Nuclear Regulatory Commission - Tennessee Valley Authority, … · 2012. 7. 20. · Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 May 15, 2012 10 CFR

Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402

May 15, 2012

10 CFR 50.4

ATTN: Document Control DeskU. S. Nuclear Regulatory CommissionWashington, D.C. 20555-0001

Watts Bar Nuclear Plant, Unit 1Facility Operating License No. NPF-90NRC Docket No. 50-390

Subject: ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATINGREPORT - 2011

In accordance with the requirements of the Watts Bar Nuclear Plant (WBN), Unit 1,Technical Specifications (TS), Section 5.9.2, "Annual Radiological EnvironmentalOperating Report," and the WBN Offsite Dose Calculation Manual (ODCM),Administrative Control Section 5.1, the WBN, Unit 1,2011 Annual RadiologicalEnvironmental Monitoring Program (REMP) results are enclosed. The report, which isrequired by WBN, Unit 1, TS Section 5.9.2 to be submitted by May 15 of each year,covers the operation of the unit for the January 1, 2011, through the December 31,2011, time period.

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

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

R etfully,

a ger, Corporate Nuclear Licensing

cc: See Page 2

Printed on recycled paper

U. S. Nuclear Regulatory CommissionPage 2May 15, 2012

Enclosure:Annual Radiological Environmental Operating Report - 2011

cc (Enclosure):NRC Regional Administrator - Region IINRC Senior Resident Inspector - Watts Bar Nuclear Plant, Unit 1NRC Senior Resident Inspector - Watts Bar Nuclear Plant, Unit 2

Enclosure

Watts Bar Nuclear PlantUnit 1

Annual Radiological Environmental Operating Report - 2011

AnnualRadiologicalEnvironmentalOperating Report

Watts BarNuclear Plant2011

ANNUAL ENVIRONMENTAL RADIOLOGICAL OPERATING REPORTWATTS BAR NUCLEAR PLANT

2011

TENNESSEE VALLEY AUTHORITY

April 2012

TABLE OF CONTENTS

Table of Contents .............................................

Executive Summ ary ..........................................

Introduction ................................................. 3Naturally Occurring and Background Radioactivity ................. 3Electric Power Production ..................................... 4

Site/Plant Description .......................................... 7

Radiological Environmental Monitoring Program .................... 9

Direct Radiation Monitoring ..................................... 12M easurement Techniques ...................................... 12R esults .................................................... 12

Atmospheric Monitoring ...................................... 15Sample Collection and Analysis ................................ 15R esults .................................................... 16

Terrestrial M onitoring ......................................... 18Sample Collection and Analysis ................................ 18R esults .................................................... 19

Liquid Pathway Monitoring ..................................... 21Sample Collection and Analysis ................................ 21R esults .................................................... 22

Assessment and Evaluation ..... ................................ 25R esults .................................................. 25Conclusions ................................................ 26

References ................................................... 27

Table 1 Comparison of Program Lower Limits of Detection with RegulatoryLimits for Maximum Annual Average Effluent ConcentrationsReleased to Unrestricted Areas and Reporting Levels ........... 28

Figure 1 Tennessee Valley Region ................................. 29

Figure 2 Environmental Exposure Pathways of Man Dueto Releases of Radioactive Materials to theAtmosphere and Lake .................................... 30

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TABLE OF CONTENTS (continued)

Appendix A Radiological Environmental Monitoring Program andSampling Locations .................................. 31

Appendix B Program Modifications ................................ 42

Appendix C Program Deviations .................................. 44

Appendix D Analytical Procedures ................................ 47

Appendix E Nominal Lower Limits of Detection (LLD) ................ 50

Appendix F Quality Assurance/Quality Control Program ............... 55

Appendix G Land Use Survey .................................... 60

Appendix H Data Tables and Figures .............................. 66

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EXECUTIVE SUMMARY

This report describes the radiological environmental monitoring program conducted by TVA in

the vicinity of the Watts Bar Nuclear Plant (WBN) in 2011. The program includes the collection

of samples from the environment and the determination of the concentrations of radioactive

materials in the samples. Samples are taken from stations in the general area of the plant and

from areas that should not be influenced by plant operations. Material sampled includes air,

atmospheric moisture, water, milk, food crops, soil, fish, sediment, and direct radiation levels.

Results from stations near the plant are compared with concentrations from control locations and

with preoperational measurements to determine potential impacts of plant operations.

The analyses performed on WBN Radiological Environmental Monitoring Program (REMP)

samples for the 2011 monitoring year did not detect any fission or activation product

radionuclides attributable to WBN plant operations. Except for the period between March 2011

and April 2011, the levels of naturally occurring radionuclides identified by these analyses were

consistent with the normal background levels measured in previous monitoring years. During

the period of March 2011 and April 2011, WBN REMP air filters, charcoal cartridge, ,and milk

samples showed low levels of radioactivity both in the on-site (indicator) and the off-site

(control) samples. as a result of the incident with the Fukushima nuclear plant in Japan on

March 11, 2011. As such, the atypical detection of these radionuclides in both indicator and

control samples is credibly attributed to the trans-Pacific transport of airborne releases from

Dai-ichi, Fukushima following the March 11, 2011 Tohoku earthquake and is not related to the

WBN plant operations. The Environmental Protection Agency (EPA) and other US nuclear

facilities identified trace amounts of radioactive iodine, cesium, and tellurium in the

environmental samples consistent with the Japanese nuclear incident. These levels are also

consistent with the levels found by a Department of Energy monitoring program. Similar results

were observed in the radiological environmental monitoring sample results following the

Chernobyl plant event in Ukraine in 1986. However, the concentrations detected in the REMP

samples during 2011 are conservatively included in this report for completeness.

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The majority of environmental radioactivity measured by the program was due to naturally

occurring radioactive materials or radionuclides commonly found in the environment as a result

of atmospheric fallout and the operation of other nuclear facilities in the area. Low levels of

Cesium (Cs)-137 were measured in soil, fish, and shoreline sediment samples. The Cs-137

concentrations were consistent with the preoperational monitoring program results and with

levels normally found in the environment as the result of past nuclear weapons testing. Trace

levels of tritium were detected in a limited number of atmospheric moisture samples. Tritium at

concentrations slightly above the analytical detection limit was also detected in a small number

of water samples collected from Chickamauga Reservoir. These levels would not represent a

significant contribution to the radiation exposure to members of the public.

Tritium was detected in onsite ground water monitoring wells. The tritium was the result of

onsite ground water contamination from previously identified and repaired leaks in plant

systems. In addition, cobalt (Co)-58, cobalt (Co)-60, Cs-137, and antimony (Sb)-125 were

identified in sediment collected from the onsite ponds. The level of activity measured in these

onsite locations would not present a risk of exposure to the general public.

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INTRODUCTION

This report describes and summarizes the results of radioactivity measurements made in the

vicinity of WBN and laboratory analyses of samples collected in the area. The measurements are

made to comply with the requirements of 10 CFR 50, Appendix A, Criterion 64 and 1.0 CFR 50,

Appendix I, Section IV.B.2, IV.B.3 and IV.C and to determine potential effects on public health

and safety. This report satisfies the annual reporting requirements of WBN Technical

Specification 5.9.2 and Offsite Dose Calculation Manual (ODCM) Administrative Control 5.1.

In addition to reporting the data prescribed by specific requirements, other information is

included to help correlate the significance of results measured by this monitoring program to the

levels of environmental radiation resulting from naturally occurring radioactive materials.

Naturally Occurring and Background Radioactivity

Most materials in our world today contain trace amounts of naturally occurring radioactivity.

Potassium (K)-40, with a half-life of 1.3 billion years, is one of the major types of radioactive

materials found naturally in our environment. Approximately 0.01 percent of all potassium is

radioactive potassium-40. Other examples of naturally occurring radioactive materials are

beryllium (Be)-7, bismuth (Bi)-212 and 214, lead (Pb)-212 and 214, thallium (Tl)-208, actinium

(Ac)-228, uraium (U)-238 and 235, thorium (Th)-234, radium (Ra)-226, radon (Ra)-222, carbon

(C) -14, and hydrogen (H)-3 (generally called tritium). These naturally occurring radioactive

materials are in the soil, ouir food, our drinking water, and our bodies. The radiation from these

materials makes up a part of the low-level natural background radiation. The remainder of the

natural background radiation results from cosmic rays.

It is possible to get an idea of the relative hazard of different types of radiation sources by

evaluating the amount of radiation the U.S. population receives from each general type of

radiation source. The information below is primarily adapted from References 2 and 3.

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U.S. GENERAL POPULATION AVERAGE DOSE EQUIVALENT ESTIMATES

Source millirem (mrem)/Year Per Person

Natural background dose equivalentCosmic 27Cosmogenic 1Terrestrial 28In the body 39Radon 200

Total 295

Release of radioactive material innatural gas, mining, ore processing, etc. 5

Medical (effective dose equivalent) 53

Nuclear weapons fallout less than I

Nuclear energy 0.28

Consumer products 0.03

Total 355 (approximately)

As can be seen from the data presented above, natural background radiation dose equivalent to

the U.S. population normally exceeds that from nuclear plants by several hundred times. This

indicates that nuclear plant operations normally result in a population radiation, dose equivalent

which is insignificant compared to that which results from natural background radiation. It

should be noted that the use of radiation and radioactive materials for medical uses has resulted

in a similar effective dose equivalent to the U.S. population as that caused by natural background

cosmic and terrestrial radiation.

Electric Power Production

Nuclear power plants are similar in many respects to conventional coal burning (or other fossil

fuel) electrical gernerating plants. The basic process behind electrical power production in both

types of plants is that fuel is used to heat water to produce steam which provides the force to turn

turbines and generators. In a nuclear power plant, the fuel is uranium and heat is produced in the

reactor through the fission of the uranium. Nuclear plants include many complex systems to

control the nuclear fission process and to safeguard against the possibility of reactor malfunction.

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

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

systems. This radioactive material can be transported throughout plant systems and some of it

released to the environment.

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

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

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

I

Releases are monitored at the onsite points of release and through the radiological environmental

monitoring program whichmeasures the environmental radiation in areas around the plant. In

this way, the release of radioactive materials from the plant is tightly controlled, and verification

is provided that the public is not exposed to significant levels of radiation or radioactive

materials as the result of plant operations.

The WBN ODCM, which describes the program required by the plant Technical Specifications,

prescribes limits for the release of radioactive effluents, as well as limits for doses to the general

public from the release of these effluents.

The dose to a member of the general public from radioactive materials released to unrestricted

areas, as given in Nuclear Regulatory Commission (NRC) guidelines and the ODCM, is limited

as follows:

Liquid Effluents

Total body <3 mrem/YearAny organ <10 mrem/Year

Gaseous Effluents

Noble gases:

Gamma radiation <10 millirad (mrad)/YearBeta radiation <20 mrad/Year

Particulates:

Any organ <15 mrem/Year

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The EPA limits for the total dose to the public in the vicinity of a nuclear power plant,

established in the Environmental Dose Standard of 40 CFR 190, are as follows:

Total body <25 mrem/yearThyroid <75 nirem/yearAny 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.

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SITE/PLANT DESCRIPTION

The WBN site is located in Rhea county, Tennessee, on the west bank of the Tennessee River at

Tennessee River Mile (TRM) 528. Figure 1 shows the site in relation to other TVA projects.

The WBN site, containing approximately 1770 acres on Chickamauga Lake, is approximately

2 miles south of the Watts Bar Dam and approximately 31 miles north-northeast of TVA's

Sequoyah Nuclear Plant (SQN) site. Also located within the reservation are the Watts Bar Dam

and Hydro-Electric Plant, the Watts Bar Steam Plant (not in operation), the TVA Central

Maintenance Facility, and the Watts Bar Resort Area.

Approximately 16,000 people live within 10 miles of the WBN site. More than 80 percent of

these live between 5 and 10 miles from the site. Two small towns, Spring City and Decatur, are

located in this area. Spring City, with a population of approximately 2,200, is northwest and

north-northwest from the site, while Decatur, with about 1,500 people, is southand south-

southwest from the plant. The remainder of the area within 10 miles of the site is sparsely

populated, consisting primarily of small farms and individual residences.

The area between 10 and 50 miles from the site includes portions of the cities of Chattanooga

and Knoxville. The largest urban concentration in this area is the city of Chattanooga, located to

the southwest and south-southwest. The city of Chattanooga has a population of about 170,000,

with approximately 80 percent located between 40 and 50 miles from the site and the remainder

located beyond 50 miles. The city of Knoxville is located to the east-northeast, with not more

than 10 percent of its 185,000 plus people living within 50 miles of the site. Three smaller urban

areas of greater than 20,000 people are located between 30 and 40 miles from the site. Oak

Ridge is approximately 40 miles to the northeast, the twin cities of Alcoa and Maryville are

located 45 to 50 miles to the east-northeast, and Cleveland is located about 30 miles to the south.

Chickamauga Reservoir is one of a series of highly controlled multiple-use reservoirs whose

primary uses are flood control, navigation, and the generation of electric power. Secondary

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

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

reservoir shoreline.

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WBN consists of two pressurized water reactors. WBN Unit 1 received a low power operating

license (NPF-20) on November 9, 1995 and achieved initial criticality in January 1996. The full

power operating license (NPF-90) was received on February 7, 1996. Commercial operation was

achieved May 25, 1996. WBN Unit 2 was deferred October 24, 2000, in accordance with the

guidance in Generic Letter 87-15, "Policy Statement on Deferred Plants." On August 3, 2007,

TVA provided notice of its intent to reactivate and complete construction of WBN Unit 2. WBN

Unit 2 resumed construction in late 2007, and expects to complete construction and request an

operating license by December 2015.

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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

Most of the radiation and radioactivity generated in a nuclear power reactor is contained within

the reactor systems. Plant effluent radiation monitors are designed to monitor radionuclides

released to the environment. Environmental monitoring is a final verification that the systems

are performing as planned. The monitoring program is designed to monitor the pathways

between the plant and the people in the immediate vicinity of the plant. Sample types are chosen

so that the potential for detection of radioactivity in the environment will be maximized. The

Radiological Environmental Monitoring Program (REMP) and sampling locations for WBN are

outlined in Appendix A.

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

humans: air and water (see Figure 2). The air pathway can be separated into two components:

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

airborne pathway consists of direct radiation and inhalation by humans. In the terrestrial

pathway, radioactive materials may be deposited on the ground or on plants and subsequently

ingested by animals and/or humans. Human exposure through the liquid pathway may result

from drinking water, eating fish, or by direct exposure at the shoreline. The types of samples

collected in this program are designed to monitor these pathways.

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

samples. The locations for the atmospheric monitoring stations were determined from a critical

pathway analysis based on weather patterns, dose projections, population distribution, and land

use. Terrestrial sampling stations were selected after reviewing such things as the locations of

dairy animals and gardens in conjunction with the air pathway analysis. Liquid pathway stations

were selected based on dose projections, water use information, and availability of media such as

fish and sediment. Table A-2 (Appendix A, Table 2: This notation system is used for all tables

and figures given in the appendices.) lists the sampling stations and the types of samples

collected from each. There were no modifications made in the WBN REMP in 2011.

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

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Deviations occur in the monitoring program due to equipment problems with automatic sampling

systems, and/or sample unavailability. Program deviations to the sampling program during 2011

are included in Appendix C.

To determine the amount of radioactivity in the environment prior to the operation of WBN, a

preoperational radiological environmental monitoring program was initiated in December 1976

and operated through December 31, 1995. Measurements of the same types of radioactive

materials that are measured currently were assessed during the preoperational phase to establish

normal background levels for various radionuclides in the environment. During the 1950s,

1960s, and 1970s, atmospheric nuclear weapons testing released radioactive material to the

environment causing fluctuations in background radiation levels. Knowledge of preexisting

radionuclide patterns in the environment permits a determination, through comparison and

trending analyses, of the actual environmental impact of WBN operation.

The determination of environmental impact during the operating phase also considers the

presence of control stations that have been established in the environment. Results of

environmental samples taken at control stations (far from the plant) are compared with those

from indicator stations (near the plant) to aid in the determination of the impacts from WBN

operation.

The sample analysis is performed by the Tennessee Valley Authority's (TVA's) Environmental

Radiological Monitoring and Instrumentation (ERM&I) group located at the Western Area

Radiological Laboratory (WARL) in Muscle Shoals, Alabama, except for the

strontium (Sr)-89, 90 analysis of soil samples which is performed by a contract laboratory.

Analyses are conducted in accordance with written and approved procedures and are based on

accepted methods. A summary of the analysis techniques and methodology is presented in

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

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

this program.

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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.

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DIRECT RADIATION MONITORING

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

These measurements include contributions from cosmic radiation, radioactivity in the

ground, fallout from atmospheric nuclear weapons tests conducted in the past, and any

radioactivity that may be present as a result of plant operations. Because of the relatively

large variations in background radiation as compared to the small levels from the plant,

contributions from the plant may be difficult to distinguish.

Measurement Techniques

The Landauer InLight environmental dosimeter is used in the radiological environmental

monitoring program for the measurement of direct radiation. This dosimeter contains

four elements consisting of aluminum oxide detectors with open windows as well as plastic and

copper filters. The dosimeter is processed using optically stimulated luminescence (OSL)

technology to determine the amount of radiation exposure.

The dosimeters are placed approximately one meter above the ground, with two at each

monitoring location. Sixteen monitor'ing points are located around the plant near the site

boundary, one location in each of the 16 compass sectors. One monitoring point is also

located in each of the 16 compass sectors at a distance of approximately four to five miles

from the plant.

Dosimeters are also placed at additional monitoring locations out to approximately

15 miles from the site. The dosimeters are exchanged every three months. Thedosimeters are

sent to Landauer InLight for processing and results reporting. The values are corrected for

transit and shielded background exposure. An average of the two dosimeter results is

calculated for each monitoring point. The system meets or exceeds the performance

specifications outlined in American National Standards Institute (ANSI) N545-1975 and Health

Physics Society (HPS) Draft Standard N 13.29 for environmental applications of dosimeters.

Results

The results for environmental dosimeter measurements are normalized to a standard

quarter (91.25 days or 2190 hours). The monitoring locations are grouped according to

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the distance from the plant. The first group consists of all monitoring points within

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

the plant. Past data have shown that the average results from the locations more than

2 miles from the plant are essentially the same. Therefore, for purposes of this report,

monitoring points 2 miles or less from the plant are identified as "onsite" stations and

locations greater than 2 miles are considered "offsite."

The quarterly gamma radiation levels determined from the dosimeters deployed around

WBN in 2011 are summarized in Table H-1. The exposures are measured in

milliroentgens (mR). For purposes of this report, one mR, one mrem and one mrad

are assumed to be numerically equivalent.

The rounded average annual exposures, as measured in 2011, are shown below. For

comparison purposes, the average direct radiation measurements made in the

preoperational phase of the monitoring program are also shown.

Annual WBN AverageDirect Radiation Levels

mR/Year

Preoperational

2011 Average

Onsite Stations 72 65

Offsite Stations 66 57

The data in Table H-I indicates that the average quarterly direct radiation levels at the

WBN onsite stations are approximately 1.5 mR/quarter higher than levels at the offsite

stations. This difference is consistent with levels measured for the preoperation and

construction phases of TVA nuclear power plant sites where the average levels onsite

were slightly higher than levels offsite. Figure H-I compares plots of the data from the onsite

stations with those from the offsite stations over the period from 1977 through 2011. The new

Landauer InLight Optically Stimulated Luminescence (OSL) dosimeters were deployed since

2007 replacing the Panasonic UD-814 dosimeters used during the previous years.

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From January 2007 to December 2010, the REMP OSL dosimeter results reported in the Annual

Environmental Operating Reports for these years included the Tungsten shield dose contribution

resulting in an over correction. This common industry issue was identified and discussed in a

presentation at the June 30, 2011, REMP industry conference. The industry guidance reference

to this new method to correct for the shield dose will be incorporated in the upcoming revision of

ANSI N13.37, Dosimetry Processing, expected to be issued in 2012. The conclusion from the

historical data analysis is that a shield dose contribution of 5.3 mR needs to be added to the

on-site and off-site quarterly results reported during 2007-2010. The corrected value is applied

both to the on-site (indicator) and off-site (control or background) OSL dosimeter quarterly data;

therefore, the corrected value has no effect on the net final results which is based on the

difference between the on-site and the off-site values. The correction to add a shield dose

contribution of 5.3 mR to the results during 2007-20 10 is included in the 2011 Annual

Radiological Environmental Operating Report.

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

reported in 2011 are consistent with direct radiation levels identified at locations which are not

influenced by the operation of WBN. There is no indication that WBN activities increased the

background radiation levels normally observed in the areas surrounding the plant.

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ATMOSPHERIC MONITORING

The atmospheric monitoring network is divided into three groups identified as local, perimeter,

and remote. Four local air monitoring stations are located on or adjacent to the plant site in the

general directions of greatest wind frequency. Four perimeter air monitoring stations are located

between 6 to 11 miles from the plant, and two air monitors are located out to 15 miles and used

as control or baseline stations. The monitoring program and the locations of monitoring stations

are identified in the tables and figures of Appendix A.

Results from the analysis of samples in the atmospheric pathway are presented in Tables H-3,

H-4, and H-5. Radioactivity levels identified in this reporting period are consistent with

background and preoperational program data. There is no indication of an increase in

atmospheric radioactivity as a result of WBN operations.

Sample Collection and Analysis

Air particulates are collected by continuously sampling air at a flow rate of approximately

2 cubic feet per minute (cfm) through a 2-inch glass fiber filter. The sampling system consists of

a pump, a magnehelic gauge for measuring the drop in pressure across the system, and a dry gas

meter to measure the total volume of air sampled. This system is housed in a building

approximately 2 feet by 3 feet by 4 feet. The filter is contained in a sampling head mounted on

the outside of the monitoring building. The filter is replaced weekly. Each filter is analyzed for

gross beta activity about 3 days after collection to allow time for the radon daughters to decay.

Every 4 weeks composites of the filters from each location are analyzed by gamma spectroscopy.

Gaseous radioiodine is sampled using a commercially available cartridge containing

Triethylenediamine (TEDA)-impregnated charcoal. This system is designed to collect iodine in

both the elemental form and as organic compounds. The cartridge is located in the same

sampling head as the air particulate filter and is downstream of the particulate filter. The

cartridge is changed at the same time as the particulate filter and samples the same volume of air.

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

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Atmospheric moisture sampling is conducted by pulling air at a constant flow rate through a

column loaded with approximately 400 grams of silica gel. Every two weeks, the column is

exchanged on the sampler. The atmospheric moisture is removed from silica gel by heating and

analyzed for tritium.

Results

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

activity in 2011 was consistent with levels reported in previous years. The average gross beta

activity measured for air particulate samples was 0.022 pCi/m3. The annual averages of the

gross beta activity in air particulate filters at these stations for the period 1977-2011 are

presented in Figure H-2. Increased levels due to fallout from atmospheric nuclear weapons

testing are evident in the years prior to 1981 and a small increase from the Chernobyl accident

can be seen in 1986. These patterns are consistent with data from monitoring programs

conducted by TVA at other nuclear power plant construction sites. Comparison with the same

data for the preoperational period of 1990-1995 indicates that the annual average gross beta

activity for air particulates as measured in the 2011 monitoring program was consistent with the

preoperational data.

During the period of March 2011 and April 2011 WBN REMP samples showed low levels of

radioactivity both in the on-site (indicator) and the off-site (control) samples as a result of the

incident with the Fukushima nuclear plant in Japan on March 11,2011. Except for this period

between March 2011 and April 2011, the levels of naturally occurring radionuclides identified by

these analyses were consistent with the normal background levels measured in previous

monitoring years. As such, the atypical detection of these radionuclides in both indicator and

control samples is credibly attributed to the trans-Pacific transport of airborne releases from

Dai-ichi Fukushima following the March 2011 event and is not related to the WBN Plant

operations. However, the concentrations detected in the REMP samples during 2011 are

conservatively included in the report for completeness.

Only natural radioactive materials were identified by the monthly gamma spectral analysis of the

air particulate samples. As shown in Table H-4, 1-131 was not detected in any charcoal cartridge

samples collected in 2011.

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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.

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TERRESTRIAL MONITORING

Terrestrial monitoring is accomplished by collecting samples of environmental media that may

transport radioactive material from the atmosphere to humans. For example, radioactive material

may be deposited on a vegetable garden and be ingested along with the vegetables or it may be

deposited on pasture grass where dairy cattle are grazing. When the cow ingests the radioactive

material, some of it may be transferred to the milk and consumed by humans who drink the milk.

Therefore, samples of milk, soil, and food crops are collected and analyzed to determine

potential impacts from exposure through this pathway. The results from the analysis of these

samples are shown in Tables H-6 through H-12.

A land use survey is conducted annually between April and October to identify the location of

the nearest milk animal, the nearest residence, and the nearest garden of greater than

500 square feet producing fresh leafy vegetables in each of 16 meteorological sectors within a

distance of 5 miles from the plant. This land use survey satisfies the requirements 10 CFR 50,

Appendix I, Section IV.B.3. From data produced by the land use survey, radiation doses are

projected for individuals living near the plant. Doses from air submersion are calculated for the

nearest residence in each sector, while doses from drinking milk or eating foods produced near

the plant are calculated for the areas with milk-producing animals and gardens, respectively.

These dose projections are hypothetical extremes and do not represent actual doses to the general

public. The results of the 2011 land use survey are presented in Appendix G.


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.

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The monitoring program includes a provision for sampling of vegetation from locations where

milk is being produced and when milk sampling cannot be conducted. There were no periods

during this year when vegetation sampling was necessary.

Soil samples are collected annually from the air monitoring locations. The samples are collected

with either a "cookie cutter" or an auger type sampler. After drying and grinding, the sample is

analyzed by gamma spectroscopy. When the gamma analysis is complete, the sample is

analyzed for Sr-89 and Sr-90.

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

individual gardens, corner markets, or cooperatives. Types of foods may vary from year to year

as a result of changes in the local vegetable gardens. Samples of apples, cabbage, corn, green

beans, and tomatoes, were collected from local vegetable gardens and/or farms. Samples of the

same food products grown in areas that would not be affected by the plant were collected as

control samples. The edible portion of each sample is analyzed by gamma spectroscopy.

Results

The results from the analysis of milk samples are presented in Table H-6. No radioactivity

attributable to WBN Plant operations was identified. All 1-131 values were below the

established nominal LLD of 0.4 pCi/liter except for the period in April 2011 attributed to the

Fukushima event. The results for the quarterly Sr-89, Sr-90 analysis were below the established

LLD's for these analyses. The gamma isotopic analysis detected only naturally occurring

radionuclides.

Consistent with most of the environment, Cs-137 was detected in the majority of the soil samples

collected in 2011. The maximum concentration of Cs-137 was 0.68 pCi/g. The concentrations

were consistent with levels previously reported from fallout. All other radionuclides reported

were naturally occurring isotopes. The results of the analysis of soil samples are summarized in

Table H-7.

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

Concentrations of Cs-137 in soil are steadily decreasing as a result of.the cessation of weapons

-19-

testing in the atmosphere, the 30 year half-life of Cs-I 37, and transport through the environment.

The radionuclides measured in food samples were naturally occurring. The results are reported

in Tables H-8 through H-12.

-20-

LIQUID PATHWAY MONITORING

Potential exposures from the liquid pathway can occur from drinking water, ingestion of fish, or

from direct radiation exposure from radioactive materials deposited in the shoreline sediment.

The aquatic monitoring program includes the collection of samples of river (surface) water,

ground water, drinking water supplies, fish, and shoreline sediment. Indicator samples were

collected downstream of the plant and control samples collected within the reservoir upstream of

the plant or in the next upstream reservoir (Watts Bar Lake).

Results from the analysis of the liquid pathway samples are presented in Table H-13 through

H-19. Radioactivity levels in surface and public water, fish, and shoreline sediment were

consistent with background and/or fallout levels previously reported. Low levels of Cs-137 were

measured in samples of shoreline sediment and fish. Low levels of tritium were detected in a

limited number of water samples collected in Chickamauga Reservoir. Results for the sediment

sampling conducted in the onsite ponds and ground water monitoring in onsite wells are

discussed later in this section.


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.

-21-

Ground water is sampled from one onsite well down gradient from the plant, one onsite well up

gradient from the plant, and four additional onsite ground water monitoring wells located along

underground discharge lines. The onsite wells are sampled with a continuous sampling system.

A composite sample is collected from the onsite wells every four weeks and analyzed for

gamma-emitting radionuclides, gross beta activity, and tritium content. In addition, a grab

sample is collected every four weeks from a private well in an area unaffected by WBN. The

grab sample is also analyzed for gross beta activity, gamma-emitting radionuclides, and for

tritium.

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

reservoirs: the reservoir on which the plant is located (Chickamauga Reservoir) and the

upstream reservoir (Watts Bar Reservoir). The samples are collected using a combination of

netting techniques and electrofishing. The ODCM specifies analysis of the edible portion of the

fish. To comply with this requirement, filleted portions are taken from several fish of each

species. The samples are analyzed by gamma spectroscopy.

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

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

Samples of sediment are also collected from the onsite ponds. A total of five samples were

collected in 2011. The samples are dried, ground, and analyzed by gamma spectroscopy.

Results

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

The gross beta concentrations averaged 3.2 pCi/liter in downstream samples and 2.5 pCi/liter in

upstream samples. These levels were consistent with results found during the preoperational

monitoring program. Low levels of tritium were detected in a total of three surface water

samples. The highest concentration was 621 pCi/liter which was significantly below the EPA

drinking water limit of 20,000 pCi/liter. A summary table of the results for surface water

samples is shown in Table H- 13. The annual average gross beta activity in surface water

samples for the period 1977 through 2011 area presented in Figure H-4.

-22-

No fission or activation products were identified by the gamma analysis of drinking water

samples from either of two downstream monitoring locations. Average gross beta activity at

downstream stations was 2.8 pCi/liter and the average for upstream stations was also

2.5 pCi/liter. Low levels of tritium were detected in a total of six samples collected from the two

downstream public water sampling locations. The tritium concentration detected was below the

LLD of 270 pCi/liter. The results are shown in Table H-14. Trend plots of the gross beta

activity in surface water and drinking water samples from 1977 through 2011 are presented in

Figure H-4.

The gamma isotopic analysis of ground water samples identified only naturally occurring

radionuclides. Gross beta concentrations in samples from the onsite indicator locations averaged

3.5 pCi/liter. The average gross beta activity for samples from the control locations was

2.5 pCi/liter. Tritium was detected in samples from the onsite monitoring wells located near

plant discharge lines. The tritium in onsite ground water was the result of previously identified

leaks from plant systems. Repairs were made to resolve the leaks but the plume of contaminated

ground water continues to move slowly across the site toward the river. The highest tritium

concentration in samples from-these monitoring locations was 2,850 pCi/liter. There was no

tritium detected in the onsite up gradient well or the offsite ground water monitoring location.

The results are presented in Table H- 15.

Measurable levels of Cs-137 were identified in a total of six fish samples. The maximum Cs-137

concentration was 0.05 pCi/g measured in game fish collected at one of the downstream

locations. Other radioisotopes found in fish were naturally occurring, with the most notable

being K-40. The results are summarized in Tables H-16 and H-17. Trend plots of the annual

average Cs-137 concentrations measured in fish samples are presented in Figure H-5. The

Cs-137 activities are consistent with preoperational results produced by fallout or effluents from

other nuclear facilities.

Cs-i 37 consistent with the concentrations present in the environment as the result of past nuclear

weapons testing or other nuclear operations in the area was measured in one shoreline sediment

sample. The results for the analysis of shoreline sediment is presented in Table H-18. Trend

plots of the average concentration of Cs-137 in shoreline sediment are presented in Figure H-6.

-23-

Consistent with previous monitoring conducted for the onsite ponds, Cs-137 was detected in the

sediment samples. The average of the Cs-137 levels measured in sediment from the onsite ponds

was 0.09 pCi/gm. In addition, Co-58, Co-60, Cs-134, and Sb-125 were also detected in some of

the samples collected from the onsite ponds. The results for the analysis of pond sediment

samples are provided in Table H- 19. Since these radionuclides were present in relatively low

concentrations and confined to the ponds located in the owner controlled area not open to the

general public, the presence of these radionuclides would not represent an increased risk of

exposure to the general public.

-24-

ASSESSMENT AND EVALUATION

Potential doses to the public are estimated from measured effluents using computer models.

These models were developed by TVA and are based on guidance provided by the NRC in

Regulatory Guide 1.109 for determining the potential dose to individuals and populations living

in the vicinity of the plant. The results of the effluent dose calculations are reported in the

Annual Radiological Effluent Release Report. The doses calculated are a representation of the

dose to a "maximum exposed individual." Some of the factors used in these calculations (such

as ingestion rates) are maximum expected values which will tend to overestimate the-dose to the

"hypothetical" person. The calculated maximum dose due to plant effluents are small fractions

of the applicable regulatory limits. In reality, the expected dose to actual individuals is

significantly lower.

Based on the very low concentrations of radionuclides actually present in the plant effluents,

radioactivity levels measured in the environment, as result of plant operations, are expected to be

negligible. The results for the radiological environmental monitoring conducted for WBN 2011

operations confirm this expectation.

Results

As stated earlier in this report, the estimated increase in radiation dose equivalent to the general

public resulting from the operation of WBN is insignificant when compared to the dose from

natural background radiation. The results from each environmental sample are compared with

the concentrations from the corresponding control stations and appropriate preoperational and

background data to determine influences from the plant. During this report period, Cs-137 was

detected in shoreline sediment, soil, and fish collected for the WBN program. The Cs-137

concentrations were consistent with levels measured during the preoperational monitoring

program. The low levels of tritium measured in water samples from Chickamauga Reservoir

represented concentrations that were a small fraction of the EPA drinking water limit.

The levels of tritium detected in the onsite ground water monitoring wells and the radionuclides

measured in samples of sediment from the onsite ponds do not represent an increased risk of

-25-

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.

-26-

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.

-27-

Table 1

COMPARISON OFPROGRAM LOWER LIMITS OF DETECTION WITH THE REGULATORY LIMITS FOR

MAXIMUM ANNUAL AVERAGE EFFLUENT CONCENTRATIONSRELEASED TO UNRESTRICTED AREAS

AND REPORTING LEVELS

Concentrations in Water, pCi/LiterEffluent Reporting Lower limit

Analysis Concentration' Level 2 of Detection 3

Concentrations in Air, pCi/Cubic MeterEffluent Reporting Lower limit

Concentration' Level 2 of Detection3

H-3Cr-51Mn-54Co-58Co-60Zn-65Sr-89Sr-90Nb-95Zr-95

Ru-103Ru-1061-131

Cs- 134Cs-137Ce-144Ba- 140La-140

1,000,000500,00030,00020,0003,0005,0008,000

50030,00020,00030,0003,0001,000

9001,0003,0008,0009,000

20,000

1,0001,000

300300

400400

23050

200200

27045555

10525

105

400.455302510

100,00030,0001,0001,000

504001,000

62,00040090020

20020020040

2,0002,000

0.91020

3.000.020.0050.0050.0050.005

0.00110.00040.0050.0050.0050.020.030.0050.0050.010.0150.01

Note: I pCi = 3.7 x10-2 Bq.

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

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

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

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

-28-

I

TENNESSEE VALLEY REGIOI(TVA NUCLEAR PLANT SITES)

t'jC'D

.1

Figure 2

ENVIRONMENTAL EXPOSURE PAT'HWAYS OF MAN

DUE TO RELEASES OF RADIOACTIVE MATERIALTO THE ATMOSPHERE AND LAKE.

ore Airborne Releases

Plume Exposure

Liquid ReleasesDiluted By Lake

HMAN

Consumed By ManAnimals(MilkMeat)

ConsumedBy Animals

ShorelineExposure

Drikin i7

DrinkingWater

I Fish

VegetationUptake From Soil

-30-

APPENDIX A

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM AND

SAMPLING LOCATIONS

-31-

Table A-I

WATTS BAR NUCLEAR PLANTRADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMa

Exposure Pathwayand/or Sample

Number of Samples andLocations b

Sampling andCollection Frequency

Type and Frequencyof Analysis

1. AIRBORNE

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

Continuous sampler operation withsample collection weekly (more(frequently if required by dustloading).

Analyze for gross beta radioactivitygreater than or equal to 24 hoursfollowing filter change. Performgamma isotopic analysis on eachsample if gross beta is greater than 10times yearly mean of control sample.Composite at least once per 31 days(by location) for gamma scan.

I'.)

b. Radioiodine

c. AtmosphericMoisture

4 samples from communitiesapproximately 6-10 miles from theplant (PM-2, 3, 4, and 5).

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

Samples from same locations as airparticulates.

4 samples from locations (in differentsectors) at or near the site boundary(LM-1, 2, 3, and 4)

2 samples from communitiesapproximately 4-10 miles distancefrom the plant (PM-2, 5).

Continuous sampler operation withfilter collection weekly.

Continuous sampler operation withsample collection biweekly.

1-131 at least once per 7 days.Analysis is performed by gammaspectroscopy.

Analyze each sample for tritium.

Table A- I



c. AtmosphericMoisture (Cont.)

Number of Samples andLocationsb



d. Soil

2. DIRECT

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

Samples from same location as airparticulates.

2 or more dosimeters placed at ornear the site boundary in each of the16 sectors.

2 or more dosimeters placed atstations located approximately 5miles from the plant in each of the16 sectors.

2 or more dosimeters in at least 8additional locations of specialinterest, including at least 2 controlstations.

Once per year.

At least once per 92 days.

Gamma scan, Sr-89, Sr-90 once peryear.

Gamma dose at least once per 92days.

Table A- I



3. WATERBORNE




a. Surface

b. Ground

2 samples downstream from plantdischarge (TRM 517.9 and TRM523.1).

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

Five sampling locations from groundwater monitoring wells adjacent to theplant (Wells No. 1, A, B, C, and F).

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

I sample from ground water sourceoffsite (Farm L).

1 sample at the first two potablesurface water supplies, downstreamfrom the plant (TRM 503.8 and TRM473.0).

Collected by automatic sequential-type sampler' with composite samplescollected over a period ofapproximately 31 days.

Gross beta, gamma scan, and tritiumanalysis of each sample.

Collected by automatic sequential-type sampler with composite samplescollected over a period ofapproximately 31 days.

Same as Well No. 1.

Grab sample at least once per 31days.

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





c. Drinking



c. Drinking (Con't)

d. Sediment fromShoreline

e. Pond Sediment


I sample at a control locationTRM 52 9 .3d.

I sample downstream from plantDischarge (TRM 513.0).

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

1 sample from at least three locationsin the Yard Holding Pond.

1 sample from milk producing animalsin each of 1-3 areas indicated by thecow census were doses are calculatedto be highest.

I or more samples from controllocations,

One sample of commercially importantspecies and one sample ofrecreationally important species.One sample of each species fromChickamauga and Watts Bar Reservoirs.


At least once per 184 days. Gamma scan of each sample.


At least once per year. Gamma scan of each sample.

5. INGESTION

a. Milk Every 2 weeks. 1-131 and gamma analysis on eachsample. Sr-89 and Sr-90 once perquarter.

b. Fish At least once per 184 days. Gamma scan on edible portions.

Table A-I

WATTS BAR NUCLEAR PLANTRADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM


c. Vegetation"(Pasturage andgrass)

d. Food Products


Samples from farms producing milkbut not providing a milk sample.

I sample each of principal foodproducts grown at private gardensand/or farms in the immediatevicinity of the plant.


At least once per 31 days.

Annually at time of harvest. Thetypes of foods available for samplingwill vary. Following is a list oftypical foods which may beavailable:

Cabbage, Lettuce and/or GreensCornGreen BeansPotatoesTomatoes


1-131 analysis and gamma scan ofeach sample.

Gamma scan on edible portion.

a. The sampling program outlined in this table is that which was in effect at the end of 2011.b. Sample locations are shown on Figures A-1, A-2, A-3.c. Samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours.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-2WATTS BAR NUCLEAR PLANT

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMSAMPLING LOCATIONS

Map Approximate Indicator (I)Location Distance or SamplesNumber' Station Sector (Miles) Control (C) Collectedb

2 PM-2 NW 7.0 1 AP,CF,S,AM3 PM-3 NNE 10.4 I AP,CF,S4 PM-4 NE/ENEc 7.6 I AP,CF,S5 PM-5 S 8.0 I AP,CF,S,AM6 RM-2 SW 15.0 C AP,CF,S,AM7 RM-3 NNW 15.0 C AP,CF,S,AM8 LM-1 SSW 0.5 1 AP,CF,S,AM9 LM-2 NNE 0.4 1 AP,CF,S,AM

10 LM-3 NNE 1.9 1 AP,CF,S,AM11 LM-4 SE 0.9 I AP,CF,S,AM12 Farm L SSW 1.3 id M,W15 Farm K ENE 11.6 C M18 Well#I S 0.6 I W20 Farm N ESE 4.1 I M22 Farm EH SSW 24.0 C M23 Well #5 N 0.5 C W25 TRM 517.9 -- 9.9e I SW26 TRM 523.1 -- 4.7e I SW27 TRM 529.3 -- 1.5e C SW,PW`31 TRM 473.0 54.8a I PW

(C. F. Industries)32 TRM 513.0 -- 14.8e I SS

33 TRM 530.2 -- 2.4e C Ss

35 TRM 503.8 -- 24.0e I PW(Dayton)

37 TRM 522.8-527.8 .. F(downstream of WBN)

38 TRM 471-530 -- -- F(Chickamauga Lake)

39 Watts Bar Reservoir C F81 Yard Pond SSE/S/SSW Onsite I PS82 Well A SSE 0.6 I W83 Well B SSE 0.5 1 W84 Well C ESE 0.3 I W85 Well F SE 0.3 I W

a. See Figures A-I, A-2, and A-3b. Sample codes:

AM = Atmospheric MoistureAP = Air particulate filter PW = Public Water SS = Shoreline sedimentCF = Charcoal filter PS = Pond Sediment SW = Surface waterF = Fish S = Soil W = Well waterM = Milk

c. Station located on the boundary between these two sectors.d. A control for well water.e. Distance from the plant discharge (TRM 527.8)f. The surface water sample is also used as a control for public water.

-37-

Table A-3WATTS BAR NUCLEAR PLANT

ENVIRONMENTAL DOSIMETERS LOCATIONS

MapaLocationNumber

234567101112144041424344454647484950515254555657585960626364656667686970717273747576777879

StationNW-3NNE-3ENE-3

S-3SW-3

NNW-4NNE-1A

SE-iASSW-2

W-2N-iN-2

NNE-INNE-2NE-INE-2NE-3ENE-IENE-2

E-IE-2

ESE-1ESE-2SE-2

SSE-IASSE-2

S-1S-2

SSW-!SSW-3SW-ISW-2

WSW-IWSW-2

W-1WNW-1WNW-2NW-INW-2

NNW-INNW-2NNW-3ENE-2ASE-2AS-2AW-2A

NW-2ASSE-l

SectorNWNNE

NE/ENES

SWNNWNNE

SESSWWNN

NNENNENENENE

ENEENE

EE

ESEESESE

SSESSE

SS

SSWSSWSSSW

WSWWSW

WWNWWNWNWNWNNWNNWNNWENESESW

NWSE

ApproximateDistance(Miles)

7.010.47.67.815.015.01.90.91.34.81.24.71.24.10.92.96.10.75.81.35.01.2

4.45.30.65.80.74.80.85.00.85.30.93.90.90.94.91.14.71.04.57.03.53.12.03.23.00.5

Onsite (On)b

orOffsite (Off)

OffOffOffOffOffOffOnOnOnOffOnOffOnOffOnOffOffOnOffOnOffOnOffOffOnOffOnOffOnOffOnOffOnOffOnOnOffOnOffOnOffOffOffOffOffOffOffOn

a. See Figures A-I, A-2, and A-3.b. Dosimeters designated "onsite" are located 2 miles or less from the plant; "offsite" are located more than 2 miles

from the plant.

-38-

Figure A- I

Radiological Environmental Sampling Locations

Within I Mile of the Plant

NW 348.75 N 11.25 N

!6.25 7133.75

27 56.25

I NUCLEAR PLANT E•/• ,,•101.25

79 •ESE

*5 SiE213.75 146,25

SSW SSE191.25 s 168.75

0 Los

-39-

Figure A-2


From 1 to 5 Miles From The Plant

Scale0 I 2

Ma..

-40-

Figure A-3


Greater Than 5 Miles From the Plant

-41-

APPENDIX B

PROGRAM MODIFICATIONS

-42-

Appendix B

Radiological Environmental Monitoring Program Modification

There were no modifications to the WBN REMP during 2011.

-43-

APPENDIX C

PROGRAM DEVIATIONS

-44-

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.

-45-

Table C-1

Radiological Environmental Monitoring Program Deviations

Sample

Date Station Location T Description

04/25/11 TRM 530.2 TRM 530.2 Shoreline The shoreline sediment samples were unable to be collected in April 2011.

TRM 513 TRM 513 Sediment Normally, these samples are collected every 184 days when the river levels

are decreased. This was documented by PER 452744.

09/06/11 TRM 529.3 TRM 529.3 Water There was no sample collected at Station 3133 TRM 529.3 (Old WB Steam Plant)

for 0-PI-CEM-12.0. The issue was identified as a malfunctioning pump that was

unable to collect the required sample. The pump has since been restored and

is collecting sample as expected. This was documented by PER 457413.

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

NE/ENE This was documented by PER 465231.

10/03/11 PM-4 7.6 MILES AF/CF* Station PM-4 (Ten Mile, TN) was discoved having no flow during the sampling

NE/ENE period for O-PI-CEM-12.0. It was noted that the wheel and belt were both

off of the pump causing a malfunction. The pump has since been fixed, and

and the sampler has been returned to normal operation. This was documented

by PER 457414.

11/07/11 LM-3 1.9 Miles NNE AF/CF* During performance of O-PI-CEM-12.0 it was noted that the pump to the air

sampler at LM-3 (REMP sample at dam) had stopped working during a

sampling period, affecting the volume of sample collected for the week.

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

*AF = Air Filter, CF = Charcoal Filter

APPENDIX D

ANALYTICAL PROCEDURES

-47-

Appendix D

Analytical Procedures

Analyses of environmental samples are performed by the radioanalytical laboratory located at the

Western Area Radiological Laboratory facility in Muscle Shoals, Alabama, except for the Sr-89, 90

analysis of soil samples which was performed by a contract laboratory. Analysis procedures are

based on accepted methods. A summary of the analysis techniques and methodology follows.

The gross beta measurements are made with an automatic low background counting system.

Normal counting times are 50 minutes. Water samples are prepared by evaporating

500 milliliter (ml) of samples to near dryness, transferring to a stainless steel planchet, and

completing the evaporation process. Air particulate filters are counted directly in a shallow

planchet.

The specific analysis of 1-131 in milk is performed by first isolating and purifying the iodine by

radiochemical separation and then counting the final precipitate on a beta-gamma coincidence

counting system. The normal count time is 50 minutes. With the beta-gamma coincidence

counting system, background counts are virtually eliminated and extremely low levels of activity

can be detected.

After a radiochemical separation, milk samples analyzed for Sr-89, 90 are counted on a low

background beta counting system. The sample is counted a second time after a 7-day ingrowth

period. From the two counts, the Sr-89 and Sr-90 concentrations can be determined.

Water samples are analyzed for tritium content by first distilling a portion of the sample and then

counting by liquid scintillation. A commercially available scintillation cocktail is used.

Gamma analyses are performed in various counting geometries depending on the sample type and

volume. All gamma counts are obtained with germanium type detectors interfaced with a high

resolution gamma spectroscopy system. Spectral data reduction is performed by the computer

program HYPERMET.

-48-

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.

-49-

APPENDIX E

NOMINAL LOWER LIMITS OF DETECTION

-50-

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.

-51-

TABLE E-1

Nominal LLD ValuesA. Radiochemical Procedures

SedimentAir Filters Water Milk Wet Vegetation and Soil

Analysis wl/m3) (p j/L) (pCiIL) (pCi/kg wet) (pCi/g dry)

Gross Beta 0.002 1.9 --Tritium 3.0 270 -- --.

Iodine- 131 -- 0.4 0.4 6.0 --Strontium-89 0.0011 5.0 3.5 31.0 1.6Strontium-90 0.0004 2.0 2.0 12.0 0.4

-52-

Table E- 1Nominal LLD ValuesB. Gamma Analyses

ParticulateFilter

Analysis pCi/m3

Ce-141Ce-144Cr-511-131

Ru-103Ru- 106Cs-134Cs-137Zr-95Nb-95Co-58

t Mn-54Zn-65Co-60K-40

Ba-140La-140Fe-59Be-7

Pb-212Pb-214Bi-214Bi-212TI-208Ra-224Ra-226Ac-228

.005

.01

.02

.005

.005

.02

.005

.005

.005

.005

.005

.005

.005

.005

.04

.015

.01

.005

.02

.005

.005

.005

.02

.002

CharcoalFilter

pCi/m3

.02

.070.150.030.020.120.020.020.030.020.020.020.030.020.300.070.040.040.150.030.070.050.200.02

Waterand Milk

Cii/L

103045105

4055

10555

105

100251010451520205010

Vegetationand GrainpCi/., dry

.07

.15

.30

.20

.03

.15

.03

.03

.05

.25

.03

.03

.05

.03

.40

.30

.20

.08

.25

.04

.50

.10

.25

.03

WetVegetationpCi/kg. wet

3511520060251903025453020204520

4001305040

200408055

25030

Soil andSedimentpCi/g. dry

.10

.20

.35

.25

.03

.20

.03

.03

.05

.04

.03

.03

.05.03.75.30.20.05.25.10.15.15.45.06.75.15.25

FoodsTomatoes

Fish Clam Flesh Potatoes, etc.pCi/g. dry pCi/g, dry pCi/kg, wet

.07

.15

.30

.20

.03

.15

.03

.03

.05

.25

.03

.03

.05

.03

.40

.30

.20

.08

.25

.04

.50.10.25.03

.35

.852.401.70.25

1.25.14.15.45.25.25.20.40.20

3.502.401.40.45

1.90.30.10.50

2.00.25

2060952025901010451010104510

2505025259040804013030

.01 0.07 20 .10 70 .10 .75 50

Table E-2

Maximum LLD Values Specified by theWBN ODCM

Analysis

gross beta

H-3

Mn-54

Fe-59

Co-58,60

Zn-65

Zr-95

Nb-95

1-131

Cs-134

Cs-137

Ba- 140

La-140

WaterDCi/L

4

2000a

15

30

15

30

30

15

1 b

15

18

60

15

AirborneParticulateor GasespCi/zm3

I x 10-2

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

7 x 10-2

5 X10"2

6x 10-2

N.A.

N.A.

FishpCi/kn. wet

N.A.

N.A.

130

260

130

260

N.A.

N.A.

N.A.

130

150

N.A.

N.A.

Milk1Ci/L

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

1

15

18

60

15

FoodProducts

pCi/ks. wet

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

60

60

80

N.A.

N.A.

SedimentpCi/kn, dry

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

150

180

N.A.

N.A.

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

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

-54-

APPENDIX F

QUALITY ASSURANCE/QUALITY CONTROL PROGRAM

-55-

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.

-56-

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

portions. Such a sample provides information about the variability of the analytical process

since two identical portions of material are analyzed side by side.

Analytical knowns are another category of quality control sample. A known amount of

radioactivity is added to a sample medium. The lab staff knows the radioactive content of the

sample. Whenever possible, the analytical knowns contain the same amount of radioactivity

each time they are run. In this way, analytical knowns provide immediate data on the quality of

the measurement process.

Blind spikes are samples containing radioactivity which are introduced into the analysis

process disguised as ordinary environmental samples. The lab staff does not know the sample

contains radioactivity. Since the bulk of the ordinary workload of the environmental laboratory

contains no measurable activity or only naturally occurring radioisotopes, blind spikes can be

used to test the detection capability of the laboratory or can be used to test the data review

process. If an analysis routinely generates numerous zeroes for a particular isotope, the presence

of the isotope is brought to the attention of the laboratory supervisor in the daily review process.

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

be detected. Furthermore, the activity can be put into such samples at the extreme limit of

detection (near the LLD) to verify that the laboratory can detect very low levels of activity.

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

known amount of radioactivity added and are presented to the lab staff labeled as cross-check

samples. This means that the quality control staff knows the radioactive content or "right

answer" but the lab personnel performing the analysis do not. Such samples test the best -

performance of the laboratory by determining if the lab can find the "right answer." These

samples provide information about the accuracy of the measurement process. Further

information is available about the variability of the process if multiple analyses are requested on

the same sample. Like blind spikes or analytical knowns, these samples can also be spiked with

low levels of activity to test detection limits. The analysis results for internal cross-check

samples met program performance goals for 2011.

-57-

I

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

measurements, the laboratory participated in an environmental level cross-check program

available through Eckert and Ziegler Analytics during 2011. The results of TVA's participation

in this cross-check program are presented in Table F-1. The results for these cross-check

samples were all within the program agreement limits.

The quality control data are routinely collected, examined and reported to laboratory supervisory

personnel. They are checked for trends, problem areas, or other indications that a portion of the

analytical process needs correction or improvement. The end result is a measurement process

that provides reliable and verifiable data and is sensitive enough to measure the presence of

radioactivity far below the levels which could be harmful to humans.

-58-

Table F-I

Results For 2011 External Cross Checks

Results

Test Period Samole Tvye / Analysis Known TVA Aeernent

First Quarter Water (pCi/L)Gross Beta 2.47E+02 2.23E+02 Yes

First Quarter Water (pCi/L)3H 4.53E+03 5,73E+03 Yes

First Quarter Water (pCi/L)

1311 9.40E+01 9.01E+01 Yes

5tCr 1.96E+02 2.02E+02 Yes134Cs 8.56E+01 7.94E+0I Yes137Cs 1.35E+02 1.36E+02 Yes5SCo 7.44E+01 7.57E+01 Yes

54Mn 1.75E+02 1.79E+02 Yes59Fe I. 15E+02 1.34E+02 Yes65Zn 1.72E+02 1.72E+02 Yes6°Co 1. 13E+02 1.16E+02 Yes

Second Quarter Synthetic Urine (pCi/L)3H 1.OOE+04 1.02E+04 Yes

Third Quarter Milk (pCi/L)1311 1.013E+02 1.03E+02 Yes

Third Quarter Water (pCi/L)3H 9.01E+03 9.41E+03 Yes

Third Quarter Sand (pCi/gram)141Ce 1.59E-01 1.56E-01 Yes5

Cr 5.39E-01 5.03E-01 Yes134

Cs 3.05E-01 2.67E-01 Yes17Cs 2.71E-01 2.60E-01 Yes5 8

Co 2.32E-01 2.15E-01 Yes54Mn 3.59E-01 3.52E-01 Yes

'9Fe 1.31E-01 1.23E-01 Yes

65Zn 4.30E-01 4.31E-0I Yes

'Co 3.74E-01 3.61E-01 Yes

Third Quarter Air Filter (pCi/Filter)Gross Beta 9.36E+01 8.91E+0I Yes

Third Quarter Air Filter (pCi/Filter)141Ce 6.51E+01 6.07E+-01 Yes5'Cr 2.21E+02 2.03E+02 Yes3Cs 1.25E+02 1.04E+02 Yes137Cs 1.11E+02 1.03E+-02 Yes58Co 9.51E+01 8,94E+01 Yes

54Mn 1.47E+02 1.48E+02 Yes55

Fe 5.35E+01 4.75E+01 Yes65Zn 1.76E+02 1.83E+02 Yes

'Co 1.53E+02 1.44E+02 Yes

Third Quarter Water (pCi/L)Gross Beta 2.49E+02 2.41E+02 Yes

Fourth Quarter Milk (pCi/L)1311 9.OOE+01 9.87E+01 Yes

89Sr 8.93E+01 8&23E+01 Yes

9°Sr 1.48E+01 1.48E+01 Yes

-59-

APPENDIX G

LAND USE SURVEY

-60-

Appendix G

Land Use Survey

A land use survey was conducted in accordance with the provisions of ODCM Control 1.3.2 to

identify the location of the nearest milk animal, the nearest residence, and the nearest garden of

greater than 500 square feet producing fresh leafy vegetables in each of 16 meteorological

sectors within a distance of 5 miles (8 km) from the plant.

The land use survey was conducted between April 1, 2011, and October 1, 2011, using

appropriate techniques such as door-to-door survey, mail survey, telephone survey, aerial survey,

or information from local agricultural authorities or other reliable sources.

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

Doses from air submersion were calculated for the nearest resident in each sector, while doses

from drinking milk or eating foods produced near the plant were calculated for the areas with

milk producing animals and gardens, respectively. These doses were calculated using historical

meteorological data. They also assume that the effluent releases are equivalent to the design

basis source terms. The calculated doses are relative in nature and do not reflect actual

exposures received by individuals living near WBN.

In response to the 2011 WBN land use survey, annual doses were calculated for air submersion,

vegetable ingestion, and milk ingestion. The location of nearest resident changed in two sectors

during 2011. In addition, the location of the nearest garden changed in a total of five sectors.

There were no changes in the location for milk ingestion.

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

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

-61-

The results for the calculated relative dose changed slightly for one garden location and one milk

cow location due to small corrections in the terrain adjustment factor for the location. In both

cases, there was no change in the actual location.

The results of the 2011 land use survey and resulting relative projected annual dose calculations

documented that there were no significant changes in land use of unrestricted areas. No required

changes in the sampling locations for the radiological environmental monitoring program were

identified as result of the land use survey.

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

2010 and 2011.

-62-

Table G-I

Watts Bar Nuclear PlantRelative Projected Annual Air Submersion Dose to the Nearest Residence

Within 8 km (5 Miles) of Planta

mtero/year

2011 2010

Sector

NNNENEENEEESESESSESSSWSWWSWWWNWNWNNW

ApproximateDistance (Meters)

4,5803,7603,3533,0593,2684,4161,3721,5241,5851,9794,1861,8292,8961,4492,0774,389

ApproximateDistance (Meters)Annual Dose

0.070.210.270.300.260.160.750.360.380.280.090.290.050.190.080.02

Annual Dose

2,1343,6003,3533,0593,2684,4161,3721,5241,5851,9794,1861,8292,8961,4492,0774,389

0.240.220.270.300.260.160.750.360.380.280.090.290.050.180.080.02

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

-63-

I

Table G-2

Watts Bar Nuclear Plant• Relative Projected Annual Ingestion Dose to Child's Bone

Organ from Ingestion of Home-Grown FoodsNearest Garden Within 8 km (5 Miles) of Plant'

mrem/year

2011 2010

Sector

NNNENEENEEESESESSESSSWSWWSWWWNWNWNNW

ApproximateDistance (Meters)

7,5674,0103,3535,0104,6694,7801,3721,7713,5422,286

b3,0603,4703,0592,0774,920

Annual Dose

0.514.475.872.443.083.06

14.86.432.785.51

2.800.851.081.630.45

ApproximateDistance (Meters) Annual Dose

7,5674,9913,3536,7824,6694,7801,3721,7713,5422,286

b4,6674,6693,0592,0774,602

0.240.220.270.300.260.160.750.360.380.280.090.290.050.180.080.02

a. Assumes the effluent releases are equivalent to design basis source terms.b. Garden not identified within 8, km (5 miles) of the plant in this sector.

-64-

Table G-3

Watts Bar Nuclear PlantRelative 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

ESESSWSSW

Approximate DistanceMeters

6,7062,2863,353

2011

0.060.270.31

Annual Dose X/Qs/mr

32010

0.030.140.16

Farm NbFarm Lb

Farm Hoc

7,97 E-72.36 E-66.80 E-7

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 byan adult and a feeding factor equivalent to 33 percent. If milk from this location were to be consumed by teens,children or infants, the estimated doses would be 0.25, 0.51 and 1.22 mrem/year, respectively.

-65-

APPENDIX H

DATA TABLES AND FIGURES

-66-

Table H-1

DIRECT RADIATION LEVELS

Average External Gamma Radiation Levels at Various Distances fromWatts Bar Nuclear Plant for Each Quarter - 2011

mR / Quarter (a)

Average External Gamma Radiation Levels (b)

1st Qtr 2nd Qtr 3rd Qtr 4th Qtr mR / Yr

Average0 - 2 miles 18.4 18.6 18.4 16.3 72

(onsite)

Average> 2 miles 16.6 17.5 16.8 14.9 66(offsite)

(a). Field periods normalized to one standard quarter (2190 hours)(b). Average of the individual measurements in the set

-67-

Table H-2 (1 of 2)


Individual Stations at Watts Bar Nuclear Plant

Environmental Radiation LevelsmR /Quarter

90

MapLocationNumber

4041421043

34445464748744

49505152115475795556

DosimeterStation

NumberN-1N-2

NNE-1NNE-1ANNE-2NNE-3NE-1NE-2NE-3

ENE-1ENE-2

ENE-2AENE-3

E-1E-2

ESE-1ESE-2SE-1ASE-2

SE-2ASSE-1

SSE-1ASSE-2

Direction,degrees

10350

21222017395447746969568592

109106138128144146161156

ApproxDistance,

miles1.24.71.21.94.110.40.92.96.10.75.83.57.61.35.01.24.40.95.33.10.50.65.8

1st QtrJan-Mar

201118.818.818.817.114.419.320.418.213.917.116.114.415.018.821.514.421.519.916.118.217.717.118.8

2nd QtrApr-Jun

201119.520.517.118.115.118.123.918.515.117.620.514.116.115.117.616.622.017.615.117.618.116.118.1

3rd QtrJul-Sep

201121.216.119.715.016.117.619.120.713.019.114.012.015.618.617.115.625.316.614.518.119.117.119.7

4th QtrOct-Dec

201117.914.017.014.515.514.519.917.012.018.912.012.014.515.517.912.520.915.015.013.017.512.516.0

Annual(')ExposuremR/Year

77.469.472.664.761.169.583.374.454.072.762.652.561.268.074.159.189.769.160.766.972.462.872.6

(1). Sum of available quarterly data normalized to 1 year for the annual exposure value.

Table H-2 (2 of 2)


Individual Stations at Watts Bar Nuclear Plant

Environmental Radiation LevelsmR /Quarter

,1P

MapLocationNumber

5758765

59126062636

646566147767686970782

7172737

DosimeterStationNumber

S-1S-2

S-2AS-3

SSW-1SSW-2SSW-3SW-'SW-2SW-3

WSW-1WSW-2

W-1W-2

W-2AWNW-1WNW-2NW-1NW-2

NW-2ANW-3

NNW-1NNW-2NNW-3NNW-4

Direction,degrees

182185177185199200199226220225255247270277268294292320313321317340333329337

ApproxDistance,

miles0.74.82.07.80.81.35.00.85.3

15.00.93.90.94.83.20.94.91.14.73.07.01.04.57.015.0

1st QtrJan-Mar

201117.711.718.814.422.618.812.320.415.513.915.018.818.216.116.124.719.316.618.215.519.915.017.113.315.0

2nd QtrApr-Jun

201119.516.123.015.121.014.616.119.518.118.119.517.117.117.119.027.921.518.518.517.619.517.118.110.713.6

3rd QtrJul-Sep

201117.612.020.712.522.216.115.020.217.615.017.121.218.616.614.525.320.215.621.716.617.616.116.114.015.0

4th QtrOct-Dec

201115.014.517.914.518.914.012.517.913.516.016.017.515.511.514.523.918.914.514.014.017.513.018.410.013.5

Annual(1 )ExposuremR/Year

69.854.380.456.584.763.555.978.064.763.067.674.669.461.364.1101.879.965.272.463.774.561.269.748.057.1

(1). Sum of available quarterly data normalized to 1 year for the annual exposure value.

Tennessee Valley Authority

RADIOACTIVITY IN AIR FILTERpCi/mA3 = 0.037 Bq/mA3

Name of Facility: WATTS BAR NUCLEAR PLANTLocation of Facility: RHEA, TENNESSEE

Type and Lower Limit Indicator LocationsTotal Number of Detection Mean (F)

of Analysis (LLD) RangePerformed See Note 1 See Note 2

GROSS BETA - 528

Docket Number: 50-390,391Reporting Period: 2011

Location with Highest Annual MeanMean (F)

Location Description with RangeDistance and Direction See Note 2

Control LocationsMean (F)

RangeSee Note 2

Number ofNonroutine

ReportedMeasurements

See Note 3

0

GAMMA SCAN (GELI) - 140

AC-228

BE-7

BI-214

CS-1 34

CS-137

K-40

PB-212

PB-214

TL-208

2.OOE-03

I .00E-02

2.OOE-02

5.OOE-03

5.OOE-03

5.OOE-03

4.OOE-02

5.00E-03

5.OOE-03

2.OOE-03

2.15E-02 (422/422)1.07E-02 - 4.01E-02

112 VALUES < LLD

1.02E-01 (109/112)4.51E-02 - 1.43E-01

3.06E-02 (96 / 112)5.30E-03 - 2.78E-01

112 VALUES < LLD

112 VALUES < LLD

4.34E-02 (31 112)4.13E-02 - 4.52E-02

1.11E-02 (1/112)1.11E-02 - 1.11E-02

3.21E-02 (90/112)5.30E-03 - 2.76E-01

112 VALUES < LLD

PM47.6 MILES NE/ENE

PM2 SPRING CITY7.0 MILES NW

LM31.9 MILES NNE

PM47.6 MILES NE/ENE

PM5 DECATUR6.2 MILES S

LM20.5 MILES N

LM31.9 MILES NNE

LM20.5 MILES N

PM47.6 MILES NE/ENE


2.24E-02 (51 / 51)1.20E-02 - 4.01E-02

14 VALUES < LLD

1.05E-01 (14 / 14)7.53E-02 - 1.37E-01

4.76E-02 (12 114)6.20E-03 - 2.30E-01

14 VALUES < LLD

14 VALUES < LLD

4.52E-02 (1 / 14)4.52E-02- 4.52E-02

1.11E-02 (1/14)1.11E-02 - 1.11E-02

4.57E-02 (12 I 14).6.10E-03 - 2.29E-01

14 VALUES < LLD

2.19E-02 (106 / 106)1.26E-02 - 3.69E-02

28 VALUES < LLD

1.08E-01 (28 / 28)6.59E-02 - 1.41E-01

2.16E-02 (25 /28)6.40E-03 - 8.84E-02

28 VALUES < LLD

28 VALUES < LLD

1.01E-01 (11/28)1.01E-01 - 1.01E-01

28 VALUES < LLD

2.30E-02 (24 / 28)

5.30E-03 - 9.65E-02

28 VALUES < LLD

CD

Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E - 12. 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


RADIOACTIVITY IN CHARCOAL FILTER

pCi/mA3 = 0.037 Bq/mA3

Name of Facility: WATLocation of Facility: RHEi

Type andTotal Number

of AnalysisPerformed


AC-228

BI-214

1-131

K-40

PB-212

PB-214

TL-208

TS BAR NUCLEAR PLANTA, TENNESSEE

Lower Limit Inof Detection

(LLD)See Note 1

dicator LocationsMean (F)

RangeSee Note 2





RangeSee Note 2

Number ofNonroutine


See Note 3

7.OOE-02

5.OOE-02

3.OOE-02

3.OOE-01

3.OOE-02

7.OOE-02

2.00E-02

422 VALUES < LLD

1.17E-01 (93/422)5.06E-02 - 5.34E-01

7.05E-02 (16/422)5.50E-02 - 8.75E-02

3.73E-01 (49 /422)3.04E-01 - 7.32E-01

422 VALUES < LLD

1.41E-01 (78/422)7.01E-02 - 5.71E-01

422 VALUES < LLD

LM20.5 MILES N

LM-4 WB0.9 MILES SE

PM310.4 MILES NNE

LM31.9 MILES NNE

PM47.6 MILES NE/ENE

LM-4 WB0.9 MILES SE


53 VALUES < LLD

2.OOE-01 (11 / 53)6.06E-02 - 5.34E-01

7.84E-02 (2 / 53)7.57E-02- 8.10E-02

4.39E-01 (8 / 53)3.07E-01- 7.32E-01

51 VALUES < LLD

2.05E-01 (10 / 53)7.11E-02 - 5.71E-01

53 VALUES < LLD

8.39E-02 (1 / 106)8.39E-02 - 8.39E-02

1.13E-01 (27/106)5.12E-02 - 5.60E-01

6.38E-02 (4 / 106)5.34E-02 - 7.03E-02

3.65E-01 (12/106)3.19E-01 - 4.80E-01

106 VALUES < LLD

1.32E-01 (20 /106)7.I1E-02 - 5.92E-01

106 VALUES < LLD

-J E



RADIOACTIVITY IN ATMOSPHERIC MOISTURE

pCi/mA3 = 0.037 Bq/m^3

Name of Facility: WATTS BAR NUCLEAR PLANT

Location of Facility: RHEA, TENNESSEEDocket Number: 50-390,391

Reporting Period: 2011



TRITIUM - 208

Lower Limitof Detection

(LLD)See Note 1

Indicator LocationsMean (F)

RangeSee Note 2



Control LocationsMean (F)Range

See Note 2

Number ofNonroutine

ReportedMeasurementsSee Note 3

3.00E+00 3.94E+00 (13/156)3.03E+00 - 7.49E+00

LM-4 WB0.9 MILES SE

4.50E+00 (1/ 26)4.50E+00 - 4.50E+00

3.33E+00 (1/ 52)3.33E+00 - 3.33E+00

0H



RADIOACTIVITY IN MILK

pCi/L = 0.037 Bq/L





IODINE-131 -104


(LLD)See Note 1

4.OOE-01

2.OOE+01


RangeSee Note 2




RangeSee Note 2

Number ofNonroutine

- Reported

MeasurementsSee Note 3

3.08E+00 (3 /52)4.45E-01 - 6.39E+00

52 VALUES < LLD


AC-228

BI-214

K-40

PB-212

PB-214

TL-208

-!j

2.OOE+01 3.54E+01 (5 / 52)2.22E+01 - 5.82E+01

1.OOE+02 1.26E+03 (52 / 52)1.08E+03 - 1.40E+03

1.50E+01 52 VALUES < LLD

2.00E+01 3.37E+01 (4 152)2.20E+01 - 4.93E+01

1.OOE+01 52 VALUES < LLD

LAYMAN FARM1.3 MILES SSW

NORTON FARM4.1 MILES ESE



LAYMAN FARM1.3 MILES SSW



6.39E+00 (1 /26)6.39E+00 - 6.39E+00

26 VALUES < LLD

3.63E+01 (4/26)2.22E+01 - 5.82E+01

1.26E+03 (26 / 26)1.16E+03 - 1.35E+03

26 VALUES < LLD

3.57E+01 (3 / 26)2.20E+01 - 4.93E+01

26 VALUES < LLD

5.60E+00 (3 / 52)6.41E-01 - 1.09E+01

2.37E+01 (1 /52)2.37E+01 - 2.37E+01

4.97E+01 (13/52)2.03E+01 - 2.93E+02

1.23E+03 (52 / 52)1.07E+03 - 1.48E+03

52 VALUES < LLD

4.24E+01 (11 /52)

2.08E+01 - 1.79E+02

52 VALUES < LLD

CH

ý1)

SR 89 -16

SR 90 -16

3.50E+00

2.OOE+00

8 VALUES < LLD

8 VALUES < LLD

8 VALUES < LLD

8 VALUES < LLD



RADIOACTIVITY IN SOILpCi/g = 0.037 Bq/g (DRY WEIGHT)

Name of Facility: WALocation of Facility: RHE




AC-228

BE-7

BI-212

BI-214

CS-137

K-40

PB-212

PB-214

TL-208

TTS BAR NUCLEAR PLANTEA, TENNESSEE

Lower Limit Inof Detection

(LLD)See Note 1



RangeSee Note 2




RangeSee Note 2

Number ofNonroutine


See Note 3

J•

2.50E-01

2.50E-01

4.50E-01

1 .50E-01

3.00E-02

7.50E-01

1 .OOE-01

1.50E-01

6.OOE-02

1.60E+00

4.OOE-01

1.01E+00 (818)7.54E-01 - 1.30E+00

3.66E-01 (3/8)2.91E-01 - 4.87E-01

1.04E+00 (8 8)7.25E-01 - 1.46E+00

6.54E-01 (8/8)4.89E-01 - 7.62E-01

2.52E-01 (7 8)3.27E-02 - 6.83E-01

1.14E+01 (8/8)3.90E+00 - 2.58E+01

9.05E-01 (8 18)6.15E-01 - 1.24E+00

7.23E-01 (8/8)4.68E-01 - 8.70E-01

3.06E-01 (8 /8)2.52E-01 - 3.82E-01

LM-4 WB0.9 MILES SE

PM310.4 MILES NNE

LM-4 WB0.9 MILES SE

LM-4 WB0.9 MILES SE

PM2 SPRING CITY7.0 MILES NW

LM-4 WB0.9 MILES SE

LM-4 WB0.9 MILES SE

PM310.4 MILES NNE

LM-4 WB0.9 MILES SE

1.30E+00 (1 /1)1.30E+00- 1.30E+00

4.87E-01 (1/ 1)4.87E-01- 4.87E-01

1.46E+00 (1/1)1.46E+00 - 1.46E+00

7.62E-01 (1 / 1)7.62E-01- 7.62E-01

6.83E-01 (1 / 1)6.83E-01- 6.83E-01

2.58E+01 (1 /1)2.58E+01 2.58E+01

1.24E+00 (1/ 1)1,24E+00 - 1.24E+00

8.70E-01 (1 /1)8.70E-01- 8.70E-01

3.82E-01 (1 1)3.82E-01- 3.82E-01

6.80E-01 (2/2)6.19E-01 - 7.40E-01

2 VALUES < LLD

6.36E-01 (2 / 2)5.62E-01 - 7.09E-01

7.48E-01 (2 / 2)7.04E-01 - 7.92E-01

3.06E-01 (2 12)1.15E-01 - 4.97E-01

4.16E+00 (2 /2)3.66E+00 - 4.65E+00

6.04E-01 (2/2)5.25E-01 - 6.83E-01

7.93E-01 (2 / 2)7.24E-01 - 8.62E-01

2.11E-01 (2/2)1.97E-01 - 2.26E-01

,D

SR 89 - 10

SR 90 - 10

8 VALUES < LLD

8 VALUES < LLD

2 VALUES < LLD

2 VALUES < LLD



RADIOACTIVITY IN CABBAGE

pCi/Kg = 0.037 Bq/Kg (WET WEIGHT)

Name of Facility: WATTS BAR NUCLEAR PLANT

Location of Facility: RHEA, TENNESSEE





(LLD)See Note 1


RangeSee Note 2




RangeSee Note 2

Number ofNonroutine



K-40

PB-212

2.50E+02 1.63E+03 (1 /1)1.63E+03- 1.63E+03

4.OOE+01 1 VALUES < LLD

2.5 MILES NE

2.5 MILES NE

1.63E+03 (1/ 1)1.63E+03 - 1.63E+03

1 VALUES < LLD

1.85E+03 (1/1)1.85E+03 - 1.85E+03

1 VALUES < LLD

ýýjY,

H"(1)



RADIOACTIVITY IN CORN


Name of Facility: WLocation of Facility: Rl-




BI-214

K-40

PB-212

PB-214

TL-208

ATTS BAR NUCLEAR PLANTLEA, TENNESSEE

Lower Limit Indof Detection

(LLD)See Note 1



See Note 2


RangeSee Note 2



Number ofNonroutine


See Note 3

4.OOE+01

2.50E+02

4.OOE+01

8.00E+01

3.00E+011

4.81E+01 (1/1)4.81E+01 - 4.81E+01

2.08E+03 (1/ 1)2.08E+03 - 2.08E+03

1 VALUES < LLD

1 VALUES < LLD

1 VALUES < LLD

2.5 MILES NE

2.5 MILES NE

2.5 MILES NE

2.5 MILES NE

2.5 MILES NE

4.81E+01 (1 /1)4.81E+01- 4.81E+01

2.08E+03 (11 1)2.08E+03- 2.08E+03

1 VALUES < LLD

1 VALUES < LLD

1 VALUES < LLD

1 VALUES < LLD

2.14E+03 (I1/1)2.14E+03 - 2.14E+03

1 VALUES < LLD

1 VALUES < LLD

1 VALUES < LLD

,-I

0H



RADIOACTIVITY IN GREEN BEANSpCi/Kg = 0.037 Bq/Kg (WET WEIGHT)






(LLD)See Note 1


RangeSee Note 2




RangeSee Note 2

Number ofNonroutine


See Note 3


BI-214

K-40

PB-214

4.OOE+01 4.60E+01 (1 / 1)4.60E+01 - 4.60E+01

2.50E+02 1.89E+03 (11/ 1)1.89E+03 - 1.89E+03

2.5 MILES NE

2.5 MILES NE

2.5 MILES NE

4.60E+01 (1 /1)4.60E+01- 4.60E+01

1.89E+03 (1/ 1)1.89E+03 - 1.89E+03

1 VALUES < LLD

4.21E+01 (1 1)4.21E+01 - 4.21E+01

3.27E+03 (1 1)3.27E+03 - 3.27E+03

1 VALUES < LLD8.00E+01 I VALUES < LLD

J• C,



RADIOACTIVITY IN TOMATOES







(LLD)See Note 1


RangeSee Note 2




RangeSee Note 2

Number ofNonroutine


See Note 3


BI-214

K-40

PB-212

PB-214

TL-208

4.OOE+01 5.42E+01 (1/1)5.42E+01 - 5.42E+01

2.50E+02 2.17E+03 (1/1)2.17E+03 - 2.17E+03

4.OOE+01

8.OOE+01

3.OOE+01

1 VALUES < LLD

I VALUES < LLD

1 VALUES < LLD

2.5 MILES NE

2.5 MILES NE

2.5 MILES NE

2.5 MILES NE

2.5 MILES NE

5.42E+01 (1 /1)5.42E+01- 5.42E+01

2.17E+03 (1/ 1)2.17E+03 - 2.17E+03

1 VALUES < LLD

1 VALUES < LLD

1 VALUES < LLD

1 VALUES < LLD

2.14E+03 (1 /1)2.14E+03 - 2.14E+03

1 VALUES < LLD

I VALUES < LLD

1 VALUES < LLD

,0,

CD



RADIOACTIVITY IN SURFACE WATER(Total)

pCi/L = 0.037 Bq/L






(LLD)See Note 1

Indicator LocationsMean (F)Range

See Note 2




RangeSee Note 2

Number ofNonroutine


GROSS BETA - 38

1.90E+00 3.22E+00 (18 /26)1.91E+00 - 5.69E+00


AC-228 2.00E+01 26 VALUES < LLD

-.3

BI-214

K-40

PB-212

PB-214

TL-208

1.00E+02

1.50E+01

26 VALUES < LLD

26 VALUES < LLD

2.OOE+01 3.15E+01 (10/26)2.20E+01 - 4.74E+01

TRM 523.1

TRM 523.1

TRM 517.9

TRM 523.1

TRM 523.1

TRM 523.1

TRM 523.1

TRM 517.9

3.30E+00 (11 / 13)1.91E+00 - 5.69E+00

3.26E+01 (3/13)2.36E+01 - 4.74E+01

13 VALUES < LLD

13 VALUES < LLD

13 VALUES < LLD 12 VALUES < LLD

6.39E+01 (2 /12)4.59E+01 - 8.20E+01

1.19E+02 (1 / 12)1.19E+02 - 1.19E+02

12 VALUES < LLD

5.77E+01 (2 /12)3.73E+01 - 7.80E+01

12 VALUES < LLD

12 VALUES < LLD

2.45E+00 (8 /12)1.98E+00 - 3.12E+00

CD

2.00E+01 2.93E+01 (6 /26)2.08E+01 " 4.23E+01


3.08E+01 (4 / 13)2.08E+01 - 4.23E+01

13 VALUES < LLD

6.21E+02 (1 / 13)6.21E+02 - 6.21E+02

TRITIUM - 38

2.70E+02 6.21E+02 (1/26)6.21E+02- 6.21E+02



RADIOACTIVITY IN PUBLIC WATER(Total)pCi/L = 0.037 Bq/L


Docket Number. 50-390,391Reporting Period: 2011




(LLD)See Note I


RangeSee Note 2




RangeSee Note 2

Number ofNonroutine


See Note 3

GROSS BETA - 38

1.90E+00 2.77E+00 (17 /26)1.92E+00 - 4.97E+00


AC-228

BI-214

K-40

PB-212

PB-214

TL-208

000

2.OOE+01

2.00E+011

1 .OOE+02

1 .50E+01

2.00E+011

1 .OOE+01

2.70E+02

26 VALUES < LLD

2.95E+01 (3/26)2.27E+01 - 4.02E÷01

26 VALUES < LLD

26 VALUES < LLD

3.01E+01 (2/26)2.47E+01 - 3.54E+01

26 VALUES < LLD

RM-2 DAYTON TN17.8 MILES NNE




CF INDUSTRIESTRM 473.0



3.07E+00 (10/13)1.96E+00 - 4.97E+00

13 VALUES < LLD

4.02E+01 (1 / 13)4.02E+01- 4.02E+01

13 VALUES < LLD

13 VALUES < LLD

3.54E+01 (1 /13)3.54E+01- 3.54E+01

13 VALUES < LLD

2.45E+00 (8 / 12)1.98E+00 - 3.12E+00

12 VALUES < LLD

6.39E+01 (2 / 12)4.59E+01 - 8.20E+01

1.19E+02 (1/12)1.19E+02 - 1.19E+02

12 VALUES < LLD

5.77E+01 (2/12)3.73E+01 - 7.80E+01

12 VALUES < LLD

0"

TRITIUM - 46

34 VALUES < LLD 12 VALUES < LLD



RADIOACTIVITY IN WELL WATER(Total)pCi/L = 0.037 Bq/L






(LLD)See Note 1


RangeSee Note 2




RangeSee Note 2

Number ofNonroutine


GROSS BETA - 98

1.90E+00 3.49E+00 (48 / 70)1.90E+00 - 6.4E+00


AC-228

BI-214

2.OOE+01

2.OOE+01

3.38E+01 (2 /70)2.95E+01 - 3.80E+01

4.OOE+01 (24 /70)2,05E+01 - 1.02E+02

K-40

00 PB-212

PB-214

TL-208

1.00E+02 1.42E+02 (1 70)1.42E+02- 1.42E+02


2.OOE+01 4.03E+01 (19/70)2.01E+01 " 9.70E+01

1.OOE+01 1.54E+01 (1 70)1.54E+01 - 1.54E+01

2.70E+02 1.47E+03 (35 /70)2.78E+02 - 2.85E+03

WBN MW-A0.58 MILES SSE)

WBN MW-A0.58 MILES SSE)

WBN MW-F0.30 MILES SE)

WBN MW-B0.45 MILES SSE)


WBN MW-F0.30 MILES SE)

WBN WELL #10.6 MILES S


3.90E+00 (4 /14)1.90E+00 " 5.40E+00

3.80E+01 (1 /14)3.80E+01- 3.80E+01

5.14E+01 (3/14)2.05E+01 - 9.29E+01

1.42E+02 (1 / 14)1.42E+02 - 1.42E+02

14 VALUES < LLD

5.12E+01 (2/14)2.19E+01 - 8.05E+01

1.54E+01 (1 / 14)1.54E+01 - 1.54E+01

2.03E+03 (14 14)1.49E+03 - 2.85E+03

2.52E+00 (7/28)1.97E+00 - 2.99E+00

2.23E+01 (1 /28)2.23E+01 - 2.23E+01

1.38E+02 (15/28)2.22E+01 - 3.33E+02

28 VALUES < LLD

28 VALUES < LLD

1.52E+02 (13 /28)2.24E+01 - 3.35E+02

28 VALUES < LLD

28 VALUES < LLD

TRITIUM - 98

Notes: 1.2.3.

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


RADIOACTIVITY IN COMMERCIAL FISHpCi/g = 0.037 Bq/g (DRY WEIGHT)






BI-214

CS-137

K-40

PB-212

PB-214

02I.)TL-208


(LLD)See Note 1

1 .00E-01

3.OOE-02

4.OOE-01

4.OOE-02

5.OOE-01

3.OOE-02


RangeSee Note 2

4 VALUES < LLD

4 VALUES < LLD

1.24E+01 (4 /4)1.09E+01 - 1.38E+01

4 VALUES < LLD

4 VALUES < LLD

4 VALUES < LLD



DOWNSTREAM STATION 1DOWNSTREAM


CHICKAMAUGA RESTRM 471-530




2 VALUES < LLD

2 VALUES < LLD

1.29E+01 (2/2)1.20E+01 - 1.38E+01

2 VALUES < LLD

2 VALUES < LLD

2 VALUES < LLD


RangeSee Note 2

6.67E-01 (2 /2)1.70E-01 - 1.16E+00

2 VALUES < LLD

1.41E+01 (2/2)1.27E+01 - 1.56E+01

2 VALUES < LLD

5.84E-01 (1/2)

5.84E-01 - 5.84E-01

2 VALUES < LLD

Number ofNonroutine


See Note 3

CH0'D



RADIOACTIVITY IN GAME FISH

pCI/g = 0.037 Bq/g (DRY WEIGHT)

Name of Facility: W,Location of Facility: RI-




81-214

CS-137

K-40

PB-212

PB-214

TL-208

ATrS BAR NUCLEAR PLANTlEA, TENNESSEE

Lower Limit Incof Detection

(LLD)See Note 1

licator LocationsMean (F)

RangeSee Note 2





RangeSee Note 2

* Number ofNonroutine


See Note 3

1 .OOE-01

3.OOE-02

4.OOE-01

4.OOE-02

5.00E-01

3.00E-02

1.28E-01 (2/4)1.18E-01 - 1.38E-01

4.75E-02 (11 4)4.75E-02 - 4.75E-02

1.33E+01 (4 4)1.02E+01 - 1.46E+01

4 VALUES < LLD

4 VALUES < LLD

4 VALUES < LLD

DOWNSTREAM STATION IDOWNSTREAM






1.38E-01 (1/2)1.38E-01 - 1.38E-01

4.75E-02 (1 /2)4.75E-02 - 4.75E-02

1.43E+01 (2 / 2)1.41E+01 - 1.46E+01

2 VALUES < LLD

2 VALUES < LLD

2 VALUES < LLD

1.45E-01 (1 /2)1.45E-01 - 1.45E-01

3.11E-02 (1 2)3.11E-02 - 3.11E-02

1.34E+01 (2 /2)1.24E+01 - 1.44E+01

2 VALUES < LLD

2 VALUES < LLD

2 VALUES < LLD60

,H

CD

CN



RADIOACTIVITY IN SHORELINE SEDIMENT

pCilg = 0.037 Bqlg (DRY WEIGHT)

Name of Facility: WAITS BAR NUCLEAR PLANT

Location of Facility: RHEA, TENNESSEE

Type and Lower Limit IncTotal Number of Detection



AC-228

BI-212

BI-214

CS-137

K-40

0 PB-212

PB-214

TL-208

(LLD)See Note 1

2.50E-01

4.50E-01

1.50E-01

3.OOE-02

7.50E-01

1.OOE-01

1.50E-01

6.OOE-02


RangeSee Note 2




RangeSee Note 2

Number ofNonroutine


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

1.32E+00 (1 1)1.32E+00- 1 .32E+00

5.44E-01 (I 11)5.44E-01 - 5.44E-01

3.31E-02 (1 /1)3.31E-02 - 3.31E-02

2.56E+01 (1 /1)2.56E+01 - 2.56E+01

1.05E+00 (1 1)1.05E+00- 1.05E+00

5.53E-01 (1 1)5.53E-01 - 5.53E-01

3.70E-01 (1 1)3.70E-01 - 3.70E-01

Location Description withDistance and Direction

COTTON PORT MARINATRM 513








RangeSee Note 2

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

1.32E+00 (1 / 1)1.32E+00 - 1.32E+00

5.44E-01 (1/1)5.44E-01- 5.44E-01

3.31E-02 (1 /1)3.31E-02- 3.31E-02

2.56E+01 (1 I 1)2.56E+01- 2.56E+01

1.05E+00 (1 /1)1.05E+00 - 1.05E+00

5.53E-01 (1 /1)5.53E-01- 5.53E-01

3.70E-01 (1 /1)3.70E-01- 3.70E-01

9.37E-01 (1 / 1)9.37E-01 - 9.37E-01

1.02E+00 (1 /1)1.02E+00 - 1.02E+00

7.81E-01 (1 1)7.81E-01 - 7.81E-01

1 VALUES < LLD

5.89E+00 (1 1)5.89E-00 - 5.89E+00

9.72E-01 (1 / 1)9.72E-01 - 9.72E-01

7.83E-01 (1 /1)7.83E-01 - 7.83E-01

3.11E-01 (1/1)3.11E-01 - 3.11E-01

CD



RADIOACTIVITY IN POND SEDIMENT

pCi/g = 0.037 Bq/g (DRY WEIGHT)

Name of Facility:

Location of Facility:



GAMMA SCAN (GELI)

AC-228

WATTS BAR NUCLEAR PLANT

RHEA, TENNESSEE

Lower Limit Indicator Locationsof Detection Mean (F)

(LLD) RangeSee Note 1 See Note 2



Docket Number: 50-390,391

Reporting Period: 2011


See Note 2

Number ofNonroutineReported

MeasurementsSee Note 3

-5

BE-7

BI-212

BI-214

CO-58

CO-60

CS-137

K-40

PB-212

PB-214

SB-125

TL-208

2.50E-01

2.50E-01

4.50E-01

1.50E-01

3.OOE-02

3.OOE-02

3.OOE-02

7.50E-01

1.OOE-01

1.50E-01

-1.OOE+00

6.OOE-02

7.44E-01 (5/ 5)4.69E-01 - 1.07E+00

3.92E-01 (4/5)2.92E-01 - 4.62E-01

8.32E-01 (4 / 5)6.66E-01 - 1.10E+00

6.63E-01 (5/ 5)5.28E-01 - 8.24E-01

1.76E-01 (2/ 5)1.60E-01 - 1.92E-01

8.30E-02 (3/ 5)4.38E-02 - 1.06E-01

9.33E-02 (5/ 5)3.17E-02 - 2.14E-01

9.21 E+00 (5/5)5.59E+00 - 1.51E+01

7.19E-01 (5/5)5.09E-01 - 1.03E+00

7.13E-01 (5/5)5.83E-01 - 9.OOE-01

8.91 E-02 (2 /5)7.63E-02 - 1.02E-01

2.44E-01 (5/5)1.44E-01 - 3.37E-01

YP-13YARD POND

YP-13YARD POND

YP-13YARD POND

YP-13YARD POND

YP-16YARD POND

YP- 16YARD POND

LV-3LOW VOL WASTE POND

YP-13YARD POND

YP-13YARD POND

YP-13YARD POND

YP-17YARD POND

YP-13YARD POND

1.07E+00 (1/1)1.07E+00 - 1.07E+00

4.62E-01 (1 / 1)4.62E-01 - 4.62E-01

1.1OE+00 (1/1)1.1OE+00 - 1.10E+00

8.24E-01 (1/ 1)8.24E-01 - 8.24E-01

1.92E-01 (1/ 1)1.92E-01 - 1.92E-01

1.06E-01 (11 1)1.06E-01 - 1.06E-01

2.14E-01 (1/ 1)2.14E-01 - 2.14E-01

1.51E+01 (1/1)1.51E+01 - 1.51E+01

1.03E+00 (1/1)1.03E+00 - 1.03E+00

9.OOE-01 (1 / 1)9.OOE-01 - 9.OOE-01

1.02E-01 (1/1)1.02E-01 - 1.02E-01

3.37E-01 (1 / 1)3.37E&01 - 3.37E-01

VALUES < LLD

VALUES < LLD

VALUES < LLD

VALUES < LLD

VALUES < LLD

VALUES < LLD

VALUES < LLD

VALUES < LLD

VALUES < LLD

VALUES < LLD

VALUES < LLD

VALUES < LLD

CD


Figure H-I

Direct Radiation

Direct Radiation LevelsWatts Bar Nuclear Plant

Four Quarter Moving Average25

• • InLight Dosimeter20Initial WBNP Deployment

=20 ,dr operation in January, 2007~January, 1996

20

I

15U415

E 1 0 '2E 0On-Site

--O--Off-Site ,

51975 1980 1985 1990 1995 2000 2005 2010 2015

Calendar Year

Dosimeters are processed quarterly. This chart shows trends in the average measurement for alldosimeters grouped as "on-site" or "off-site". The data from preoperational phase, prior to1996, show the same trend of "on-site" measurements higher than "off-site" measurements thatis observed in current data indicating that the slightly higher "on-site" direct radiation levels arenot related to plant operations.

- 86 -

Figure H-2

Radioactivity in Air Filters

Annual Average Gross Beta Activityin Air Filters

Watts Bar Nuclear Plant0.15..

A-Indicator-B-Control

F-O.10Initial Operation of

C" WBNP in January,* 1996

r.0.05

0.001975 1980 1985 1990 1995 2000 2005 2010 2015

Calendar Year

As can be seen in the trend plot of gross beta activity, the gross beta levels in air particulateshave remained relatively constant with the exception of years when the beta activity waselevated due to fallout from nuclear weapons testing. The data also shows that there is nodifference in the levels for sampling conducted at the indicator stations as compared to thecontrol stations. The Watts Bar monitoring program was suspended for one year in 1989. Thepreoperational monitoring was restarted in 1990.

- 87 -

Figure H-3

Cs-137 in Soil

Annual Average Activityof Cs-137 in Soil

Watts Bar Nuclear Plant

'F

M.

1.0 -

0.8 -

0.6 -

0.4 -

0.210.0

1975

Initial WBN Operation in

0.4 - -l--dndicato

Indicator

E3 Control

1980 1985 1990 1995 2000 2005 2010 2015

Calendar Year

Cesium-137 was produced by past nuclear weapons testing and is present in almost everyenvironmental soil sample exposed to the atmosphere. The "control" and "indicator" locationshave generally trended downward with year-to-year variation, since the beginning of the WattsBar monitoring program.

- 88 -

Figure H-4

Gross Beta Activity in Surface Water

Annual Average Gross Beta Activityin Surface Water

Watts Bar Nuclear Plant5-

AInitial WBN Operation•3 " in January, 1996

4

1-3

Z-& Downstream

1 -2-- Upstream

0 I I I II I

1975 1980 1985 1990 1995 2000 2005 2010 2015Calendar Year

As shown in the graph, the gross beta activity has been essentially the same in samples from thedownstream and upstream locations. The average gross beta activity in these samples has beenrepresentative of the levels measured during preoperational monitoring.

- 89 -

Figure H-5

Gross Beta Activity in Drinking Water

Annual Average Gross Beta Activityin Drinking Water

Watts Bar Nuclear Plant

6 -

5 Initial WBN Operation inJanuary, 1996

.- 14

(3

< 2--a- Downstream

1 -- 6- Upstream

01975 1980 1985 1990 1995 2000 2005 2010 2015

Calendar Year

The average gross beta activity in drinking water samples from the upstream control locationshas been essentially the same as the activity level measured in samples from the downstreamindicator locations. The annual average gross beta activity has been relatively constant since thestart of plant operations in 1996 and is slightly lower than preoperational levels.

- 90 -

Figure H-6

Radioactivity in Fish

Annual Average Activity of Cs-137 in Commerical FishWatts Bar Nuclear Plant

'E

0.30

0.25

0.20

0.150.10

0.05

0.001975

I ndicator Initial WBNE3 Con l Operation in

-f-C--ontrol January, 1996

1 1 5 - - M9752

1980 1985 1990 1995 2000 2005 2010 2015

Calendar Year

Annual Average Activity of Cs-137 in Game FishWatts Bar Nuclear Plant

-~0.30

,. 0.25 Initial WBN - IndicatOperation in

Q 0.20 - January, 1996 -El-Contro, 0.15

:I-& 0.10IS 0.05

0.00

1975 1980 1985 1990 1995 2000 2005 2010

Calendar Year

or

I

2015

The concentrations of Cs- 137 found in fish are consistent with levels present in the TennesseeRiver due to past atmospheric nuclear weapons testing and operation of other nuclear facilitiesin the upper reaches of the Tennessee River Watershed.

-91-

Figure H-7

Radioactivity in Shoreline Sediment

Annual Average Activity of Cs-137 in Shoreline SedimentWatts Bar Nuclear Plant

0.6 -

Initial WBNOperation in

M January, 1996 --- Indicator

CL E3 Control

2•

0.1

1975 1980 1985 1990 1995 2000 2005 2010 212015

Calendar Year

The Cs-137 present in the shoreline sediments of the Tennessee River system was producedboth by testing of nuclear weapons and operation of other nuclear facilities in the upper reachesof the Tennessee River Watershed. The amounts of Cs-137 have declined significantly duringthe course of monitoring for the Watts Bar site, so much so that not all samples containdetectable levels.

- 92 -

Documents

Nuclear Regulatory Commission - Tennessee Valley Authority, … · 2012. 7. 20. · Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 May 15, 2012 10 CFR