Text

Submittal of Annual Radiological Environmental Operating Report - 2012
	ML13140A043
Person / Time
Site:	Watts Bar
Issue date:	05/15/2013
From:	James Shea; Tennessee Valley Authority
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML13140A043 (97)
	v • d • e

Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 May 15, 2013 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 - 2012 Enclosed is the subject Annual Radiological Environmental Operating Report for the period of January 1, 2012, through December 31, 2012. This report is being submitted as required by Watts Bar Nuclear Plant (WBN), Unit 1, Technical Specification (TS) 5.9.2, "Annual Radiological Environmental Operating Report," and the WBN Offsite Dose Calculation Manual (ODCM), Administrative Control Section 5.1.

There are no regulatory commitments in this letter. If you have any questions concerning this matter, please contact Donna Guinn, Site Licensing Manager, at (423) 365-1589.

RResp c ully, J/W.

ea ice F~tesident, Nuclear Licensing nclosure:

Annual Radiological Environmental Operating Report - 2012 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 N1f25 Printed on reycled paper

Enclosure Watts Bar Nuclear Plant Unit I Annual Radiological Environmental Operating Report - 2012

Annual Radiological Environmental Operating Report Watts Bar Nuclear Plant 2012

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

i Executive Summary..........................................

I Introduction.................................................

2 Naturally Occurring and Background Radioactivity...................

2 Electric Power Production.....................................

3 Site/Plant Description..........................................

6 Radiological Environmental Monitoring Program....................

8 Direct Radiation M onitoring.....................................

11 M easurement Techniques......................................

11 R esults....................................................

12 Atmospheric M onitoring.......................................

14 Sample Collection and Analysis................................

14 Results...............

15 Terrestrial M onitoring.........................................

16 Sample Collection and Analysis................................

16 R esults....................................................

17 Liquid Pathway Monitoring.....................................

19 Sample Collection and Analysis................................

19 R esults...................................................

20 Assessment and Evaluation.....................................

23 R esults 23 C onclusions................................................

24 References...................................................

25 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...........

26 Figure I Tennessee Valley Region.................................

27 Figure 2 Environmental Exposure Pathways of Man Due to Releases of Radioactive Materials to the Atmosphere and Lake....................................

28

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TABLE OF CONTENTS (continued)

Appendix A Radiological Environmental Monitoring Program and Sampling Locations..................................

29 Appendix B Program Modifications................................

40 Appendix C Program Deviations..................................

42 Appendix D Analytical Procedures...............................

45 Appendix E Nominal Lower Limits of Detection (LLD)................

48 Appendix F Quality Assurance/Quality Control Program...............

53 Appendix G Land Use Survey....................................

59 Appendix H Data Tables and Figures..............................

65

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ANNUAL ENVIRONMENTAL RADIOLOGICAL OPERATING REPORT WATTS BAR NUCLEAR PLANT 2012 TENNESSEE VALLEY AUTHORITY April 2013

EXECUTIVE

SUMMARY

This report describes the radiological environmental monitoring program conducted by TVA in the vicinity of the Watts Bar Nuclear Plant (WBN) in 2012. The program includes the collection of samples from the environment and the deternination 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 2012 monitoring year did not detect any fission or activation product radionuclides attributable to WBN plant operations.

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)-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 10 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, uranium (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, our food, our drinking water, and our bodies. The radiation from these materials makes up a part of the low-level natural background radiation. The remainder of the natural background radiation 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 I

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

Releases are monitored at the onsite points of release and through the radiological environmental monitoring program which measures 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 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 mrem/year Any other organ

<25 mrem/year Appendix B to 10 CFR 20 presents annual average limits for the concentrations of radioactive materials released in gaseous and liquid effluents at the boundary of the unrestricted areas.

Table 1 of this report 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 south and 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 I 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 2012.

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 2012 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.

DI RECT 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 fbr 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 monitoring points are located around the plant near the site boundary, one location in each of the 16 compass sectors. One monitoring point is also located in each of the 16 compass sectors at a distance of approximately fbur 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. The dosimeters 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 (HIPS) Draft Standard N13.29 for environmental applications of dosimeters.

WBN Technical Specification 5.9.2, Annual Radiological Environmental Operating Report, requires that the Annual Radiological Environmental Operating Report identify TLD results that represent collocated dosimeters in relation to the NRC TLD program and the exposure period H

associated with each result. The NRC collocated T1,I) program was terminated by the NRC at the end of 1997, therefore, there are no Ti.,I) results that represent collocated dosimeters included in this report.

Re..sults The results for environmental dosimeter measurements are normalized to a standard quarter (91.25 days or 2190 hours0.0253 days 0.608 hours 0.00362 weeks 8.33295e-4 months ). The monitoring locations are grouped according to the distance from the plant. The first group consists of all monitoring points within 2 miles of the plant. The second group is made up of all locations greater than 2 miles from the plant. Past data have shown that tlhe 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 "offisite."

The quarterly gamma radiation levels determined from the dosimeters deployed around WBN in 2012 are summarized in Table B-..

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 2012, 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 2012 Average Onsite Stations 68 65 Offsite Stations 61 57 The data in Table H-I indicates that the average quarterly direct radiation levels at the WBN onsite stations are approximately 1.8 mR/quarter higher than levels at the offsite stations. This difference is consistent with levels measured for the preoperation and construction phases of TVA nuclear power plant sites where the average levels onsite were slightly higher than levels offsite. Figure 11-1 compares plots of the data from the onsite stations with those from the offsite stations over the period from 1977 through 2012. The new Landauer InLight Optically Stimulated Luminescence (OSL) dosimeters were deployed since 2007 replacing the Panasonic UD-814 dosimeters used during the previous years.

The data in Table H-2 contains the results of the individual monitoring stations. The results reported in 2012 are consistent with direct radiation levels identified at locations which are not influenced by the operation of WI3N. 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 (cfmn) 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 2012 was consistent with levels reported in previous years. The average gross beta activity measured for air particulate samples was 0.023 pCi/m 3. The annual averages of the gross beta activity in air particulate filters at these stations for the period 1977-2012 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 2012 monitoring program was consistent with the preoperational data.

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 2012.

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/m3. These values were consistent with previously reported expected data.

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-11.

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 2012 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, comer markets, or cooperatives. Types of foods may vary from year to year as a result of changes in the local vegetable gardens. Samples of potatoes, cabbage, com, 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. The results for the quarterly Sr-89 analysis were below the established LLD's for these analyses. One milk sample contained low level of Sr-90 of 2.4 pCi/liter. The presence of low level of Sr-90 is consistent with levels expected in the environment resulting from past nuclear weapons testing. 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 2012. The maximum concentration of Cs-137 was 0.54 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-137, and transport through the environment.

The radionuclides measured in food samples were naturally occurring. The results are reported in Tables H-8 through H-11.

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-12 through H-18. 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 2012. 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 2.9 pCi/liter in downstream (indicator) samples and 2.5 pCi/liter in upstream (control) 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 908 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-12. The annual average gross beta activity in surface water samples for the period 1977 through 2012 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 (indicator) stations was 2.9 pCi/liter and the average for upstream (control) 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 which were significantly below the EPA drinking water limit of 20,000 pCi/liter. The results are shown in Table H-13. Trend plots of the gross beta activity in drinking water samples from 1977 through 2012 are presented in Figure H-5.

The gamma isotopic analysis of ground water samples identified only naturally occurring radionuclides. Gross beta concentrations in samples from the onsite indicator locations averaged 3.0 pCi/liter. The average gross beta activity for samples from the control locations was 2.7 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 1,520 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-14.

Measurable levels of Cs-137 were identified in a total of two fish samples. The maximum Cs-137 concentration was 0.03'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-15 and H-16. Trend plots of the annual average Cs-137 concentrations measured in fish samples are presented in Figure H-6. The Cs-137 activities are consistent with preoperational results produced by fallout or effluents from other nuclear facilities.

Cs-137 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-17. Trend plots of the average concentration of Cs-137 in shoreline sediment are presented in Figure H-7.

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 0.11 pCi/gm. In addition, Co-60 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-18. 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 2012 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 I COMPARISON OF PROGRAM LOWER LIMITS.OF DETECTION WITH THE REGULATORY LIMITS FOR MAXIMUM ANNUAL AVERAGE EFFLUENT CONCENTRATIONS RELEASED TO UNRESTRICTED AREAS AND REPORTING LEVELS Concentrations in Water, pCi/Liter Effluent Reporting Lower limit Analysis Concentration' Level2 of Detection3 Concentrations in Air, pCi/Cubic Meter Effluent Reporting Lower limit Concentration' Level2 of Detection3 H-3 Cr-51 Mn-54 Co-58 Co-60 Zn-65 Sr-89 Sr-90 Nb-95 Zr-95 Ru-103 Ru-106 1-131 Cs-134 Cs-137 Ce-144 Ba-140 La-140 1,000,000 500,000 30,000 20,000 3,000 5,000 8,000 500 30,000 20,000 30,000 3,000 1,000 900 1,000 3,000

.8,000 9,000 20,000 1,000 1,000 300 300 400 400 2

30 50 200 200 270 45 5

5 5

10 5

2 5

10 5

40 0.4 5

5 30 25 10 100,000 30,000 1,000 1,000 50 400 1,000 6

2,000 400 900 20 200 200 200 40 2,000 2,000 0.9 10 20 3.00 0.02 0.005 0.005 0.005 0.005 0.0011 0.0004 0.005 0.005 0.005 0.02 0.03 0.005 0.005 0.01 0.015 0.01 Note: I pCi = 3.7 xI0"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-I of this report.

PADkC m0.~

TENNESSEE VALLEY REGIOI (TVA NUCLEAR PLANT SITES)

W V A.

C K

Y

-.1

~T1 JACKSON#

RML MPHIS

/.J S

C A R.

M I S S.

A L

A B

A' G EO RG I A I -WATTS BAR NUCLEAR PLANT SEQUOYAH NUCLEAR PLANT

-IELLEFONTE NUCLEAR PLANT BROWNS FERRY NUCLEAR PLANT

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

Plums Exposure Plm xpsr orne Releases Liquid Releases Diluted By Lake Animals (MilkMeat)

Consumed By Animals LIIJLJJ MAN Consumed By Man Shoreline Exposure

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

1. AIRBORNE

a. Particulates 4 samples from locations (in different sectors) at or near the site boundary (LM-1, 2, 3, and 4).

Continuous sampler operation with sample collection weekly (more (frequently if required by dust loading).

Analyze for gross beta radioactivity greater than or equal to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following filter change. Perform 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.

41

b. Radioiodine

c. Atmospheric Moisture 4 samples from communities 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).

Samples from same locations as air particulates.

4 samples from locations (in different sectors) at or near the site boundary (LM-1, 2, 3, and 4) 2 samples from communities approximately 4-10 miles distance from the plant (PM-2, 5).

Continuous sampler operation with filter collection weekly.

Continuous sampler operation with sample collection biweekly.

1-131 at least once per 7 days.

Analysis is performed by gamma spectroscopy.

Analyze each sample for tritium.

Table A-I WATTS BAR NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMa Exposure Pathway and/or Sample

c. Atmospheric Moisture (Cont.)

Number of Samples and Locationsb Sampling and Collection Frequency Type and Frequency of Analysis

d. Soil

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

Samples from same location as air particulates.

2 or more dosimeters placed at or near the site boundary in each of the 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.

Once per year.

At least once per 92 days.

Gamma scan, Sr-89, Sr-90 once per year.

Gamma dose at least once per 92 days.

Table A-I WATTS BAR NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRANM Exposure Pathway and/or SampIe

3. WATERBORNE Number of Samples and Locationsb Sampling and Collection Frequency Type and Frequency of Analysis

a. Surface 1;J

b. Ground 2 samples downstream from plant discharge (TRM 517.9 and TRM 523.1).

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

Five sampling locations from ground water monitoring wells adjacent to the plant (Wells No. 1, A, B, C, and F).

1 sample from ground water source up gradient (Well No. 5).

I sample from ground water source offsite (Farm L).

1 sample at the first two potable surface water supplies, downstream from the plant (TRM 503.8 and TRM 473.0).

Collected by automatic sequential-type sampler' with composite samples collected over a period of approximately 31 days.

Gross beta, gamma scan, and tritium analysis of each sample.

Collected by automatic sequential-type sampler with composite samples collected over a period of approximately 31 days.

Same as Well No. 1.

Grab sample at least once per 31 days.

Collected by automatic sequential-type sampler' with composite sample collected monthly.

Gross beta, gamma scan, and tritium analysis of each sample.

c. Drinking

WATTS BAR NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM2 Exposure Pathway and/or Sample

c. Drinking (Con't)

d. Sediment from Shoreline

e. Pond Sediment

5. INGESTION Number of Samples and Locationsb 1 sample at a control location TRM 52 9.3d.

1 sample downstream from plant Discharge (TRM 513.0).

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

1 sample from at least three locations in the Yard Holding Pond.

I sample from milk producing animals in each of 1-3 areas indicated by the cow census were doses are calculated to be highest.

1 or more samples from control locations.

One sample of commercially important species and one sample of recreationally important species.

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

Sampling and Collection Freguency At least once per 184 days.

Gamma scan of each sample.

Type and Frequency of Analysis At least once per year.

Gamma scan of each sample.

a. Milk Every 2 weeks.

1-131 and gamma analysis on each sample. Sr-89 and Sr-90 once per quarter.

b. Fish At least once per 184 days.

Gamma scan on edible portions.

Table A-I WATTS BAR NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway and/or Sample

c. Vegetatione (Pasturage and grass)

Number of Samples and Locationsb Sampling and Collection Frequency Type and Frequency of Analysis Samples from farms producing milk At least once per 31 days.

but not providing a milk sample.

1-131 analysis and gamma scan of each sample.

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

Annually at time of harvest. The types of foods available for sampling will vary. Following is a list of typical foods which may be available:

Cabbage, Lettuce and/or Greens Corn Green Beans Potatoes Tomatoes Gamma scan on edible portion.

a. The sampling program outlined in this table is that which was in effect at the end of 2012.

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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

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 Location

__Numbera 2

3 4

5 6

7 8

9 10 II 12 15 18 20 22 23 25 26 27 31 32 33 35 37 38 39 81 82 83 84 85 Approximate Distance Sector (Miles)

Stati-on PM-2 PM-3 PM-4 PM-5 RM-2 RM-3 LM-I LM-2 LM-3 LM-4 Farm L Farm K Well #1 Farm N Farm EH Well #5 TRM 517.9 TRM 523.1 TRM 529.3 TRM 473.0 (C. F. Industries)

TRM 513.0 TRM 530.2 TRM 503.8 (Dayton)

TRM 522.8-527.8 (downstream of WBN)

TRM 471-530 (Chickamauga Lake)

Watts Bar Reservoir Yard Pond Well A Well B Well C Well F NW NNE NE/ENEC S

SW NNW SSW NNE NNE SE SSW ENE S

ESE SSW N

7.0 10.4 7.6 8.0 15.0 15.0 0.5 0.4 1.9 0.9 1.3 11.6 0.6 4.1 24.0 0.5 9.9e 4.7*

! 5e 54.8e 14.8e 2.4e 24.0e Indicator (I) or Control (C)

I I

C C

I II C

I C

C I

I C

I Samples Collectedb AP,CF,S,AM AP,CF,S AP,CF,S AP,CF,S,AM AP,CF,S,AM AP,CF,S,AM AP,CF,S,AM AP,CF,S,AM AP,CF,S,AM AP,CF,S,AM M,W M

W M

M W

SW SW swPWf PW I

C I

Ss SS PW I

I F

F SSE/S/SSW SSE SSE ESE SE Onsite 0.6 0.5 0.3 0.3 CI I

I I

F PS W

W W

W

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

b. Sample codes:

AM = Atmospheric Moisture AP = Air particulate filter CF = Charcoal filter F = Fish M = Milk PW = Public Water PS = Pond Sediment S

= Soil SS = Shoreline sediment SW = Surface water W =Well water

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 Maps Approximate Location Distance Number Station Sector fMik 2

NW-3 NW 7.0 3

NNE-3 NNE 10.4 4

ENE-3 NE/ENE 7.6 5

S-3 S

7.8 6

SW-3 SW 15.0 7

NNW-4 NNW 15.0 10 NNE-IA NNE 1.9 11 SE-IA SE 0.9 12 SSW-2 SSW 1.3 14 W-2 W

4.8 40 N-I N

1.2 41 N-2 N

4.7 42 NNE-I NNE 1.2 43 NNE-2 NNE 4.1 44 NE-i NE 0.9 45 NE-2 NE 2.9 46 NE-3 NE 6.1 47 ENE-I ENE 0.7 48 ENE-2 ENE 5.8 49 E-I E

1.3 50 E-2 E

5.0 51 ESE-I ESE 1.2 52 ESE-2 ESE 4.4 54 SE-2 SE 5.3 55 SSE-IA SSE 0.6 56 SSE-2 SSE 5.8 57 S-1 S

0.7 58 S-2 S

4.8 59 SSW-I SSW 0.8 60 SSW-3 SSW 5.0 62 SW-I SS 0.8 63 SW-2 SW 5.3 64 WSW-!

WSW 0.9 65 WSW-2 WSW 3.9 66 W-i W

0.9 67 WNW-I WNW 0.9 68 WNW-2 WNW 4.9 69 NW-I NW 1.1 70 NW-2 NW 4.7 71 NNW-l NNW 1.0 72 NNW-2 NNW 4.5 73 NNW-3 NNW 7.0 74 ENE-2A ENE 3.5 75 SE-2A SE 3.1 76 S-2A S

2.0 77 W-2A W

3.2 78 NW-2A NW 3.0 79 SSE-1 SE 0.5

a. See Figures A-1, A-2, and A-3.

b. Dosimeters designated "onsite" are located 2 miles or less from the plant; "offsite'" are locat from the plant Onsite (On)b or Offsite (Off)

Off Off Off Off Off Off On On On Off On Off On Off On Off Off On Off On Off On Off Off On Off On Off On Off On Off On Off On On Off On Off On Off Off Off Off Off Off Off On ed more than 2 miles Figure A-I Radiological Environmental Sampling Locations Within 1 Mile of the Plant 348.75 N

11.25 26.25 7133.75

//NE 2

56.25 47.8.75

~WATTS BAR NUCLEAR PLANT E

191.25 sl 168.7'5 SE02 79 Figure A-2 Radiological Environmental Sampling Locations From I to 5 Miles From The Plant 48.75 N

SSE Scale 0

i 2

W~ee Figure A-3 Radiological Environmental Sampling Locations Greater Than 5 Miles From the Plant 348.78

11.25

) 78.78 AK E-2101.2 C 5 10 15 20 26 APPENDIX B PROGRAM MODIFICATIONS Appendix B Radiological Environmental Monitoring Program Modification There were no modifications to the WBN REMP during 2012.

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 Date Station Location Sample Type Descriotion 1st Qtr 2012 45 WBS-2 4.8 Miles Dosimeter The dosimeters could not be located for the quarterly change out.

The property owner has cleared the area,using a dozer, where the dosimeters were located. The casing and dosimeters were replaced for the next quarter. PER #541774 11/13/12 3173 2.5 Miles NE Tomatoes A vegetable sample for gamma was identified as lost in processing. The missed sample was included In the 2012 AREOR report. PER #711957

,=

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.

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-I Nominal LLD Values A. Radiochemical Procedures Sediment Air Filters Water Milk Wet Vegetation and Soil Analysis (Rci/m3 )

(pcilu (D I/L*

(RCi/k* 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-I Nominal LLD Values B. Gamma Analyses Particulate Filter Analysis pCi/m3 Ce-141 Ce-144 Cr-51 1-131 Ru-103 Ru-106 Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Mn-54 Zn-65 Co-60 K-40 Ba-140 La-140 Fe-59 Be-7 Pb-212 Pb-214 Bi-214 Bi-212 TI-208 Ra-224 Ra-226 Ac-228

.005

.01

.02

.005

.02

.005

.04

.015

.01

.005

.02

.005

.02

.002 Charcoal Filter

" Ci/m3

.02

.07 0.15 0.03 0.02 0.12 0.02 0.02 0.03 0.02 0.02 0.02 0.03 0.02 0.30 0.07 0.04 0.04 0.15 0.03 0.07 0.05 0.20 0.02 0.07 Water and Milk 10 30 45 10 5

40 5

5 10 5

5 5

10 5

100 25 10 10 45 15 20 20 50 10 Vegetation and Grain

_RCi/P-dry

.07

.15

.30

.20

.03

.15

.03

.05

.25

.03

.05

.03

.40

.30

.20

.08

.25

.04

.50

.10

.25

.03 Wet Vegetation pCi/k& wet 35 115 200 60 25 190 30 25 45 30 20 20 45 20 400 130 50 40 200 40 80 55 250 30 Soil and Sediment pci/g

.10

.20

.35

.25

.03

.20

.03

.05

.04

.03

.05

.03

.75

.30

.20

.05

.25

.10

.15

.45

.06

.75

.15

.25 Foods Tomatoes Fish Clam Flesh Potatoes, etc.

pCi/2. dry pCi/g. dry pCi/kg, wet

.07

.15

.30

.20

.03

.15

.03

.05

.25

.03

.05

.03

.40

.30

.20

.08

.25

.04

.50

.10

.25

.03

.10

.35

.85 2.40 1.70

.25 1.25

.14

.15

.45

.25

.20

.40

.20 3.50 2.40 1.40 A5 1.90

.30

.10

.50 2.00

.25

.75 20 60 95 20 25 90 10 10 45 10 10 10 45 10 250 50 25 25 90 40 80 40 130 30 50

.01 20

.10 70

Table E-2 Maximun LLD Values Specified by the waN oDCM yth

_Analysis gross beta HI-3 Mn-54 Fe-59 Co-5g,60 Zn-65 Zr-95 Nb-95 1-131 Cs-1,34 Cs-13 7 IBa-140 La-140 Water 4

2000n 15 30 15 30 30 15 I b 18 60 15 Airborne Particular(

or Gases I x 10.2 N,A.

N.A.

7x 10.2 5 xlO-2 6 x 10.2 N.A.

N.A.

Fish N.A.

N.A.

130 260 130 260 N.A.

N.A.

130 150 N.A.

N.A.

NA.

N.A.

15 18 60 15 Food Products PCi/g _Wei N.A.

N.A.

60 60 80 N.A.

N.A.

Sediment N.A.

N.A.

N,A.

N.A.

150 180 N.A.

N.A.

a.

Ifno drinking water Pathway exists, a value of 300P

b..f no driking 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-cheek samples met program performance goals for 2012.

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 2012. 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 2012 External Cross Checks Test Period First Quarter First Quarter First Quarter First Quarter Sample Type / Analysis Water (pCi/L)

Gross Beta Results Known TVA 2.85E+02 3.03E+02 4.47E+03 4.53E+03 Agreement Yes Yes Water (pCi/L)

Water (pCi/L)

Milk (pCi/L) 3 H 131 1 51 Cr 137 C 58Co 54 Mn 59 Fe 65 Zn 60Co 1.84E+02 9.38E+01 3.09E+02 1.06E+02 1.13E+02 9.34E+01 1.38E+02 1.19E+02 2.35E+02 1.97E+02 1.80E+02 9.54E+01 2.98E+02 9.53E+01 1.12E+02 8.98E+01 1.49E+02 1.16E+02 2.37E+02 2.06E+02 8.22E+01 6.85E+O 1 1.25E+01 Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes 1311 89Sr 90Sr 9.29E+0I 9.60E+0 1 1.37E+O1 First Quarter Air Filter (pCi/Filter)

Gross Beta 8.51E+01 7.36E+01 Table F-I continued Results For 2012 External Cross Checks Test Period Sample Type / Analysis Results Known TVA 1.30E+04 1.36E+04 Agreement Third Quarter Third Quarter Water (pCi/L)

Sand (pCi/gram) 141Ce 51Cr 134 Cs 137 Cs 58 Co 54 Mn 59 Fe 65 Zn 60Co 3.85E-01 5.83E-01 2.54E-01 4.09E-01 2.36E-01 4.60E-01 3.57E-01 4.52E-0 1 3.57E-0I 3.39E-01 5.25E-01 2.54E-01 3.76E-01 2.2 1E-01 4.48E-01 3.08E-01 4.51 E-0 1 3.45E-01 0

Third Quarter Third Quarter Air Filter (pCi/Filter)

Gross Beta Air Filter (pCi/Filter) 141Ce 51Cr 134 Cs 137Cs SSCo 54Mn 59Fe 65Zn 6OCo 9.12E+01 8.29E+01 Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes 1.72E+02 2.61E+02 1.14E+02 1.83E+02 1.06E+02 2.06E+02 1.60E+02 2.02E+02 1.60E+02 1.611E+02 2.5 1E+02 1.02E+02 1.80E+02 1.03E+02 2.12E+02 1.54E+02

2. 10OE+02 1.64E+02 9.96E+O1 1.08E+02 1.41E+01 Third Quarter Milk (pCi/L) 131 1 89 Sr 90Sr 9.98E+0 I I.OOE+02 1.61E+01 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 kin) from the plant.

The land use survey was conducted between April 1, 2012, and October 1, 2012, 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 2012 WBN land use survey, annual doses were calculated for air submersion, vegetable ingestion, and milk ingestion. The location of nearest resident remained unchanged during 2012. In addition, the location of the nearest garden changed in a total of six 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 2012 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 2012 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 mrem/year 2011 Approximate Distance (Meters)

Annual Dose 2012 Approximate Distance (Meters)

Sector N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Annual Dose 4,580 3,760 3,353 3,059 3,268 4,416 1,372 1,524 1,585 1,979 4,186 1,829 2,896 1,449 2,077 4,389 0.07 0.21 0.27 0.30 0.26 0.16 0.75 0.36 0.38 0.28 0.09 0.29 0.05 0.19 0.08 0.02 4,590 3,750 3,399 3,072 3,263 4,654 1,409 1,646 1,550 1,832 4,141 2,422 2,901 1,448 2,065 4,376 0.07 0.21 0.27 0.29 0.26 0.14 0.72 0.34 0.40 0.31 0.09 0.19 0.05 0.19 0.08 0.02

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

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 kIn (5 Miles) of Plane mrem/year 2011 2012 Sector N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Approximate Distance (Meters) 7,567 4,010 3,353 5,010 4,669 4,780 1,372 1,771 3,542 2,286 b

3,060 3,470 3,059 2,077 4,920 Approximate Distance (Meters)

Annual Dose 0.51 4.47 5.87 2.44 3.08 3.06 14.80 6.43 2.78 5.51 2.80 0.85 1.08 1.63 0.45 Annual Dose 6,658 5,030 3,793 4,847 4,656 4,931 1,409 1,711

.3,535 b

b 3,080 3,138 2,963 2,065 4,607 0.62 2.79 4.90 2.73 3.09 2.92 14.20 6.76 2.79 2.77 0.99 1.13 1.64 0.50

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 Location Cows Sector ESE SSW SSW Approximate Distance Meters 6,889 2,286 3,353 Annual Dose 2012 2011 0.06 0.27 0.31 X/9 s/in, Farm Nb Farm Lb Farm Hoc 0.05 0.27 0.31 1.31 E-6 2.36 E-6 1.36 E-6 a.

b.

C.

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

Milk being sampled at these locations.

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 0.50, 1.03 and 2.44 mrern/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 - 2012 mR / Quarter (a)

Averaae External Gamma Radiation Levels (b) 1st Qtr 18.9 2nd Otr 17.5 Average 0 - 2 miles (onsite)

Average

> 2 miles (offsite) 3rd Qtr 15.3 13.7 4th Qtr 16.2 15.1 mR/Yr 68 16.4 15.3 61 (a). Field periods normalized to one standard quarter (2190 hours0.0253 days 0.608 hours 0.00362 weeks 8.33295e-4 months )

(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 Location Number 40 41 42 10 43 3

44 45 46 47 48 74 4

49 50 51 52 11 54 75 79 55 56 Dosimeter Station Number N-I N-2 NNE-1 NNE-1A NNE-2 NNE-3 NE-1 NE-2 NE-3 ENE-1 ENE-2 ENE-2A ENE-3 E-1 E-2 ESE-1 ESE-2 SE-1A SE-2 SE-2A SSE-1 SSE-1A SSE-2 Direction, deorees 10 350 21 22 20 17 39 54 47 74 69 69 56 85 92 109 106 138 128 144 146 161 156 Approx

Distance, miles 1.2 4.7 1.2 1.9, 4.1 10.4 0.9 2.9 6.1 0.7 5.8 3.5 7.6 1.3 5.0 1.2 4.4 0.9 5.3 3.1 0.5 0.6 5.8 1st Qtr Jan-Mar 2012 16.6 18.8 17.1 18.2 15.5 11.6 16.6 17.1 13.8 18.8 16.0 12.1 16.0 16.0 16.0 19.3 19.3 21.6 13.8 16.6 17.1 16.0 18.8 2nd Qtr Apr-Jun 2012 19.1 19.1 16.7 14.3 13.8 14.8 21.1 16.7 12.8 16.7 15.3 13.3 16.7 14.3 14.3 12.8 17.7 16.2 13.8 12.8 18.2 12.8 18.6 3rd Qtr Jul-Sep 2012 15.8 17.2 15.3 13.0 13.5 12.1 12.6 15.8 8.9 18.5 14.4 11.2 13.9 13.9 13.9 11.2 21.3 13.5 11.6 12.6 14.9 13.5 13.9 4th Qtr Oct-Dec 2012 17.2 17.7 16.2 14.1 12.1 12.6 18.8 17.2 11.6 18.2 15.2 14.1 15.7 14.1 18.8 12.1 19.8 16.7 12.6 14.1 16.7 13.1 18.2 Annual(')

Exposure mR/Year 68.7 72.8 65.3 59.6 54.9 51.1 69.1 66.8 47.1 72.2 60.9 50.7 62.3 58.3 63.0 55.4 78.1 68.0 51.8 56.1 66.9 55.4 69.5 (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 Location Station Direction,

Distance, Jan-Mar Apr-Jun 00 Number Number 57 S-1 58 S-2 76 S-2A 5

S-3 59 SSW-1 12 SSW-2 60 SSW-3 62 SW-1 63 SW-2 6

SW-3 64 WSW-1 65 WSW-2 66 W-1 14 W-2 77 W-2A 67 WNW-1 68 WNW-2 69 NW-1 70 NW-2 78 NW-2A 2

NW-3 71 NNW-1 72 NNW-2 73 NNW-3 7

NNW-4 dearees 182 185 177 185 199 200 199 226 220 225 255 247 270 277 268 294

.292 320 313 321 317 340 333 329 337 miles 0.7 4.8 2.0 7.8 0.8 1.3 5.0 0.8 5.3 15.0 0.9 3.9 0.9 4.8 3.2 0.9 4.9 1.1 4.7 3.0 7.0 1.0 4.5 7.0 15.0 2012 18.8 (1) 17.1 16.0 28.3 18.8 14.3 19.3 16.6 14.9 18.8 18.8 19.9 14.9 16.0 29.4 21.6 16.0 17.7 14.9 23.8 13.2 17.7 9.3 19.3 2012 18.2 11.4 20.1 13.8 21.6 16.7 9.9 21.6 16.2 14.8 15.3 19.1 17.2 14.8 12.3 26.4 20.1 19.6 16.2 15.3 15.7 14.3 16.7 13.3 15.3 3rd Qtr Jul-Sep 2012 13.5 8.9 19.0 14.9 18.5 13.0 12.1 19.0 13.0 8.9 14.9 17.2 14.4 11.2 16.7 22.7 15.3 16.2 11.2 16.2 15.8 16.7 13.9 10.7 13.0 4th Qtr Annual(1)

Oct-Dec Exposure 2012 mR/Year 15.2 65.7 12.1 43.2 16.7 72.9 13.6 58.3 17.2 85.6 14.7 63.2 11.6 47.9 18.2 78.1 13.6 59.4 15.7 54.3 16.2 65.2 18.2 73.3 15.7 67.2 12.6 53.5 16.2 61.2 23.9 102.4 17.7 74.7 16.7 68.5 17.7 62.8 15.2 61.6 17.7 73.0 13.6 57.8 14.7 63.0 12.1 45.4 12.6 60.2 (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 Location of Facility. RHEA, TENNESSEE Type and Lower Limit Indicator Locations Total Number of Detection Mean (F) of Analysis (LLD)

Range Performed See Note 1 See Note 2 GROSS BETA - 520 Location with Highest Annual Mean Mean (F)

Location Description with Range Distance and Direction See Note 2 Docket Number.

50-390,391 Reporting Period:

2012 Control Locations Mean (F)

Range See Note 2 Number of Nonroutine Reported Measurements See Note 3 GAMMA SCAN (GELI) - 130 AC-228 BE-7 BI-214 K-40 PB-212 PB-214 TL-208 2.00E-03 1.00E-02 2.0012-02 5.OOE-03 4.OOE-02 5.OOE-03 5.OOE-03 2.OOE-03 2.25E-02 (416 1416) 2.49E 4.17E-02 104 VALUES < LLD 1.08E-01 (104/104) 3.52E 1.62E-01 2.33E-02 (87 / 104) 5.OOE 8.50E-02 104 VALUES < LLD 5.23E-03 (4 /104) 5.OOE 5.40E-03 2.33E-02 (81 / 104) 5.30E 8.27E-02 2.00E-03 (1 1 104) 2.OOE 2.00E-03 LMI 0.5 MILES SSW PM2 SPRING CITY 7.0 MILES NW PM3 10.4 MILES NNE PM3 10.4 MILES NNE PM4 7.6 MILES NE/ENE PM3 10.4 MILES NNE LM2 0.5 MILES N LM3 1.9 MILES NNE 2.36E-02 (52 152) 1.21E 4.14E-02 13 VALUES < LLD 1.12E-01 (13113) 3.52E 1.62E-01 2.86E-02 (11 / 13) 9.90E-03 -- 8.43E-02 13 VALUES < LLD 5.40E-03 (1 113) 5.40E 5.40E-03 2.84E-02 (10 / 13) 9.80E 5.84E-02 2.OOE-03 (1113) 2.OOE 2.O0E-03 2.30E-02 (1041104) 1.16E 4.36E-02 26 VALUES < LLD 1.16E-01 (26/26) 8.15E 1.71E-01 2.34E-02 (21 126) 5.20E 6.54E-02 26 VALUES < LLD 5.35E-03 (2 / 26) 5.OOE 5.70E-03 2.38E-02 (20 / 26) 540E 6.31E-02 2.10E-03 (1126) 2.10E 2.10E-03 0%

,H 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/m^3 = 0.037 Bq/m^3 Name of Facility: WAT Location of Facility: RHEA Type and Total Number of Analysis Performed GAMMA SCAN (GELI) - 520 AC-228 BI-214 1-131 K-40 PB-212 PB-214 TL-208 "S BAR NUCLEAR PLANT

s. TENNESSEE Lower Limit Indicator Locations of Detection Mean (F)

(LLD)

Range See Note 1 See Note 2 Location with Highest Annual Mean Mean (F)

Location Description with Range Distance and Direction See Note 2 Docket Number 50-390,391 Reporting Period:

2012 Control Locations Mean (F)

Range See Note 2 Number of Nonroutine Reported Measurements See Note 3 7.OOE-02 5.00E-02 3.OOE-02 3.OOE-01 3.OOE-02 7.OOE-02 2.0012-02 416 VALUES < LLD 9.51E-02 (139/416) 5.01E 3.45E-01 SEE NOTE 4 3.55E-01 (51 /416) 3.03E 4.71E-01 3.07E-02 (1/416) 3.07E 3.07E-02 1.24E-01 (75 /416) 7.05E 3.15E-01 416 VALUES < LLD LMI 0.5 MILES SSW PM3 10.4 MILES NNE LM-4 WB 0.9 MILES SE LM3 1.9 MILES NNE LM2 0.5 MILES N LM-4 WB 0.9 MILES SE 52 VALUES < LLD 1.11E-01 (20/52) 5.02E 2.73E-01 4.01E-01 (6152) 3.66E 4.59E-01 3.07E-02 (1 / 52) 3.07E 3.07E-02 1.56E-01 (8 / 52) 8.34E 2.76E-01 52 VALUES - LLD 104 VALUES < LLD 8.27E-02 (33 / 104) 5.OOE 2.02E-01 3.52E-01 (17/ 104) 301E-01

- 4.22E-01 104 VALUES < LLD 1.11E-01 (11 /104) 7.18E 2.01E-01 104 VALUES < LLD H

I, i4 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

4. The analysis of Charcoal Filters was performed by Gamma Spectroscopy. No 1-131 was detected. The LLD for 1-131 by Gamma Spectroscopy was 0.03 pCi/cubic meter.

Tennessee Valley Authority RADIOACTIVITY IN ATMOSPHERIC MOISTURE pCil/mA3 = 0.037 Bq/mA3 Name of Facility: WATTS BAR NUCLEAR PLANT Locationi of Facility: RHEA. TENNESSEE Docket Number.

50-390,391 Reporting Period:

2012 Type and Total Number of Analysis Performed Lower Limit of Detection (LLD)

See Note 1 Indicator Locations Mean (F)

Range See Note 2 Location with Highest Annual Mean Mean (F)

Location Description with Range Distance and Direction See Note 2 Control Locations Mean (F)

Range See Note 2 Number of Nonroutine Reported Measurements See Note 3 TRITIUM - 208 3.OOE+00 4.29E+00 (13/156) 3.03E+00 - 8.04E+00 LM2 0.5 MILES N 4.59E+00 (8 126) 3.03E+00 -

8.04E+00 3.32E+00 (1 / 52) 3.32E+00

- 3.32E+00

"-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 MILK pCIL. = 0.037 Bq/L Name of Facility: WATTS BAR NUCLEAR PLANT Location of Facility: RHEA, TENNESSEE Docket Number:

50-390,391 Reporting Period:

2012 Type and Total Number of Analysis Performed Lower Limit of Detection (LLD)

See Note 1 Indicator Locations Mean (F)

Range See Note 2 52 VALUES < LLD Location with Highest Annual Mean Mean (F)

Location Description with Range Distance and Direction See Note 2 IODINE-131 - 104 4.OOE-01 GAMMA SCAN (GELI) - 104 AC-228 BI-214 K-40 PB-212 PB-214 TL-208 2.OOE+01 2.08E+01 (1 52) 2.08E+01 2.08E+01 2.OOE+01 4.07E+01 (18/52) 2.01E+01 - 9.95E+01 1.OOE+02 1.28E+03 (52 /52) 1.10E+03 -

1.42E+03 1.50E+01 1.58E+01 (3 /52) 1.51E+01 -

1.69E+01 2.OOE÷01 3.28E+01 (13/52) 2.02E+01 - 6.33E+01 1.00E+01 52 VALUES < LLD LAYMAN FARM 1.3 MILES SSW LAYMAN FARM 1.3 MILES SSW LAYMAN FARM 1.3 MILES SSW NORTON FARM 4.1 MILES ESE LAYMAN FARM 1.3 MILES SSW LAYMAN FARM 1.3 MILES SSW 2.08E+01 (1/26) 2.08E+01 -

2.08E+01 4.49E+01 (9 /26) 2.29E+01 -

9.95E+01 1.30E+03 (26/ 26) 1.19E+03 -

1.40E+03 1.61E+01 (2/26) 1.53E+01 -

1.69E+01 3.33E+01 (7 / 26) 2.02E+01 -

6.33E+01 26 VALUES < LLD Control Locations Mean (F)

Range See Note 2 52 VALUES < LLD 3.22E+01 (1 1 52) 3.22E+01 3.22E+01 3.21E+01 (25 /52) 2.05E+01 - 8.09E+01 1.25E+03 (52 / 52) 1.11E+03 - 1.40E+03 1.78E+01 (3 52) 1.74E+01 1.81E+01 3.28E+01 (13/52) 2.08E+01 - 5.85E+01 52 VALUES < LLD Number of Nonroutine Reported Measurements See Note 3

--J t,,3 CD SR 89 - 15 SR90 - 15 3.50E+00 8 VALUES < LLD 7 VALUES c LLD 7 VALUES < LLD 2.OOE+00 2.42E+00 (1 / 8) 2.42E+00 - 2.42E+00 LAYMAN FARM 1.3 MILES SSW 2.42E+00 (1 /4) 2.42E+00 -.2.42E+00 Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1

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

3. Blanks in this column Indicate no nonrountine measurements

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

Name of Facility. WATTS BAR NUCLEAR PLANT Location of Facility RHEA, TENNESSEE Type and Lower Limit Ind Total Number of Detection of Analysis (LLD)

Performed See Note 1 GAMMA SCAN (GELI) -10 AC-228 2.50E-01 1.18E+i 8.82 BI-212 4.50E-01 1.22E+'

8.54 BI-214 1.50E-01 9.76E-0 8.87 CS-137 3.00E-02 2.03E-C 3.62 K-40 7.50E-01 1.34E+

3.361 PB-212 1.00E-01 1.13E+

8.55 PB-214 1.50E-01 1.05E+

9.32 TL-202

-1.OOE+00 4.02E-0 4.02 TL-208 6.00E-02 3.88E-(

icator Locations Mean (F)

Range See Note 2 00 (8/8)

E 1.31E+00 00 (8/8)

E 1.47E+00 1 (8/8)

E 1.08E+00 11 (6/8)

E 5.39E-01 01 (8/8)

E+00-2.25E+01 00 (8/8)

E 1.27E+00 00 (8/8)

E 1.12E+00 02 (1/8)

E 4.02E-02 11 (8/8)

E 4.31E-01 Location with Highest Annual Mean Mean (F)

Location Description with Range Distance and Direction See Note 2 Docket Number:

50-390,391 Reporting Period:

2012 Control Locations Mean (F)

Range See Note 2 Number of Nonroutine Reported Measurements See Note 3 PM4 7.6 MILES NE/ENE PM2 SPRING CITY 7.0 MILES NW LMI 0.5 MILES SSW PM2 SPRING CITY 7.0 MILES NW LM-4 WB 0.9 MILES SE PM2 SPRING CITY 7.0 MILES NW LM2 0.5 MILES N PM4 7.6 MILES NE/ENE PM4 7.6 MILES NE/ENE 1.31E+00 (1 /1) 1.31E+00-1.31E+00 1.47E+00 (1 /1) 1.47E+00 -

1.47E+00 1.08E+00 (1 /1) 1.08E+00-1.08E+00 5.39E-01 (1 /1) 5.39E 5.39E-01 2.25E+01 (1 1) 2.25E+01-2.25E+01 1.27E+00 (1 / 1) 1.27E+00 -

1.27E+00 1.12E+00 (1 /1) 1.12E+00 -

1.12E+00 4.02E-02 (1/ 1) 4.02E 4.02E-02 4.31E-01 (1 / 1) 4.31E 4.31E-01 7.00E-01 (212) 6.26E 7.73E-01 6.88E-01 (2/2) 6.28E 7.47E-01 9.59E-01 (2/ 2) 8.86E 1.03E+00 2.70E-01 (2 /2) 1.012-01

- 4.40E-01 4.19E+00 (2 /2) 3.78E+00 - 4.60E+00 7.05E-01 (2 /2) 6.21E-01

- 7.88E-01 9.89E-01 (2 / 2) 9.30E 1.05E+00 2 VALUES < LLD 2.20E-01 (2 /2) 1.92E-01

- 2.48E-01

'0~

SR 89 -10 SR 90 -10 1.60E+00 4.00E-01 2.78 8 VALUES < LLD 8 VALUES < LLD 2 VALUES < LLD 2 VALUES < LLD Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1

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

3. Blanks In this column Indicate no nonrountine measurements

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

Name of Facility. WATTS BAR NUCLEAR PLANT Location of Facility: RHEA, TENNESSEE Docket Number:

50-390,391 Reporting Period:

2012, Type and Total Number of Analysis Performed Lower Limit of Detection (LLD)

See Note 1 Indicator Locations Mean (F)

Range See Note 2 1 VALUES e LLD Location with Highest Annual Mean Mean (F)

Location Description with Range Distance and Direction See Note 2 Control Locations Mean (F)

Range See Note 2 Number of Nonroutine Reported Measurements See Note 3 GAMMA SCAN (GELI) - 2 BI-214 K40 PB-214 4.OOE+01 2.50E+02 1.32E+03 (11 1) 1.32E+03-1.32E+03 2.5 MILES NE 2.5 MILES NE 2.5 MILES NE 1 VALUES < LLD 1.32E+03 (1 /1) 1.32E+03 -

1.32E+03 1 VALUES < LLD i VALUES < LLD 1.85E+03 (1/ 1) 1.85E+03 - 1.85E+03 1 VALUES < LLD 8.00E+01 1 VALUES < LLD

.r~.

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

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

3. Blanks in this column indicate no nonrountine measurements

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

Name of Facility: WATTS BAR NUCLEAR PLANT Location of Facility: RHEA, TENNESSEE Docket Number 50-390,391 Reporting Period:

2012 Type and Total Number of Analysis Performed Lower Limit of Detection (LLD)

See Note I "Indicator Locations Mean (F)

Range See Note 2 Location with Highest Annual Mean Mean (F)

Location Description with Range Distance and Direction See Note 2 Control Locations Mean (F)

Range See Note 2 Number of Nonroutine Reported Measurements See Note 3 GAMMA SCAN (GELI) - 2 BI-214 4.OOE+01 5.78E+01 (111) 5.78E+01 5.78E+01 K-40 PS-214 2.50E+02 1.69E+03 (1 1) 1.69E+03-1.69E+03 8.OOE+01 1 VALUES < LLD WBNP 2.5 MILES WNW WBNP 2.5 MILES WNW WBNP 2.5 MILES WNW 5.78E+01 (1 1) 5.78E+01-5.78E+01 1.69E+03 (1 f 1) 1.69E+03 -

1.69E+03 1 VALUES < LLD 6.61E+01 (1 / 1) 6.51E+01

- 6.51E+01 1.82E+03 (1 /1) 1.82E+03 -

1.82E+03 1 VALUES < LLD CD~

i L/t l

Notes: 1.

2.

3.

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

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 Location of Facility: RHEA, TENNESSEE Docket Number.

50-390,391 Reporting Period:

2012 Type and Total Number of Analysis Performed Lower Limit of Detection (LLD)

See Note 1 Indicator Locations Mean (F)

Range See Note 2 Location with Highest Annual Location Description with Distance and Direction Mean Mean (F)

Range See Note 2 Control Locations Mean (F)

Range See Note 2 Number of Nonroutine Reported Measurements See Note 3 GAMMA SCAN (GELI) - 2 BI-214 K-40 PB-212 PB-214 TL-208 4.OOE+01 1.16E+02 (1 /1) 1.16E+02 1.16E+02 2.50E+02 2.06E+03 (1l1) 2.06E+03

-2.06E+03 4.OOE+01 4.33E+01 (1l1) 4.33E+01

-4.33E+01 WBNP 2.5 MILES WNW WBNP 2.5 MILES WNW WBNP 2.5 MILES WNW WBNP 2.5 MILES WNW WBNP 2.5 MILES WNW 1.16E+02 (1 / 1) 1.16E+02 -

1.16E+02 2.06E+03 (1/ 1) 2.06E+03 -

2.06E+03 4.33E+01 (I 11) 4.33E+01 -

4.33E+01 1.01E+02 (1/1) 1.01E+02 -

1.01E+02 1 VALUES < LLD 1.OOE+02 (1/ 1) 1.OOE+02 -

1.00E+02 2.23E+03 (1 1) 2.23E+03 2.23E+03 I VALUES < LLD 8.01E+01 (1 /1) 8.01E+01

- 8.01E+01 1 VALUES < LLD 8.OOE+01 3.00E+01 1.01E+02 (1/1) 1.01E+02 -

1.01E+02 1 VALUES < LLD

-4 0ý 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 POTATOES pCi/Kg = 0.037 Bq/Kg (WET WEIGHT)

Name of Facility; WATTS BAR NUCLEAR PLANT Location of Facility. RHEA, TENNESSEE Docket Number. 50-390,391 Reporting Period:

2012 Type and Total Number of Analysis Performed Lower Limit of Detection (LLD)

See Note 1 4.OOE+01 Indicator Locations Mean (F)

Range See Note 2 Location with Highest Annual Mean Mean (F)

Location Description with Range Distance and Direction See Note 2 Control Locations Mean (F)

Range.

See Note 2 Number of Nonroutine Reported Measurements See Note 3 GAMMA SCAN (GELI) - 2 BI-214 1.D8E+02 (1l1) 1.08E+02

-1

.08E+02 K-40 PB-214 2.50E+02 4.05E+03 (1l1) 4.05E+03

-4.05E+03 8.OOE+01 9.49E+01 (1/l1) 9.49E+01 9.49E+01 WBNP 4 MILES NNW WBNP 4 MILES NNW WBNP 4 MILES NNW 1.08E+02 (1l1) 1.08E+02 -1

.08E+02 4.05E+03 (1/l1) 4.05E+03 -

4.05E+03 9.49E+01 (11l1) 9.49E+01 9.49E+01 1.25E+02 (11/1) 1.25E+02

-1.25E+02 3.51 E+03 (1/1) 3.51E+03

-3.51E+03

1. 12E+02 (1/1) 1.12E+02

-1.12E+02

--4 CD 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 Location of Facility: RHEA, TENNESSEE Type and Lower Limit Indicator Locations Total Number of Detection Mean (F) of Analysis (LLD)

Range Performed See Note 1 See Note 2 GROSS BETA - 39 1.90E+00 2.91E+00 (18/26) 1.91E+00 - 5.65E+00 Location with Highest Annual Mean Mean (F)

Location Description with Range Distance and Direction See Note 2 Docket Number.

50-390,391 Reporting Period:

2012 Control Locations Mean (F)

Range See Note 2 Number of Nonroutine Reported Measurements See Note 3 GAMMA SCAN (GELI) - 39 AC-228 BI-212 BI-214 K-40 PB-212 PB-214 TL-208 00 2.00E+01 5.00E+01 2.00E+01 1.00E+02 1.50E+01 2.OOE+01 1.00E+01 2.02E+01 (1126) 2.02E+01 -

2.02E+01 26 VALUES < LLD 3.52E+01 (13/26) 216E+01 -

1.12E+02 26 VALUES < LLD 1.59E+01 (1 26) 1.59E+01 -

1.59E+01 3.41 E+01 (9 /26) 2.05E+01 -

1.07E+02 26 VALUES < LLD TRM 523.1 TRM 523.1 TRM 523.1 TRM 523.1 TRM 523.1 TRM 523.1 TRM 523.1 TRM 517.9 TRM 517.9 2.95E+00 (10/13) 1.91E+00 -

4.61E+00 2.02E+01 (1 113) 2.02E+01 -

2.02E+01 13 VALUES < LLD 3.96E+01 (7 113) 2.16E+01 -

1.12E+02 13 VALUES < LLD 1.59E+01 (1 / 13) 1.59E+01 -

1.59E+01 4.19E+01 (5/13) 2 05E+01 -

1.07E+02 13 VALUES < LLD 9.08E+02 (1 /13) 9.08E+02 -

9.08E+02 2.54E+00 (7 /13) 1.90E+00

- 3.07E+00 13 VALUES < LLD 13 VALUES < LLD 3.33E+01 (6 /13) 2.53E+01 5.02E+01 13 VALUES < LLD 13 VALUES < LLD 2.82E+01 (5 / 13) 2.15E+01 - 3.46E+01 13 VALUES < LLD 0~

TRITIUM - 39 2.70E+02 5.95E+02 (3 / 26) 2.70E+02 - 9.08E+02 13 VALUES < LLD Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1

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

3. Blanks in this column indicate no nonrountine measurements

Tennessee Valley Authority RADIOACTIVITY IN PUBLIC (DRINKING) WATER (Total) pCi/L = 0.037 Bq/L Name of Facility: WATTS BAR NUCLEAR PLANT Location of Facility: RHEA, TENNESSEE Docket Number.

50-390,391 Reporting Period:

2012 Type and Total Number of Analysis Performed Lower Limit of Detection (LLD)

See Note 1 Indicator Locations Mean (F)

Range See Note 2 Location with Highest Annual Mean Mean (F)

Location Description with Range Distance and Direction See Note 2 Control Locations Mean (F)

Range See Note 2 Number of Nonroutine Reported Measurements See Note 3 GROSS BETA - 39 GAMMA SCAN (GELI) - 39 AC-228

'l BI-214 K-40 PB-212 PB-214 TL-208 1.90E+00 2.86E+00 (14 /26) 2.01E+00 - 4.57E+00 2.OOE+01 2.34E+01 (2 26) 2.14E+01 -

2.54E+01 2.OOE+01 3.04E+O1 (12 126) 2.08E+01 - 5.31E+01 1.00E+02 26 VALUES < LLD 1.50E+01 26 VALUES < LLD 2.OOE+01 2.96E+01 (7/26) 2.15E+01 -

3.44E+01 1.00E+01 26 VALUES < LLD 2.70E+02 7.26E+02 (6 /34) 4.83E+02-1.13E+03 CF INDUSTRIES TRM 473.0 CF INDUSTRIES TRM 473.0 CF INDUSTRIES TRM 473.0 RM-2 DAYTON TN 17.8 MILES NNE RM-2 DAYTON TN 17.8 MILES NNE RM-2 DAYTON TN 17.8 MILES NNE RM-2 DAYTON TN 17.8 MILES NNE RM-2 DAYTON TN 17.8 MILES NNE 3.OOE+00 (5 /13) 2.45E+00 -

3.68E+00 2.54E+01 (1 / 13) 2.54E+01 -

2.54E+01 3.39E+01 (6 /13) 2.59E+01 -

5.31E+01 13 VALUES < LLD 13 VALUES < LLD 3.02E+01 (2 /13) 2.78E+01. -

3.26E+01 13 VALUES < LLD 7.43E+02 (3 / 17) 4.98E+02 -

1.13E+03 2.54E+00 (7 / 13) 1.90E+00

- 3.07E+00 3.33E+01 (6/13) 2.53E+01 - 5.02E+01 13 VALUES < LLD 13 VALUES < LID 2.82E+01 (5 / 13) 2.15E+01

- 3.46E+01 13 VALUES < LLD 13 VALUES < LLD 13 VALUES < LLD TRITIUM - 47 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 (GROUND) WATER (Total) pCi/L = 0.037 Bq/L Name of Facility: WATTS BAR NUCLEAR PLANT Location of Facility: RHEA, TENNESSEE Type and Lower Limit Indicator Locations Total Number of Detection Mean (F) of Analysis (LLD)

Range Performed See Note 1 See Note 2 GROSS BETA - 91 1.90E+00 3.03E+00 (48 / 65) 1.95E+00 - 6.19E+00 Location with Highest Annual Mean Mean (F)

Location Description with Range Distance and Direction See Note 2 Docket Number.

50-390,391 Reporting Period:

2012 Control Locations Mean (F)

Range See Note 2 Number of Nonroutine Reported Measurements See Note 3 WBN WELL #1 0.6 MILES S 00 0

GAMMA SCAN (GELI) - 91 AC-228 BI-212 BI-214 CS-137 K-40 PB-212 PB-214 TL-208 2.OOE+01 5.OOE+01 2.0012+01 5.OOE+00 1.OOE.02 1.50E*01 2.OOE+01 1.OOE+01 2.25E+01 (3/65) 2.19E+01 - 2.37E+01 65 VALUES < LLD 3.96E+01 (31 /65) 2.12E+01 -

8.71E+01 65 VALUES < LLD 1.32E+02 (1 65) 1.32E+02-1.32E+02 1.67E+01 (7 / 65) 1.51E+01 -

1.91E+01 3.84E+01 (20 / 65) 2.06E+01 - 7.94E÷01 65 VALUES < LLD WBN MW-B 0.45 MILES SSE)

WBN MW-B 0.45 MILES SSE)

WBN WELL #1 0.6 MILES S WBN MW-C 0.25 MILES ESE)

WBN MW-C 0.25 MILES ESE)

WBN MW-S 0.45 MILES SSE)

WBN MW-B 0.45 MILES SSE) 3.51E+00 (11 / 13) 1.97E+00-6.19E+00 2.37E+01 (1/13) 2.37E+01-2.37E+01 13 VALUES < LLD 5.38E+01 (4/13) 2.50E+01 -

7.87E+01 13 VALUES < LLD 1.32E+02 (1 113) 1.32E+02 -

1.32E+02 1.91E+01 (1 /13) 1.91E+01 -

1.91E+01 4.30E+01 (4/13) 3.30E+01 -

5.61E+0i 13 VALUES < LWD 1.38E+03 (13 / 13) 1.21E+03 -

1.52E+03 2.71E4-00 (9 /26) 1.91E+00 - 4.61E+00 2.09E+01 (1 /26) 2.09E+01

- 2.09E+01 5.74E+01 (1 /26) 5.74E+01

- 5.74E+01 6.39E+01 (14/26) 2.49E+01 - 1.68E+02 26 VALUES < LLD 26 VALUES < LLD 1.75E+01 (2 126) 1.61E+01

- 1.89E+01 6.28E+01 (12 /26) 2.32E+01 - 1.66E+02 26 VALUES < LLD CD TRITIUM - 91 2.70E+02 1.07E+03 (33 / 65) 4.31E+02 -

1.52E+03 26 VALUES < LLD Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1

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

3. Blanks in this column indicate no nonrountine measurements

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

Name of Facility. Wi Location of Facility: RH Type and Total Number of Analysis Performed GAMMA SCAN (GELI) - 6 AC-228 BI-212 BI-214 CS-137 K-40 PB-212 PB-214 TL-208 ATTS BAR NUCLEAR PLANT lEA, TENNESSEE Lower Limit Indicator Locations of Detection Mean (F)

(LLD)

Range See Note 1 See Note 2 Docket Number:

50-390,391 Reporting Period:

2012 Control Locations Mean (F)

Range See Note 2 Location with Highest Annual Mean Mean (F)

Location Description with Range Distance and Direction See Note 2 Number of Nonroutine Reported Measurements See Note 3 1.OOE-01 2.50E-01 1.00E-01 3.OOE-02 4.00E-01 4.OOE-02 5.OOE-01 3.OOE-02 4 VALUES < LLD 4 VALUES < LLD 1.56E-01 (314) 1.02E 2.16E-01 4 VALUES < LLD 1.27E+01 (4 /4) 1.14E+01 -

1.50E+01 4.61E-02 (214) 4.35E 4.86E-02 4 VALUES < LLD 4 VALUES < LLD DOWNSTREAM STATION 1 DOWNSTREAM CHICKAMAUGA RES TRM 471-530 CHICKAMAUGA RES TRM 471-530 CHICKAMAUGA RES TRM 471-530 CHICKAMAUGA RES TRM 471-530 DOWNSTREAM STATION I DOWNSTREAM DOWNSTREAM STATION 1 DOWNSTREAM CHICKAMAUGA RES TRM 471-530 2 VALUES < LLD 2 VALUES < LLD 1.59E-01 (2 /2) 1.02E 2.16E-01 2 VALUES < LLD 1.37E+01 (2/2) 1.24E+01-1.50E+01 4.86E-02 (1 2) 4.86E 4.86E-02 2 VALUES < LLD 2 VALUES < LLD 2 VALUES < LLD 2 VALUES < LLD 1.90E-01 (1 12) 1.90E 1.90E-01 3.OOE-02 (1 12) 3.OOE 3.OOE-02 1.17E+01 (2/2) 9.26E+00 1.42E+01 5.50E-02 (1 2) 5.50E 5.50E-02 2 VALUES c LLD 2 VALUES < LLD CD 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 pCil/g = 0.037 Bq/g (DRY WEIGHT)

Name of Facility: Wi Location of Facility: RH Type and Total Number of Analysis Performed GAMMA SCAN (GELI) -6 81-214 CS-1 37 K-40 PB-212 PB-214 TL-208 ATTS BAR NUCLEAR PLANT lEA, TENNESSEE Lower Limit Indicator Locations of Detection Mean (F)

(LLD)

Range See Note 1 See Note 2 1.00E-01 1.73E-01 (2/4) 1.69E 1.77E-01 3.00E-02 3.06E-02 (1 4) 3.06E 3.06E-02 4.00E-01 1.41E+01 (4/4) 1.27E+01 -

1.61E+01 4.00E-02 4 VALUES < LLD 5.00E-01 4 VALUES < LLD 3.00E-02 4 VALUES < LLD Location with Highest Annual Mean Mean (F)

Location Description with Range Distance and Direction See Note 2 Docket Number-50-390,391 Reporting Period:

2012 Control Locations Mean (F)

Range See Note 2 Number of Nonroutine Reported Measurements See Note 3 DOWNSTREAM STATION 1 DOWNSTREAM DOWNSTREAM STATION 1 DOWNSTREAM DOWNSTREAM STATION 1 DOWNSTREAM DOWNSTREAM STATION 1 DOWNSTREAM CHICKAMAUGA RES TRM 471-530 CHICKAMAUGA RES TRM 471-530 1.73E-01 (2/2) 1.69E 1.77E-01 3.08E-02 (1/2) 3.06E 3.06E-02 1.51E+01 (2/2) 1.41E+01 -

1.61E+01 2 VALUES < LLD 2 VALUES < LLD 2 VALUES < LLD 1.13E-01 (2/2) 1.07E 1.19E-01 2 VALUES < LLD 1.45E+01 (2 2) 1.44E+01 1.46E+01 2 VALUES < LLD 2 VALUES < LLD 2 VALUES < LLD 43 CdI I00 Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1

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

3. Blanks In this column indicate no nonrountine measurements

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

Name of Facility: WATTS BAR NUCLEAR PLANT Location of Facility: RHEA, TENNESSEE Type and Lower Limit Indicator Locations Total Number of Detection Mean (F) of Analysis (LLD)

Range Performed See Note 1 See Note 2 GAMMA SCAN (GELI) - 4 AC-228 2.50E-01 1.17E+00 (1/2) 1.17E+00-1.17E+00 BE-7 2.50E-01 1.88E+00 (2 2) 1.87E+00-1.89E+00 SI-212 4.50E-01 1.13E+00 (1 /2) 1.13E+00 -

1.13E+00 BI-214 1.50E-01 8.38E-01 (2 /2) 2.81E-01 1.39E+00 CS-137 3.OOE-02 1.38E-01 (1 /2) 1.38E 1.38E-01 K-40 7.50E-01 8.05E+00 (2 12) 4.34E+00 - 1.18E+01 PB-212 1.00E-01 6.91E-01 (2 12) 2.19E 1.16E+00 PB-214 1.50E-01 8.67E-01 (2 /2) 2.84E-01 1.45E+00 TL-208 6.OOE-02 2.45E-01 (2 /2) 6.77E 4.22E-01 Docket Number-50-390,391 Reporting Period:

2012 Control Locations Mean (F)

Location with Highest Annual Mean Mean (F)

Number of Nonroutine Reported Measurements See Note 3 Location Description with Distance and Direction COTTON PORT MARINA TRM 513 COTTON PORT MARINA TRM 513 COTTON PORT MARINA TRM 513 COTTON PORT MARINA TRM 513 COTTON PORT MARINA TRM 513 COTTON PORT MARINA TRM 513 COTTON PORT MARINA TRM 513 COTTON PORT MARINA TRM 513 COTTON PORT MARINA TRM 513 Range See Note 2 Range See Note 2 1.17E+00 (1/2) 1.17E+00 -

1.17E+00 1.88E+00 (2 / 2) 1.87E+00 -

1.89E+00 1.13E+00 (1/2) 1.13E+00 -

1.13E+00 8.38E-01 (2/2) 2.81E 1.39E+00 1.38E-01 (1/ 2) 1.38E 1.38E-01 8.05E+00 (2 / 2) 4.34E+00-1.18E+01 6.91E-01 (2/2) 2.19E 1.16E+00 8.67E-01 (2 / 2) 2.84E 1.45E+00 2.45E-01 (2/2) 6.77E 4.22E-01 9.61E-01 (2/2) 3.95E 1.53E+00 2 VALUES < LLD 1.63E+00 (1 / 2) 1.63E+00 -

1.63E+00 8.65E-01 (212) 5.59E-01

- 1.17E+00 2 VALUES < LLD 1.15E+01 (2/2) 7.19E+00 - 1.59E+01 9.46E-01 (2 /2) 3.75E 1.52E+00 8.77E-01 (2 2) 5.02E-01

- 1.25E+00 3.15E-01 (2/2) 1.18E 5.11E-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: WA Location of Facility: RHE Type and Total Number of Analysis Performed GAMMA SCAN (GELI)

- 5 AC-228 BE-7 BI-212 BI-214 CO-58 CO-60 CS-1 37 K-40 PB-212 PB-214 SB-125 TL-208 Number of Nonroutine Reported Measurements' See Note 3 ITS BAR NUCLEAR PLANT A, TENNESSEE Lower Limit Indicator Locations of Detection Mean (F)

(LLD)

Range See Note 1 See Note 2 2.50E-01 8.38E-01 (5/5) 7.19E 9.26E-01 2.50E-01 2.77E-01 (3/5) 2.57E 2.92E-01 4.50E-01 9.08E-01 (5/5) 7.02E 1.09E+00 1.50E-01 7.50E-01 (515) 6.35E 8.84E-01 3.OOE-02 5 VALUES < LLD 3.OOE-02 7.26E-02 (4/5) 3.86E 1.69E-01 3.OOE-02 1.11E-01 (4/5) 5.83E 1.65E-01 7.50E-01 1.02E+01 (5/5) 8.68E+00 -

1.36E+01 1.00E-01 8.15E-01 (5/5) 6.97E 9.67E-01 1.50E-01 7.96E-01 (5/5) 6.63E 9.61E-01

-1.00E+00 1.23E-01 (2/5) 2.90E 2.17E-01 6.00E-02 2.67E-01 (5/5) 2.21E 3.19E-01 Location with Highest Annual Mean Mean (F)

Location Description with Range Distance and Direction See Note 2 Docket Number.

50-390,391 Reporting Period:

2012 Control Locations Mean (F)

Range See Note 2 0

YP-5 YARD POND YP-13 YARD POND YP-5 YARD POND YP-5 YARD POND YP-17 YARD POND YP-16 YARD POND LV-3 LOW VOL WASTE POND YP-5 YARD POND YP-5 YARD POND YP-5 YARD POND YP-16

-YARD POND YP-5 YARD POND 9.26E-01 (1l1) 9.26E 9.26E-01 2.92E-01 (1ll) 2.92E-01 2.92E-01 1.09E+00 (1/1) 1.09E+00 1.09E+00 8.84E-01 (1/1) 8.84E-01 8.84E-01 1 VALUES < LLD 1.69E-01 (11l/l) 1.69E-01 1.69E-01 1.65E-01 (Il/l) 1.65E-01 1.65E-01 1.36E+01 (1l1) 1.36E+01 -

1.36E+01 9.67E-01 (11/1) 9.67E-01 9.67E-01 9.61 E-01 (1l1) 9.61E 9.61 E-01 2.17E-01 (1l1) 2.17E 2.17E-0i 3.19E-01 (1l1) 3.19E-01 3.19E-01 VALUES < LLD VALUES < LLD VALUES < LLD VALUES < LLD VALUES < LLD VALUES < LLD VALUES < LLD VALUES < LLD VALUES < LLD VALUES < LLD VALUES < LLD VALUES < LD 00 Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 1

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

3. Blanks in this column indicate no nonrountine measurements

- Figure-H-1--

Direct Radiation Direct Radiation Levels Watts Bar Nuclear Plant Four Quarter Moving Average 25 InLight Dosimeter

1*

11*Deployment 20 Inial WRNP January. 2007

koperation in

" R~r*)

,j3,..*

"*January, 1996 a

I I

E 10

-- - On-Site I

I Off-Site II I

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 Initial Operation of WBNP E

0.10 in January, 1996 0.

2 0.05 0.001985 1

1 2

2 2

2 1975 1980 1985 1990 1995 2000 2005 2010 2015 Calendar Year

-- Idctor

-S3 Control 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 0.9 0.8

0.

Initial WBN Operation in 0.7 January,, 1996 0.5 C.

0.4 i

0.3 0.2 0.1 0.0 I

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

-- 3 Control 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.

Figure-H-4 Gross Beta Activity in Surface Water Annual Average Gross Beta Activity in Surface Water Watts Bar Nuclear Plant 5

4 3

2 Initial WBN Operation in January, 1996

-I a.

U 1

197 5 1980 1985 1990

.1995 2000 2005 2010 2015 Calendar Year

-a Indicator (Downstream) Control (Upstream)

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.

~

Figure-H-5--

Gross Beta Activity in Drinking Water 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.

- Figure H Radioactivity in Fish Annual Average Activity of Cs-137 in Commerical Fish 0.30

.. Watts Bar Nuclear Plant 0.25 0.20 0.15 Initial WBN Operation I1 in January, 1996 CL 0.10 0.05 0.00 1975 1980 1985 1990 1995 2000 2005 2010 201 Calendar Year is r

Indicator Control 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 Radioactivity in Shoreline Sediment 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.

ML13140A043

Text

Subject:

SUMMARY

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