 VALUES < LLD 1.20E-01 (52/52) 7.98E-02 1.72E-01 1.82E-02 (50/52) 5.00E-03 8.34E-02 4.40E-02 (1/52) 4.40E-02 4.40E-02 52 VALUES < LLD 1.81 E-02 (49/52) 5.00E-03 7.71 E-02 2.00E-03 (1/52) 2.00E-03 2.00E-03 Note:

1.

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

2.

Mean and Range based upon detectable measurements only.

Fraction of detectable measurements at specified location is indicated in parentheses (F).

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory RADIOACTIVITY IN CHARCOAL FILTER PCI/M3 - 0.037 BQ/M3 Name of Facility:

Location of Facility:

Type and Total Number of Analysis Performed GAMMA SCAN (GELI)

BI-214 1-131 K-40 PB-212 PB-214 i

TL-208 SEQUOYAH NUCLEAR PLANT HAMILTON TENNESSEE Lower Limit of Detection (LLD)

See Note 1 623 5.00E-02 3.00E-02 3.00E-01 3.00E-02 7.00E-02 2.00E-02 Indicator Locations Mean (F)

Range See Note 2 7.72E-02 (137/416) 5.01E-02 2.13E-01 SEE NOTE 3 3.79E-01 (84/416) 3.01 E-01 5.52E-01 416 VALUES < LLD 1.02E-01 (75/416) 7.00E-02 2.59E-01 416 VALUES < LLD Location with Highest Name Distance and Direction LM-5 WARE POINT 1.8 MILES NNE LM-2 NORTH 0.8 MILES NORTH PM-2 COUNTY PARK TN 3.8 MILES SW LM-2 NORTH 0.8 MILES NORTH LM-2 NORTH 0.8 MILES NORTH Docket Number:

50-327,328 Reporting Period: 2008 Annual Mean Mean (F)

Range See Note 2 8.71 E-02 (12/52) 5.08E-02 1.44E-01 4.02E-01 (8/52) 3.24E-01 5.52E-01 52 VALUES < LLD 1.21 E-01 (9/52) 7.37E-02 1.99E-01 52 VALUES < LLD Control Locations Mean (F)

Range See Note 2 7.53E-02 (56/207) 5.02E-02 1.41 E-01 3.70E-01 (43/207) 3.01 E-01 4.90E-01 207 VALUES < LLD 9.91 E-02 (29/207) 7.03E-02 1.89E-01 207 VALUES < LLD Number of Nonroutine Reported Measurements Note:

1.

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

2.

Mean and Range based upon detectable measurements only.

Fraction of detectable measurements at specified location is indicated in parentheses (F).

Note:

3.

The analysis of Charcoal Filters was performed by Gamma Spectroscopy.

No 1-131 was detected.

The LLD for 1-131 by Gamma Spectroscopy was 0.03 pCi/cubic meter.

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory RADIOACTIVITY IN MILK PCI/L - 0.037 BQ/L Name of Facility:

SEQUOYAH NUCLEAR PLANT Location of Facility:

HAMILTON TENNESSEE Docket Number:

50-327,328 Reporting Period: 2008 Type and Total Number of Analysis Performed IODINE-131 GAMMA SCAN (GELI)

AC-228 BI-214 K-40

^

PB-212 OO PB-214 TL-208 SR89 SR90 Lower Limit of Detection (LLD)

See Note 1 103 4.00E-01 103 2.00E+01 2.00E+01 1.00E+02 1.50E+01 2.00E+01 1.00E+01 16 3.50E+00 16 2.00E+00 Indicator Locations Mean (F)

Range See Note 2 52 VALUES < LLD 52 VALUES < LLD 3.42E+01 (23/52) 2.00E+01 7.10E+01 1.34E+03 (52/52) 8.33E+02 1.55E+03 52 VALUES < LLD 3.08E+01 (18/52) 2.05E+01 5.85E+01 52 VALUES < LLD 8 VALUES < LLD 2.80E+00 (3/8) 2.12E+00 3.59E+00 Location with Highest Name Distance and Direction H. SMITH FARM 4.6 MILES E H WALKER FARM 1.2 MILES NW H. SMITH FARM 4.6 MILES E H WALKER FARM 1.2 MILES NW H WALKER FARM 1.2 MILES NW H. SMITH FARM 4.6 MILES E H WALKER FARM 1.2 MILES NW Annual Mean Mean (F)

Range See Note 2 26 VALUES < LLD 3.55E+01 (13/26) 2.01E+01 7.10E+01 1.39E+03 (26/26) 1.27E+03 1.53E+03 26 VALUES < LLD 3.34E+01 (10/26) 2.11E+01 5.85E+01 26 VALUES < LLD 2.86E+00 (2/4) 2.12E+00 3.59E+00 Control Locations Mean (F)

Range See Note 2 51 VALUES < LLD 51 VALUES < LLD 3.92E+01 (19/51) 2.03E+01 9.27E+01 1.28E+03 (51/51) 1.13E+03 1.43E+03 51 VALUES < LLD 3.20E+01 (15/51) 2.07E+01 5.72E+01 51 VALUES < LLD 8 VALUES < LLD 8 VALUES < LLD Number of Nonroutine Reported Measurements Note:

1.

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

2.

Mean and Range based upon detectable measurements only.

Fraction of detectable measurements at specified location is indicated in parentheses (F).

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

ON Name of Facility:

SEQUOYAH NUCLEAR PLANT Location of Facility:

HAMILTON TENNESSEE Type and Total Number of Analysis Performed GAMMA SCAN (GELI) 12 AC-228 BE-7 BI-212 BI-214 CS-137 K-40 PB-212 PB-214 RA-224 RA-226 TL-208 SR89 12 SR90 12 Lower Limit of Detection (LLD)

See Note 1 2.50E-01 2.50E-01 4.50E-01 1.50E-01 3.00E-02 7.50E-01 1.00E-01 150E-01 7.50E-01 1.50E-01 6.00E-02 1.60E+00 4.00E-01 Indicator Locations Mean (F)

Range See Note 2 9.11E-01 (8/8) 5.44E-01 1.23E+00 3.17E-01 (5/8) 2.59E-01 3.53E-01 9.80E-01 (8/8) 5.20E-01 1.32E+00 9.43E-01 (8/8) 6.92E-01 1.26E+00 3.79E-01 (8/8) 1.26E-01 5.66E-01 5.79E+00 (8/8) 2.35E+00 1.20E+01 8.83E-01 (8/8) 5.32E-01 1.16E+00 1.02E+00 (8/8) 7.93E-01 1.33E+00 1.11E+00 (3/8) 1.03E+00 1.20E+00 9.43E-01 (8/8) 6.92E-01 1.26E+00 2.96E-01 (8/8) 1.59E-01 3.80E-01 8 VALUES < LLD 8 VALUES < LLD Location with Highest Name Distance and Direction LM-4 SKULL ISLAND 1.5 MILES NE PM-8 HARRISON TN 8.7 MILES SSW LM-4 SKULL ISLAND 1.5 MILES NE LM-4 SKULL ISLAND 1.5 MILES NE LM-4 SKULL ISLAND 1.5 MILES NE LM-2 NORTH 0.8 MILES NORTH LM-2 NORTH 0.8 MILES NORTH LM-4 SKULL ISLAND 1.5 MILES NE LM-2 NORTH 0.8 MILES NORTH LM-4 SKULL ISLAND 1.5 MILES NE LM-4 SKULL ISLAND 1.5 MILES NE Docket Number:

50-327,328 Reporting Period: 2008 Annual Mean Control Locations Number of Mean (F)

Mean (F)

Nonroutine Range Range Reported See Note 2 See Note 2 Measurements 1.23E+00 (1/1) 1.23E+00 1.23E+00 3.53E-01 (1/1) 3.53E-01 3.53E-01 1.32E+00 (1/1) 1.32E+00 1.32E+00 1.26E+00 (1/1) 1.26E+00 1.26E+00 5.66E-01 (1/1) 5.66E-01 5.66E-01 1.20E+01 (1/1) 1.20E+01 1.20E+01 1.16E+00 (1/1) 1.16E+00 1.16E+00 1.33E+00 (1/1) 1.33E+00 1.33E+00 1.20E+00 (1/1) 1.20E+00 1.20E+00 1.26E+00 (1/1) 1.26E+00 1.26E+00 3.80E-01 (1/1) 3.80E-01 3.80E-01 7.85E-01 (4/4) 5.18E-01 1.02E+00 3.87E-01 (3/4) 2.73E-01 5.26E-01 8.14E-01 (4/4) 4.94E-01 1.08E+00 8.63E-01 (4/4) 6.64E-01 1.01E+00 2.05E-01 (4/4) 1.38E-01 3.58E-01 5.02E+00 (4/4) 3.51 E+00 6.38E+00 7.65E-01 (4/4) 4.76E-01 1.04E+00 9.63E-01 (4/4) 7.03E-01 1.17E+00 1.11 E+00 (1/4) 1.11E+00 1.11E+00 8.63E-01 (4/4) 6.64E-01 1.01 E+00 2.62E-01 (4/4) 1.63E-01 3.27E-01 4 VALUES < LLD 4 VALUES < LLD CD*

Note:

1.

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

2.

Mean and Range based upon detectable measurements only.

Fraction of detectable measurements at specified location is indicated in parentheses (F).

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

Name of Facility:

SEQUOYAH NUCLEAR PLANT Location of Facility:

HAMILTON TENNESSEE Docket Number:

50-327,328 Reporting Period: 2008 Type and Total Number of Analysis Performed GAMMA SCAN (GELI)

BI-214 K-40 PB-212 PB-214 Lower Limit of Detection (LLD)

See Note 1 2

4.00E+01 2.50E+02 4.00E+01 8.00E+01 Indicator Locations Mean (F)

Range See Note 2 6.42E+01 (1/1) 6.42E+01 6.42E+01 8.32E+02 (1/1) 8.32E+02 8.32E+02 1 VALUES < LLD 1 VALUES < LLD Location with Highest Name Distance and Direction SQNP 1.1 MILES WNW SQNP 1.1 MILES WNW SQNP 1.1 MILES WNW SQNP 1.1 MILES WNW Annual Mean Mean (F)

Range See Note 2 6.42E+01 (1/1) 6.42E+01 6.42E+01 8.32E+02 (1/1) 8.32E+02 8.32E+02 1 VALUES < LLD 1 VALUES < LLD Control Locations Mean (F)

Range See Note 2 5.07E+01 (1/1) 5.07E+01 5.07E+01 8.79E+02 (1/1) 8.79E+02 8.79E+02 1 VALUES < LLD 1 VALUES < LLD Number of Nonroutine Reported Measurements 9

i:

Note:

1.

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

2.

Mean and Range based upon detectable measurements only.

Fraction of detectable measurements at specified location is indicated in parentheses (F).

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

Name of Facility:

SEQUOYAH NUCLEAR PLANT Location of Facility:

HAMILTON TENNESSEE Docket Number:

50-327,328 Reporting Period: 2008 Type and Total Number of Analysis Performed GAMMA SCAN (GELI)

BI-214 K-40 PB-214 Lower Limit of Detection (LLD)

See Note 1 2

4.00E+01 2.50E+02 8.00E+01 Indicator Locations Mean (F)

Range See Note 2 6.80E+01 (1/1) 6.80E+01 6.80E+01 1.62E+03 (1/1) 1.62E+03 1.62E+03 1 VALUES < LLD Location with Highest Name Distance and Direction H WALKER FARM 1.2 MILES NW H WALKER FARM 1.2 MILES NW H WALKER FARM 1.2 MILES NW Annual Mean Mean (F)

Range See Note 2 6.80E+01 (1/1) 6.80E+01 6.80E+01 1.62E+03 (1/1) 1.62E+03 1.62E+03 1 VALUES < LLD Control Locations Mean (F)

Range See Note 2 7.14E+01 (1/1) 7.14E+01 7.14E+01 1.22E+03 (1/1) 1.22E+03 1.22E+03 1 VALUES < LLD Number of Nonroutine Reported Measurements CO Note:

1.

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

2.

Mean and Range based upon detectable measurements only.

Fraction of detectable measurements at specified location is indicated in parentheses (F).

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

Name of Facility:

SEQUOYAH NUCLEAR PLANT Location of Facility:

HAMILTON TENNESSEE Docket Number:

50-327,328 Reporting Period: 2008 Type and Total Number of Analysis Performed GAMMA SCAN (GELI)

BI-214 K-40 PB-214 Lower Limit of Detection (LLD)

See Note 1 2

4.00E+01 2.50E+02 8.00E+01 Indicator Locations Mean (F)

Range See Note 2 6.10E+01 (1/1) 6.10E+01 6.10E+01 1.98E+03 (1/1) 1.98E+03 1.98E+03 1 VALUES < LLD Location with Highest Name Distance and Direction GOINS FARM 1.5 MILES NNW GOINS FARM 1.5 MILES NNW GOINS FARM 1.5 MILES NNW Annual Mean Mean (F)

Range See Note 2 6.10E+01 (1/1) 6.10E+01 6.10E+01 1.98E+03 (1/1) 1.98E+03 1.98E+03 1 VALUES < LLD Control Locations Mean (F)

Range See Note 2 5.77E+01 (1/1) 5.77E+01 5.77E+01 1.70E+03 (1/1) 1.70E+03 1.70E+03 1 VALUES < LLD Number of Nonroutine Reported Measurements to Note:

1.

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

2.

Mean and Range based upon detectable measurements only.

Fraction of detectable measurements at specified location is indicated in parentheses (F).

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

Name of Facility:

SEQUOYAH NUCLEAR PLANT Location of Facility:

HAMILTON TENNESSEE Docket Number:

50-327,328 Reporting Period: 2008 Type and Total Number of Analysis Performed GAMMA SCAN (GELI)

AC-228 BI-214 K-40 PB-214 Lower Limit of Detection (LLD)

See Note 1 2

5.00E+01 4.00E+01 2.50E+02 8.00E+01 Indicator Locations Mean (F)

Range See Note 2 1 VALUES < LLD 1.59E+02 (1/1) 1.59E+02 1.59E+02 2.71 E+03 (1/1) 2.71 E+03 2.71 E+03 1.36E+02 (1/1) 1.36E+02 1.36E+02 Location with Highest Name Distance and Direction SQNP 1.1 MILES WNW SQNP 1.1 MILES WNW SQNP 1.1 MILES WNW SQNP 1.1 MILES WNW Annual Mean Mean (F)

Range See Note 2 1 VALUES < LLD 1.59E+02 (1/1) 1.59E+02 1.59E+02 2.71 E+03 (1/1) 2.71 E+03 2.71 E+03 1.36E+02 (1/1) 1.36E+02 1.36E+02 Control Locations Mean (F)

Range See Note 2 1 VALUES < LLD 1.06E+02 (1/1) 1.06E+02 1.06E+02 2.22E+03 (1/1) 2.22E+03 2.22E+03 1.04E+02 (1/1) 1.04E+02 1.04E+02 Number of Nonroutine Reported Measurements OJ a

o Note:

1.

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

2.

Mean and Range based upon detectable measurements only.

Fraction of detectable measurements at specified location is indicated in parentheses (F).

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory Name of Facility:

SEQUOYAH NUCLEAR PLANT Location of Facility:

HAMILTON TENNESSEE Type and Total Number of Analysis Performed Lower Limit of Detection (LLD)

See Note 1 Indicator Locations Mean (F)

Range See Note 2 RADIOACTIVITY IN TOMATOES PCI/KG - 0.037 BQ/KG (WET WT)

Location with Highest Name Distance and Direction Docket Number:

50-327,328 Reporting Period: 2008 Annual Mean Control Locations Number of Mean (F)

Mean (F)

Nonroutine Range Range Reported See Note 2 See Note 2 Measurements GAMMA SCAN (GELI) 2 BI-214 4.00E+01 K-40 PB-214 2.50E+02 8.00E+01 1.08E+02 (1/1) 1.08E+02 1.08E+02 2.34E+03 (1/1) 2.34E+03 2.34E+03 1.21 E+02 (1/1) 1.21 E+02 1.21 E+02 GOINS FARM 1.5 MILES NNW GOINS FARM 1.5 MILES NNW GOINS FARM 1.5 MILES NNW 1.08E+02 (1/1) 1.08E+02 1.08E+02 2.34E+03 (1/1) 2.34E+03 2.34E+03 1.21 E+02 (1/1) 1.21 E+02 1.21 E+02 4.89E+01 (1/1) 4.89E+01 4.89E+01 2.15E+03 (1/1) 2.15E+03 2.15E+03 1 VALUES < LLD ffi Note:

1.

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

2.

Mean and Range based upon detectable measurements only.

Fraction of detectable measurements at specified location is indicated in parentheses (F).

Tennessee Valley Authority Environmental Radiological Monitoring and Instrumentation Western Area Radiological Laboratory Name of Facility:

SEQUOYAH NUCLEAR PLANT Location of Facility:

HAMILTON TENNESSEE Type and Total Number of Analysis Performed GROSS BETA 26 GAMMA SCAN (GELI) 26 AC-228 Bl-214 K-40 PB-212 PB-214 TL-208 TRITIUM 21 Lower Limit of Detection (LLD)

See Note 1 1.90E+00 2.00E+01 2.00E+01 1.00E+02 1.50E+01 2.00E+01 1.00E+01 2.70E+02 Indicator Locations Mean (F)

Range See Note 2 2.69E+00 (11/13) 2.20E+00 3.96E+0C 13 VALUES < LLD 4.10E+01 (7/13) 2.58E+01 6.97E+01 13 VALUES < LLD 13 VALUES < LLD 3.67E+01 (5/13) 2.11E+01 6.38E+01 13 VALUES < LLD 4.77E+02 (2/4) 3.31 E+02 6.22E+02 RADIOACTIVITY IN SURFACE WATER(Total)

PCI/L - 0.037 BQ/L Location with Highest Name Distance and Direction TRM 483.4 TRM 483.4 TRM 483.4 TRM 483.4 TRM 483.4 TRM 483.4 TRM 483.4 TRM 483.4 Docket Number:

50-327,328 Reporting Period: 2008 Annual Mean Control Locations Number of Mean (F)

Mean (F)

Nonroutine Range Range Reported See Note 2 See Note 2 Measurements 2.69E+00 (11/13) 2.20E+00 3.96E+00 13 VALUES < LLD 4.10E+01 (7/13) 2.58E+01 6.97E+01 13 VALUES < LLD 13 VALUES < LLD 3.67E+01 (5/13) 2.11E+01 6.38E+01 13 VALUES < LLD 4.77E+02 (2/4) 3.31 E+02 6.22E+02 2.67E+00 (12/13) 1.94E+00 3.93E+00 13 VALUES < LLD 4.95E+01 (8/13) 2.05E+01 1.33E+02 13 VALUES < LLD 13 VALUES < LLD 4.78E+01 (5/13) 2.73E+01 9.72E+01 13 VALUES < LLD 4.55E+02 (3/17) 4.09E+02 5.31 E+02 ffi Note:

1.

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

2.

Mean and Range based upon detectable measurements only.

Fraction of detectable measurements at specified location is indicated in parentheses (F).

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

PCI/L - 0.037 BQ/L Name of Facility:

SEQUOYAH NUCLEAR PLANT Location of Facility:

HAMILTON TENNESSEE O\\

Type and Total Number of Analysis Performed GROSS BETA GAMMA SCAN (GELI)

AC-228 BI-214 K-40 PA-234M PB-212 PB-214 TL-208 fRITIUM Lower Limit of Detection (LLD)

See Note 1 52 1.90E+00 52 2.00E+01 2.00E+01 1.00E+02 8.00E+02 1.50E+01 2.00E+01 1.00E+01 42 2.70E+02 Indicator Locations Mean (F)

Range See Note 2 3.08E+00 (25/39) 1.91E+00 5.74E+00 39 VALUES < LLD 5.52E+01 (30/39) 2.15E+01 1.37E+02 1.12E+02 (1 /39) 1.12E+02 1.12E+02 39 VALUES < LLD 39 VALUES < LLD 4.53E+01 (23/39) 2.27E+01 1.24E+02 39 VALUES < LLD 3.88E+02 (8/25) 2.83E+02 6.31 E+02 Location with Highest Name Distance and Direction CF INDUSTRIES TRM 473.0 E.I. DUPONT TRM 470.5 CF INDUSTRIES TRM 473.0 CF INDUSTRIES TRM 473.0 CF INDUSTRIES TRM 473.0 E.I. DUPONT TRM 470.5 CF INDUSTRIES TRM 473.0 CHATTANOOGA TRM 465.3 CF INDUSTRIES TRM 473.0 Annual Mean Mean (F)

Range See Note 2 3.27E+00 (11/13) 2.58E+00 4.62E+00 13 VALUES < LLD 6.00E+01 (9/13) 2.53E+01 1.37E+02 1.12E+02 (1/13) 1.12E+02 1.12E+02 13 VALUES < LLD 13 VALUES < LLD 4.95E+01 (7/13) 2.48E+01 1.24E+02 13 VALUES < LLD 3.98E+02 (7/17) 2.83E+02 6.31 E+02 Docket Number:

50-327,328 Reporting Period: 2008 Control Locations Mean (F)

Range See Note 2 2.67E+00 (12/13) 1.94E+00 3.93E+00 13 VALUES < LLD 4.95E+01 (8/13) 2.05E+01 1.33E+02 13 VALUES < LLD 13 VALUES < LLD 13 VALUES < LLD 4.78E+01 (5/13) 2.73E+01 9.72E+01 13 VALUES < LLD 4.55E+02 (3/17) 4.09E+02 5.31 E+02 Number of Nonroutine Reported Measurements Note:

1.

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

2.

Mean and Range based upon detectable measurements only.

Fraction of detectable measurements at specified location is indicated in parentheses (F).

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

PCI/L - 0.037 BQ/L Name of Facility:

SEQUOYAH NUCLEAR PLANT Location of Facility:

HAMILTON TENNESSEE Type and Total Number of Analysis Performed GROSS BETA GAMMA SCAN (GELI)

AC-228 BI-214 K-40 PB-212 PB-214 TL-208 fRITIUM Lower Limit of Detection (LLD)

See Note 1 8

1.90E+00 17 2.00E+01 2.00E+01 1.00E+02 1.50E+01 2.00E+01 1.00E+01 17 2.70E+02 Indicator Locations Mean (F)

Range See Note 2 2.81 E+00 (3/4) 2.30E+00 3.61 E+00 13 VALUES < LLD 4.71 E+01 (7/13) 3.00E+01 7.29E+01 13 VALUES < LLD 13 VALUES < LLD 3.36E+01 (6/13) 2.28E+01 4.44E+01 13 VALUES < LLD 13 VALUES < LLD Location with Highest Name Distance and Direction SQN WELL #6 ONSITE NNE SQN WELL #6 ONSITE NNE SQN WELL #6 ONSITE NNE SQN WELL #6 ONSITE NNE SQN WELL #6 ONSITE NNE SQN WELL #6 ONSITE NNE SQN WELL #6 ONSITE NNE Annual Mean Mean (F)

Range See Note 2 2.81 E+00 (3/4) 2.30E+00 3.61 E+00 13 VALUES < LLD 4.71E+01 (7/13) 3.00E+01 7.29E+01 13 VALUES < LLD 13 VALUES < LLD 3.36E+01 (6/13) 2.28E+01 4.44E+01 13 VALUES < LLD Docket Number:

50-327,328 Reporting Period: 2008 Control Locations Mean (F)

Range See Note 2 8.16E+00 (4/4) 2.11 E+00 1.39E+01 4 VALUES < LLD 4.48E+02 (3/4) 3.15E+02 5.57E+02 4 VALUES < LLD 4 VALUES < LLD 4.34E+02 (3/4) 2.99E+02 5.34E+02 4 VALUES < LLD 4 VALUES < LLD Number of Nonroutine Reported Measurements ffi Note:

1.

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

2.

Mean and Range based upon detectable measurements only.

Fraction of detectable measurements at specified location is indicated in parentheses (F).

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

Name of Facility:

SEQUOYAH NUCLEAR PLANT Location of Facility:

HAMILTON TENNESSEE Docket Number:

50-327,328 Reporting Period: 2008 Type and Total Number of Analysis Performed GAMMA SCAN (GELI)

BI-214 CS-137 K-40 PB-214 Lower Limit of Detection (LLD)

See Note 1 4

1.00E-01 3.00E-02 4.00E-01 5.00E-01 Indicator Locations Mean (F)

Range See Note 2 125E-01 (2/2) 1.13E-01 1.37E-01 3.07E-02 (1/2) 3.07E-02 3.07E-02 1.10E+01 (2/2) 9.20E+00 1.28E+01 2 VALUES < LLD Location with Highest Name Distance and Direction CHICKAMAUGA RES TRM 471-530 CHICKAMAUGA RES TRM 471-530 CHICKAMAUGA RES TRM 471-530 CHICKAMAUGA RES TRM 471-530 Annual Mean Mean (F)

Range See Note 2 1.25E-01 (2/2) 1.13E-0.1 1.37E-01 3.07E-02 (1/2) 3.07E-02 3.07E-02 1.10E+01 (2/2) 9.20E+00 1.28E+01 2 VALUES < LLD Control Locations Mean (F)

Range See Note 2 1.63E-01 (1/2) 1.63E-01 1.63E-01 5.49E-02 (2/2) 4.24E-02 6.73E-02 1.10E+01 (2/2) 1.05E+01 1.14E+01 2 VALUES < LLD Number of Nonroutine Reported Measurements CO ffi Note:

1.

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

2.

Mean and Range based upon detectable measurements only.

Fraction of detectable measurements at specified location is indicated in parentheses (F).

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

Name of Facility:

SEQUOYAH NUCLEAR PLANT Location of Facility:

HAMILTON TENNESSEE Docket Number:

50-327,328 Reporting Period: 2008 Type and Total Number of Analysis Performed GAMMA SCAN (GELI)

BI-214 CS-137 K-40 PB-212 PB-214 Lower Limit of Detection (LLD)

See Note 1 4

1.00E-01 3.00E-02 4.00E-01 4.00E-02 5.00E-01 Indicator Locations Mean (F)

Range See Note 2 1.32E-01 (2/'2) 1.03E-01 1.61E-01 2 VALUES < LLD 1.21E+01 (2/2) 1.01E+01 1.40E+01 2 VALUES < LLD 2 VALUES < LLD Location with Highest Name Distance and Direction CHICKAMAUGA RES TRM 471-530 CHICKAMAUGA RES TRM 471-530 CHICKAMAUGA RES TRM 471-530 CHICKAMAUGA RES TRM 471-530 CHICKAMAUGA RES TRM 471-530 Annual Mean Mean (F)

Range See Note 2 1.32E-01 (2/2) 103E-01 1.61E-01 2 VALUES < LLD 1.21E+01 (2/2) 1.01E+01 1.40E+01 2 VALUES < LLD 2 VALUES < LLD Control Locations Mean (F)

Range See Note 2 1.09E-01 (1/2) 1.09E-01 1.09E-01 5.55E-02 (2/2) 4.35E-02 6.75E-02 129E+01 (2/2) 1.26E+01 1.32E+01 2 VALUES < LLD 2 VALUES < LLD Number of Nonroutine Reported Measurements vo ctT Note:

1.

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

2.

Mean and Range based upon detectable measurements only.

Fraction of detectable measurements at specified location is indicated in parentheses (F).

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

Name of Facility:

Location of Facility:

Type and Total Number of Analysis Performed GAMMA SCAN (GELI)

AC-228 BE-7 BI-212 BI-214 CS-137 K-40 PB-212 PB-214 RA-224 RA-226 TL-208 SEQUOYAH NUCLEAR PLANT HAMILTON TENNESSEE Lower Limit of Detection (LLD)

See Note 1 6

2.50E-01 2.50E-01 4.50E-01 1.50E-01 3.00E-02 7.50E-01 1.00E-01 1.50E-01 7.50E-01 1.50E-01 6.00E-02 Indicator Locations Mean (F)

Range See Note 2 1.27E+00 (4/4) 1.14E+00 1.40E+00 4.45E-01 (1/4) 4.45E-01 4.45E-01 1.25E+00 (4/4) 1.15E+00 1.33E+00 8.43E-01 (4/4) 5.96E-01 1.12E+00 3.83E-02 (1/4) 3.83E-02 3.83E-02 1.91E+01 (4/4) 7.50E+00 3.31 E+01 1.27E+00 (4/4) 1.12E+00 1.38E+00 9.06E-01 (4/4) 6.29E-01 1.19E+00 1.39E+00 (3/4) 1.32E+00 1.44E+00 8.43E-01 (4/4) 5.96E-01 1.12E+00 3.98E-01 (4/4) 3.67E-01 4.23E-01 Location with Highest Name Distance and Direction TRM 479.0 TRM 479.0 TRM 480.0 TRM 480.0 TRM 479.0 TRM 479.0 TRM 479.0 TRM 479.0 TRM 480.0 TRM 480.0 TRM 480.0 TRM 480.0 TRM 480.0 TRM 480.0 TRM 479.0 TRM 479.0 TRM 479.0 TRM 479.0 TRM 479.0 TRM 479.0 TRM 479.0 TRM 479.0 Docket Number:

50-327,328 Reporting Period: 2008 Annual Mean Mean (F)

Range See Note 2 1.34E+00 (2/2) 1.28E+00 1.40E+00 4.45E-01 (1/2) 4.45E-01 4.45E-01 1.30E+00 (2/2) 1.26E+00 1.33E+00 1.06E+00 (2/2) 9.99E-01 1.12E+00 3.83E-02 (1/2) 3.83E-02 3.83E-02 3.01 E+01 (2/2) 2J0E+01 3.31 E+01 1.29E+00 (2/2) 1.25E+00 1.32E+00 1.16E+00 (2/2) 1.12E+00 1.19E+00 1.44E+00 (1/2) 1.44E+00 1.44E+00 1.06E+00 (2/2) 9.99E-01 1.12E+00 4.14E-01 (2/2) 4.05E-01 4.23E-01 Control Locations Mean (F)

Range See Note 2 1.17E+00 (2/2) 8.68E-01 1.47E+00 3.54E-01 (1/2) 3.54E-01 3.54E-01 1.31E+00 (2/2) 8.93E-01 1.72E+00 1.03E+00 (2/2) 6.56E-01 1.40E+00 4.76E-02 (1/2) 4.76E-02 4.76E-02 6.09E+00 (2/2) 3.78E+00 8.40E+00 1.07E+00 (2/2) 7.77E-01 1.37E+00 1.08E+00 (2/2) 6.84E-01 1.48E+00 2 VALUES < LLD 1.03E+00 (2/2) 6.56E-01 1.40E+00 3.82E-01 (2/2) 2.67E-01 4.96E-01 Number of Nonroutine Reported Measurements Note:

1.

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

2.

Mean and Range based upon detectable measurements only.

Fraction of detectable measurements at specified location is indicated in parentheses (F).

25 20 00 s

3 15 o

Q.

X Lit 2

a>

10 5

1970 Direct Radiation Levels Sequoyah Nuclear Plant Four Quarter Moving Average Initial SQNP operation in July, 1980 InLight OSL deployment in Jan 2007 A On-Site

-O-Off-Site o

1975 1980 1985 1990 1995 Calendar Year 2000 2005 2010 2015

Annual Average Gross Beta Activity in Air Filters Sequoyah Nuclear Plant 00 to CO E

o 0.25 r

0.20 0.15 3

0.10 0) 2 0.05 0.00 Initial SQNP Operation in July, 1980

- Indicator

- Control O

I to 1965 1970 1975 1980 Note:

no gross beta measurements w ere made in 1974 1985 1990 Calendar Year 1995 2000 2005 2010

00 3.0 Annual Average Activity ofCs-137inSoil Sequoyah Nuclear Plant Initial SQNP Operation in July, 1980

- Indicator

- Control O

U) 1975 1980 1985 1990 Calendar Year 1995 2000 2005 2010

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

r-o Q.

I 3 5

0 1970 Initial SQNP Operation in July, 1980

- Indicator

- Control o

1975 1980 1985 1990 Calendar Year 1995 2000 2005 2010

00 6.0 5.0 4.0 1.0 0.0 1970 Annual Average Gross Beta Activity in Drinking Water Sequoyah Nuclear Plant Initial SQNP Operation in July, 1980 FVeoperational Average o

- Indicator

- Control 1975 1980 1985 1990 Calendar Year 1995 2000 2005 2010

Annual Average Activity Cs-137 in Game Fish Sequoyah Nuclear Plant oo 0.60 0.50 E

0.40 O

a 0.30 0.20 l

i 0.10 0.00 1970 Initial SQNP Operation in July, 1980

- Dow nstream

- Upstream II o

On 1975 1980 1985 1990 Calendar Year 1995 2000 2005 2010

Annual Average Activity Cs-137 in Shoreline Sediment Sequoyah Nuclear Plant 00 0.30 0.25 2

0.20 o

Q.

I*

0.15 I

0.10 I

0.05 0.00 Note:

Initial SQNP Operation in July, 1980.

There was no preoperational sampling of shoreline sediment

- Dow nstream

- Upstream a

1970 1975 1980 1985 1990 Calendar Year 1995 2000 2005 2010