ML12137A870

Annual Radiological Environmental Operating Report - 2011

ML12137A870
Person / Time
Site:	Watts Bar
Issue date:	05/15/2012
From:	James Shea Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML12137A870 (99)

Text

Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 May 15, 2012 10 CFR 50.4 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 1 Facility Operating License No. NPF-90 NRC Docket No. 50-390

Subject:

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - 2011 In accordance with the requirements of the Watts Bar Nuclear Plant (WBN), Unit 1, Technical Specifications (TS), Section 5.9.2, "Annual Radiological Environmental Operating Report," and the WBN Offsite Dose Calculation Manual (ODCM),

Administrative Control Section 5.1, the WBN, Unit 1,2011 Annual Radiological Environmental Monitoring Program (REMP) results are enclosed. The report, which is required by WBN, Unit 1, TS Section 5.9.2 to be submitted by May 15 of each year, covers the operation of the unit for the January 1, 2011, through the December 31, 2011, time period.

Prior WBN Annual Radiological Environmental Operating Reports included a data supplement, which presented the results of the individual sample analyses and radiation measurements. Since WBN did not find a regulatory basis for the inclusion of the data supplement with the Annual REMP, it is not included with this current submittal.

There are no regulatory commitments in this letter. Please direct any questions concerning this matter to Kara Stacy, Program Manager at (423) 751-3489.

R etfully, a ger, Corporate Nuclear Licensing cc: See Page 2 Printedon recycledpaper

U. S. Nuclear Regulatory Commission Page 2 May 15, 2012

Enclosure:

Annual Radiological Environmental Operating Report - 2011 cc (Enclosure):

NRC Regional Administrator - Region II NRC Senior Resident Inspector - Watts Bar Nuclear Plant, Unit 1 NRC Senior Resident Inspector - Watts Bar Nuclear Plant, Unit 2

Enclosure Watts Bar Nuclear Plant Unit 1 Annual Radiological Environmental Operating Report - 2011

Annual Radiological Environmental Operating Report Watts Bar Nuclear Plant 2011

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

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

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

Introduction ................................................. 3 Naturally Occurring and Background Radioactivity ................. 3 Electric Power Production ..................................... 4 Site/Plant Description .......................................... 7 Radiological Environmental Monitoring Program .................... 9 Direct Radiation Monitoring ..................................... 12 Measurement Techniques ...................................... 12 Results .................................................... 12 Atmospheric Monitoring ...................................... 15 Sample Collection and Analysis ................................ 15 Results .................................................... 16 Terrestrial M onitoring ......................................... 18 Sample Collection and Analysis ................................ 18 Results .................................................... 19 Liquid Pathway Monitoring ..................................... 21 Sample Collection and Analysis ................................ 21 Results .................................................... 22 Assessment and Evaluation ..... ................................ 25 R esults .................................................. 25 Conclusions ................................................ 26 References ................................................... 27 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 ........... 28 Figure 1 Tennessee Valley Region ................................. 29 Figure 2 Environmental Exposure Pathways of Man Due to Releases of Radioactive Materials to the Atmosphere and Lake .................................... 30

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TABLE OF CONTENTS (continued)

Appendix A Radiological Environmental Monitoring Program and Sampling Locations .................................. 31 Appendix B Program Modifications ................................ 42 Appendix C Program Deviations .................................. 44 Appendix D Analytical Procedures ................................ 47 Appendix E Nominal Lower Limits of Detection (LLD) ................ 50 Appendix F Quality Assurance/Quality Control Program ............... 55 Appendix G Land Use Survey .................................... 60 Appendix H Data Tables and Figures .............................. 66

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EXECUTIVE

SUMMARY

This report describes the radiological environmental monitoring program conducted by TVA in the vicinity of the Watts Bar Nuclear Plant (WBN) in 2011. The program includes the collection of samples from the environment and the determination of the concentrations of radioactive materials in the samples. Samples are taken from stations in the general area of the plant and from areas that should not be influenced by plant operations. Material sampled includes air, atmospheric moisture, water, milk, food crops, soil, fish, sediment, and direct radiation levels.

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

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

The majority of environmental radioactivity measured by the program was due to naturally occurring radioactive materials or radionuclides commonly found in the environment as a result of atmospheric fallout and the operation of other nuclear facilities in the area. Low levels of Cesium (Cs)-137 were measured in soil, fish, and shoreline sediment samples. The Cs-137 concentrations were consistent with the preoperational monitoring program results and with levels normally found in the environment as the result of past nuclear weapons testing. Trace levels of tritium were detected in a limited number of atmospheric moisture samples. Tritium at concentrations slightly above the analytical detection limit was also detected in a small 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.

Tritium was detected in onsite ground water monitoring wells. The tritium was the result of onsite ground water contamination from previously identified and repaired leaks in plant systems. In addition, cobalt (Co)-58, cobalt (Co)-60, Cs-137, and antimony (Sb)-125 were identified in sediment collected from the onsite ponds. The level of activity measured in these onsite locations would not present a risk of exposure to the general public.

INTRODUCTION This report describes and summarizes the results of radioactivity measurements made in the vicinity of WBN and laboratory analyses of samples collected in the area. The measurements are made to comply with the requirements of 10 CFR 50, Appendix A, Criterion 64 and 1.0 CFR 50, Appendix I,Section 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 WBN Technical Specification 5.9.2 and Offsite Dose Calculation Manual (ODCM) Administrative Control 5.1.

In addition to reporting the data prescribed by specific requirements, other information is included 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 Most materials in our world today contain trace amounts of naturally occurring radioactivity.

Potassium (K)-40, with a half-life of 1.3 billion years, is one of the major types of radioactive materials found naturally in our environment. Approximately 0.01 percent of all potassium is radioactive potassium-40. Other examples of naturally occurring radioactive materials are beryllium (Be)-7, bismuth (Bi)-212 and 214, lead (Pb)-212 and 214, thallium (Tl)-208, actinium (Ac)-228, uraium (U)-238 and 235, thorium (Th)-234, radium (Ra)-226, radon (Ra)-222, carbon (C) -14, and hydrogen (H)-3 (generally called tritium). These naturally occurring radioactive materials are in the soil, ouir 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 results from cosmic rays.

It is possible to get an idea of the relative hazard of different types of radiation sources by evaluating the amount of radiation the U.S. population receives from each general type of radiation source. The information below is primarily adapted from References 2 and 3.

U.S. GENERAL POPULATION AVERAGE DOSE EQUIVALENT ESTIMATES Source millirem (mrem)/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 I Nuclear energy 0.28 Consumer products 0.03 Total 355 (approximately)

As can be seen from the data presented above, natural background radiation dose equivalent to the U.S. population normally exceeds that from nuclear plants by several hundred times. This indicates that nuclear plant operations normally result in a population radiation, dose equivalent which is insignificant compared to that which results from natural background radiation. It should be noted that the use of radiation and radioactive materials for medical uses has resulted in a similar effective dose equivalent to the U.S. population as that caused by natural background cosmic and terrestrial radiation.

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

Paths through which radioactivity from a nuclear power plant is routinely released are monitored.

Liquid and gaseous effluent monitors record the radiation levels for each release. These monitors also provide alarm mechanisms to prompt termination of any release above limits.

I Releases are monitored at the onsite points of release and through the radiological environmental monitoring program whichmeasures the environmental radiation in areas around the plant. In this way, the release of radioactive materials from the plant is tightly controlled, and verification is provided that the public is not exposed to significant levels of radiation or radioactive materials as the result of plant operations.

The WBN ODCM, which describes the program 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 millirad (mrad)/Year Beta radiation <20 mrad/Year Particulates:

Any organ <15 mrem/Year

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The EPA limits for the total dose to the public in the vicinity of a nuclear power plant, established in the Environmental Dose Standard of 40 CFR 190, are as follows:

Total body <25 mrem/year Thyroid <75 nirem/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 presents the annual average concentration limits for the principal radionuclides associated with nuclear power plant effluents. The table also presents (1) the concentrations of radioactive materials in the environment which would require a special report to the NRC and (2) the detection limits for measured radionculides. It should be noted that the levels of radioactive materials measured in the environment are typically below or only slightly above the lower limit of detection.

SITE/PLANT DESCRIPTION The WBN site is located in Rhea county, Tennessee, on the west bank of the Tennessee River at Tennessee River Mile (TRM) 528. Figure 1 shows the site in relation to other TVA projects.

The WBN site, containing approximately 1770 acres on Chickamauga Lake, is approximately 2 miles south of the Watts Bar Dam and approximately 31 miles north-northeast of TVA's Sequoyah Nuclear Plant (SQN) site. Also located within the reservation are the Watts Bar Dam and Hydro-Electric Plant, the Watts Bar Steam Plant (not in operation), the TVA Central Maintenance Facility, and the Watts Bar Resort Area.

Approximately 16,000 people live within 10 miles of the WBN site. More than 80 percent of these live between 5 and 10 miles from the site. Two small towns, Spring City and Decatur, are located in this area. Spring City, with a population of approximately 2,200, is northwest and north-northwest from the site, while Decatur, with about 1,500 people, is southand south-southwest from the plant. The remainder of the area within 10 miles of the site is sparsely populated, consisting primarily of small farms and individual residences.

The area between 10 and 50 miles from the site includes portions of the cities of Chattanooga and Knoxville. The largest urban concentration in this area is the city of Chattanooga, located to the southwest and south-southwest. The city of Chattanooga has a population of about 170,000, with approximately 80 percent located between 40 and 50 miles from the site and the remainder located beyond 50 miles. The city of Knoxville is located to the east-northeast, with not more than 10 percent of its 185,000 plus people living within 50 miles of the site. Three smaller urban areas of greater than 20,000 people are located between 30 and 40 miles from the site. Oak Ridge is approximately 40 miles to the northeast, the twin cities of Alcoa and Maryville are located 45 to 50 miles to the east-northeast, and Cleveland is located about 30 miles to the south.

Chickamauga Reservoir is one of a series of highly controlled multiple-use reservoirs whose primary uses are flood control, navigation, and the generation of electric power. Secondary uses include industrial and public water supply and waste disposal, fishing, and recreation.

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

WBN consists of two pressurized water reactors. WBN Unit 1 received a low power operating license (NPF-20) on November 9, 1995 and achieved initial criticality in January 1996. The full power operating license (NPF-90) was received on February 7, 1996. Commercial operation was achieved May 25, 1996. WBN Unit 2 was deferred October 24, 2000, in accordance with the guidance in Generic Letter 87-15, "Policy Statement on Deferred Plants." On August 3, 2007, TVA provided notice of its intent to reactivate and complete construction of WBN Unit 2. WBN Unit 2 resumed construction in late 2007, and expects to complete construction and request an operating license by December 2015.

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Most of the radiation and radioactivity generated in a nuclear power reactor is contained within the reactor systems. Plant effluent radiation monitors are designed to monitor radionuclides released to the environment. Environmental monitoring is a final verification that the systems are performing as planned. The monitoring program is designed to monitor the pathways between the plant and the people in the immediate vicinity of the plant. Sample types are chosen so that the potential for detection of radioactivity in the environment will be maximized. The Radiological Environmental Monitoring Program (REMP) and sampling locations for WBN are 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 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 things as the locations of dairy animals and gardens in conjunction with the air pathway analysis. Liquid pathway stations were selected based on dose projections, water use information, and availability of media such as fish and sediment. Table A-2 (Appendix A, Table 2: This notation system is used for all tables and figures given in the appendices.) lists the sampling stations and the types of samples collected from each. There were no modifications made in the WBN REMP in 2011.

Appendix B is included in this report as a place keeper.

Deviations occur in the monitoring program due to equipment problems with automatic sampling systems, and/or sample unavailability. Program deviations to the sampling program during 2011 are included in Appendix C.

To determine the amount of radioactivity in the environment prior to the operation of WBN, a preoperational radiological environmental monitoring program was initiated in December 1976 and operated through December 31, 1995. 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. During the 1950s, 1960s, and 1970s, atmospheric nuclear weapons testing released radioactive material to the environment causing fluctuations in background radiation levels. Knowledge of preexisting radionuclide patterns in the environment permits a determination, through comparison and trending analyses, of the actual environmental impact of WBN operation.

The determination of environmental impact during the operating phase also considers the presence of control stations that have been established in the environment. Results of environmental samples taken at control stations (far from the plant) are compared with those from indicator stations (near the plant) to aid in the determination of the impacts from WBN operation.

The sample analysis is performed by the Tennessee Valley Authority's (TVA's) Environmental Radiological Monitoring and Instrumentation (ERM&I) group located at the Western Area Radiological Laboratory (WARL) in Muscle Shoals, Alabama, except for the strontium (Sr)-89, 90 analysis of soil samples which is performed by a contract laboratory.

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

The Data Supplement to this report contains the results of all measurements made as a part of this program.

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 measurement process is defined in terms of the lower limit of detection (LLD).

A description of the nominal LLDs for the ERM&I laboratory is presented in Appendix E.

The ERM&I laboratory operates under 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 which are included alongside routine environmental samples. To provide for interlaboratory comparison program, the laboratory participates in an environmental cross-check program administered by Eckert and Ziegler Analytics. A complete description of the program is presented in Appendix F.

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

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

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

The dosimeters are placed approximately one meter above the ground, with two at each monitoring location. Sixteen monitor'ing 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 15 miles from the site. The dosimeters are exchanged every three months. Thedosimeters are sent to Landauer InLight for processing and results reporting. The values are corrected for transit and shielded background exposure. An average of the two dosimeter results is calculated for each monitoring point. The system meets or exceeds the performance specifications outlined in American National Standards Institute (ANSI) N545-1975 and Health Physics Society (HPS) Draft Standard N 13.29 for environmental applications of dosimeters.

Results The results for environmental dosimeter measurements are normalized to a standard quarter (91.25 days or 2190 hours0.0253 days <br />0.608 hours <br />0.00362 weeks <br />8.33295e-4 months <br />). The monitoring locations are grouped according to the distance from the plant. The first group consists of all monitoring points within 2 miles of the plant. The second group is made up of a 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 WBN in 2011 are summarized in Table H-1. The exposures are measured in milliroentgens (mR). For purposes of this report, one mR, one mrem and one mrad are assumed to be numerically equivalent.

The rounded average annual exposures, as measured in 2011, are shown below. For comparison purposes, the average direct radiation measurements made in the preoperational phase of the monitoring program are also shown.

Annual WBN Average Direct Radiation Levels mR/Year Preoperational 2011 Average Onsite Stations 72 65 Offsite Stations 66 57 The data in Table H-I indicates that the average quarterly direct radiation levels at the WBN onsite stations are approximately 1.5 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-I compares plots of the data from the onsite stations with those from the offsite stations over the period from 1977 through 2011. The new Landauer InLight Optically Stimulated Luminescence (OSL) dosimeters were deployed since 2007 replacing the Panasonic UD-814 dosimeters used during the previous years.

From January 2007 to December 2010, the REMP OSL dosimeter results reported in the Annual Environmental Operating Reports for these years included the Tungsten shield dose contribution resulting in an over correction. This common industry issue was identified and discussed in a presentation at the June 30, 2011, REMP industry conference. The industry guidance reference to this new method to correct for the shield dose will be incorporated in the upcoming revision of ANSI N13.37, Dosimetry Processing, expected to be issued in 2012. The conclusion from the historical data analysis is that a shield dose contribution of 5.3 mR needs to be added to the on-site and off-site quarterly results reported during 2007-2010. The corrected value is applied both to the on-site (indicator) and off-site (control or background) OSL dosimeter quarterly data; therefore, the corrected value has no effect on the net final results which is based on the difference between the on-site and the off-site values. The correction to add a shield dose contribution of 5.3 mR to the results during 2007-20 10 is included in the 2011 Annual Radiological Environmental Operating Report.

The data in Table H-2 contains the results of the individual monitoring stations. The results reported in 2011 are consistent with direct radiation levels identified at locations which are not influenced by the operation of WBN. There is no indication that WBN 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 between 6 to 11 miles from the plant, and two air monitors are located out to 15 miles and used as control or baseline stations. The monitoring program and the locations of monitoring stations are identified in the tables and figures of Appendix A.

Results from the analysis of samples in the atmospheric pathway are presented in Tables H-3, H-4, and H-5. Radioactivity levels identified in this reporting period are consistent with background and preoperational program data. There is no indication of an increase in atmospheric radioactivity as a result of WBN operations.

Sample Collection and Analysis Air particulates are collected by continuously sampling air at a flow rate of approximately 2 cubic feet per minute (cfm) through a 2-inch glass fiber filter. The sampling system consists of a pump, a magnehelic gauge for measuring the drop in pressure across the system, and a dry gas meter to measure the total volume of air sampled. This system is housed in a building approximately 2 feet by 3 feet by 4 feet. The filter is contained in a sampling head mounted on the outside of the monitoring 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.

Gaseous radioiodine is sampled using a commercially available cartridge containing Triethylenediamine (TEDA)-impregnated charcoal. This system is designed to collect iodine in both the elemental form and as organic compounds. The cartridge is located in the same sampling head as the air particulate filter and is downstream of the particulate filter. The cartridge is changed at the same time as the particulate filter and samples the same volume of air.

Each cartridge is analyzed for 1-131 by gamma spectroscopy analysis.

Atmospheric moisture sampling is conducted by pulling air at a constant flow rate through a column loaded with approximately 400 grams of silica gel. Every two weeks, the column is exchanged on the sampler. The atmospheric moisture is removed from silica gel by heating and analyzed for tritium.

Results The results from the analysis of air particulate samples are summarized in Table H-3. Gross beta activity in 2011 was consistent with levels reported in previous years. The average gross beta activity measured for air particulate samples was 0.022 pCi/m 3 . The annual averages of the gross beta activity in air particulate filters at these stations for the period 1977-2011 are presented in Figure H-2. Increased levels due to fallout from atmospheric nuclear weapons testing are evident in the years prior to 1981 and a small increase from the Chernobyl accident can be seen in 1986. These patterns are consistent with data from monitoring programs conducted by TVA at other nuclear power plant construction sites. Comparison with the same data for the preoperational period of 1990-1995 indicates that the annual average gross beta activity for air particulates as measured in the 2011 monitoring program was consistent with the preoperational data.

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

Only natural radioactive materials were identified by the monthly gamma spectral analysis of the air particulate samples. As shown in Table H-4, 1-131 was not detected in any charcoal cartridge samples collected in 2011.

The results for atmospheric moisture sampling are reported in Table H-5. Tritium was measured in a limited number of atmospheric moisture samples at levels slightly above the nominal LLD value of 3.0 pCi/m 3.

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-6 through H-12.

A land use survey is conducted annually between April and October to identify the location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 square feet producing fresh leafy vegetables in each of 16 meteorological sectors within a distance of 5 miles from the plant. This land use survey satisfies the requirements 10 CFR 50, Appendix I, Section IV.B.3. From data produced by the land use survey, radiation doses are projected for individuals living near the plant. Doses from air submersion are calculated for the nearest residence 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.

These dose projections are hypothetical extremes and do not represent actual doses to the general public. The results of the 2011 land use survey are presented in Appendix G.

Sample Collection and Analysis Milk samples are collected every two weeks from two indicator dairies and from at least one control dairy. Milk samples are placed on ice for transport to the radioanalytical laboratory.

A specific analysis for 1-131 and a gamma spectral analysis are performed on each sample and once per quarter samples are analyzed for Sr-89 and Sr-90.

The monitoring program includes a provision for sampling of vegetation from locations where milk is being produced and when milk sampling cannot be conducted. There were no periods during this year when vegetation sampling was necessary.

Soil samples are collected annually from the air monitoring locations. The samples are collected with either a "cookie cutter" or an auger type sampler. After drying and grinding, the sample is analyzed by gamma spectroscopy. When the gamma analysis is complete, the sample is analyzed for Sr-89 and Sr-90.

Samples representative of food crops raised in the area near the plant are obtained from individual gardens, corner markets, or cooperatives. Types of foods may vary from year to year as a result of changes in the local vegetable gardens. Samples of apples, cabbage, corn, green beans, and tomatoes, were collected from local vegetable gardens and/or farms. Samples of the same food products grown in areas that would not be affected by the plant were collected 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-6. No radioactivity attributable to WBN Plant operations was identified. All 1-131 values were below the established nominal LLD of 0.4 pCi/liter except for the period in April 2011 attributed to the Fukushima event. The results for the quarterly Sr-89, Sr-90 analysis were below the established LLD's for these analyses. The gamma isotopic analysis detected only naturally occurring radionuclides.

Consistent with most of the environment, Cs-137 was detected in the majority of the soil samples collected in 2011. The maximum concentration of Cs-137 was 0.68 pCi/g. The concentrations were consistent with levels previously reported from fallout. All other radionuclides reported were naturally occurring isotopes. The results of the analysis of soil samples are summarized in Table H-7.

A plot of the annual average Cs- 137 concentrations in soil is presented in Figure H-3.

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-I 37, and transport through the environment.

The radionuclides measured in food samples were naturally occurring. The results are reported in Tables H-8 through H-12.

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

The aquatic monitoring program includes the collection of samples of river (surface) water, ground water, drinking water supplies, fish, and shoreline sediment. Indicator samples were collected downstream of the plant and control samples collected within the reservoir upstream of the plant or in the next upstream reservoir (Watts Bar Lake).

Results from the analysis of the liquid pathway samples are presented in Table H-13 through H-19. Radioactivity levels in surface and public water, fish, and shoreline sediment were consistent with background and/or fallout levels previously reported. Low levels of Cs-137 were measured in samples of shoreline sediment and fish. Low levels of tritium were detected in a limited number of water samples collected in Chickamauga Reservoir. Results for the sediment sampling conducted in the onsite ponds and ground water monitoring in onsite wells are discussed later in this section.

Sample Collection and Analysis Samples of surface water are collected from the Tennessee River using automatic sampling systems from two downstream stations and one upstream station. A timer turns on the system at least once every two hours. The line is flushed and a sample collected into a composite container. A one-gallon sample is removed from the container at 4-week intervals and the remaining water is discarded. Each sample is analyzed for gamma-emitting radionculides, gross beta activity, and tritium.

Samples are also collected by an automatic sampling system at the first two downstream drinking water intakes. These samples are collected in the same manner as the surface water samples.

These monthly samples are analyzed for gamma-emitting radionuclides, gross beta activity, and tritium. The samples collected by the automatic sampling device are taken directly from the river at the intake structure. Since the sample at this point is raw water, the upstream surface water sample is used as a control sample for drinking water.

Ground water is sampled from one onsite well down gradient from the plant, one onsite well up gradient from the plant, and four additional onsite ground water monitoring wells located along underground discharge lines. The onsite wells are sampled with a continuous sampling system.

A composite sample is collected from the onsite wells every four weeks and analyzed for gamma-emitting radionuclides, gross beta activity, and tritium content. In addition, a grab sample is collected every four weeks from a private well in an area unaffected by WBN. The grab sample is also analyzed for gross beta activity, gamma-emitting radionuclides, and for 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. The ODCM specifies analysis of the edible portion of the fish. To comply with this requirement, filleted portions are taken from several fish of each species. The samples are analyzed by gamma spectroscopy.

Samples of shoreline sediment are collected from recreation areas in the vicinity of the plant.

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

Samples of sediment are also collected from the onsite ponds. A total of five samples were collected in 2011. The samples are dried, ground, and analyzed by gamma spectroscopy.

Results Gross beta activity was detectable above the nominal LLD in most of the surface water samples.

The gross beta concentrations averaged 3.2 pCi/liter in downstream samples and 2.5 pCi/liter in upstream samples. These levels were consistent with results found during the preoperational monitoring program. Low levels of tritium were detected in a total of three surface water samples. The highest concentration was 621 pCi/liter which was significantly below the EPA drinking water limit of 20,000 pCi/liter. A summary table of the results for surface water samples is shown in Table H- 13. The annual average gross beta activity in surface water samples for the period 1977 through 2011 area presented in Figure H-4.

No fission or activation products were identified by the gamma analysis of drinking water samples from either of two downstream monitoring locations. Average gross beta activity at downstream stations was 2.8 pCi/liter and the average for upstream stations was also 2.5 pCi/liter. Low levels of tritium were detected in a total of six samples collected from the two downstream public water sampling locations. The tritium concentration detected was below the LLD of 270 pCi/liter. The results are shown in Table H-14. Trend plots of the gross beta activity in surface water and drinking water samples from 1977 through 2011 are presented in Figure H-4.

The gamma isotopic analysis of ground water samples identified only naturally occurring radionuclides. Gross beta concentrations in samples from the onsite indicator locations averaged 3.5 pCi/liter. The average gross beta activity for samples from the control locations was 2.5 pCi/liter. Tritium was detected in samples from the onsite monitoring wells located near plant discharge lines. The tritium in onsite ground water was the result of previously identified leaks from plant systems. Repairs were made to resolve the leaks but the plume of contaminated ground water continues to move slowly across the site toward the river. The highest tritium concentration in samples from-these monitoring locations was 2,850 pCi/liter. There was no tritium detected in the onsite up gradient well or the offsite ground water monitoring location.

The results are presented in Table H- 15.

Measurable levels of Cs-137 were identified in a total of six fish samples. The maximum Cs-137 concentration was 0.05 pCi/g measured in game fish collected at one of the downstream locations. Other radioisotopes found in fish were naturally occurring, with the most notable being K-40. The results are summarized in Tables H-16 and H-17. Trend plots of the annual average Cs-137 concentrations measured in fish samples are presented in Figure H-5. The Cs-137 activities are consistent with preoperational results produced by fallout or effluents from other nuclear facilities.

Cs-i 37 consistent with the concentrations present in the environment as the result of past nuclear weapons testing or other nuclear operations in the area was measured in one shoreline sediment sample. The results for the analysis of shoreline sediment is presented in Table H-18. Trend plots of the average concentration of Cs-137 in shoreline sediment are presented in Figure H-6.

Consistent with previous monitoring conducted for the onsite ponds, Cs-137 was detected in the sediment samples. The average of the Cs-137 levels measured in sediment from the onsite ponds was 0.09 pCi/gm. In addition, Co-58, Co-60, Cs-134, and Sb-125 were also detected in some of the samples collected from the onsite ponds. The results for the analysis of pond sediment samples are provided in Table H- 19. Since these radionuclides were present in relatively low concentrations and confined to the ponds located in the owner controlled area not open to the general public, the presence of these radionuclides would not represent an increased risk of exposure to the general public.

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 guidance provided by the NRC in Regulatory Guide 1.109 for determining the potential dose to individuals and populations living in the vicinity of the plant. The results of the effluent dose calculations are reported in the Annual Radiological 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 the "hypothetical" person. The calculated maximum dose 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 result of plant operations, are expected to be negligible. The results for the radiological environmental monitoring conducted for WBN 2011 operations confirm this expectation.

Results As stated earlier in this report, the estimated increase in radiation dose equivalent to the general public resulting from the operation of WBN is insignificant when compared to the dose from natural background radiation. The results from each environmental sample are compared with the concentrations from the corresponding control stations and appropriate preoperational and background data to determine influences from the plant. During this report period, Cs-137 was detected in shoreline sediment, soil, and fish collected for the WBN program. The Cs-137 concentrations were consistent with levels measured during the preoperational monitoring program. The low levels of tritium measured in water samples from Chickamauga Reservoir represented concentrations that were a small fraction of the EPA drinking water limit.

The levels of tritium detected in the onsite ground water monitoring wells and the radionuclides measured in samples of sediment from the onsite ponds do not represent an increased risk of exposure to the public. These radionuclides were limited to the owner controlled area and would not present an exposure pathway for the general public.

Conclusions It is concluded from the above analysis of environmental samples and from the trend plots presented in Appendix H, that exposure to members of the general public which may have been attributable to WBN is negligible. The radioactivity reported herein is primarily the result of fallout or natural background. Any activity which may be present in the environment as a result of plant operations does not represent a significant contribution to the exposure of members of the public.

REFERENCES

1. Merril Eisenbud, Environmental Radioactivity, Academic Press, Inc., New York, NY, 1987.

2. National Council on Radiation Protection and Measurements, Report No. 93, "Ionizing Radiation Exposure of the Population of the United States," September 1987.

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

Table 1 COMPARISON OF PROGRAM LOWER LIMITS OF DETECTION WITH THE REGULATORY LIMITS FOR MAXIMUM ANNUAL AVERAGE EFFLUENT CONCENTRATIONS RELEASED TO UNRESTRICTED AREAS AND REPORTING LEVELS Concentrations in Water, pCi/Liter Concentrations in Air, pCi/Cubic Meter Effluent Reporting Lower limit Effluent Reporting Lower limit Analysis Concentration' Level 2 of Detection 3 Concentration' Level 2 of Detection3 H-3 1,000,000 20,000 270 100,000 3.00 Cr-51 500,000 45 30,000 0.02 Mn-54 30,000 1,000 5 1,000 0.005 Co-58 20,000 1,000 5 1,000 0.005 Co-60 3,000 300 5 50 0.005 Zn-65 5,000 300 10 400 0.005 Sr-89 8,000 5 1,000 0.0011 Sr-90 500 2 6 0.0004 Nb-95 30,000 400 5 2,000 0.005 Zr-95 20,000 400 10 400 0.005 Ru-103 30,000 5 900 0.005 Ru-106 3,000 40 20 0.02 1-131 1,000 2 0.4 200 0.9 0.03 Cs- 134 900 30 5 200 10 0.005 Cs-137 1,000 50 5 200 20 0.005 Ce-144 3,000 30 40 0.01 Ba- 140 8,000 200 25 2,000 0.015 La-140 9,000 200 10 2,000 0.01 Note: I pCi = 3.7 x10-2 Bq.

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

1. Source: Table 2 of Appendix B to 10 CFR 20.1001-20.2401

2. Source: WBN Offsite Dose Calculation Manual, Table 2.3-2.

3. Source: Table E-1 of this report.

I TENNESSEE VALLEY REGIOI (TVA NUCLEAR PLANT SITES) t'j C'D

.1

Figure 2 ENVIRONMENTAL EXPOSURE PAT'HWAYS OF MAN DUE TO RELEASES OF RADIOACTIVE MATERIAL TO THE ATMOSPHERE AND LAKE.

ore Airborne Releases Plume Exposure Liquid Releases Diluted By Lake MAN H Consumed By Man Animals (MilkMeat) Shoreline Exposure Consumed Drikin By Animals i 7

Drinking Water I Fish Vegetation Uptake From Soil APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM AND SAMPLING LOCATIONS Table A-I WATTS BAR NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMa Exposure Pathway Number of Samples and Sampling and Type and Frequency and/or Sample Locations b Collection Frequency of Analysis

1. AIRBORNE

a. Particulates 4 samples from locations (in different Continuous sampler operation with Analyze for gross beta radioactivity sectors) at or near the site boundary sample collection weekly (more greater than or equal to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (LM-1, 2, 3, and 4). (frequently if required by dust following filter change. Perform loading). gamma isotopic analysis on each sample if gross beta is greater than 10 times yearly mean of control sample.

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

4 samples from communities I'.)

approximately 6-10 miles from the plant (PM-2, 3, 4, and 5).

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

b. Radioiodine Samples from same locations as air Continuous sampler operation with 1-131 at least once per 7 days.

particulates. filter collection weekly. Analysis is performed by gamma spectroscopy.

c. Atmospheric 4 samples from locations (in different Continuous sampler operation with Analyze each sample for tritium.

Moisture sectors) at or near the site boundary sample collection biweekly.

(LM-1, 2, 3, and 4) 2 samples from communities approximately 4-10 miles distance from the plant (PM-2, 5).

Table A- I WATTS BAR NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMa Exposure Pathway Number of Samples and Sampling and Type and Frequency and/or Sample Locationsb Collection Frequency of Analysis

c. Atmospheric 2 samples from control location Moisture (Cont.) greater than 10 miles from the plant (RM-2 and RM-3).

d. Soil Samples from same location as air Once per year. Gamma scan, Sr-89, Sr-90 once per particulates. year.

2. DIRECT 2 or more dosimeters placed at or At least once per 92 days. Gamma dose at least once per 92 near the site boundary in each of the days.

16 sectors.

2 or more dosimeters placed at stations located approximately 5 miles from the plant in each of the 16 sectors.

2 or more dosimeters in at least 8 additional locations of special interest, including at least 2 control stations.

Table A- I WATTS BAR NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMa Exposure Pathway Number of Samples and Sampling and Type and Frequency and/or Sample Locationsb Collection Frequency of Analysis

3. WATERBORNE

a. Surface 2 samples downstream from plant Collected by automatic sequential- Gross beta, gamma scan, and tritium discharge (TRM 517.9 and TRM type sampler' with composite samples analysis of each sample.

523.1). collected over a period of approximately 31 days.

I sample at a control location upstream from the plant discharge (TRM 529.3).

b. Ground Five sampling locations from ground Collected by automatic sequential- Gross beta, gamma scan, and tritium water monitoring wells adjacent to the type sampler with composite samples analysis of each sample.

plant (Wells No. 1, A, B, C, and F). collected over a period of approximately 31 days.

1 sample from ground water source Same as Well No. 1. Gross beta, gamma scan, and tritium up gradient (Well No. 5). analysis of each sample.

I sample from ground water source Grab sample at least once per 31 Gross beta, gamma scan, and tritium offsite (Farm L). days. analysis of each sample.

c. Drinking 1 sample at the first two potable Collected by automatic sequential- Gross beta, gamma scan, and tritium surface water supplies, downstream type sampler' with composite sample analysis of each sample.

from the plant (TRM 503.8 and TRM collected monthly.

473.0).

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

c. Drinking (Con't) I sample at a control location TRM 52 9 .3d.

d. Sediment from I sample downstream from plant At least once per 184 days. Gamma scan of each sample.

Shoreline Discharge (TRM 513.0).

1 sample from a control location upstream from plant discharge (TRM 530.2).

e. Pond Sediment 1 sample from at least three locations At least once per year. Gamma scan of each sample.

in the Yard Holding Pond.

5. INGESTION

a. Milk 1 sample from milk producing animals Every 2 weeks. 1-131 and gamma analysis on each in each of 1-3 areas indicated by the sample. Sr-89 and Sr-90 once per cow census were doses are calculated quarter.

to be highest.

I or more samples from control locations,

b. Fish One sample of commercially important At least once per 184 days. Gamma scan on edible portions.

species and one sample of recreationally important species.

One sample of each species from Chickamauga and Watts Bar Reservoirs.

Table A-I WATTS BAR NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples and Sampling and Type and Frequency and/or Sample Locationsb Collection Frequency of Analysis

c. Vegetation" Samples from farms producing milk At least once per 31 days. 1-131 analysis and gamma scan of (Pasturage and but not providing a milk sample. each sample.

grass)

d. Food Products I sample each of principal food Annually at time of harvest. The Gamma scan on edible portion.

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

Cabbage, Lettuce and/or Greens Corn Green Beans Potatoes Tomatoes

a. The sampling program outlined in this table is that which was in effect at the end of 2011.

b. Sample locations are shown on Figures A-1, A-2, A-3.

c. 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 samples collected at TRMs 503.8 and 473.0 are taken from the raw water supply, therefore, the upstream surface water sample will be considered the control sample for drinking water.

e. Vegetation sampling is applicable only for farms that meet the criteria for milk sampling and when milk sampling cannot be performed.

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

Location Distance or Samples Number' Station Sector (Miles) Control (C) Collectedb 2 PM-2 NW 7.0 1 AP,CF,S,AM 3 PM-3 NNE 10.4 I AP,CF,S 4 PM-4 NE/ENEc 7.6 I AP,CF,S 5 PM-5 S 8.0 I AP,CF,S,AM 6 RM-2 SW 15.0 C AP,CF,S,AM 7 RM-3 NNW 15.0 C AP,CF,S,AM 8 LM-1 SSW 0.5 1 AP,CF,S,AM 9 LM-2 NNE 0.4 1 AP,CF,S,AM 10 LM-3 NNE 1.9 1 AP,CF,S,AM 11 LM-4 SE 0.9 I AP,CF,S,AM 12 Farm L SSW 1.3 id M,W 15 Farm K ENE 11.6 C M 18 Well#I S 0.6 I W 20 Farm N ESE 4.1 I M 22 Farm EH SSW 24.0 C M 23 Well #5 N 0.5 C W 25 TRM 517.9 -- 9.9e I SW 26 TRM 523.1 -- 4.7e I SW 27 TRM 529.3 -- 1.5e C SW,PW`

31 TRM 473.0 54.8a I PW (C. F. Industries) 32 TRM 513.0 -- 14.8e I SS 33 TRM 530.2 -- 2.4e C Ss 35 TRM 503.8 -- 24.0e I PW (Dayton) 37 TRM 522.8-527.8 .. F (downstream of WBN) 38 TRM 471-530 -- -- F (Chickamauga Lake) 39 Watts Bar Reservoir C F 81 Yard Pond SSE/S/SSW Onsite I PS 82 Well A SSE 0.6 I W 83 Well B SSE 0.5 1 W 84 Well C ESE 0.3 I W 85 Well F SE 0.3 I W

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

b. Sample codes:

AM = Atmospheric Moisture AP = Air particulate filter PW = Public Water SS = Shoreline sediment CF = Charcoal filter PS = Pond Sediment SW = Surface water F = Fish S = Soil W = Well water M = Milk

c. Station located on the boundary between these two sectors.

d. A control for well water.

e. Distance from the plant discharge (TRM 527.8)

f. The surface water sample is also used as a control for public water.

Table A-3 WATTS BAR NUCLEAR PLANT ENVIRONMENTAL DOSIMETERS LOCATIONS Mapa Approximate Onsite (On)b Location Distance or Number Station Sector (Miles) Offsite (Off) 2 NW-3 NW 7.0 Off 3 NNE-3 NNE 10.4 Off 4 ENE-3 NE/ENE 7.6 Off 5 S-3 S 7.8 Off 6 SW-3 SW 15.0 Off 7 NNW-4 NNW 15.0 Off 10 NNE-1A NNE 1.9 On 11 SE-iA SE 0.9 On 12 SSW-2 SSW 1.3 On 14 W-2 W 4.8 Off 40 N-i N 1.2 On 41 N-2 N 4.7 Off 42 NNE-I NNE 1.2 On 43 NNE-2 NNE 4.1 Off 44 NE-I NE 0.9 On 45 NE-2 NE 2.9 Off 46 NE-3 NE 6.1 Off 47 ENE-I ENE 0.7 On 48 ENE-2 ENE 5.8 Off 49 E-I E 1.3 On 50 E-2 E 5.0 Off 51 ESE-1 ESE 1.2 On 52 ESE-2 ESE 4.4 Off 54 SE-2 SE 5.3 Off 55 SSE-IA SSE 0.6 On 56 SSE-2 SSE 5.8 Off 57 S-1 S 0.7 On 58 S-2 S 4.8 Off 59 SSW-! SSW 0.8 On 60 SSW-3 SSW 5.0 Off 62 SW-I SS 0.8 On 63 SW-2 SW 5.3 Off 64 WSW-I WSW 0.9 On 65 WSW-2 WSW 3.9 Off 66 W-1 W 0.9 On 67 WNW-1 WNW 0.9 On 68 WNW-2 WNW 4.9 Off 69 NW-I NW 1.1 On 70 NW-2 NW 4.7 Off 71 NNW-I NNW 1.0 On 72 NNW-2 NNW 4.5 Off 73 NNW-3 NNW 7.0 Off 74 ENE-2A ENE 3.5 Off 75 SE-2A SE 3.1 Off 76 S-2A S 2.0 Off 77 W-2A W 3.2 Off 78 NW-2A NW 3.0 Off 79 SSE-l SE 0.5 On

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

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

Figure A- I Radiological Environmental Sampling Locations Within I Mile of the Plant NW 348.75 N 11.25 N

!6.25 7133.75 27 56.25 INUCLEAR PLANT E

• /* ,,*101.25 79*ESE

• 5 SiE 213.75 146,25 SSW SSE 191.25 s 168.75 0 Los Figure A-2 Radiological Environmental Sampling Locations From 1 to 5 Miles From The Plant Scale 0 I 2 Ma..

Figure A-3 Radiological Environmental Sampling Locations Greater Than 5 Miles From the Plant APPENDIX B PROGRAM MODIFICATIONS Appendix B Radiological Environmental Monitoring Program Modification There were no modifications to the WBN REMP during 2011.

APPENDIX C PROGRAM DEVIATIONS Appendix C Program Deviations Table C-I provides the information on missed samples. A review of the details of the program deviations did not identify any adverse trend in equipment performance.

Table C-1 Radiological Environmental Monitoring Program Deviations Sample Date Station Location T Description 04/25/11 TRM 530.2 TRM 530.2 Shoreline The shoreline sediment samples were unable to be collected in April 2011.

TRM 513 TRM 513 Sediment Normally, these samples are collected every 184 days when the river levels are decreased. This was documented by PER 452744.

09/06/11 TRM 529.3 TRM 529.3 Water There was no sample collected at Station 3133 TRM 529.3 (Old WB Steam Plant) for 0-PI-CEM-12.0. The issue was identified as a malfunctioning pump that was unable to collect the required sample. The pump has since been restored and is collecting sample as expected. This was documented by PER 457413.

09/26/11 PM-4 7.6 MILES AF/CF* Plug loose, belt shredded. Replaced belt, performed PM and returned to service.

NE/ENE This was documented by PER 465231.

10/03/11 PM-4 7.6 MILES AF/CF* Station PM-4 (Ten Mile, TN) was discoved having no flow during the sampling NE/ENE period for O-PI-CEM-12.0. It was noted that the wheel and belt were both off of the pump causing a malfunction. The pump has since been fixed, and and the sampler has been returned to normal operation. This was documented by PER 457414.

11/07/11 LM-3 1.9 Miles NNE AF/CF* During performance of O-PI-CEM-12.0 it was noted that the pump to the air sampler at LM-3 (REMP sample at dam) had stopped working during a sampling period, affecting the volume of sample collected for the week.

Pump was replaced and put back in-service. This was documented by PER 460355.

• AF = Air Filter, CF = Charcoal Filter

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, except for the Sr-89, 90 analysis of soil samples which was performed by a contract laboratory. 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 milliliter (ml) of samples to near dryness, transferring to a stainless steel planchet, and completing the evaporation process. Air particulate filters are counted directly in a shallow planchet.

The specific analysis of 1-131 in milk is performed by first isolating and purifying the iodine by radiochemical separation and then counting the final precipitate on a beta-gamma coincidence counting system. The normal count time is 50 minutes. With the beta-gamma coincidence counting system, background counts are virtually eliminated and extremely low levels of activity can be detected.

After a radiochemical separation, milk samples analyzed for Sr-89, 90 are counted on a low background beta counting system. The sample is counted a second time after a 7-day ingrowth period. 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 high resolution gamma spectroscopy 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.

Atmospheric moisture samples are collected on silica gel from a metered air flow. The moisture is released from the silica gel by heating and a portion of the distillate is counted by liquid scintillation for tritium using commercially available scintillation cocktail.

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 Appendix E Nominal Lower Limits of Detection A number of factors influence the Lower Limit of Detection (LLD), 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 in accordance with the methodology prescribed in the ODCM, are presented in Table E-1. The maximum LLD values for the lower limits of detection specified in the ODCM are shown in Table E-2.

The nominal LLD values are also presented in the data tables. For analyses for which nominal LLDs have not been established, an LLD of zero is assumed in determining if a measured activity is greater than the LLD.

TABLE E-1 Nominal LLD Values A. Radiochemical Procedures Sediment Air Filters Water Milk Wet Vegetation and Soil Analysis 3 wl/m ) (p j/L) (pCiIL) (pCi/kg wet) (pCi/g dry)

Gross Beta 0.002 1.9 --

Tritium 3.0 270 -- --.

Iodine- 131 -- 0.4 0.4 6.0 --

Strontium-89 0.0011 5.0 3.5 31.0 1.6 Strontium-90 0.0004 2.0 2.0 12.0 0.4 Table E- 1 Nominal LLD Values B. Gamma Analyses Foods Particulate Charcoal Water Vegetation Wet Soil and Tomatoes Filter3 Filter and Milk and Grain Vegetation Sediment Fish Clam Flesh Potatoes, etc.

Analysis pCi/m pCi/m3 Cii/L pCi/., dry pCi/kg. wet pCi/g. dry pCi/g, dry pCi/kg, wet pCi/g. dry Ce-141 .005 .02 10 .07 35 .10 .07 .35 20 Ce-144 .01 .07 30 .15 115 .20 .15 .85 60 Cr-51 .02 0.15 45 .30 200 .35 .30 2.40 95 1-131 .005 0.03 10 .20 60 .25 .20 1.70 20 Ru-103 .005 0.02 5 .03 25 .03 .03 .25 25 Ru- 106 .02 0.12 40 .15 190 .20 .15 1.25 90 Cs-134 .005 0.02 5 .03 30 .03 .03 .14 10 Cs-137 .005 0.02 5 .03 25 .03 .03 .15 10 Zr-95 .005 0.03 10 .05 45 .05 .05 .45 45 Nb-95 .005 0.02 5 .25 30 .04 .25 .25 10 Co-58 .005 0.02 5 .03 20 .03 .03 .25 10 t Mn-54 .005 0.02 5 .03 20 .03 .03 .20 10 Zn-65 .005 0.03 10 .05 45 .05 .05 .40 45 Co-60 .005 0.02 5 .03 20 .03 .03 .20 10 K-40 .04 0.30 100 .40 400 .75 .40 3.50 250 Ba-140 .015 0.07 25 .30 130 .30 .30 2.40 50 La-140 .01 0.04 10 .20 50 .20 .20 1.40 25 Fe-59 .005 0.04 10 .08 40 .05 .08 .45 25 Be-7 .02 0.15 45 .25 200 .25 .25 1.90 90 Pb-212 .005 0.03 15 .04 40 .10 .04 .30 40 Pb-214 .005 0.07 20 .50 80 .15 .50 .10 80 Bi-214 .005 0.05 20 .10 55 .15 .10 .50 40 Bi-212 .02 0.20 50 .25 250 .45 .25 2.00 130 TI-208 .002 0.02 10 .03 30 .06 .03 .25 30 Ra-224 .75 Ra-226 .15 Ac-228 .01 0.07 20 .10 70 .25 .10 .75 50

Table E-2 Maximum LLD Values Specified by the WBN ODCM Airborne Particulate Food Water or Gases Fish Milk Products Sediment Analysis DCi/L pCi/zm 3 pCi/kn. wet 1Ci/L pCi/ks. wet pCi/kn, dry gross beta 4 I x 10-2 N.A. N.A. N.A. N.A.

H-3 2000a N.A. N.A. N.A. N.A. N.A.

Mn-54 15 N.A. 130 N.A. N.A. N.A.

Fe-59 30 N.A. 260 N.A. N.A. N.A.

Co-58,60 15 N.A. 130 N.A. N.A. N.A.

Zn-65 30 N.A. 260 N.A. N.A. N.A.

Zr-95 30 N.A. N.A. N.A. N.A. N.A.

Nb-95 15 N.A. N.A. N.A. N.A. N.A.

1b 1-131 7x 10-2 N.A. 1 60 N.A.

2 Cs-134 15 5 X10" 130 15 60 150 Cs-137 18 6x 10-2 150 18 80 180 Ba- 140 60 N.A. N.A. 60 N.A. N.A.

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

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

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

APPENDIX F QUALITY ASSURANCE/QUALITY CONTROL PROGRAM Appendix F Quality Assurance/Quality Control Program A quality assurance program is employed by the laboratory to ensure that the environmental monitoring data are reliable. This program includes the use of written, approved procedures in performing the work, provisions for staff training and certification, internal self assessments of program performance, audits by various external organizations, and a laboratory quality control program.

The quality control program employed by the radioanalytical laboratory is designed to ensure that the sampling and analysis process is working as intended. The program includes equipment checks and the analysis of quality control samples along with routine samples. Instrument quality control checks include background count rate and counts reproducibility. In addition to these two general checks, other quality control checks are performed on the variety of detectors used in the laboratory. The exact nature of these checks depends on the type of device and the method it uses to detect radiation or store the information obtained.

Quality control samples of a variety of types are used by the laboratory to verify the performance of different portions of the analytical process. These quality control samples include blanks, replicate samples, analytical knowns, blind samples, and cross-checks.

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

Duplicate samples are generated at random by the sample computer program which schedules the collection of the routine samples. For example, if the routine program calls for four milk samples every week, on a random basis each farm might provide an additional sample several times a year. These duplicate samples are analyzed along with other routine samples. They provide information about the variability of radioactive content in the various sample media.

If enough sample is available for a particular analysis, the laboratory staff can split it into two portions. Such a sample provides information about the variability of the analytical process since two identical portions of material are analyzed side by side.

Analytical knowns are another category of quality control sample. A known amount of radioactivity is added to a sample medium. The lab staff knows the radioactive content of the sample. Whenever possible, the analytical knowns contain the same amount of radioactivity each time they are run. In this way, analytical knowns provide immediate data on the quality of the measurement process.

Blind spikes are samples containing radioactivity which are introduced into the analysis process disguised as ordinary environmental samples. The lab staff does not know the sample contains radioactivity. Since the bulk of the ordinary workload of the environmental laboratory contains no measurable activity or only naturally occurring radioisotopes, blind spikes can be used to test the detection capability of the laboratory or can be used to test the data review process. If an analysis routinely generates numerous zeroes for a particular isotope, the presence of the isotope is brought to the attention of the laboratory supervisor in the daily review process.

Blind spikes test this process since the blind spikes contain radioactivity at levels high enough to be detected. Furthermore, the activity can be put into such samples at the extreme limit of detection (near the LLD) to verify that the laboratory can detect very low levels of activity.

Another category of quality control samples is the internal cross-checks. These samples have a known amount of radioactivity added and are presented to the lab staff labeled as cross-check samples. This means that the quality control staff knows the radioactive content or "right answer" but the lab personnel performing the analysis do not. Such samples test the best -

performance of the laboratory by determining if the lab can find the "right answer." These samples provide information about the accuracy of the measurement process. Further information is available about the variability of the process if multiple analyses are requested on the same sample. Like blind spikes or analytical knowns, these samples can also be spiked with low levels of activity to test detection limits. The analysis results for internal cross-check samples met program performance goals for 2011.

I To provide for an independent verification of the laboratory's ability to make accurate measurements, the laboratory participated in an environmental level cross-check program available through Eckert and Ziegler Analytics during 2011. The results of TVA's participation in this cross-check program are presented in Table F-1. The results for these cross-check samples were all within the program agreement limits.

The quality control data are routinely collected, examined and reported to laboratory supervisory personnel. They are checked for trends, problem areas, or other indications that a portion of the analytical process needs correction or improvement. The end result is a measurement process that provides reliable and verifiable data and is sensitive enough to measure the presence of radioactivity far below the levels which could be harmful to humans.

Table F-I Results For 2011 External Cross Checks Results Test Period Samole Tvye / Analysis Known TVA Aeernent First Quarter Water (pCi/L)

Gross Beta 2.47E+02 2.23E+02 Yes First Quarter Water (pCi/L) 3 H 4.53E+03 5,73E+03 Yes First Quarter Water (pCi/L) 1311 9.40E+01 9.01E+01 Yes 5tCr 1.96E+02 2.02E+02 Yes 134Cs 8.56E+01 7.94E+0I Yes 137Cs 1.35E+02 1.36E+02 Yes 5

SCo 7.44E+01 7.57E+01 Yes 54Mn 1.75E+02 1.79E+02 Yes 59Fe I. 15E+02 1.34E+02 Yes 65Zn 1.72E+02 1.72E+02 Yes 6

°Co 1.13E+02 1.16E+02 Yes Second Quarter Synthetic Urine (pCi/L) 3 H 1.OOE+04 1.02E+04 Yes Third Quarter Milk (pCi/L) 1311 1.013E+02 1.03E+02 Yes Third Quarter Water (pCi/L) 3 H 9.01E+03 9.41E+03 Yes Third Quarter Sand (pCi/gram) 141Ce 1.59E-01 1.56E-01 Yes 5

Cr 5.39E-01 5.03E-01 Yes 34 1 Cs 3.05E-01 2.67E-01 Yes 17Cs 2.71E-01 2.60E-01 Yes 58 Co 2.32E-01 2.15E-01 Yes 54Mn 3.59E-01 3.52E-01 Yes 9

' Fe 1.31E-01 1.23E-01 Yes 6

5Zn 4.30E-01 4.31E-0I Yes

'Co 3.74E-01 3.61E-01 Yes Third Quarter Air Filter (pCi/Filter)

Gross Beta 9.36E+01 8.91E+0I Yes Third Quarter Air Filter (pCi/Filter) 141Ce 6.51E+01 6.07E+-01 Yes 5'Cr 2.21E+02 2.03E+02 Yes 3Cs 1.25E+02 1.04E+02 Yes 137Cs 1.11E+02 1.03E+-02 Yes 58 Co 9.51E+01 8,94E+01 Yes 54Mn 1.47E+02 1.48E+02 Yes 55 Fe 5.35E+01 4.75E+01 Yes 65 Zn 1.76E+02 1.83E+02 Yes

'Co 1.53E+02 1.44E+02 Yes Third Quarter Water (pCi/L)

Gross Beta 2.49E+02 2.41E+02 Yes Fourth Quarter Milk (pCi/L) 1311 9.OOE+01 9.87E+01 Yes 89 Sr 8.93E+01 8&23E+01 Yes 9°Sr 1.48E+01 1.48E+01 Yes APPENDIX G LAND USE SURVEY Appendix G Land Use Survey A land use survey was conducted in accordance with the provisions of ODCM Control 1.3.2 to identify the location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 square feet producing fresh leafy vegetables in each of 16 meteorological sectors within a distance of 5 miles (8 km) from the plant.

The land use survey was conducted between April 1, 2011, and October 1, 2011, 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 the survey data, relative radiation doses were projected for individuals near the plant.

Doses from air submersion were calculated for the nearest resident in each sector, while doses from drinking milk or eating foods produced near the plant were calculated for the areas with milk producing animals and gardens, respectively. These doses were calculated using historical meteorological data. They also assume that the effluent 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 WBN.

In response to the 2011 WBN land use survey, annual doses were calculated for air submersion, vegetable ingestion, and milk ingestion. The location of nearest resident changed in two sectors during 2011. In addition, the location of the nearest garden changed in a total of five sectors.

There were no changes in the location for milk ingestion.

As in previous years, the owner of Farm Ho did not want to participate in the milk sampling.

Milk samples were obtained from the farm between Farm Ho and the plant.

The results for the calculated relative dose changed slightly for one garden location and one milk cow location due to small corrections in the terrain adjustment factor for the location. In both cases, there was no change in the actual location.

The results of the 2011 land use survey and resulting relative projected annual dose calculations documented that there were no significant changes in land use of unrestricted areas. No required changes in the sampling locations for the radiological environmental monitoring program were identified as result of the land use survey.

Tables G-1, G-2, and G-3 compare results of the relative projected annual dose calculations for 2010 and 2011.

Table G-I Watts Bar Nuclear Plant Relative Projected Annual Air Submersion Dose to the Nearest Residence Within 8 km (5 Miles) of Planta mtero/year 2011 2010 Approximate Approximate Sector Distance (Meters) Annual Dose Distance (Meters) Annual Dose N 4,580 0.07 2,134 0.24 NNE 3,760 0.21 3,600 0.22 NE 3,353 0.27 3,353 0.27 ENE 3,059 0.30 3,059 0.30 E 3,268 0.26 3,268 0.26 ESE 4,416 0.16 4,416 0.16 SE 1,372 0.75 1,372 0.75 SSE 1,524 0.36 1,524 0.36 S 1,585 0.38 1,585 0.38 SSW 1,979 0.28 1,979 0.28 SW 4,186 0.09 4,186 0.09 WSW 1,829 0.29 1,829 0.29 W 2,896 0.05 2,896 0.05 WNW 1,449 0.19 1,449 0.18 NW 2,077 0.08 2,077 0.08 NNW 4,389 0.02 4,389 0.02

a. Assumes the effluent releases are equivalent to design basis source terms.

I

Table G-2 Watts Bar Nuclear Plant

• Relative Projected Annual Ingestion Dose to Child's Bone Organ from Ingestion of Home-Grown Foods Nearest Garden Within 8 km (5 Miles) of Plant' mrem/year 2011 2010 Approximate Approximate Sector Distance (Meters) Annual Dose Distance (Meters) Annual Dose N 7,567 0.51 7,567 0.24 NNE 4,010 4.47 4,991 0.22 NE 3,353 5.87 3,353 0.27 ENE 5,010 2.44 6,782 0.30 E 4,669 3.08 4,669 0.26 ESE 4,780 3.06 4,780 0.16 SE 1,372 14.8 1,372 0.75 SSE 1,771 6.43 1,771 0.36 S 3,542 2.78 3,542 0.38 SSW 2,286 5.51 2,286 0.28 SW b b 0.09 WSW 3,060 2.80 4,667 0.29 W 3,470 0.85 4,669 0.05 WNW 3,059 1.08 3,059 0.18 NW 2,077 1.63 2,077 0.08 NNW 4,920 0.45 4,602 0.02

a. Assumes the effluent releases are equivalent to design basis source terms.

b. Garden not identified within 8, km (5 miles) of the plant in this sector.

Table G-3 Watts Bar Nuclear Plant Relative Projected Annual Dose to Receptor Thyroid from Ingestion of Milk' (Nearest Milk-Producing Animal Within 8km (5 Miles) of Plant) mrem/year Approximate Distance Annual Dose X/Q3 Location Sector Meters 2011 2010 s/mr Cows Farm Nb ESE 6,706 0.06 0.03 7,97 E-7 Farm Lb SSW 2,286 0.27 0.14 2.36 E-6 Farm Hoc SSW 3,353 0.31 0.16 6.80 E-7

a. Assumes the plant is operating and effluent releases are equivalent to design basis source terms.

b. Milk being sampled at these locations.

C. Owner unwilling to provide samples or information. The dose calculated assumes consumption of the milk by an adult and a feeding factor equivalent to 33 percent. If milk from this location were to be consumed by teens, children or infants, the estimated doses would be 0.25, 0.51 and 1.22 mrem/year, respectively.

APPENDIX H DATA TABLES AND FIGURES Table H-1 DIRECT RADIATION LEVELS Average External Gamma Radiation Levels at Various Distances from Watts Bar Nuclear Plant for Each Quarter - 2011 mR / Quarter (a)

Average External Gamma Radiation Levels (b) 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr mR / Yr Average 0 - 2 miles 18.4 18.6 18.4 16.3 72 (onsite)

Average

> 2 miles 16.6 17.5 16.8 14.9 66 (offsite)

(a). Field periods normalized to one standard quarter (2190 hours0.0253 days <br />0.608 hours <br />0.00362 weeks <br />8.33295e-4 months <br />)

(b). Average of the individual measurements in the set Table H-2 (1 of 2)

DIRECT RADIATION LEVELS Individual Stations at Watts Bar Nuclear Plant Environmental Radiation Levels mR /Quarter Map Dosimeter Approx 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Annual(')

Location Station Direction, Distance, Jan-Mar Apr-Jun Jul-Sep Oct-Dec Exposure Number Number degrees miles 2011 2011 2011 2011 mR/Year 40 N-1 10 1.2 18.8 19.5 21.2 17.9 77.4 41 N-2 350 4.7 18.8 20.5 16.1 14.0 69.4 42 NNE-1 21 1.2 18.8 17.1 19.7 17.0 72.6 10 NNE-1A 22 1.9 17.1 18.1 15.0 14.5 64.7 43 NNE-2 20 4.1 14.4 15.1 16.1 15.5 61.1 3 NNE-3 17 10.4 19.3 18.1 17.6 14.5 69.5 44 NE-1 39 0.9 20.4 23.9 19.1 19.9 83.3 90 45 NE-2 54 2.9 18.2 18.5 20.7 17.0 74.4 46 NE-3 47 6.1 13.9 15.1 13.0 12.0 54.0 47 ENE-1 74 0.7 17.1 17.6 19.1 18.9 72.7 48 ENE-2 69 5.8 16.1 20.5 14.0 12.0 62.6 74 ENE-2A 69 3.5 14.4 14.1 12.0 12.0 52.5 4 ENE-3 56 7.6 15.0 16.1 15.6 14.5 61.2 49 E-1 85 1.3 18.8 15.1 18.6 15.5 68.0 50 E-2 92 5.0 21.5 17.6 17.1 17.9 74.1 51 ESE-1 109 1.2 14.4 16.6 15.6 12.5 59.1 52 ESE-2 106 4.4 21.5 22.0 25.3 20.9 89.7 11 SE-1A 138 0.9 19.9 17.6 16.6 15.0 69.1 54 SE-2 128 5.3 16.1 15.1 14.5 15.0 60.7 75 SE-2A 144 3.1 18.2 17.6 18.1 13.0 66.9 79 SSE-1 146 0.5 17.7 18.1 19.1 17.5 72.4 55 SSE-1A 161 0.6 17.1 16.1 17.1 12.5 62.8 56 SSE-2 156 5.8 18.8 18.1 19.7 16.0 72.6 (1). Sum of available quarterly data normalized to 1 year for the annual exposure value.

Table H-2 (2 of 2)

DIRECT RADIATION LEVELS Individual Stations at Watts Bar Nuclear Plant Environmental Radiation Levels mR /Quarter Map Dosimeter Approx 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Annual(1 )

Location Station Direction, Distance, Jan-Mar Apr-Jun Jul-Sep Oct-Dec Exposure Number Number degrees miles 2011 2011 2011 2011 mR/Year 57 S-1 182 0.7 17.7 19.5 17.6 15.0 69.8 58 S-2 185 4.8 11.7 16.1 12.0 14.5 54.3 76 S-2A 177 2.0 18.8 23.0 20.7 17.9 80.4 5 S-3 185 7.8 14.4 15.1 12.5 14.5 56.5 59 SSW-1 199 0.8 22.6 21.0 22.2 18.9 84.7 12 SSW-2 200 1.3 18.8 14.6 16.1 14.0 63.5 60 SSW-3 199 5.0 12.3 16.1 15.0 12.5 55.9 62 SW-' 226 0.8 20.4 19.5 20.2 17.9 78.0

,1P 63 SW-2 220 5.3 15.5 18.1 17.6 13.5 64.7 6 SW-3 225 15.0 13.9 18.1 15.0 16.0 63.0 64 WSW-1 255 0.9 15.0 19.5 17.1 16.0 67.6 65 WSW-2 247 3.9 18.8 17.1 21.2 17.5 74.6 66 W-1 270 0.9 18.2 17.1 18.6 15.5 69.4 14 W-2 277 4.8 16.1 17.1 16.6 11.5 61.3 77 W-2A 268 3.2 16.1 19.0 14.5 14.5 64.1 67 WNW-1 294 0.9 24.7 27.9 25.3 23.9 101.8 68 WNW-2 292 4.9 19.3 21.5 20.2 18.9 79.9 69 NW-1 320 1.1 16.6 18.5 15.6 14.5 65.2 70 NW-2 313 4.7 18.2 18.5 21.7 14.0 72.4 78 NW-2A 321 3.0 15.5 17.6 16.6 14.0 63.7 2 NW-3 317 7.0 19.9 19.5 17.6 17.5 74.5 71 NNW-1 340 1.0 15.0 17.1 16.1 13.0 61.2 72 NNW-2 333 4.5 17.1 18.1 16.1 18.4 69.7 73 NNW-3 329 7.0 13.3 10.7 14.0 10.0 48.0 7 NNW-4 337 15.0 15.0 13.6 15.0 13.5 57.1 (1). Sum of available quarterly data normalized to 1 year for the annual exposure value.

Tennessee Valley Authority RADIOACTIVITY IN AIR FILTER pCi/mA3 = 0.037 Bq/mA3 Name of Facility: WATTS BAR NUCLEAR PLANT Docket Number: 50-390,391 Location of Facility: RHEA, TENNESSEE Reporting Period: 2011 Number of Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Total Number of Detection Mean (F) Mean (F) Mean (F) Reported of Analysis (LLD) Range Location Description with Range Range Measurements Performed See Note 1 See Note 2 Distance and Direction See Note 2 See Note 2 See Note 3 GROSS BETA - 528 2.OOE-03 2.15E-02 (422/422) PM4 2.24E-02 (51 / 51) 2.19E-02 (106 / 106) 1.07E 4.01E-02 7.6 MILES NE/ENE 1.20E 4.01E-02 1.26E 3.69E-02 GAMMA SCAN (GELI) - 140 AC-228 I .00E-02 112 VALUES < LLD PM2 SPRING CITY 14 VALUES < LLD 28 VALUES < LLD 7.0 MILES NW BE-7 2.OOE-02 1.02E-01 (109/112) LM3 1.05E-01 (14 / 14) 1.08E-01 (28 / 28) 4.51E 1.43E-01 1.9 MILES NNE 7.53E 1.37E-01 6.59E-02 - 1.41E-01 BI-214 5.OOE-03 3.06E-02 (96 / 112) PM4 4.76E-02 (12 114) 2.16E-02 (25 /28) 5.30E 2.78E-01 7.6 MILES NE/ENE 6.20E 2.30E-01 6.40E-03 - 8.84E-02 CS-1 34 5.OOE-03 112 VALUES < LLD PM5 DECATUR 14 VALUES < LLD 28 VALUES < LLD 0 CD 6.2 MILES S CS-137 5.OOE-03 112 VALUES < LLD LM2 14 VALUES < LLD 28 VALUES < LLD 0.5 MILES N K-40 4.OOE-02 4.34E-02 (31 112) LM3 4.52E-02 (1 / 14) 1.01E-01 (11/28) 4.13E 4.52E-02 1.9 MILES NNE 4.52E 4.52E-02 1.01E 1.01E-01 PB-212 5.00E-03 1.11E-02 (1/112) LM2 1.11E-02 (1/14) 28 VALUES < LLD 1.11E 1.11E-02 0.5 MILES N 1.11E 1.11E-02 2.30E-02 (24 / 28)

PB-214 5.OOE-03 3.21E-02 (90/112) PM4 4.57E-02 (12 I 14).

5.30E 2.76E-01 7.6 MILES NE/ENE 6.10E 2.29E-01 5.30E 9.65E-02 TL-208 2.OOE-03 112 VALUES < LLD PM5 DECATUR 14 VALUES < LLD 28 VALUES < LLD 6.2 MILES S Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1

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

3. Blanks in this column indicate no nonrountine measurements

Tennessee Valley Authority RADIOACTIVITY IN CHARCOAL FILTER pCi/mA3 = 0.037 Bq/mA3 Name of Facility: WATTS BAR NUCLEAR PLANT Docket Number: 50-390,391 Location of Facility: RHEiA, TENNESSEE Reporting Period: 2011 Number of Type and Lower Limit In dicator Locations Location with Highest Annual Mean Control Locations Nonroutine Total Number of Detection Mean (F) Mean (F) Mean (F) Reported of Analysis (LLD) Range Location Description with Range Range Measurements Performed See Note 1 See Note 2 Distance and Direction See Note 2 See Note 2 See Note 3 GAMMA SCAN (GELI) - 528 AC-228 7.OOE-02 422 VALUES < LLD LM2 53 VALUES < LLD 8.39E-02 (1 / 106) 0.5 MILES N 8.39E 8.39E-02 BI-214 5.OOE-02 1.17E-01 (93/422) LM-4 WB 2.OOE-01 (11 / 53) 1.13E-01 (27/106) 5.06E 5.34E-01 0.9 MILES SE 6.06E 5.34E-01 5.12E 5.60E-01 1-131 3.OOE-02 7.05E-02 (16/422) PM3 7.84E-02 (2 / 53) 6.38E-02 (4 / 106) 5.50E 8.75E-02 10.4 MILES NNE 7.57E 8.10E-02 5.34E 7.03E-02 K-40 3.OOE-01 3.73E-01 (49 /422) LM3 4.39E-01 (8 / 53) 3.65E-01 (12/106) 3.04E 7.32E-01 1.9 MILES NNE 3.07E 7.32E-01 3.19E 4.80E-01 PB-212 3.OOE-02 422 VALUES < LLD PM4 51 VALUES < LLD 106 VALUES < LLD

-J 7.6 MILES NE/ENE E PB-214 7.OOE-02 1.41E-01 (78/422) LM-4 WB 2.05E-01 (10 / 53) 1.32E-01 (20 /106) 7.01E 5.71E-01 0.9 MILES SE 7.11E 5.71E-01 7.I1E 5.92E-01 TL-208 2.00E-02 422 VALUES < LLD PM5 DECATUR 53 VALUES < LLD 106 VALUES < LLD 6.2 MILES S Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1

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

3. Blanks in this column indicate no nonrountine measurements

Tennessee Valley Authority RADIOACTIVITY IN ATMOSPHERIC MOISTURE pCi/mA3 = 0.037 Bq/m^3 Name of Facility: WATTS BAR NUCLEAR PLANT Docket Number: 50-390,391 Location of Facility: RHEA, TENNESSEE Reporting Period: 2011 Number of Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Total Number of Detection Mean (F) Mean (F) Mean (F) Reported of Analysis (LLD) Range Location Description with Range Range Measurements Performed See Note 1 See Note 2 Distance and Direction See Note 2 See Note 2 See Note 3 TRITIUM - 208 3.00E+00 3.94E+00 (13/156) LM-4 WB 4.50E+00 (1/ 26) 3.33E+00 (1/ 52) 3.03E+00 - 7.49E+00 0.9 MILES SE 4.50E+00 - 4.50E+00 3.33E+00 - 3.33E+00 0H Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1

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

3. Blanks in this column indicate no nonrountine measurements

Tennessee Valley Authority RADIOACTIVITY IN MILK pCi/L = 0.037 Bq/L Name of Facility: WATTS BAR NUCLEAR PLANT Docket Number: 50-390,391 Location of Facility: RHEA, TENNESSEE Reporting Period: 2011 Number of Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Total Number of Detection Mean (F) Mean (F) - Reported Mean (F) of Analysis (LLD) Range Location Description with Range Range Measurements Performed See Note 1 See Note 2 Distance and Direction See Note 2 See Note 2 See Note 3 IODINE-131 -104 4.OOE-01 3.08E+00 (3 /52) LAYMAN FARM 6.39E+00 (1 /26) 5.60E+00 (3 / 52) 4.45E 6.39E+00 1.3 MILES SSW 6.39E+00 - 6.39E+00 6.41E 1.09E+01 GAMMA SCAN (GELI) - 104 AC-228 2.OOE+01 52 VALUES < LLD NORTON FARM 26 VALUES < LLD 2.37E+01 (1 /52) 4.1 MILES ESE 2.37E+01 - 2.37E+01 BI-214 2.OOE+01 3.54E+01 (5 / 52) NORTON FARM 3.63E+01 (4/26) 4.97E+01 (13/52) 2.22E+01 - 5.82E+01 4.1 MILES ESE 2.22E+01 - 5.82E+01 2.03E+01 - 2.93E+02 K-40 1.OOE+02 1.26E+03 (52 / 52) NORTON FARM 1.26E+03 (26 / 26) 1.23E+03 (52 / 52) 1.08E+03 - 1.40E+03 4.1 MILES ESE 1.16E+03 - 1.35E+03 1.07E+03 - 1.48E+03 CH

-!j PB-212 1.50E+01 52 VALUES < LLD LAYMAN FARM 26 VALUES < LLD 52 VALUES < LLD 1.3 MILES SSW ý1) 4.24E+01 (11 /52)

PB-214 2.00E+01 3.37E+01 (4 152) NORTON FARM 3.57E+01 (3 / 26) 2.20E+01 - 4.93E+01 4.1 MILES ESE 2.20E+01 - 4.93E+01 2.08E+01 - 1.79E+02 TL-208 1.OOE+01 52 VALUES < LLD NORTON FARM 26 VALUES < LLD 52 VALUES < LLD 4.1 MILES ESE SR 89 -16 3.50E+00 8 VALUES < LLD 8 VALUES < LLD SR 90 -16 2.OOE+00 8 VALUES < LLD 8 VALUES < LLD Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1

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

3. Blanks in this column indicate no nonrountine measurements

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

Name of Facility: WA TTS BAR NUCLEAR PLANT Docket Number: 50-390,391 Location of Facility: RHEEA, TENNESSEE Reporting Period: 2011 Number of Type and Lower Limit In dicator Locations Location with Highest Annual Mean Control Locations Nonroutine Total Number of Detection Mean (F) Mean (F) Mean (F) Reported of Analysis (LLD) Range Location Description with Range Range Measurements Performed See Note 1 See Note 2 Distance and Direction See Note 2 See Note 2 See Note 3 GAMMA SCAN (GELI) - 10 AC-228 2.50E-01 1.01E+00 (818) LM-4 WB 1.30E+00 (1 /1) 6.80E-01 (2/2) 7.54E 1.30E+00 0.9 MILES SE 1.30E+00- 1.30E+00 6.19E 7.40E-01 BE-7 2.50E-01 3.66E-01 (3/8) PM3 4.87E-01 (1/ 1) 2 VALUES < LLD 2.91E 4.87E-01 10.4 MILES NNE 4.87E 4.87E-01 BI-212 4.50E-01 1.04E+00 (8 8) LM-4 WB 1.46E+00 (1/1) 6.36E-01 (2 / 2) 7.25E-01 - 1.46E+00 0.9 MILES SE 1.46E+00 - 1.46E+00 5.62E 7.09E-01 BI-214 1 .50E-01 6.54E-01 (8/8) LM-4 WB 7.62E-01 (1 / 1) 7.48E-01 (2 / 2) 4.89E 7.62E-01 0.9 MILES SE 7.62E 7.62E-01 7.04E-01 - 7.92E-01 CS-137 3.00E-02 2.52E-01 (7 8) PM2 SPRING CITY 6.83E-01 (1 / 1) 3.06E-01 (2 12)

J* 3.27E 6.83E-01 7.0 MILES NW 6.83E 6.83E-01 1.15E-01 - 4.97E-01 K-40 7.50E-01 1.14E+01 (8/8) LM-4 WB 2.58E+01 (1 /1) 4.16E+00 (2 /2)

,D 3.90E+00 - 2.58E+01 0.9 MILES SE 2.58E+01 2.58E+01 3.66E+00 - 4.65E+00 PB-212 1.OOE-01 9.05E-01 (8 18) LM-4 WB 1.24E+00 (1/ 1) 6.04E-01 (2/2) 6.15E 1.24E+00 0.9 MILES SE 1,24E+00 - 1.24E+00 5.25E-01 - 6.83E-01 PB-214 1.50E-01 7.23E-01 (8/8) PM3 8.70E-01 (1 /1) 7.93E-01 (2 / 2) 4.68E 8.70E-01 10.4 MILES NNE 8.70E 8.70E-01 7.24E 8.62E-01 TL-208 6.OOE-02 3.06E-01 (8 /8) LM-4 WB 3.82E-01 (1 1) 2.11E-01 (2/2) 2.52E 3.82E-01 0.9 MILES SE 3.82E 3.82E-01 1.97E 2.26E-01 SR 89 - 10 1.60E+00 8 VALUES < LLD 2 VALUES < LLD SR 90 - 10 4.OOE-01 8 VALUES < LLD 2 VALUES < LLD Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1

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

3. Blanks in this column indicate no nonrountine measurements

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

Name of Facility: WATTS BAR NUCLEAR PLANT Docket Number: 50-390,391 Location of Facility: RHEA, TENNESSEE Reporting Period: 2011 Number of Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Total Number of Detection Mean (F) Mean (F) Mean (F) Reported of Analysis (LLD) Range Location Description with Range Range Measurements Performed See Note 1 See Note 2 Distance and Direction See Note 2 See Note 2 See Note 3 GAMMA SCAN (GELI) - 2 K-40 2.50E+02 1.63E+03 (1 /1) 2.5 MILES NE 1.63E+03 (1/ 1) 1.85E+03 (1/1) 1.63E+03- 1.63E+03 1.63E+03 - 1.63E+03 1.85E+03 - 1.85E+03 PB-212 4.OOE+01 1 VALUES < LLD 2.5 MILES NE 1 VALUES < LLD 1 VALUES < LLD H"

(1)

ýýj Y,

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

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

3. Blanks in this column indicate no nonrountine measurements

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

Name of Facility: WATTS BAR NUCLEAR PLANT Docket Number: 50-390,391 Location of Facility: Rl-LEA, TENNESSEE Reporting Period: 2011 Number of Type and Lower Limit Inddicator Locations Location with Highest Annual Mean Control Locations Nonroutine Total Number of Detection Mean (F) Mean (F) Mean (F) Reported of Analysis (LLD) Range Location Description with Range Range Measurements Performed See Note 1 See Note 2 Distance and Direction See Note 2 See Note 2 See Note 3 GAMMA SCAN (GELI) - 2 BI-214 4.OOE+01 4.81E+01 (1/1) 2.5 MILES NE 4.81E+01 (1 /1) 1 VALUES < LLD 4.81E+01 - 4.81E+01 4.81E+01- 4.81E+01 K-40 2.50E+02 2.08E+03 (1/ 1) 2.5 MILES NE 2.08E+03 (11 1) 2.14E+03 (I1/1) 2.08E+03 - 2.08E+03 2.08E+03- 2.08E+03 2.14E+03 - 2.14E+03 PB-212 4.OOE+01 1 VALUES < LLD 2.5 MILES NE 1 VALUES < LLD 1 VALUES < LLD PB-214 8.00E+01 1 VALUES < LLD 2.5 MILES NE 1 VALUES < LLD 1 VALUES < LLD TL-208 3.00E+011 1 VALUES < LLD 2.5 MILES NE 1 VALUES < LLD 1 VALUES < LLD 0H

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

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

3. Blanks in this column indicate no nonrountine measurements

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

Name of Facility: WATTS BAR NUCLEAR PLANT Docket Number: 50-390,391 Location of Facility: RHEA, TENNESSEE Reporting Period: 2011 Number of Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Total Number of Detection Mean (F) Mean (F) Mean (F) Reported of Analysis (LLD) Range Location Description with Range Range Measurements Performed See Note 1 See Note 2 Distance and Direction See Note 2 See Note 2 See Note 3 GAMMA SCAN (GELI) - 2 BI-214 4.OOE+01 4.60E+01 (1 / 1) 2.5 MILES NE 4.60E+01 (1 /1) 4.21E+01 (1 1) 4.60E+01 - 4.60E+01 4.60E+01- 4.60E+01 4.21E+01 - 4.21E+01 K-40 2.50E+02 1.89E+03 (11/1) 2.5 MILES NE 1.89E+03 (1/ 1) 3.27E+03 (1 1) 1.89E+03 - 1.89E+03 1.89E+03 - 1.89E+03 3.27E+03 - 3.27E+03 PB-214 8.00E+01 I VALUES < LLD 2.5 MILES NE 1 VALUES < LLD 1 VALUES < LLD J* C, Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1

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

3. Blanks in this column indicate no nonrountine measurements

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

Name of Facility: WATTS BAR NUCLEAR PLANT Docket Number: 50-390,391 Location of Facility: RHEA, TENNESSEE Reporting Period: 2011 Number of Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Total Number of Detection Mean (F) Mean (F) Mean (F) Reported of Analysis (LLD) Range Location Description with Range Range Measurements Performed See Note 1 See Note 2 Distance and Direction See Note 2 See Note 2 See Note 3 GAMMA SCAN (GELI) - 2 BI-214 4.OOE+01 5.42E+01 (1/1) 2.5 MILES NE 5.42E+01 (1 /1) 1 VALUES < LLD 5.42E+01 - 5.42E+01 5.42E+01- 5.42E+01 K-40 2.50E+02 2.17E+03 (1/1) 2.5 MILES NE 2.17E+03 (1/ 1) 2.14E+03 (1 /1) 2.17E+03 - 2.17E+03 2.17E+03 - 2.17E+03 2.14E+03 - 2.14E+03 PB-212 4.OOE+01 1 VALUES < LLD 2.5 MILES NE 1 VALUES < LLD 1 VALUES < LLD PB-214 8.OOE+01 I VALUES < LLD 2.5 MILES NE 1 VALUES < LLD I VALUES < LLD TL-208 3.OOE+01 1 VALUES < LLD 2.5 MILES NE 1 VALUES < LLD 1 VALUES < LLD CD

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

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

3. Blanks in this column indicate no nonrountine measurements

Tennessee Valley Authority RADIOACTIVITY IN SURFACE WATER(Total) pCi/L = 0.037 Bq/L Name of Facility: WATTS BAR NUCLEAR PLANT Docket Number: 50-390,391 Location of Facility: RHEA, TENNESSEE Reporting Period: 2011 Number of Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Total Number of Detection Mean (F) Mean (F) Mean (F) Reported of Analysis (LLD) Range Location Description with Range Range Measurements Performed See Note 1 See Note 2 Distance and Direction See Note 2 See Note 2 See Note 3 GROSS BETA - 38 1.90E+00 3.22E+00 (18 /26) TRM 523.1 3.30E+00 (11 / 13) 2.45E+00 (8 /12) 1.91E+00 - 5.69E+00 1.91E+00 - 5.69E+00 1.98E+00 - 3.12E+00 GAMMA SCAN (GELI) - 38 AC-228 2.00E+01 26 VALUES < LLD TRM 523.1 13 VALUES < LLD 12 VALUES < LLD BI-214 2.OOE+01 3.15E+01 (10/26) TRM 517.9 3.26E+01 (3/13) 6.39E+01 (2 /12) 2.20E+01 - 4.74E+01 2.36E+01 - 4.74E+01 4.59E+01 - 8.20E+01 K-40 1.00E+02 26 VALUES < LLD TRM 523.1 13 VALUES < LLD 1.19E+02 (1 / 12) 1.19E+02 - 1.19E+02

-.3 PB-212 1.50E+01 26 VALUES < LLD TRM 523.1 13 VALUES < LLD 12 VALUES < LLD CD PB-214 2.00E+01 2.93E+01 (6 /26) TRM 523.1 3.08E+01 (4 / 13) 5.77E+01 (2 /12) 2.08E+01 " 4.23E+01 2.08E+01 - 4.23E+01 3.73E+01 - 7.80E+01 TL-208 1.00E+01 26 VALUES < LLD TRM 523.1 13 VALUES < LLD 12 VALUES < LLD TRITIUM - 38 2.70E+02 6.21E+02 (1/26) TRM 517.9 6.21E+02 (1 / 13) 12 VALUES < LLD 6.21E+02- 6.21E+02 6.21E+02 - 6.21E+02 Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1

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

3. Blanks in this column indicate no nonrountine measurements

Tennessee Valley Authority RADIOACTIVITY IN PUBLIC WATER(Total) pCi/L = 0.037 Bq/L Name of Facility: WATTS BAR NUCLEAR PLANT Docket Number. 50-390,391 Location of Facility: RHEA, TENNESSEE Reporting Period: 2011 Number of Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Total Number of Detection Mean (F) Mean (F) Mean (F) Reported of Analysis (LLD) Range Location Description with Range Range Measurements Performed See Note I See Note 2 Distance and Direction See Note 2 See Note 2 See Note 3 GROSS BETA - 38 1.90E+00 2.77E+00 (17 /26) RM-2 DAYTON TN 3.07E+00 (10/13) 2.45E+00 (8 / 12) 1.92E+00 - 4.97E+00 17.8 MILES NNE 1.96E+00 - 4.97E+00 1.98E+00 - 3.12E+00 GAMMA SCAN (GELI) - 38 AC-228 2.OOE+01 26 VALUES < LLD RM-2 DAYTON TN 13 VALUES < LLD 12 VALUES < LLD 17.8 MILES NNE BI-214 2.00E+011 2.95E+01 (3/26) RM-2 DAYTON TN 4.02E+01 (1 / 13) 6.39E+01 (2 / 12) 2.27E+01 - 4.02E÷01 17.8 MILES NNE 4.02E+01- 4.02E+01 4.59E+01 - 8.20E+01 K-40 1.OOE+02 26 VALUES < LLD RM-2 DAYTON TN 13 VALUES < LLD 1.19E+02 (1/12) 17.8 MILES NNE 1.19E+02 - 1.19E+02 0" 00 PB-212 1.50E+01 26 VALUES < LLD CF INDUSTRIES 13 VALUES < LLD 12 VALUES < LLD 0

TRM 473.0 PB-214 2.00E+011 3.01E+01 (2/26) RM-2 DAYTON TN 3.54E+01 (1 /13) 5.77E+01 (2/12) 2.47E+01 - 3.54E+01 17.8 MILES NNE 3.54E+01- 3.54E+01 3.73E+01 - 7.80E+01 TL-208 1.OOE+01 26 VALUES < LLD RM-2 DAYTON TN 13 VALUES < LLD 12 VALUES < LLD 17.8 MILES NNE TRITIUM - 46 2.70E+02 34 VALUES < LLD 12 VALUES < LLD Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1

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

3. Blanks in this column indicate no nonrountine measurements

Tennessee Valley Authority RADIOACTIVITY IN WELL WATER(Total) pCi/L = 0.037 Bq/L Name of Facility: WATTS BAR NUCLEAR PLANT Docket Number: 50-390,391 Location of Facility: RHEA, TENNESSEE Reporting Period: 2011 Number of Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Total Number of Detection Mean (F) Mean (F) Mean (F) Reported of Analysis (LLD) Range Location Description with Range Range Measurements Performed See Note 1 See Note 2 Distance and Direction See Note 2 See Note 2 See Note 3 GROSS BETA - 98 1.90E+00 3.49E+00 (48 / 70) WBN MW-A 3.90E+00 (4 /14) 2.52E+00 (7/28) 1.90E+00 - 6.4E+00 0.58 MILES SSE) 1.90E+00 " 5.40E+00 1.97E+00 - 2.99E+00 GAMMA SCAN (GELI) - 98 AC-228 2.OOE+01 3.38E+01 (2 /70) WBN MW-A 3.80E+01 (1 /14) 2.23E+01 (1 /28) 2.95E+01 - 3.80E+01 0.58 MILES SSE) 3.80E+01- 3.80E+01 2.23E+01 - 2.23E+01 BI-214 2.OOE+01 4.OOE+01 (24 /70) WBN MW-F 5.14E+01 (3/14) 1.38E+02 (15/28) 2,05E+01 - 1.02E+02 0.30 MILES SE) 2.05E+01 - 9.29E+01 2.22E+01 - 3.33E+02 K-40 1.00E+02 1.42E+02 (1 70) WBN MW-B 1.42E+02 (1 / 14) 28 VALUES < LLD 1.42E+02- 1.42E+02 0.45 MILES SSE) 1.42E+02 - 1.42E+02 00 PB-212 1.50E+01 70 VALUES < LLD WBN MW-B 14 VALUES < LLD 28 VALUES < LLD 0.45 MILES SSE)

PB-214 2.OOE+01 4.03E+01 (19/70) WBN MW-F 5.12E+01 (2/14) 1.52E+02 (13 /28) 2.01E+01 " 9.70E+01 0.30 MILES SE) 2.19E+01 - 8.05E+01 2.24E+01 - 3.35E+02 TL-208 1.OOE+01 1.54E+01 (1 70) WBN WELL #1 1.54E+01 (1 / 14) 28 VALUES < LLD 1.54E+01 - 1.54E+01 0.6 MILES S 1.54E+01 - 1.54E+01 TRITIUM - 98 2.70E+02 1.47E+03 (35 /70) WBN MW-B 2.03E+03 (14 14) 28 VALUES < LLD 2.78E+02 - 2.85E+03 0.45 MILES SSE) 1.49E+03 - 2.85E+03 Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1

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

3. Blanks in this column indicate no nonrountine measurements

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

Name of Facility: WATTS BAR NUCLEAR PLANT Docket Number: 50-390,391 Location of Facility: RHEA, TENNESSEE Reporting Period: 2011 Number of Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Total Number of Detection Mean (F) Mean (F) Mean (F) Reported of Analysis (LLD) Range Location Description with Range Range Measurements Performed See Note 1 See Note 2 Distance and Direction See Note 2 See Note 2 See Note 3 GAMMA SCAN (GELI) - 6 BI-214 1.00E-01 4 VALUES < LLD DOWNSTREAM STATION 1 2 VALUES < LLD 6.67E-01 (2 /2)

DOWNSTREAM 1.70E-01 - 1.16E+00 CS-137 3.OOE-02 4 VALUES < LLD DOWNSTREAM STATION 1 2 VALUES < LLD 2 VALUES < LLD DOWNSTREAM K-40 4.OOE-01 1.24E+01 (4 /4) CHICKAMAUGA RES 1.29E+01 (2/2) 1.41E+01 (2/2) 1.09E+01 - 1.38E+01 TRM 471-530 1.20E+01 - 1.38E+01 1.27E+01 - 1.56E+01 PB-212 4.OOE-02 4 VALUES < LLD DOWNSTREAM STATION 1 2 VALUES < LLD 2 VALUES < LLD DOWNSTREAM PB-214 5.OOE-01 4 VALUES < LLD DOWNSTREAM STATION 1 5.84E-01 (1/2) CH 2 VALUES < LLD DOWNSTREAM 5.84E-01 - 5.84E-01 0'D 02 I.)TL-208 3.OOE-02 4 VALUES < LLD CHICKAMAUGA RES 2 VALUES < LLD 2 VALUES < LLD TRM 471-530 Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1

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

3. Blanks in this column indicate no nonrountine measurements

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

Name of Facility: W,ATrS BAR NUCLEAR PLANT Docket Number: 50-390,391 Location of Facility: RI- lEA, TENNESSEE Reporting Period: 2011

• Number of Type and Lower Limit Inclicator Locations Location with Highest Annual Mean Control Locations Nonroutine Total Number of Detection Mean (F) Mean (F) Mean (F) Reported of Analysis (LLD) Range Location Description with Range Range Measurements Performed See Note 1 See Note 2 Distance and Direction See Note 2 See Note 2 See Note 3 GAMMA SCAN (GELI) - 6 81-214 1.OOE-01 1.28E-01 (2/4) DOWNSTREAM STATION I 1.38E-01 (1/2) 1.45E-01 (1 /2) 1.18E 1.38E-01 DOWNSTREAM 1.38E 1.38E-01 1.45E 1.45E-01 CS-137 3.OOE-02 4.75E-02 (11 4) DOWNSTREAM STATION 1 4.75E-02 (1 /2) 3.11E-02 (1 2) 4.75E 4.75E-02 DOWNSTREAM 4.75E 4.75E-02 3.11E 3.11E-02 K-40 4.OOE-01 1.33E+01 (4 4) CHICKAMAUGA RES 1.43E+01 (2 / 2) 1.34E+01 (2 /2) 1.02E+01 - 1.46E+01 TRM 471-530 1.41E+01 - 1.46E+01 1.24E+01 - 1.44E+01 PB-212 4.OOE-02 4 VALUES < LLD DOWNSTREAM STATION 1 2 VALUES < LLD 2 VALUES < LLD DOWNSTREAM

,H PB-214 5.00E-01 4 VALUES < LLD DOWNSTREAM STATION 1 2 VALUES < LLD 2 VALUES < LLD DOWNSTREAM 60 CD TL-208 3.00E-02 4 VALUES < LLD DOWNSTREAM STATION 1 2 VALUES < LLD 2 VALUES < LLD DOWNSTREAM CN Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1

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

3. Blanks in this column indicate no nonrountine measurements

Tennessee Valley Authority RADIOACTIVITY IN SHORELINE SEDIMENT pCilg = 0.037 Bqlg (DRY WEIGHT)

Name of Facility: WAITS BAR NUCLEAR PLANT Docket Number: 50-390,391 Location of Facility: RHEA, TENNESSEE Reporting Period: 2011 Number of Type and Lower Limit Incdicator Locations Location with Highest Annual Mean Control Locations Nonroutine Total Number of Detection Mean (F) Mean (F) Mean (F) Reported of Analysis (LLD) Range Location Description with Range Range Measurements Performed See Note 1 See Note 2 Distance and Direction See Note 2 See Note 2 See Note 3 GAMMA SCAN (GELI) - 2 AC-228 2.50E-01 1.12E+00 (1/1) COTTON PORT MARINA 1.12E+00 (1 / 1) 9.37E-01 (1 / 1) 1.12E+00- 1.12E+00 TRM 513 1.12E+00 - 1.12E+00 9.37E-01 - 9.37E-01 BI-212 4.50E-01 1.32E+00 (1 1) COTTON PORT MARINA 1.32E+00 (1 / 1) 1.02E+00 (1 /1) 1.32E+00- 1.32E+00 TRM 513 1.32E+00 - 1.32E+00 1.02E+00 - 1.02E+00 BI-214 1.50E-01 5.44E-01 (I 11) COTTON PORT MARINA 5.44E-01 (1/1) 7.81E-01 (1 1) 5.44E-01 - 5.44E-01 TRM 513 5.44E 5.44E-01 7.81E-01 - 7.81E-01 CS-137 3.OOE-02 3.31E-02 (1 /1) COTTON PORT MARINA 3.31E-02 (1 /1) 1 VALUES < LLD 3.31E 3.31E-02 TRM 513 3.31E 3.31E-02 K-40 7.50E-01 2.56E+01 (1 /1) COTTON PORT MARINA 2.56E+01 (1 I 1) 5.89E+00 (1 1) 2.56E+01 - 2.56E+01 TRM 513 2.56E+01- 2.56E+01 5.89E 5.89E+00 0 PB-212 CD 1.OOE-01 1.05E+00 (1 1) COTTON PORT MARINA 1.05E+00 (1 /1) 9.72E-01 (1 / 1) 1.05E+00- 1.05E+00 TRM 513 1.05E+00 - 1.05E+00 9.72E-01 - 9.72E-01 PB-214 1.50E-01 5.53E-01 (1 1) COTTON PORT MARINA 5.53E-01 (1 /1) 7.83E-01 (1 /1) 5.53E-01 - 5.53E-01 TRM 513 5.53E 5.53E-01 7.83E-01 - 7.83E-01 TL-208 6.OOE-02 3.70E-01 (1 1) COTTON PORT MARINA 3.70E-01 (1 /1) 3.11E-01 (1/1) 3.70E 3.70E-01 TRM 513 3.70E 3.70E-01 3.11E 3.11E-01 Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1

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

3. Blanks in this column indicate no nonrountine measurements

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

Name of Facility: WATTS BAR NUCLEAR PLANT Docket Number: 50-390,391 Location of Facility: RHEA, TENNESSEE Reporting Period: 2011 Number of Type and Lower Limit Indicator Locations Location with Highest Annual Mean Control Locations Nonroutine Total Number of Detection Mean (F) Mean (F) Mean (F) Reported of Analysis (LLD) Range Location Description with Range Range Measurements Performed See Note 1 See Note 2 Distance and Direction See Note 2 See Note 2 See Note 3 GAMMA SCAN (GELI) -5 AC-228 2.50E-01 7.44E-01 (5/ 5) YP-13 1.07E+00 (1/1) VALUES < LLD 4.69E 1.07E+00 YARD POND 1.07E+00 - 1.07E+00 BE-7 2.50E-01 3.92E-01 (4/5) YP-13 4.62E-01 (1 / 1) VALUES < LLD 2.92E 4.62E-01 YARD POND 4.62E 4.62E-01 BI-212 4.50E-01 8.32E-01 (4 / 5) YP-13 1.1OE+00 (1/1) VALUES < LLD 6.66E 1.10E+00 YARD POND 1.1OE+00 - 1.10E+00 BI-214 1.50E-01 6.63E-01 (5/ 5) YP-13 8.24E-01 (1/ 1) VALUES < LLD 5.28E 8.24E-01 YARD POND 8.24E 8.24E-01 CO-58 3.OOE-02 1.76E-01 (2/ 5) YP-16 1.92E-01 (1/ 1) VALUES < LLD 1.60E 1.92E-01 YARD POND 1.92E 1.92E-01 CO-60 3.OOE-02 8.30E-02 (3/ 5) YP- 16 1.06E-01 (11 1) VALUES < LLD 4.38E 1.06E-01 YARD POND 1.06E 1.06E-01 CD CS-137 3.OOE-02 9.33E-02 (5/ 5) LV-3 2.14E-01 (1/ 1) VALUES < LLD 3.17E 2.14E-01 LOW VOL WASTE POND 2.14E 2.14E-01 K-40 7.50E-01 9.21 E+00 (5/5) YP-13 1.51E+01 (1/1) VALUES < LLD 5.59E+00 - 1.51E+01 YARD POND 1.51E+01 - 1.51E+01 PB-212 1.OOE-01 7.19E-01 (5/5) YP-13 1.03E+00 (1/1) VALUES < LLD 5.09E 1.03E+00 YARD POND 1.03E+00 - 1.03E+00 PB-214 1.50E-01 7.13E-01 (5/5) YP-13 9.OOE-01 (1 / 1) VALUES < LLD 5.83E 9.OOE-01 YARD POND 9.OOE 9.OOE-01 SB-125 -1.OOE+00 8.91 E-02 (2 /5) YP-17 1.02E-01 (1/1) VALUES < LLD 7.63E 1.02E-01 YARD POND 1.02E 1.02E-01 TL-208 6.OOE-02 2.44E-01 (5/5) YP-13 3.37E-01 (1 / 1) VALUES < LLD 1.44E 3.37E-01 YARD POND 3.37E&01 - 3.37E-01 Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1

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

3. Blanks in this column indicate no nonrountine measurements

Figure H-I Direct Radiation Direct Radiation Levels Watts Bar Nuclear Plant Four Quarter Moving Average 25

• InLight Dosimeter I 20Initial WBNP Deployment

=20 ,dr operation in January, 2007

~January, 1996 20 15U415 E 10 '2 E 0On-Site

-- O--Off-Site ,

5 1975 1980 1985 1990 1995 2000 2005 2010 2015 Calendar Year Dosimeters are processed quarterly. This chart shows trends in the average measurement for all dosimeters grouped as "on-site" or "off-site". The data from preoperational phase, prior to 1996, show the same trend of "on-site" measurements higher than "off-site" measurements that is observed in current data indicating that the slightly higher "on-site" direct radiation levels are not related to plant operations.

Figure H-2 Radioactivity in Air Filters Annual Average Gross Beta Activity in Air Filters Watts Bar Nuclear Plant 0.15..

A-Indicator

-B-Control F-O.10 Initial Operation of C" WBNP in January,

• 1996 r.0.05 0.00 1975 1980 1985 1990 1995 2000 2005 2010 2015 Calendar Year As can be seen in the trend plot of gross beta activity, the gross beta levels in air particulates have remained relatively constant with the exception of years when the beta activity was elevated due to fallout from nuclear weapons testing. The data also shows that there is no difference in the levels for sampling conducted at the indicator stations as compared to the control stations. The Watts Bar monitoring program was suspended for one year in 1989. The preoperational monitoring was restarted in 1990.

Figure H-3 Cs-137 in Soil Annual Average Activity of Cs-137 in Soil Watts Bar Nuclear Plant 1.0 -

'F Initial WBN Operation in 0.8 -

M.

0.6 -

0.4 - Indicator 0.21 E3 Control 0.0 0.4

- -l--dndicato 1975 1980 1985 1990 1995 2000 2005 2010 2015 Calendar Year Cesium-137 was produced by past nuclear weapons testing and is present in almost every environmental soil sample exposed to the atmosphere. The "control" and "indicator" locations have generally trended downward with year-to-year variation, since the beginning of the Watts Bar monitoring program.

- 88 -

Figure H-4 Gross Beta Activity in Surface Water Annual Average Gross Beta Activity in Surface Water Watts Bar Nuclear Plant 5- *3 " in January, 1996 AInitial WBN Operation 4

1-3 Z-& Downstream 1 - Upstream 0 I I I II I 1975 1980 1985 1990 1995 2000 2005 2010 2015 Calendar Year As shown in the graph, the gross beta activity has been essentially the same in samples from the downstream and upstream locations. The average gross beta activity in these samples has been representative of the levels measured during preoperational monitoring.

- 89 -

Figure H-5 Gross Beta Activity in Drinking Water Annual Average Gross Beta Activity in Drinking Water Watts Bar Nuclear Plant 6 -

5 Initial WBN Operation in January, 1996

.- 14 (3

< 2--a- Downstream 1 - Upstream 0

1975 1980 1985 1990 1995 2000 2005 2010 2015 Calendar Year The average gross beta activity in drinking water samples from the upstream control locations has been essentially the same as the activity level measured in samples from the downstream indicator locations. The annual average gross beta activity has been relatively constant since the start of plant operations in 1996 and is slightly lower than preoperational levels.

- 90 -

Figure H-6 Radioactivity in Fish Annual Average Activity of Cs-137 in Commerical Fish Watts Bar Nuclear Plant 0.30 Indicator Initial WBN 0.25 E3 Con l Operation in

-f-C--ontrol January, 1996 0.20

'E 0.15 0.10 0.05 0.00 1 - - M9752 15 1975 1980 1985 1990 1995 2000 2005 2010 2015 Calendar Year Annual Average Activity of Cs-137 in Game Fish Watts Bar Nuclear Plant

-~0.30

,. 0.25 Initial WBN - Indicat or Operation in Q 0.20 - January, 1996 -El-Contro I

, 0.15

I-

& 0.10 IS 0.05 0.00 1975 1980 1985 1990 1995 2000 2005 2010 2015 Calendar Year The concentrations of Cs- 137 found in fish are consistent with levels present in the Tennessee River due to past atmospheric nuclear weapons testing and operation of other nuclear facilities in the upper reaches of the Tennessee River Watershed.

Figure H-7 Radioactivity in Shoreline Sediment Annual Average Activity of Cs-137 in Shoreline Sediment Watts Bar Nuclear Plant 0.6 -

Initial WBN Operation in M January, 1996 --- Indicator CL E3 Control 2*

0.1 1975 1980 1985 1990 1995 2000 2005 2010 2015 21 Calendar Year The Cs-137 present in the shoreline sediments of the Tennessee River system was produced both by testing of nuclear weapons and operation of other nuclear facilities in the upper reaches of the Tennessee River Watershed. The amounts of Cs-137 have declined significantly during the course of monitoring for the Watts Bar site, so much so that not all samples contain detectable levels.

- 92 -