ML17135A145

Watts Bar, Units 1 and 2 - Annual Radiological Environmental Operating Report - 2016

ML17135A145
Person / Time
Site:	Watts Bar
Issue date:	05/15/2017
From:	Simmons P Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML17135A145 (84)

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{{#Wiki_filter:Tennessee Valley Authority, P.O. Box 2000, Spring City, Tennessee 37381-2000May 15, 201710 cFR 50 4U.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, D.C. 20555-0001Watts Bar Nuclear Plant, Units 1 and 2Facility Operating License Nos. NPF-90 and NPF-96NRC Docket Nos. 50-390 and 50-391

Subject:

Watts Bar Nuclear Plant - Annual Radiological EnvironmentalOperating Report - 2016Enclosed is the subject report for the period of January 1,2016, throughDecember 31,2016. This report is being submitted as required by Watts Bar NuclearPlant (WBN) Units 1 and 2, Technical Specification (TS) 5.9.2, "Annual RadiologicalEnvironmental Operating Report," and the WBN Offsite Dose Calculation Manual(ODCM), Administrative Control Section 5.1. This report is required to be submitted tothe Nuclear Regulatory Commission (NRC) by May 15 of each year.There are no new regulatory commitments in this letter. lf you have any questionsconcerning this matter, please contact Kim Hulvey, WBN Licensing Manager, at(423) 365-7720.Respectfully,Paul SimmonsSite Vice PresidentWatts Bar Nuclear Plant

Enclosure:

Annual Radiological Environmental Operating Report - Watts Bar Nuclear Plant 2016cc: See Page 2 U.S. Nuclear Regulatory CommissionPage 2May 15, 2017cc (Enclosure):NRC Regional Administrator - Region llNRC Project Manager - watts Bar Nuclear PlantNRC Senior Resident lnspector - Watts Bar Nuclear Plant ENCLOSURETEN NESSEE VALLEY AUTHORITYWATTS BAR NUCLEAR PLANTAnnual Radiological Environmental Operating ReportWatts Bar Nuclear Plant 2016 AnnualRadiologicalEnvironmentalOperating ReportWatts BarNuclear Plant2016 AI{NUAL ENVIRONMEN'TAL RADIOLOGICAL OPERATING REPORTWATTS BAR NUCLEAR PLA}{T2016TENNESSEE VALLEY AUTHORITYApril 2017 TABLE OF CONTENTSTable of ContentsExecutive Summarylnfroduction. . . .Naturally Occuning and Background RadioactivityElectric Power ProductionSite/Plant DescriptionRadiological Environmental Monitoring Program.Direct Radiation MonitoringMeasurement TechniquesResults.Atnospheric MonitoringSampleCollectionandAnalysis.... .... i.....Results.Terrestial MonitoringSample Collection and Analysis. . . . .ResultsLiquid Pathway MonitoringSample Collection and Analysis. . . .ResultsAssessment and Evaluation. . .Results .:....Conclusions.. . ..References.223l111t2t4t415t6l6t7r8l8l92t2T2223Table IFigrre IFigrrre 2Comparison of Prograrn Lower Limits of Detection with RegulatoryLimits for Maximum Annual Average Effluent ConcentrationsReleased to Unrestricted Areas and Reporting Levels. . . . . . . . . . .TennesseeValleyRegiofl. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .Environmental Exposure Pathways of Man Dueto Releases of Radioactive Materials to theAtrrosphereandlakg. . . . . . r . .. . . . . . . . . . . . . . . . . . . r . . . o . . .2425a-l-26 TABLE OF CONTENTS (continued)Appendix A Radiological Environmental Monitoring Program andSampling Locations.Appendix C Program Deviations.Appendix D Analytical ProceduresAppendix ENominal lower Limits ofDetection (LLD).Appendix F Quality Assurance,/Quality Control Program.Appendix G Irnd Use SurveyAppendix H Data Tables and Figures27384043465l5661-ll-DGCUTIVE SUMMARYThis report describes the Radiological Environmental Monitoring Program (RElrfP) conductedby TVA in the vicinity of the Watts BarNuclear Plant (WBN).during the monitoring period of2016. The program is conducted in accordance with regulatory requirements to monitor theenvironment per l0 CFR 20 and l0 CFR 50, and in accordance with TVA procedures. TheREMP includes the collection and subsequent determination of radioactive material content inenvironmental samples. Various tlpes of sanrples are collected within the vicinity of the planLincluding air, water, milk, food crops, soil, fislr, shoreline sedimen! and the measurement ofdirect radiation levels. The radiation levels of these samples are measured and then comparedwith results at control stations located outside the plant's vicinity and data collected at WBNprior to operations (preoperationd data). This report contains an evaluation of the potentialimpact of WBN operations on the environment and general public.The vast majority of radioactivity measured in environmental samples from the WBN Fogramcan be contributed to naturally occurring radioactive materials. Low levels of Cesium (Cs)-137were measur*d in soil, shoreline sediment, and fish samples. The concentrations wer* typical ofthe levels expected to be present in the environment from past nuclear weapons testing oroperation of other nuclear facilities in the regron. The fallout from accidents at the Chernobylplant in the Ukraine in 1986 and the Fukushima plant in Japan in 201I may have also contibutedto the low levels of Cs-137 measured in environmental sarnples. Trace levels of titium weredetected in atnospheric moisture samples. Also, titium, at a fraction of the EPA drinking waterlimit was detected in water samples collected from Chickamauga Reservoir. These levels wouldnot represent a significant contibution to the radiation exposur* to members of&e public.Tritium was detected in onsite Sound water monitoring wells. The titium was the result ofonsite gromd water contamination from previously identified and repafued leaks in plantsystems. In addition, cobalt (Co)-60 and Cs-137 were identified, above the nominal LLD, insediment collected from the onsite ponds. The level of activity measurd in these onsitelocations would not present a risk of expostre to the general public.-t-INTRODUCTIONThis report describes and summarizes the resulrc of radioactivity measurements made in thevicinity of WBN and laboratory analyses of samples collected in the area The measurements aremade to comply with the requirements of 10 CFR 50, Appendix A" Criterion 64 and l0 CFR 50,Appendix I, Section IV.B.2, IV.B.3 and IV.C and to determine potential effects on public healthand safety. This report satisfies the annual reporting requirements of WBN TechnicalSpecification 5.9.2 and Offsite Dose Calculation Manual (ODCM) Administrative Contol5.l.In addition to reporting the data prescribed by specific requirements, other information isincluded to help correlate the significance of results measnred by this monitoring program to thelevels of environmental radiation resulting from naturally occurring radioactive materials.Naturallv Occunine aod Backeround RadioactivitvMost materials in our world today contain tace amounts of nattually occurring radioactivity.Potiusium (K)-40, with a half-life of 1.3 billion years, is one of the major tpes of radioactivematerials formd naturally in our environment. Approximately 0.01 percent of all potassium isradioactive potassium-4O. Other examples ofnaturally occur.ring radioactive materials areberyllinm (Be)-7, bismuth (Bi)-212 and2l4,lead (Pb)-212 and 214, thallium (Tl)-208, actiniun(Ac)-228,uranium (U)-238 and,23l,thoritrm CIh)-234, radium (Ra)-226,radon (Rn)-222 and220, carbon (C) -14, and hydrogen (H)-3 (generally called titium). These naturally occuningradioactive materials are in the soil, our food our drinking water, and our bodies. The radiationfrom these materials makes up a part of the lowJevel natural background radiation. Theremainder of the natural background radiation results from cosmic rays.It is possible to get an idea of the relative hazud of different types of radiation sources byevaluating the amount of radiation the U.S. population receives from each general tlpe ofradiation sounce. The information below is primarily adapted from References 2 and 3. U.S. GENERAL POPULATION AVERAGE DOSE EQUIVALENT ESTIMATESSourcemillirem (mrem)'/Year Per PersonNattual background dose equivalentCosmicTenestrialIn the bodyRadonTotalMedical (effective dose equivalent)Nuclear energyConsumer products332t292283ll300a.2gl3Totall. One-thousandth of a Roentgen equivalent man Gem)624 (approximately)As can be seen from the datapresented above, natural background radiation dose equivalelrt tothe U.S. population normally exceeds that from nuclear plants by several hundred times. Thisindicates that nuclear plant operations normally result in a population radiation dose equivaleirtu&ich is insignificant as compared to the dose from natual background radiation. It should benoted that the use of radiation and radioactive materials for medical uses has resulted in a similareffective dosc equivalent to the U.S. population as that cansed by natural backgrormd cosmic andterrestial radiation.Electic Power ProductionNuclear power plants are simifus in many respects to conventional coal burning (or other fossilfuel) electical generating plants. The basic prooess behind electical power production in powerplants is that fuel is used to heat water to produce steam which provides the force to tunr trubinesand generators. In a nuclear power planL the fuel is uranium and heat is produced in the reactorthough the fission of the uranium. Nuclear plants include many complex systems to control thenuclear fission process and to safeguard against the possibility of reactor malfirnction. Thenuclear 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 tansported throughout plant systems and some of it may bereleased to the environment.Paths through which radioactivity from a nuclear power plant is routinely released are monitored.Liquid and gaseous efluent monitors record the radiation levels for each release. Thesemonitors also provide alam mechanisms to prompt t*nnination of any nelease above limits.Releases are monitored at the onsite points of release and through the radiological environmentalmonitoring progam which measures the environmental radiation in areas around the plant In .this way, the release of radioactive materials from the plant is tightly contolled, and verificationis provided that the public is not exposed to significant levels of radiation or radioactivematerials as the result of plant operations.The WBN ODCM, which describes the program required by the plant Technical Spccifications,prescribes limits for the release of radioactive efluents, as well as limih for doses to the generalpublic from the release of these effiuents.The dose to a member of the general public from radioactive materials released to unresEictedarEas, as given in Nuclear Regulatory Commission (NRC) guidelines and the ODCM, is limitedas follows:LiouidEfluentsTotal bodyAny organGaseous EffluentsNoble gases:Gamma radiation <10 millirad (mrad)/YearBeta radiation <20 mrad/YearParticulates:Any organ<3 mrem/Year4-<15 rnrem/Year The EPA limits for the total dose to the public in the vicinity of a nuclear power planqestablished in the Environmental Dose Standard of 40 CFR 190, are as follows:Total body <25 mrern/yearThyroid s/5 mrem/yearAny other organ <25 mrern/yearAppendix B to l0 CFR 20 presents annual average limits for the concentations of radioactivematerials released in gaseous and liquid efluents at the boundary of the unresticted areas.Table I of this report presents the annual average concentration limits for the principalradionuclides associated with nuclear power plant efluents. The table also presents theconcentations of radioactive materials in the environment which would requirc a special r*portto the NRC and the detection limits for measured radionculides. It should be noted that thelevels of radioactive materials measured in the environment are typically below or only slightlyabove the lower limit of detection. SITE/PLA}.IT DESCRIPTIONThe WBN site is located in Rhea @uU, Tehnessee, on the west bank of the Teonessee River atTennessee Nver Mile (TRM) 528. Figure I shows the site in relation to other TVA projects.The WBN site, containing approximately 1770 acres on Chickamauga Laken is approximaGly2 miles souttr of the Watts Bar Dam and approximately 3l miles north-northeast of TVA'sSequoyah Nuclear Plant (SQN) site. Also located wiein the resenration are the Wans Bar Damand Hydro-Electic Plant, the Watts Bar Steam Plant (not in operation), the TVA CentalMaintenance Facility, and the Watts Bar Resort AreaApproximately 18,500 people live within l0 miles of the WBN site. More than 80 pencent ofthese live between 5 and l0 miles from the site. Two small towns, Spring City and Decatur, arelocated in this area Spring City, with apopulation of approximately 2,200, is northwest andnorth-northwest from the site, while Decatur, with about 1,500 people, is south and south-southwest from the plant The remainder of the area within l0 miles of the site is sparselypopulated, consisting primarily of small farms and individual residences.The area between l0 and 50 miles fiom the site includes portions of the cities of Chattanoogaand l(noxville. The largest urban concenfration in this area is the city of Chattanoogq located tothe 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 fiom the site and the remainderlocated beyond 50 miles. The city of Knoxville is located to the east-northeast with not morethan l0 percent of its 185,000 phs people living within 50 miles of the site. Three smaller urbanareas of greater than 20,000 people are located betlveen 30 and 40 miles from the site. OalcRidge is approximately 40 miles to the northeast, the trnin cities of Alcoa and Maryville arelocated 45 to 50 miles to the east-northeasL and Cleveland is located about 30 miles to the south.Chickamauga Rescrvoir is one of a series of highly controlled multiple-rse reservoirs whoseprimary uaes are flood contol, navigation, and the generation of electric power. Secondaryuses include industrial and public water supply and waste disposal, fishing, and recreation.Public ac@ss areiasr, boat docks, and residential subdivisions have been developed along theresenroir shoreline. WBN consists of two pressurized water reactors. WBN Unit I received a low power operatingIicense (NPF-20) on November 9,1995 and achieved initial criticality in January 1996. The fullpower operating license (NPF-90) was received on February 7,1996. Commercial operation wasachieved May 25,1996. WBN Unit 2 was deferred October 24,2OOO,in accordance with theguidance in Generic Letter 87-15, '?olicy Statement on Deferred Plaots.' On Augtst 3,2W7,TVA provided notice of ie intent to reactivate and complete constrtrction of WBN Unit 2. WBNUnit 2 resuned conshrction in late 2007. October 22,2015 the operating license was issued.Initial criticality was achieved on May 23,2016 and commercial operation was achieved onOctober 19,2016.-7' Most of the radiation and radioactivity generated in a nuclear power reactor is contained withinthe reactor systems. Plant efluent radiation monitors are designed to monitor radionuclidesreleased to the environment. Environmental monitoring is a final verification that the systemsare performing as plaoned. The monitoring program is designed to monitor the pathwaysbetween the plant and the people in the immediate vicinity of the plant. Sample tlpes are chosenso that the potential for detection of radioactivity in the environment will be maximized. TheRadiological Environmental Monitoring Program (RElt{P) and sampling locations for WBN areoutlined in Appendix A.There are two primary pathways by which radioactivity can move through the environment tohnmans: air and water (see Figrue 2). The air pathway can be separated into two components:the direct (airbome) pathway and the indirect (ground or (errestrial) pathway. The directairbome pathway consists of direct radiation and inhalation by humans. ln the terrestrialpathunay, mdioactive materials may be deposited on the ground or on plants and subsequentlyingesrcd by animals and/or hunans. Human exposure througlr the liquid pathway may resultfrom &inking water, eating fish, or by direct exposure at the shoreline. The tlpes of sarrplescollected in this progrcno are designed to monitor these pathways.A number of factors were considered in determining the locations for collecting elrvironmentalsamples. The locations for the atmospheric monitoring stations were detennined from a criticalpathway analysis based on weather patterns, dose projections, population distibution, and landuse. Terrestrial sampling stations were selected after reviewing susfu things as the locations ofdairy enimals and gardens in conjunction with the air pathuay analysis. Liquid pathnay stationswere selected based on dose projections, water use informatio& and availability of media such asfish and sediment. Table A-2 (Appendix A, Table 2: This notation system is used for all tablesand figures given in the appendices.) lists the sampling stations and the tyryes of samplescollected from each. Modifications rnade to the WBN monitoring program in 2016 are reportedin Appendix B. Deviations to the sampling program during 2016 are included in Appeirdix C. To daermine the amount of radioactivity in the environment pnor to the operation of WBN, apreoperatiooal radiological environmental monitoring program was initiarcd in Docember 1976and operated through December 31, 1995. Measurements of the same types of radioactivematerials that are measured currently were assessed duing the preoperational phase to establishnormal background levels for various radionuclides in the environment. During the 1950s,1960s, and 1970s, atnospheric nuclear weapons testing released radioactive material to theenvironment causing fluctuations in backgrormd radiation levels. Ifuowledge of preexistingradionrclide patterns in the environment pemrits a determination, through comparison andhending analyses, ofthe actual environmental impact of WBN operation.The determination of environmental impact during the operating phase also considers thepresence of control stations that have been established in the environment. Results ofenvironmental samples taken at contol stations (far from the plant) are compared with thosefrom indicator stations (near the plan$ to aid in the determination of the impacts from WBNoperation.1[s samfle analysis is performed by the Tennessee Valley Auttrority's (TVA's) EnvironmentalRadiological Monitoring and Instnrmentation (ERIvI&I) group located at the Western AreaRadiological Laboratory (WARL) in Muscle Shoals, Alabama, except for thesfrontium (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 onaccepted mefhods. A summary of the analysis techniques and methodology is presented inAppendix D. Data tables summarizing the sample analysis results are presented in Appendix H.The radiation detection devices and analysis methods used to determine the radionuclide contentof sarnples collected in the environment are very sensitive to small amounts of radioactivity. Thesensitivity of the measurement plocess 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.-9' The ERM&I laboratory operates under a comprehensive quality assnrance/quality contolprogram to monitor laboratory performance throughout the year. The program is intended todetect 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 areworking properly and the analysis of quality control samples which are included alongsideroutine environmental samples. To provide for interlaboratory comparison program, thelaboratory participates in an environmental cross-check program administered by Eckert andZtegler Analytics. A complete description ofthe program is presented in Appendix F.- l0-DIRECT RADIATION MONITORINGDircct radiation levels are measured at various monitoring points around the plant site.These measurements include contibutions fiom cosmic radiation, radioactivity in theground, fallout from afuospheric nuclear weapons tests conducted in the past, and anyradioactivity that may be present as a result of plant operations. Because of the relativelylarge variations in background radiation as compared to the small levels from the plan!contibutions from the plant may be difficult to distinguish.Measurement TechniquesThe Landauer Inlight environmental dosimeter is used in the radiological environmentalmonitoring progam for the measurement of direct radiation. This dosimeter containsfour elments consisting of aluminum oxide detectors with open windows as well as plastic andcopper filters. The dosimeter is processed using optically stimulated luminessense (OSL)technology to determine the amount of radiation exposure.The dosimeters are placed approximately one meter above the ground, with trryo at eachmonitoring location. Sbrc*n monitoring points are located around the plant near the siteboundary, one location in each of the 16 compass sectors. One monitoring point is alsolocated in each ofthe 16 compass sectors at a distance of approximately four to five milesfrom the plant.Dosimeters are also placed at additional monitoring locations out to approximately15 miles from the site. The dosimeters are exchanged every three months. The dosimeters aresent to Iandauer Inligbt for processing and results reporting. The values are corrected fortansit and shielded background exposure. An average of the two dosimeter results iscalculated for each monitoring point. The system meets or exceeds the performancespecifications outlined in American National Standards lnstitute (AI.ISI) N545-I975 and HealthPhysics Society GPS) Drafr Standard N13.29 for environmental applications of dosimeters.WBN Technical Specification 5.9.2,Anrua1Radiological Environmental Operating Reportrequires that the Annual Radiological Environmental Operating Report identify TLD results thatrepresent collocated dosimeters in relation to the NRC TLD program and the exposure period-l l-associated with eaph result. The NRC collocated TLD program was terminated by the NRC atthe end of 1997,therefore, there are no TLD results that represent collocated dosimeters includedin this r*portResultsThe resulg for environmental dosimeter measurements are norrralizqdto a standardquarter (91.25 days or 2190 hours). The monitoring locations are grouped according tothe distance from the plant The first group consists of all monitoring points within2 miles of the plant The second group is made up of all locations greater than 2 miles fromthe plant Past data have shown that the average results from the locations more than2 miles from the plant are essentially the same. Therefore, forpurposes of this r*porqmonitoring points 2 miles or less from the plant are identified as "onsite" stations andlocations greater than 2 miles are considered "offsite."The quarterly gamma radiation levels determined from the dosimeters deployed arormdWBN in 2016 are summarizednTable H-1. The exposurcs are measured inmilliroentgens (mR). For purposes of this r*po$ one mR, one ilu*m and one mradare assumed to be numerically equivalentThe rounded average annual exposures, as measured lm20l6,are shonm below. Forcomparison purlDses, the average direct radiation measurements made in theprmperational phase ofthe monitoringprogram are also shown.Annual WBN AverageDirect Radiation LevelsmR/YearPreoperational2016 AverageOnsite Stations 69 65Offsite Stations 65 57'12-The data in Table H-l indicates that the average quarterly direct radiation levels at theWBN onsite stations are approximately 0.9 mR/quarter higher than levels at the offsite stations.This equates to 3.7 mR/year detected at the onsite locations. This value falls below the EPAlimit of 25 mrem/year total body. The difference in onsite and offsite averages is consistent withIevels measured for the preoperational and construction phases of TVA nuclear power plant siteswhere the average levels onsite were slightly higher than levels offsite. Figure H-l comparesplots of the data from the onsite stations with those from the offsite stations over the period from1977 through 2016. The new Landauer Inlight Optically Stimulated Luminescence (OSL)dosimeters were deployed since 2007 replacing the Panasonic UD-814 dosimeters used duringthe previous yearc.The data in Table H-2 contains the results of the individual monitoring stations. The resultsreported in 2016 are consistent with direct radiation levels identified at locations which are notinfluenced by the operation of WBN. There is no indication that WBN activities increased thebackground radiation levels normally observed in the areas surrounding the plant. ATMOSPHERIC MONITORINGThe atnospheric 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 thegeneral directions of greatest wind frequency. Four perimeter air monitoring stations are locatedbetween 6 to l l miles from the plang'and two air monitors are located out to 15 miles and usedas control or baseline stations. The monitoring program and the locations of monitoring stationsare identified in the tables and figures of Appendix A.Results from the analysis of samples in the atuospheric pathway are prcsented in Tables H-3,H-4, and H-5. Radioactivity levels identified in this reporting period are consis"tent withbackground and preoperational program data. There is no indication of an increase inatuospheric radioactivity as a result of WBN operations.Sample Collection and AnalysisAir particulates are collected by continuously sampling air at a flow rate of approximately2 cubic feet per minute (cfo) tbrough a 2-inch glass fiber filter. The saurpling system consists ofa Vacuum Florescent Display (VFD), a bnrshless motor, and a precision-machined mechanicalditrerential pressure flow sensor. It is equipped with automatic flow control, on-board datastorage, and alarm notifications for flow, P, T, and higher filter DP. This system is housed in aweather resistant environnrental enclosure approximately 3 feet by 2 feet by 4 feet. The filter iscontained in a sampling head mounted on the outside of the monitoring building. The filter isreplaced weekly. Each filter is analped for gross beta activity about 3 days after collection toallowtime forthe radon daughters to decay. Every 4 weeks composites ofthe filters fiom eachlocation are analyzed by gamma spectroscopy.Gaseous radioiodine is sampled using a cominercially available cartidge containingTriethylenediamine (TEDA)-impregnated charcoal. This system is designed to collect iodine inboth the elemental form and as organic compounds. The cartridge is located in the sarnesampling head as the air particulate filter and is downsteam of the particulate filter. Thecartridge is changed at the same time as the particulate filter and samples the same volume of air.Each cartidge is analped for I-l3l by gamma spectroscopy analysis. Atuospheric moisture sampling is conducted by pulling air at a constant flow rate through acolumn loaded with approximately 400 grams of silica gel. Every two weeks, the column isexchanged on the sampler. The atmospheric moisture is removed from silica gel by heating andanalyzed fortitium.ResultsThe resuls from the analysis of air particulsts samples are strmmarized in Table H-3. Gross betaactivity in 2016 was consistent with levels reporrcd in previous years. The average gross betaactivity measured for air particulate samples was 0.020 pCi/m3. The annual averages of thegross beta activrty in air particulate filters at these stations for the period 1977-2016 arcpresented in Figurc H-2. lncreased lerrels due to fallout from atuospheric nuclear weaporurtesting are evident in the years prior to l98l and a small increase from the Chernobyl accidentcan be seen in 1986. These patterns are consistent with data from monitoring programsconducted by TVA at other nuclear power plant construction sites. Comparison with the samedata for the preoperational period of 1990-1995 indicat*s that the annual average gross betaactivity for air particulates as measured in the 2016 monitoring program was consistent with thepreoperational dataOnly natural radioactive materials were identified by the monthly gamma spectal analysis of theair particulate samples. As shorm in Table H4, I-l3l was not detected in any charcoal cartridgesamples collected in 2016.The results for atnospheric moisture sarrpling are reported in Table H-5. Tritium was measured,above the nominal LLD value of 3.0 pCi/m3, in affiospheric moisture samples from both theindicator and contol locations. The highest concentration from the indicator locations was7.4pCilm3 and the highest concenfration from the confrol locations was 5.2 pCi/m3.-l 5-TERRESTRIAL MONITORINGTerrestial monitoring it apssmFlished by collecting samples of environmental media that maytansport radioactive material from the atnosphere to humans. For example, radioactive materialmay be deposited on a vegetable garden and be ingested along with the vegetables or it may bedeposited on pasture grass where dairy caule are grazing. When the cow ingests the radioactivematerial, some of it may be hansfened to the milk and consumed by humans who drink the milk.Therefore, samples of milk, soil, and food crops are collected and analyzed to determinepotential impacs from exposure through this pathway. The results from the analysis of thesesamples are shown in Tables H-6 through H-l l.A land use survey is conducted annually between April and October to identify the location ofthe nearest milk animal, the nearest residence, and the nearest garden of greater than5fi) square feet producing fresh lea$ vegetables in each of 16 meteorological sectors within adistance of 5 miles from the plant. This land use surrey satisfies the requirements l0 CFR 50,Appendix I, Section IV.B.3. From data produced by the land use suwey, radiation doses areprojected for individuals living near the plant Doses from air submersion are calculated for thenearest residence in each s@tor, while doses from drinking milk or eating foods produced nearthe plant are calculated for the areas with milk-producing animals and gardens, respectively.These dose projectioru are hypothetical extremes and do not represent actual doses to the generalpublic. The results of the 2016 land use survey are presented in Appendix G.Sample Collection and AnalvsisMilk samples ar* collected every two weeks from two indicator dairies and from at least onecontol dairy. Milk samples af,e placed on ice for transport to the radioanalytical laboratory.A radiochemical separation analysis for I-l3l and a gamma spectral analysis are performed oneach sample and Sr-89,90 analysis is perfomred quarterly.The monitoring program includes a provision for sampling of vegctation from locations wheremilk is being produced and when milk sampling cannot be condusted. There were no periodsduring this year when vegetation sampling was necessary.- l6-Soil samples are collected annually from the air monitoring locations. The samples are collectedwith either a "cookie cutter'or an auger tlpe sampler. After drying and grinding the sample isanalyzed by gamma spectoscopy and for Sr-89 and Sr-90.$amples representative of food crops raised in the area near the plant are obtained fromindividual gardens. Tlryes of foods may vary fiom year to year as a result of changes in the localvegetable gardens. $amples of cabbage, conl green beans, and tomatoes were collected fromlocal vegetable gardens and/or farms. $emfles of the same food products gtown in areas thatwould not be atrect*d by the plant were obtained from area produce markets as contol samples.The edible portion of each sample is analyzed by gamma spectoscopy.ResultsThe rcsults from the analysis of milk samples are presented in Table H-6. No radioactivityattributable to WBN Plant operations was identified. All I-l3l values were below theestablished nominal LLD of 0.4 pCi/liter. The gamma isotopic analysis detected only nahrallyoccurring radionuclides. The results for the quarterly Sr-89 and Sr-90 analyses were below theestablished LLD's for these analyses.Consistent with most of the environnen! Cs-137 was detected in the majority of the soil samplescollected in 2016. The maximrrm corc*trtotion of Cs-137 was 0.38 pCi/g. The concentationswerp consistent with levels previously reported from fallout All other radionuclides reportedwere naturally occurring isotopes. The results ofthe analysis of soil samples are summarized inTable H-7. Aplot of the aonual average Cs-137 concentrations in soil is presented inFigure H-3. Concentrations of Cs-137 in soil are steadily decreasing as a result of the cessationof weapons testing in the atuosphere, the 30 year half-life of Cs-137, and tansportthrough theenvironment.The radionuclides measured in food samples were naturally occurring. The results are reportedin Tables H-8 through H-l l. LIOUID PATHWAY MONITORINGPotential exposures from the liquid pathway can occur from drinlcing water, ingestion of fis[ orfrom direct radiation exposue from radioactive materials deposited in the shoreline sediment.The aquatic monitoring program includes thc collection of samples of river (surface) watcr,ground water, drinking water supplies, fislU and shoreline sediment Indicator samples werecollected dortnstream of the plant and conEol samples collected within the reservoir upsteam ofthe plant or in the next upsteam resewoir (Watts Bar Lalce).Sample Collection and Analvsis$amfles of surface water are collected from the Tennessee River using automatic samplingsystems from two doumstneam stations and one upsteam station. A timer firms on the system atleast once every two hours. The line is flushed and a sample is collected into a compositecontainer. A one-gallon sample is removed from the container at 4-week intervals and theremaining water is discarded. Each sample is analyzed for gamma-emiuing radionculides, gnossbeta activity, and titium.Samples are also collected by an automatic sampling system at the first truo downstream drinkingwater 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, andtitium. The samples collected by the automatic sampling device are taken directly from theriver at the intake structure. Since these samples are unteated water collected at plant intalce,the upstream surface water sample is used as a contol sample for drinking water.Cnound nater is sampled from one onsite well down gradient from the plan! one onsite well upgradient from the planq and four additional onsirc ground water monitoring wells located alongunderground 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 analped forgamma-emitting radionuclides, gross beta activity, and tritium content.Samples of commercial and game fish species are collected semiannually from each of trnoreservoirs: the reservoir on which the plant is located (Chickamauga Reservoir) and the-lg-upsteam rcservoir (Watts Bar Reservoir). The samples are collected using a combination ofnetting techniques and electrofishing. The ODCM spwifies analysis of the edible portion of thefish. To comply with this requiremen! filleted portions are taken from several fish of eachspecies. The samples are analped by gamma specfioscopy.Samples of shoreline sediment are collected from reueation arsas in the vicinity of the plantThe samples are dried, grormd, and analyzed by gamma spectoscopy.Samples of sediment are also collected from the onsite ponds. A total of five samples werecollected in 2016. The samples are dried, ground, and analped by gamma spectoscopy.ResultsCrloss beta activity was detectable above the nominal LLD in most ofthe surface water samples.The gross treta concentations averaged 3.0 pCi/titer in dormsteam (indicator) samples and2.3 pCilLin upsfream (control) samples. These levels were consistent with results found duringthe preoperational monitoring program. The gammz isotopic analysis of surface water samplesidentified only naturally occurring radionuclides. Low levels of Eitium were detected in somestrrfrce water samples. The highest tritium concentration was 1,620 pCrlliter which issignificantly below the EPA &inking water limit of 20,000 pCi/liter. A summary table of theresults for surface water samples is shown in Table H-12. The annual average gross beta activityin snrface water samples for the period 1977 through 2016 aepresented in Figur* H4.No fission or activation products were identffied by the gamma analysis of &inking wakrsamples from the two downstream monitoring locations. Average gross beta activity atdownstream (indicator) stations was 2.3 pCi/liter and the average for the upsteam (contnol)station was 2.3 pCi/liter. Low levels of titium were detected in approximately half of thesamples collected from the two downstream public water sampling locations. The highesttritium concentration was 1,010 pCifliter. The titium levels were significantly below the EPAdrinking water limit of 20,000 pCi/liter. The results are shown in Table H-l3. Trend plots of thegross beta activity in drinking water samples from1977 through 2015 are presented in FigureH-5.-l9-The gamma isotopic analysis of ground water samples identified only nafirally occurringradionuclides. Gross beta concentrations in samples from the onsite indicator locations averaged3.1 pCi/liter. The average gross beta activrty for samples from the contol locations was2.3 pCilhter. Trititim was detected in samples from the onsite monitoring wells located nearplant discharge lines. The titium in onsite ground water was the result of previously identifiedleaks from plant systems. Repairs were made to resolve the leaks but ttre plume of contaminatedground water continues to move slowly acnoss the sirc toward the river. The highest titiumconcentration in samples from these monitoring locations was 1,130 pCi/liter. There was notritium detected in the onsite up gradient well. The results are presented in Table H-14.Cs-137 was identified in one 6sh samFle. The Cs-l3Z concentation was 0.03 pcilg measrned ingame fish collected at the upstream location. Other radioisotopes found in fish were naturallyoccurring, with the most notable being K40. The results arc surnmarized in Tables H-15 and H-16. Trend plots of the annual ayerage Cs-I37 concentations measured in fish samples arepresented in Figure H-6. The Cs-137 activities are consistent with preoperational resultsproduced by fallout or efluents from other nuclear facilities.Cs-I37, consistent with the concentations present in the environment as the result of pastnuclear weapons testing or other nuclear operations in the area, was measured in one shorelinesediment sample. The results for the analysis of shoreline sediment are presented in Table H-I7.Trend plots of the average concentation of Cs-137 in shoreline sediment arre presented in FigureH-7.Consis'tent with previous monitoring conducted for the onsite ponds, Cs-137 was detected in thesediment samples. The average of the Cs-137 levels measurcd in sediment from the onsite pondswas 0.09 pCi/gm. In addition, Co-60 was also detected in some of the samples collected fromthe onsite ponds. The average of the Co-60 levels measured in sediment from the onsite pondswas 0.08 pCi/gm. The results for the analysis of pond sediment samples are provided in TableH-18. Since these radionuclides were present in relatively low concentrations and confined tothe ponds located in the owner conEolled area not open to the general public, the presence ofthese radionuclides would uot represent an increased risk of exposure to the general public. ASSESSMENT Al.lD EVALUATIONPotential 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 inRegulatory Guide 1.109 for determining the potential dose to individuals and populations livingin the vicinity of the plant. The results of the effIuent dose calculations are reported in theannuat Radiological Efluent Release Report. The doses calculated are a representation of thedose to a "maximum exposed individual." Some of the factors used in these calculations (suchas ingestion rates) are manimum expected values which will tend to overestimate the dose to the"hypothetical" person. The calculated ma:rimum dose due to plant efluents are small fractionsof the applicable regulatory limits. In reality, the expected dose to actual individuals issignificantly lower.Based on the very low concentations of radionuclides actually present in the plant effluents,radioactivity levels measured in the environmen! as result of plant olrcrations, are expected to benegligible. The results for the radiological environmental monitoring conducted for WBN 2016operations confirm this expectation.ResultsAs staGd earlier in this repoft, the estimated increase in radiation dose equivalent to the generalpublic resulting from the operation of WBN is insignificant when compared to the dose fromnatral background radiation. The results from each environmental sample are compared withthe concentations from the corresponding contol stations and appropriate preoperational andbackground datato determine influences from the plant. During this report period, Cs-137 wasdetected in soil, sediment and fish collected forthe WBN program. The Cs-137 concentationswere consistent with levels measured during the preoperational monitoring program. The levelsof titium measured in water samples from Chickamauga Reservoir represented concentrationsthat were a mall fraction ofthe EPA drinking water limit.The levels of tritium detected in the onsite ground water monitoring wells and the radionuclidesmeasured in samples of sediment from the onsite ponds do not represent an increased risk of-2t-exlrosure to the public. These radionuclides werie limited to the owner confiolled area and wouldnot prcsent an exposur* pathway for the general public.ConclusionsIt is concluded fiom the above analysis of environmental samples and from the tend plotspresented in Appendix H, that exposure to members ofthe general public which may have bcenattributable to WBN is negligible. The radioactivity reported herein is primarily the result offallout or natural backgound. Any activity which may be present in the environment as a resultofplant operations does not rcpresent a significant contribution to the exposure of members ofthe public.a2-REFERENCESl. Menil Eisenbud, Environmental Radioactivitv. Academic Press, Inc., New Yorlq NY, 1987.2. National Council on Radiation Protection and Measnrements, Report No. 160, "IonizingRadiation Exposure of the Population of the United States,,'March 2009.3. United States Nuclear Regulatory Comnissio& Regulatory Guide 8.29, "InstructionConcerning Risks from Occupational Radiation Exposnt*," Febnrary t996. Tablc ICOMPARISON OFPROGRAM LOWER UMITS OF DETECTION WITH THE REGULATORY LIMITS TORMAXIMUM ANNUAL AVERAGB EFFLUENT CONCENTRATIONSRELEASED TO I.'NRESTRICTED AREASAND REPORTING LEVELSAnalysisH-3Cr-51Mn-54Co-S8Co-60Zn-65Sr-89Sr-90Nb-9sk-95Ru-103Ru-106I-13 ICs-134Cs-137Ce-l44Ba-140La-1401,000,000500,00030,00020,0003,0005,0008,00050030,00020,00030,0003,0001,0009001,0003,0008,0009,00020,0001,0001,000300300Concentrations in Water. pCi/LiterEffIuent Reporting Lower limitConcenhationl Lrvel2- of Detection3Concentrations in Air. pCi/Cubic MeterEffluent Reporting Lower limitConcentrationl I**t'- of Delgction3100,00030,0001,0001,000504001,00062,00040090020200200200402,0002,0002704555510.0050.0050.0050.020.030.0050.0050.010.0150.01------0.9l0205l05400.4553025l04003',23050--200200Note: I pCi : 3.7 xl0'2 Bq.Note: For thoc* rcporting levels and lower limits of detection that re blank, no value is given in the reference.l. Source: Table 2 of Appendix B to l0 CFR 20. 100 I -20J/i012. Sonrce: WBN Oftite Dose Calculation Manual, Table2.3-2.3. Source: Table Bl of this reporl ItND.ft !K'l.!'-\j- "\//\'?-\.g (\ei\ia'\a*;oltt)\LL.rt\( *'*^to' j \..\,,i'\.,,1 \1ij:-.----f.--!\t'/*5H^fYYloAr\\rlI+'i\--- lut^\ i^riliN-.\ N(ElI/ll1-,fi,.), A R.sc"-'-\r-\. \,-f\/\/))/I-n- iv -)').,*n"-'-------Sg99,A1_ _L - - _ -- _ -ff__ f 7'-\\\-\-:/(a/t*[MIMPHIS---.- ---------J-.\\MIS S.r-'ta),,\\aft,iJt/1GEORGIAEf,TilH\.- /-rt ?' sCAR.LEGEND- tf,ATT3 BAR TI'GLEAN PLATUT- SEq,OYAH TII'CLEAR PLAIIIT- EELLEFOilTE 'S'lCLEAN PLATT- BROUNTI FERRY ]TUCLEAR PLAfITt,t Iv..atfl.rltcLE$roAL8l'-.aIItIIJilIi,-\I";L\I\\t::H.oa=Flou*, EN\,I]TCINMENTAL E)(PC!BL,FE PATHI,VAYA ClF MANEIUE TCl FIELEASEE ClF FIAEIICIACTI\,E MATEHIALTCl THE ATMCISPHE]IE ANE' LAKE.Airborne BeleasesPIum8DExposureLiquid BeleasesDiluted By lakeMANAnimalstililk,teatlGofirroConsumed By illanShorelineExposuleBy AnimalsDrinkingWaterFishUegetationUptake From Soi!Figure 2 APPENDXARADIOLOGICAL W MOMTORING PROGRAIU A}IDSAIVIPLING LOCATIONSa7-Table A-lWATTS BAR NUCLEAR PLANTRADIOLOGIC AL E}-TIYIRONMENTAL MOMTORING PROGRAM"Exposure Pathwayand/or SampleI. AIRBORNEa. Particulatesb. Radioiodinec. AtmosphericMoismreNumber of Samples andLocationsb4 samples from locations (in differcntsectors) at or near the site boundary(LM-1,2,3, and 4).Sampling andCollection FrequencyContinuous sampler operation withsample collection weekly (more(frequently if required by dustloading).Ty?e and FrequencyofAnalYsis-Analyze for gross beta radioactivitygreater than or equal to 24 hoursfollowing filter change. Performgamma isotopic analysis on eachsample if gross beta is greater than l0times yearly mean of control sample.Composite at least once per 3l days(bV location) for gamma scan.I- 13 I at least once per 7 days.Analysis is performed by gammaspectroscopy.Analyze each sample for tritium.4 samples from communitiesapproximately 6-10 miles from theplant (PM-2, 3,4, and 5).2 samples from control locationsgreater than l0 miles from the plant(RlvI-2 and 3).Samples from same locations as airparticulates.4 samples from locations (in differentsectors) at or near the site boundary(LM-lr2r 3, and 4)2 samples from communitiesapproximately 4-10 miles distancefrom the plant (PM-Z,5).Continuous sampler operation withfilter collection weekly.Continuous sampler operation withsample collection biweekly. Table A-lWATTS BAR NUCLEAR PLAI{TRADIOLOGICAL EIWIRONMENTAL MOMTORING PROGRAM"Exposure Pathway Number of Samples andand/or Sample Locationsbc. Atmospheric 2 samples from control locationMoisture (Cont.) greater than t0 miles from the plant(RIVI-2 and RM-3).Sampling andCollection FrequencyType and Frequencyof AnalvsisGamma scan, Sr-89, Sr-90 once peryear.Gamma dose at least once per 92days.d. Soil2. DIRECTSamples from same location as air Once per year.particulates.2 or more dosimeters placed at or At least once per 92 days.near the site boundary in each of the16 sectors.2 or more dosimeters placed atstations located approximately 5miles fiom the plant in each of the16 sectors.2 or mone dosimeters in at least 8additional locations of specialinteresf including at least 2 controlstations. Table A-lWATTS BAR NUCLEAR PLANTRADIOLOGI CAL E}WIRONMENTAL MONITORING PROGRAM"Exposure Pathway Number of Samples andand/or Sample Locationsb3. WATERBORNESampling andCollection FrequencyType and Frequencyof Analysisa Surface 2 samples downstneam from plant Collected by automatic sequential- Gross baq gamma scan, and tritiumdischarge (TRM 517.9 and TRM type samplef witr composirc mmples analysis of each sample.523.1). collected over a period ofapproximately 3l days.I sample at a contol locationupstream from the plant discharge(rRM 529.3).b. Ground Five sampling locations from ground Collected by automatic sequcntial- Gross beta, gamma scan, and tritiumrvater monitoring wells adjacent to thc tlrye sampler with composite samples analysis of each samplc.plant (Wclls No. l, A, B, C, and F). collected over a period ofapproximat*ly 3l days.I sample from ground water soutre Same as Well No. l. Gross beta, gEmma scan, and tritiumup gradient (Well No. 5). analysis of each sample.c. Ihinking I sample at the first two poable Collected by automatic sequential- Gross baa, gamma scan, and tritiumsurface water supplies, downstneam tpe samplef with composirc sample analysis of each sample.from thc plant (TRM 503.t and TRM collected monthly.473.0).I sample at a control loc*ionTRM 529.3d. Exposure Pathwayand/or SampleTable A-lWATTS BAR NUCLEAR PLANTRADIOLOGI CAL ETWIRONMENTAL MONITORING PROGRAM'Number of Samples andLocationsbSampling andCollection FrequencyType and Frequencyof Analysisd. Sediment from I sample downsneam from plant At least once per 184 days. Gamma scan of each sample.Shoreline Discharge (TRM 513.0).I sample fiom a confirol locationupsfream fiom plant discharge(TRM 530.2).e. PondSediment I samplefiomatleastttrcelocations Atleastonceperyear. Gammascanofeachsample.in the Yard Holding Pond.5. INGESTIONa- Milk I samplefrommilkproducinganimals Every2weeks. I-l3l andgammaanalysisoneachin each of l-3 areas indicated by the sample. Si-gg anA Sr-b0 once percow census were doses are calculated quarter.to be highestI ormorc samples from controllocations.b. Fish One sample of commetcially important At least once per t84 days. Gamma scan on edible portions.species and one sample ofreoeationally important species.One sample of each species ftomChickamauga and Watts Bar Reservoirs.-3 l-Table A-lWATTS BAR NUCLEAR PLA}.ITRADIOLOGICAL EWAL MONITORING PROGRAMExposure Pathwayand/or SampleVegetation"@asturage andgrass)d. Food ProductsNumber of Samples andLocationsbSamples from farms producing milkbut not providing a milk sample.Sampling andCollection FreguencyAt least once per 3l days.Annually at time of harvest. Thebpes of foods available for samplingwill vary. Following is a list oftlpical foods which may beavailable:Cabbage, Lettuce and/or GreensCornGreen BeansPotatoesTomatoesType and Frequencyof AnalvsisI-l3l analysis and gamma scan ofeach sample.I sample each of principal foodproducts grown at private gardensand/or farms in the immediatevicinity of the plant.Gamma scan on edible portion.The sampling ptogram outlined in this table is that which was in effect at the end of 2016.Sample locations are shown on Figures A-1, A-2,A-3.Samples shall be collected by collecting an aliquot at interrrals not exceeding 2 hotns.The samples collected d TRMs 503.t and 473.0 arc taken fiom the raw uratcr suppln thereforc, the upstneamsurface nater sample will be considered ttre 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.a.b.c.d.-32' Table A-2WATTS BAR NUCLEAR PLAI{TRADI OLOGICAL EN V IRON MENTAL MON TTORIN G PROGRAT{SAI\4PLING LOCATIONSApproxirnateDistanccSector (Miles)_lndicator (l)or SamplesConuol (C) Collectedb-MaplocationNumbef-567E9r0lll820232526273l37StationPM.2PM.3PM-4PM-5RM-2RM-3LM-ILM-2LM-3LM4Well #lFarm NWell #5TRM 517.9TRM 523.1TRM 529.3TRI\{ 473.0(C. F. Industries)TRM 513.0TRM 530.2TRM 503.9(Dayton)TRM 522.9-527.9(dovmsheam of WBN)TRM 471-530(Cltickamauga Lake)TRM 530-602(Watts Bar Rescrvoir)Yard PondWell AWell BWell CWell FFarm FIIIFarm BBNWNNENE/ENE"SSWNNWsswNNENNESESESEI----::SSE/SISSWSSESSEESESESSWSWAP,CF,S,AMAP,CF,SAP,CF,SAP,CF,S,AI\,IAP,CF,S,AIdAP,CF,S,AlvIAP,CF,S,AI\{AP,CF,S,AI\dAP,CRS,AI\dAP,CF,S,AtrtwMwSWSWsw,Pw'PW2347,010.47,68.015.015.00.50.4t.90.90.64.10.5e.*4.7dl.5d54.9dl4.gd2.4d24.0dOnsite0.60.50.30.31.7518.6CCcIIcIIcI323335c3839EIE283E4858687SSSSPWFFFPSwwwwMM&b.See Figures A-1, A-\ and A-3Sample codes:Alvl : Atmoqpheric MoistursAP = Air particulate filterCF = Charcoal filterF - FisttM : MilkPublic WatcrPond SedimentSoilPW=PS:S:SS : Shorcline sedimentSW = Surfacc watcrW : Wcll waterc. Station located on the boundary bctwcen thesc two scctors.d. Distance ftom the plant discharge (TRM 527.8)e. The surface water saurple is also used as a control for public water. Table A-3WATTS BAR NUCLEAR PLANITENVIRONMENTAL DOSIMETERS LOCATIONSMap"LocationNumber234567l0lll2l4404l4243u4546474849505l52545556575E596062636465666768697A7t7273747576777879StationNW-3NNE-3ENE.3s-3sw-3NNW-fNNE-IASE-IAssw-2w-2N-lN-2NNE-INNE-2NE.INE-2NE-3. ENE.IENE-2E-lE-2ESE-IESE.2SE-2SSE-IASSE.2S-Ts-2SSW-Issw-3sw-lsw-2wsw-lwsw-2w-lwNw-lwNw-2NW-lNW-2NNW.INNW.2NNW-3ENE.2ASE-2AS.2Aw-2ANW-2ASSE.ISectorNWNNENE/ENEsSWNNWNNESEsswwNNNNENNENENENEENEENEEEESEESESESSESSESssswsswswSWwswwswwwNwwNwNWNWNNWNNWNNWENESEswNWSEApproximateDistancc(Miles)7.010.4'1.67,815.015.01.90.91.34.9t.24,71.24.10.92.96.10,75.81.35.01.24,45.30.65.90.74.90.95.00.95.30.93.90.90.94.9l.l4.71.04.57,03.53.12,03.23.00.5Onsite (Onforoffsirc (ofinotrotrotrotrotrotrOnOnOnoffOnotrOnotrOnotrotrOnotrOnotrOnoffotrOnotrOnoffOnotrOnoffOnotrOnOnotrOnotrOnoffotrotrotroffotroffOna Scc Figurcs A-1, A-a and A-3.b. Ilosimctsrs &signatcd'onsitc' arc locarcd 2 miles or less from thc plar4 "offsitc' arp locatcd rnorc 0ran 2 milcsfiomlhcplant'34-303.75Figure A-lRadiological Environmental Sarnpling LocationsWithin I Mile of the Plant191.25 SwNw287.25w258.75ws56.25123.75ENE78.75Eto I ,26ESEWATTS BABNUGLEAR PLANT.r'mr 14 Figure A-2Radiological Environmental Sampling LocationsFrom I to 5 Miles From The PlantwArrs BAR NucLeee p[ur lI Pd: Figure A-3Radiological Environmental Sarnpling LocationsGreater Than 5 Miles From the Plant APPENDD(BPRO GRAN{ MODIFICATIONS Appendix BRadiological Envirorunental Monitorine Prosram ModificationThe farm identified as Farm K closed its operation in 2015 and was replaced by Bacon Farm.However, it was not removed from the REMP collection schedule until January of 2016. Farm Kwas a control milk location. The change is reflected in the Tables and Figures of Appendix A ofthis report. There were no other modifcations to the WBN REMP program during 2016. APPENDIXCPROGRAI\{ DEVIATIONS-,40-Appendix CProEram DeviationsProblems with equipment resulted in missed air samples from three locations during 2016.Problems with low moisture resulted in 2 missed atrrospheric samples. The samples werecollected but unable to be analped due to the low moisture content. The low moisture from oneof the samples was due to damaged equipment.Table C-l provides additional information on the missed samples. A review of the details of theprogram deviations did not identi& any adverse tend in equipment performance.4l-Table C-lRadiological Environmental Monitoring Progrram DeviationsDate0912012016StationPI&d-ztolt4l20t6 LM-ttolra2u6RI\d.3r l/1 5120t6PM-5tu29l20r6PM-5Location Sample TWe7.0 MilesNW AF/CF0.5 Miles SSW AF/CF15 MilesNNW AF/CF8.0 Miles SAfrnosphericMoisture8.0 Miles SAtnosphericMoistueDessriptionWhile performing the routine REMPcollection, it was discovered that themotor at PM-2 (station 3106, SpringCity) had failed, which resulted inmissed air samples. The entire unitwas replaced on 9120116. The issuewas documented in CR 1214561.Chemistry was informed that theLM-l REMP air monitoring statiotr,located near the MET tower, was notrunning. Upon investigation, themonitor was found off. Attempts torestart the monitor failed. The issuewas documented in CR 1222800.While performing the routine REMPcollection, it was discovered thatRM-3 (station 3205, Alloway) airsampler had failed before obtainingthe minimum required volume. Theissue was documented in CR1223692.A canister was broken duringshipment causing the sample to havelow moisture content. The samplewas analyzed but unable to becalculated. The problem wasidentified in CR 1234087.The sample was collected but unableto be analyzed due to low rnoisturecontent. The problem was identifiedin CR 1241477. APPEI{DD(DAI{ALYTICAL PROCEDI JRES43-Appendix DAnalytical ProceduresAnalyses of environmental samples ar* performed by the radioanalytical laboratory located at theWestern Area Radiological Laboratory facility in Muscle Shoals, Alabama, except for the Sr-89, 90aaalysis of soil samFles which was performed by a contract laboratory. Analysis procedures arebased on accepted methods. A sunrmary ofthe analysis techniques and methodology follows.The gross betameasurements are made with an automatic lowbackground counting systertr.Normal counting times are 50 minutes. Water samples are prepared by evaporating500 milliliter (ml) of samples to near drymess, tansferring to a stainless steel plancha, andcompleting the evaporation process. Air particulate filters are counted directly in a shallowplanchetThe specific analysis of I-l3l in milk is performed by first isolating and ptui$ing the iodine byradiochemical separation and then counting the final precipitate on a beta-gamma coincidencecounting system. The normal count time is 50 minutes. With the beta-gamma coincidencecounting system, background counts are virtually sliminated and e:rtemely low levels of activitycan be det*cted.After a radiochemical separation, milk samples analyzed for Sr-89, 90 are counted on a lowbackground bAa counting system. The sample is counted a second time after a minimum ingrowltperiod of six days. From the two counts, the Sr-89 and Sr-90 concentrations can be determined.Water samples are analyzed for titium content by first distilling a portion of the sample and thencounting by liquid scintillation. A cornmercially available scintillation cocltail is used.Gamma analyses are performed in various counting geometries depending on the sample tlpe andvolume. All gamma counts are obtained with germanium type detectors interfrced with a highresolution gamma spectroscopy system. The charcoal cartidges used to sample gaseous radioiodine are analyzed by gamma spectroscopyusing a high resolution gamma spectroscopy system with germanium detectors.Atuospheric moisture samples are collected on silica gel from ametered air flow. The moisture isreleased from the silica gel by heating and a portion of the distillate is counrcd by liquidscintillation fortitium using commercially available scintillation cocktail.The necessary efficiency values, weight-efficiency cunres, and geometry tables are established andmaintained on each detector and counting system. A series of daily and periodic quality contolchecks are perfonned to monitor counting instnrmentation. System logbooks and contol charts areused to document the results of the quality contol checks.'45' APPENDIXENOMINAL LOWER LIMITS OF DETECTION46-Appendix ENorninal lower Limits of DetectionA number of factors influence the Lower Limit of Detection (LLD), including sample size, count time,cormting efficiency, chemical prooess*s, radioactive decay factors, and interfering isotopes encormteredin the sample. The most probable values for these factors have been evaluated for the various analysesperformed in the environmental monitoring program. The nominal LLDs are calculated in accordancewith the methodology prescribed in the ODCM, are presented in Table E-1. The maximum LLD valuesfor the lower limits of detection specified in the ODCM ane shown in Table E-2.The nominal LLD values are also presented in the data tables. For analyses for which nominal LLDshave not been establishe4 an LLD of zero is assumed in determining if a measued activity is greaterthan the LLD. In these cases, the LLD value will appear as -1.00E+00 in the data tables inAppendix H.47-TABLEE-INominal LLD ValuesA. Radiochemical ProceduresAnalvsis-l-Gross BetaTritiumIodine-l31Strontium-89Strontium-90Air(pCi/m3)0.0021:--Water(pCi/L)6.0Mitk(pGi/L)0.43.52.01.9270:lWet Vegetation(pCi/kg wet)Sedimentand Soil(pci/g dry)----1.60.448-Table E-lNominal LLD VatuesB. Gamma AnalysesWater Wetand Milk VegetationpC;ilL pCi/kg, wetAnalysisCe-l4lCe-144Cr-51I-131Ru-103Ru-106Cs-134Cs-l37Zr-95hlb-95Co-58Mn-54Zn-65Co-60K40Ba-140La-140Fe-S9Be-7Pb-212Pb-i2t4Bi-214Bi-212TI-208Ra-224Ra-226Ac-228Pa-234mAirParticutateJrCi/m3-.005.01.02.005.005.02.005.005.005.005.005.005.005.005.04.015.01.005.02.005.005.005.42.002CharcoatFilterpCi/m30.020.070.150.030.020.124.020.020.030.020.020.020.030.020.300.070.040.M0.150.030.070.050.20,:,0.07Soil andSedimentpCi/g. dry.10.24.35.25.03.20.03.03.05.04.03.03.05.03.75.30.20.05.25.10.15.15.45.06.75.15.254.0FishpCi/g. dry.07.15.30.20.03.15.03.03.05' .25.03.03.05.03.4A.30.20.08.25.04.10.10.25.03FoodsTomatoesPotatoes, etc.oCifte. wet2060952A2590l0l045l0t0l045l02s0s0252590408040t30:3--50l03045l054055t0555l0510025l0l045t5202A50i:208007035ll52006025r903025453020204520400r305040204408055250:3.10.01 Table EAMaximum LLD Values Specified by theWBNODCMAnalysisgross betaH-3Mn-54Fe-59Co-58,60Zn-65k-95Nb-95I-13 ICs-134Cs-137Ba-140La-I40WaterpCtlL42000"l530l53030l5lbl5l860l5AirborneParticulateor GasespCi/m3I x l0-2N.A.N.A.N.A.N.A.N.A.N.A.N.A.7 x l0-25 xl0-26 x t0'2N.A.N.A.FishpCi&g. w.e!N.A.N.A.130260t30260N.A.N.A.N.A.130150N.A.N.A.MilkoCdLa-N.A.N.A.N.A.N.A.N.A.N.A.N.A.N.A.Il5t860l5FoodProductsoCi/ks. wet!a-lr-N.A.N.A.N.A.N.A.N.A.N.A.N.A.N.A.606080N.A.N.A.SedimentnCi/ks. drvF-L-<bN.A.N.A.N.A.N.A.N.A.N.A.N.A,N.A.N.A.ls0180N.A.N.A.a.b.If no drinking water pathway exists, a value of 3000 pCi/liter may be used.If no drinking water pattrway exists, I value of 15 pCi/liter may be used. APPEhTDIXFQUATITY AS STJRA}.ICBQUALITY CONTROL PROGRAN{-5 l-Appendix FOualiry AssurancdOualiB Contol ProcramA quality assurance pogram is ernployed by the laboratory to ensure that the environmentaldata are reliable. This program includes the use of written, approved procedures inperforming the work" provisions for staffhaining and certification, internal self assesments ofprogram performance, atrdits by various external organizations, and a laboratoryquality contol progam.The quality control prosam ernployed by the radioanalytical laboratory is designed to ensurethat the sampling and analysis process is working as intended. The program includeschecks and the analysis of quality control samples along with routine samples. Instrumentqtnltty contol checks include backgroturd count rate and counts reproducibillty. In addition tothese two general checks, other qtrality control checks are perfomred on the variety of detectorsused in the laboratory. The exact nafirrc of these checks depends on the tlpe of device and themethod it uses to detect radiation or store the information obtained.Qualtty control samples of a variety of t1ryes are used by the laboratory to verifo the performanceof differentportions of the analytical process. These qualrty control samples include blanks,replicate samples, aoalyhcal knowns, blind samples, and cross-checks.Blaol 2 miles 16.2 15.5 17.2 16.0 65(otrsite)(a) Field periods normalized to one standard quarter (2190 houre)(b) Average of the lndividual measurements in the set(c) The 3.7 mR/yr fur onsite locations falls below the 25 mrem totialbody limit in 10 CFR 190. Table H-2(1 of 2)DIRECT MDIATION LEVELSlndividual Stations at Watb Bar Nuclear PlantEnvironmental Radiation LevelsmR /QuarterMap Dosimeter Approx 1st Qf 2nd Qt 3rd QtrLocation S-tation Dircction, Distance, Jan-Mar Apr.lun Jul-SepNumber Number deorces miles 2016 2016 201640 N-1 10 1.2 21.7 19.3 16.541 N-2 350 4.7 17.8 19.1 17.242 NNE-1 21 1.2 17.1 17.3 19.910 NNE-IA 22 1.9 15.9 12.9 16.643 NNE-2 20 4.'t 16.2 13.0 17.03 NNE-3 17 10.4 16.7 15.9 16.144 NE-1 39 0.9 18.1 15.3 19.445 NE-2 U 2.9 15.9 17.1 19.246 NE* 47 6.1 13.4 11.5 12.747 ENE-1 74 0.7 16.6 13.3 13.148 ENE-2 69 5.8 15.4 10.9 16.874 ENE-24 69 3.5 13.8 12.0 16.34 ENE-3 56 7.6 13.9 12.0 15.449 E-1 85 1.3 17.6 15.3 16.550 E-2 92 5.0 14.3 2'1.2 21.151 ESE-I 109 1.2 14.4 11.8 14.052 ESE-2 106 4.4 17.8 19.7 22.111 SE-1A 138 0.9 15.5 11.3 17.4il sE-2 128 5.3 14.3 14.5 15.975 SE-24 144 3.1 16.3 16.5 16.979 SSE-I 146 0.5 17.1 17.8 18.555 SSE-1A 161 0.6 15.0 12.8 15.656 SSE-2 156 5.8 20.2 16.1 17.34th QtrOct-Dec201617.917.617.915.214.616.819.617.913.617.914.51 1.310.716.320.514.617.217.414.518.916.712.416.7Annual(l)ExposuremRlfear75.471.772.260.660.965.572.470.051.260.957.653.452.065.777.154.976.861.659.268.670.155.970.3(1) Sum of available quarterly data normalized to 1 year br the annual exposurc value. Table H-2 (2 of 2)DIRECT RADIATION LEVELSlndividual Stations at Watts Bar Nuclear PlantEnvironmental Radiation LevelsmR /QuarterMap Dosimeter Approx 1st QtrLocation S-tation Directior, Distance, Jan-MarNumber Number degrees miles 201A57 S-1 192 0.7 16.358 S-2 195 4.9 13.976 S-2A 177 2.0 '17.55 S-3 195 7.9 13.959 ssw-1 1gg 0.9 21 .112 SSW-2 200 1.3 14.960 ssw-3 1gg 5.0 14.362 SW-1 226 0.9 19.363 SW-2 22A 5.3 19.66 SW-3 225 15.0 15.164 WSW-1 255 0.9 15.665 WSW-2 247 3.9 17.666 W-1 270 0.9 17.214 W-2 277 4.8 16.677 W-2A 269 3.2 19.267 WNW-1 294 0.9 24.36g wNW-2 292 4.9 20.269 NW-1 320 1.1 14.570 NW-2 31 3 4.7 17.378 NW-2A 321 3.0 17.12 NW-3 317 7.0 17.971 NNW-1 340 1.0 15.472 NNW-2 333 4.5 17.873 NNW-3 329 7.0 14.07 NNW.4 337 15.0 15.22nd Qtr 3rd QtrApr-Jun Jul-Sep2016 201616.3 14.113.0 14.917.3 16.014.4 13.024.6 21 .513.8 19.413.0 14.021 .0 20.521 .2 1g.g1 1 .5 14.615.4 16.617.0 20.918.5 17.614.4 15.917 .0 19.425.4 25.718.8 22.517.3 19.718.8 19.317.8 19.719.0 23.514.4 16.015.6 15.89.4 11.713.9 14.5Annual(l)ExposuremRAfear61 .853.570.256.685.564.358,778.779.855.861.074.471 .159.270.9100.579.365.275.967.877.763.267.448.157.34th QrOct-Dec201615.11 1.919.415.318.317.217.418.920.114.613.419.017.912.?16.325.117.814.720.514.217.417.419.213.0'13.7(1) Sum of available quarterly data normalized to 1 year fur the annual exposure value. Name of Facility: WATTS BAR NUCLEAR PLANTLocation of Facility: RHEA, TENNESSEEType and Loner Limit lndicator LocationsTotal Number of Detection Mean (F)of Analysis (LLD) RangePerformed See Note 1 See Note 2GROSS BETA - 5272.C/rE-02 (422 I 422')6.01E 5.16E-021.94E-02 (1 I 112',)1.94E-02 1.94E-021.15E-01 (1 12 I 11216.66E-02 1.65E-012.77E-02 (109 t 11215.40E 1.32E-015.25E-02 (1 t 112)5.25E-02 5.25E-026.80E-03 (6 t 11216.00E-03 9.50E-032.80E-02 (103 I 11215.20E-03 1.38E{15.28E-03 (4 t 112)3.908-03 6.70E-03Tennessee Valley AuthorltyRADIOACTIVITY IN AIR FILTERpCi/m^3 = 0.037 Bg/m^3Location with Highest Annual MeanDocket Numben 50-390,391Reporting Period: 2016Hper)d(!hratt{t(,to\UtIGAMMA SCAN (GELl) - 140AC-228BE-7Bl-214K-,40PB-212P&214TL-2092.00E431.00E-022.00E-025.00E-034.00E-025.00E-035.00E-032.00E-03Location Description withDistance and DirectionPMs DECATUR6.2 MILES SLM20.5 MILES NPM5 DECATUR6.2 MILES SPM47.6 MILES NE/ENEPM310.4 MILES NNEL[,120.5 MILES NPM5 DECATUR6.2 MILES SLM20.5 MILES NMean (F)RangeSee Note 22.16E-02 (53 / 53)6.01E 4.gE-021.94E-02 (1 I 1411.948 1.94E-021.20E-01 (14 I 14)8.10E-02 1.59E-013.63E-02 (13 I '.t4',)7.10E 1.32E-015.25E-02 (1 I 14)5.25E 5.25E-028.50E-03 (1 I 14',t8.50E 9.50E-033.69E-02 (13 I 1415.60E-03 1.34E-015.50E-03 (1 t 1415.50E 5.50E-03Control LocationsMean (F)RangeSee Note 21 .96E-02 (105 / 105)5.69E 3.95E4228 VALUES < LLD1.16E-01 (28 t 2816.47E42 - 1.918-012.65E42 (27 t28l5.60E 1.05E-0128 VALUES < LLD9.40E-03 (2 I 2817.00E 1 .1gE-022.45E-A2 Q6 t 28l5.20E-03 6.73E-026.90E-03 (1 t28)6.90E-03 6.90E-03Number ofNonroutineReportedMeasurementsSee Note 3Notes: l. ],lominal Lovuer Lgvgl of Debdlon (LLD) ae doacribed in Table E - 12. ilean and Range baaed upon d*tectable meagurcmsntg only. Fraction of detedable m*asurements at spoclfled tocation b indlcatod in panntheses (F).3. Blankr ln thic column lndlceto no nonrountine mcaaurBment! Name of FacilitY:Location of FacilitY:Type andTotal Numberof AnalysisPerformedt-131K40PB-212PB-214TL-209WATTS BAR NUCLEAR PTANTRHEA, TENNESSEELower Limitof Detection(LLD)See Note 1Tennessee Valley AuthorityRADIOACTIVIW IN CHARCOAL FILTERpCi/m^3 = 0.037 Bq/m^3Location with Highest Annual Mean50-390,3912016Control LocationsMean (F)RangeSee Note 2s.29E{2 (3e / 105)5.04E-02 2.36E-013.48E-01 (15 / 105)3.02E 5.25E-01105 VALUES < LLD1 .1 7E-01 (1 9 / 105)7.25E-02 2,gtE-01105 VALUES < LLDDocket Number:Reporting Period:lndicator Locationstvlean (F)RangeSee Note 29.6 E-02 (178 t 422)5.02E-02 2.66E-01SEE NOTE 43,65E-01 (71 I 42213.02E-01 6.96E-01422 VALUES < LLD1.16E-01 (1 14 I 42217.02E-O2 3.95E-01422 VALUES < LLDLocation Elescription withDistance and DirectionLM10.5 MILES SSWLM10.5 MILES SSWLM31.9 MILES NNEPM310.4 MILES NNEPMz SPRING CITY7.0 MILES NWMean (F)RangeSee Note 21.05E-01 (17 I 52)5.1EE 1.92E-013.94E-01 (5 l52l3.12E-01 6.96E-0153 VALUES < LLD1.36E-01 (16 / 53)7.06E-02 3.95E-0152 VALUES < LLDNumber ofNonroutineReportedMeasurementsSee Note 3GAMMA SCAN (GELl) - 527Bt-214 5.00E-02HDtflEl(!Hf*{I5Io\o\I3.00E-023.00E-013.00E{27.00E-022.00E-02Notes: 1. Nominal Lryer Lerol of DeGclbn (LLD) as d$cribed in Tabte E - I2. liban and Rango bas*d upon detoctable measuEment3 only. Fnac{ion of dctedabb measur*mcnt3 at spcct'ficd location b lndacebd in paontheses (F).3. Blanks ln thls column indlcab no nonrounline m*asur"mentg4. Thc analyais of Charcoal Filters was poilomad by Gamma Spoctroscopv. No l-131 wes d*toded. The LLD for l-131 bv Gamma SpsctrolcoDy wae 0.03 DcUcublc mct r. Name of Facility:Location of Facility:Type andTotal Numberof AnalysisPerformedTRTTIUM - 206WATTS BAR NUCLEAR PLANTRHEA, TENNESSEELoupr Limitof Detection(LLD)See Note 13.00E+00Tennessee Valley AuthorityRADIOACTIVIW IN ATMOSPHERIC MOISTUREpCi/m^3 = 0.037 Bq/m^3Location with Highest Annual Meanlndicator LocationsMean (F)RangeSee Note 23.98E+00 (47 t 130)3.03E+OO 7.42E+OOLocation Description withDistance and DirectionLM20.5 MILES NMean (F)RangeSee Note 24.45E+00 (14 126)3.24E+00 - 7,42E+00Docket Number:Reporting Period:5G390,3912016Control LocationsMean (F)RangeSee Note 23.89E+OO (11 I 52')3.19E+OO 5.23E+00Number ofNonroutineReportedMeasurementsSee Note 3-lsdiir-tDFt*{tL'IIo\{INotes: l. Norninal Lovyer Level of Detection (LLD) as descdbed ln Table E - 12. liban and Range based upon dstcdabb measurgmenE only. Fraction of detedable msasurpmsnig at opccificd locatkm b lndlcated in paentheses (F).3. Bbnks in this column indbab no nonrcuntino mcaaur*ments Name of Facility: WATTS BAR NUCLEAR PLANTLocatlon of Facility: RHEA, TENNESSEEType and Lourer Limit lndicator LocationsTotal Number of Detection Mean (F)of Analysis (LLD) RangePerformed See Note I See Note 2toDtNE-l31 -78GAIUMA SCAN (GELl) -7852 VALUES < LLD52 VALUES < LLD3.94E+01 (28 I 5212.04E+01 1.14E+021.30E+03 (52 t 5218.95E+02 1.44E+0352 VALUES < LLD3.76E+01 (19 t 5212.01E+01 8.48E+012.37E+00 (1 I 52)2.37E+00 2.37E+00S?VALUES < LLD8 VALUES < LLD8 VALUES < LLD1. Nominal Lower Level of Detestion (LLD) as described in Table2. Mean and Range based upon detectable measurements only.3. Blanks in this column indicate no nonrountine measurementsTennessee Valley AuthorityRADIOACT]VITY IN MILKpCi/L = 0.037 Bq/LLocation with Highest Annual MeanLocation Desoiption withDistance and DirectionMean (F)RangeSee Note 226 VALUES < LLD4.35E+01 (1 4t2612.33E+01 - 1j4E+021.30E+03 ee t 2618.95E+0e - 1.42E+0326 VALUES < LLD3.88E+01 (10 I 26)2.01E+01 8.4EE+0t2.37E+00 (1 t 2612.37E+00 2,37E+0026 VALUES < LLDDocket Number:Reporting Period:50-390,39120t6Control LocationsMean (F)RangeSee Note 226 VALUES < LLD2.03E+01 (1 t26l2.038+01 - 2.03E+013.93E+01 (13 t 26l2.13E+01 - 1.05E+021 .31E+03 (26 I 2611.18E+03 - 1.48E+0326 VALUES < LLD4.20E+01 (7 I 26)2.29E+A1 - E.27E+0126 VALUES < LLD26 VALUES < LLD4 VALUES < LLD4 VALUES < LLDNumber ofNonroutineReportedMeasurementsSee Note 3t.lDcrt-o,rat&to\to\6IAC-228Bl-214K.00PBA12P&l214TL-202TL-208sR89 -12sR90 -124.00E-012.00E+0t2.00E+011.00E+021.50E+012.00E+01-1.00E+001.00E+013.50E+002.00E+00NORTON FARM4.1 MILES ESE1.75 MILES SSW1.75 MILES SSW1.75 MILES SSW1.75 MILES SSWNORTON FARM4.1 MILES ESENORTON FARM4.1 MILES ESEE-1Fraction of detectable measurements at specified location is indicated in parentheses (F).Notes: Name of Facility: WATTS BAR NUCLEAR PISNTLocation of Facility: RHEA, TENNESSEEType and Lower Limit lndicator LocationsTotal Number of Detection lUban (F)of Analysis (LLD) RangePerfurmed See Note 1 See Note 2GAMMA SCAN (GELl) - 10Tennessee Valley AuthorityRADIOACTIVIW IN SOILpCi/g = 0.037 Bq/g (DRY WEIGHT)Location with Highest Annual McanDocket Number: 50-390,391Reporting Period: 2016F.lpdlEat!-rt4.I\tao\\oIAG228BE.7sanBt-214cs-l37K40PA-234MPB-212P*214RA-226TL-z06. 2.s0E-012.50E-014.50E-011.50E-013.008-027.50E-014.00E+001.00E-011.50E-011.50E-016.00E-021.60E+004.00E{11.08E+00 (8 / 8)6.60E 1.33E+008.52E-01 (3 / 8)3.75E-01 1.63E+001.19E+00 (8 / 8)6.38E 1.51E+007.54E-01 (g / 8)5.33E 9.14E-011.33E-01 (6 / 8)4.69E-02 2.96E-011.07E+01 (8 / 8)3.86E+00 - 2.67E+018 VALUES < LLD1.04E+00 (8 / 8)6.24E{1 - 1.30E+008.40E-01 (g / g)6.31E 1.03E+007.54E-01 (8 / g)5.33E 9.14E-013.47E-01 (8 / 8)2.11E-01 4.25E-018 VALUES < LLD8 VALUES < LLDLocation Description withDistance and_DirectionPMs DECATUR6.2 MILES SPMz SPRING CITY7.0 MILES NWLMl0.5 MILES SSWLM31.9 MILES NNELM20.5 MILES NLfrI4 WB0.9 MILES SELM20.5 MILES NPMs DECATUR6.2 MILES SLM31.9 MILES NNELIr/l31.9 MILES NNELM-4 WB0,9 MILES SEMean (F)RangeSee Note 21.33E+00 (1 t 1l1.33E+00 - 1.33E+OO1.63E+00 (1 / 1)1.63E+00 1.63E+001.51E+00 (1 t 1l1 .51E+00 1.51E+009.14E-01 (1 I 1)9.14E41 - 9.14E-012.96E-01 (1 I 1)2.96E 2.96E-012.678+01 (1 / 1)2.67E+01 - 2.67E+O11 VALUES < LLD1.30E+00 (1 t 1l1.30E+00 1.30E+001.03E+00 (1 / 1)1.03E+OO 1.03E+009.14E-01 (1 I 1)9.14E 9.14E-014.25E-01 (1 I 1l4.25E 4.25E-01Control LocationsMean (F)RangeSee Note 26.66E-01 (2 t 2l6.40E 6.91E-014.26E-01 (1 t 2)4.26E{1 - 4.26E41717E-01 (2 I 2)6.25E g.0gE-016.57E-01 (2 I 2')5.98E 7.16E-013.84E-01 (1 I 2)3.84E 3.94E-014,58E+00 (2 I 2l4.54E+00 4.62E+002 VALUES < LLD6.81E-01 (2 t 2)5.90E 7.728-017.17E.o1 (2 t 2)6.24E 9.10E-016.57E-01 (2 t 2)5.98E 7.16E-012.20E-01 (2 I 2l2.04E-01 2.37E-012 VALUES < LLD2 VALUES < LLDNumber ofNonroutineReportedMeasurementsSee Note 3sR89 -10sR90 -10Notca: 1. Nominal Lo*ur lsvel of Detcction (LLD) as d*scribcd in Tablc E - I2. i/ben and Range bas*d upott dctectable measulcmonts only. Fractlon of dst*c0abb mcasupmentB at spscmod bcatlon b indlcated in parunthcses (F).3. Blanks in thb column indlcat! no nonountlnc measurumcntg Name of Facility: WAfiS BAR NUCLEAR PIANTLocation of Facility: RHEA, TENNESSEETennessee Valley AuthorityRADIOACTIVIW IN CABBAGEPCi/Kg = 0.037 Bq/Kg WET WEIGHT)Location with H(;hest Annual MeanDocketNumber: 50-390,391Reporting Period: 2016Type andTotal Numberof AnalysisPerbrmedGAMMA SCAN (GELl)Bl-214K.40PB-212PB-214Lower Limitof Detection(LLD)See Note 14.00E+012.50E+024.00E+018.00E+01-3lndicator LocationsMean (F)RangeSee Note 26.58E+01 (1 / 1)6.58E+01 - 6.58E+012.54E+03 (1 t 1)2.54E+03 2.54E+031 VALUES < LLD1 VALUES < LLDLocation Desoiption withDistance and Direction3.0 MILES SE3.0 MILES SE3.0 MILES SE3.0 MILES SEMean (F)RangeSee Note-26.58E+01 (1 / 1)6.58E+01 - 6.58E+012.&4E+03 (1 I 1)2.54E+03 2.54E+031 VALUES < LLD1 VALUES < LLDControl LocationsMean (F)RangeSee Note 22 VALUES < LLD2.32E+03 (2 t 2l2.07E+03 2.57E+032 VALUES < LLD2 VALUES < LtDNumber ofNonroutineReportedMeasurementsSee Note 3-lg,C'-(Dt+lt4{IooI{otNotes: 1. Nominal Lorer lowl of Debctbn (LLD) as described in Table E - 12. i/lean hnd Rango based upon dcbctabb moesurrmcnt8 only. Fraction of dctacfable mcasurcmcntg at specifisd location b indicated ln parcnthcrs (F).3. Blanks ln thi! column lndbate no nonrountino m*asuromontB Name of Facility: WATTS BAR NUCLEAR PISNTLocation of Facility: RHEA, TENNESSEEType and Lower Limit lndicator LocationsTotal Number of Detection Mean (F)of Analysis (LLD) RangePerformed See Note I See Note 2GAMMA SCAN (GELI) - 2Tennessee Valley AuthorityRADIOACTIVITY IN CORNPCi/Kg = 0.037 Bq/Kg WET WEIGHT)Location with Highest Annual MeanDocket Number: 50-390,391Reporting Period: 2016GAILocation Description withDistance and DirectionNORTON FARM4.1 MILES ESENORTON FARM4.1 MILES ESENORTON FARM4.1 MILES ESENORTON FARM4.1 MILES ESENORTON FARM4.1 MILES ESEMean (F)RangeSee Note 26.72E+01 (1 t 1)6.72E+01 - 6.72E+011 .69E+03 (1 / 1)1.69E+03 1.69E+Og1 VALUES < LLD1 VALUES < LLD1 VALUES < LLDControl LocationsMean (F)RangeSee Note 21 VALUES < LLD2.16E+03 (1 t 1l2.16E+03 2.16E+031 VALUES < LLD1 VALUES < LLD1 VALUES < LLDNumber ofNonroutineReportedMeasurementsSee Note 3Bl-214K-,40PB-212PB-214TL-2094.00E+0't2.50E+024.00E+018.00E+013.00E+016.72E+01 (1 / 1)6.72E+01 - 6.72E+0t1.69E+03 (1 / 1)1.69E+03 1.69E+031 VALUES < LLD1 VALUES < LLD1 VALUES < LLDt\t!-II{t\,IdEcrEtTldtJrI\oNol$: 1. Nominal Lwucr Lcvol of Dotaction (LLD) aB d$cdbed ln Table E - 12' Mean end Renge basad upon rteteciabls rnsasuEm*nta only. Fraction of detectabb moasur*monts st specified location is indicated in par*ntho3e3 (F).3, Blanks ln thB column indicete no nonrountans moesulrments Name of Facili$:Location of Facility:Type andTotal Numberof AnalysisPerformedGAMMA SCAN (GELI)Bl-214K.00PB-l214WATTS BAR NUCLEAR PI,ANTRHEA, TENNESSEELower Limitof Detection(LLD)See Note I-24.00E+01Tennessee Valley AuthorityRADIOACTIVITY IN GREEN BEANSPCi/Kg = 0.037 Bq/Kg WET WEIGHT)Location with Highest Annual Mean5G3g0,39l2016Control LocationsMean (F)RangeSee Note 25.53E+01 (1 t 1)5.53E+01 - 5.53E+013.70E+03 (1 I 1l3.708+03 - 3.70E+031 VALUES < LLDDocket Number:Reporting Period:lndicator LocationsMean (F). RangeSee l$ote 29.72E+01 (1 I 1')9.72E+01 - 9.72E+011.90E+03 (1 t 1l1.90E+03 - 1.90E+039.61E+01 (1 / 1)9.61E+01 9.61E+01Location Description withDistanoe and Direction3.0 MILES SE3.0 MILES SE3.0 MILES SEMean (F)RangeSee Note 29.72E+01 (1 / 1)9.72E+01 - 9.72E+0t1.90E+03 (1 t 1l1.90E+03 - 1.90E+039.61E+01 (1 t 1l9.61E+01 9.61E+01Number ofNonroutineReportedMeasurementsSee Note 32.50E+028.00E+01-lstcr-atTf+lFLIhJoa\tt\)I],lotes: 1. Nominal Lomr Lewl of Dctedion (LLD) as desqibe<t in Table E - 12. iiean and Rang* bas*d upon detedable measurcm*nts only. Fraction of detsctabl* msasur*mont3 at spocifi*d locatbn is indicatsd ln parentheces (F).3. Blanks in this column andlcato no nonrountinc mcalurcmentg Name of Facility: WATTS BAR NUCLEAR PIANTLocation of Facility: RHEA, TENNESSEETennessee Valley AuthorityRADIOACTIVITY IN TOMATOESPCi/Kg = 0.037 Bq/Kg WET WEIGHT)Location with Highest Annual MeanDocket Number: 5G390,391Reporting Period: 2016Type andTotal Numberof AnalysisPerformedGAMMA SCAN (GELl)Bl-214K-40Pt214TL-209Louer Limitof Detection(LLD)See Note 1-24.00E+012.50E+028.00E+013.fr)E+Otlndicator LocationsMean (F)RangeSee Note 24.94E+01 (1 / 1)4.94E+01 - 4.94E+0t2.01E+03 (1 / 1)2.01E+03 - 2.01E+031 VALUES < LLD1 VALUES < LLDLocation Description withDistance and Direction3.0 MILES SE3.0 MILES SE3.0 MILES SE3.0 MILES SEMean (F)RangeSee Note 24.94E+01 (1 t U4.94E+01 - 4.94E+012.01E+03 (1 I 1)2.01E+03 2.01E+031 VALUES < LLD1 VALUES < LLDControl LocationslVlean (F)RangeSee Note 24.05E+01 (1 t 1)4.05E+01 - 4.05E+011.90E+03 (1 I 1l1.90E+09 1.90E+031 VALUES < LLD1 VATUES < LLDNumber ofNonroutineReportedMeasurementsSee Note 3HF'Chaol+frlItdH!{f.AlINotes: 1. Norninal Louuer Level of Detection (LLD) as deecribed in Table2. Mean and Range based upon detectable measurements only.3. Blanks in this column indicate no nonrountine measurementsE-1Fraction of detectable rneasurements at specified location is indicated in parentheses (F). Name of Facility: WATTS BAR NUCLEAR PIANTLocation of Facility: RHEA, TENNESSEETen nessee Valley AuthorityRADIOACTIVIW lN SURFACE WATER Cl'otal)pCi/L = 0.037 BqlLLocation with Highest Annual Mean50-390,3912016Control LocationsMean (F)RangeSee Note 22.33E+00 (7 t 13)1.928+fi) 3.24E+0013 VALUES < LLD5.96E+01 (5 / 13)2.42E+0t 1.3llE+O213 VALUES < LLD13 VALUES < LLD4.92E+01 (5 / 13)2.01E+01 1.12E+0213 VALUES < LLD13 VALUES < LLDDocket Number:Reporting Period:Type andTotal Numberof AnalyslsPerformedGROSS BETA - 39GAMMA SCAN (GELl) - 3eAe-229Bt-214K,40PB-212P*214TL-208TRITIUM - 39Lourcr Limitof Detection(LLD)See Note 11.90E+002.00E+012.00E+011.(DE+021.50E+012.00E+011.00E+012.70E+02lndlcator LocationsMean (F)RangeSee Note 22.95E+OO (18 / 26)2.08E+OO - 5.78E+0026 VALUES < LLD4.88E+01 (1 4126)2.18E+01 - 1.37E+0226 VALUES < LLD26 VALUES < LLD4.75E+01 (10 I 26)2.18E+01 - 1.19E+0226 VALUES < LLD7.22E+02 (8 I 26')3.11E+02 - 1.62E+03Location Description withDistance and DirectionTRM 517.9TRM 523.1TRM 517.9TRM 523.1TRM 517.9TRM 517.9TRM 523.1TRM s23.1Mean (F)RangeSee Note 23.1 1E+00 (8 / 13)2.08E+00 4.34E+00I3 VALUES < LLD5.55E+01 (7 / 13)2.62E+A1 - 1.37E+O213 VALUES < LLD13 VALUES < LLD5.10E+01 (6 / 13)2.18E+01 - 1.19E+0213 VALUES < LLD7.30E+02 (4 t 13)4,97E+02 - 1.15E+03Number ofNonroutineReportedMeasurementsSee Note 3*ls(rhao:rlr{IhJhJt{5I1. Nominal Louuer Level of Detec{ion (LLD) as described in Table2. Mean and Range based upon detectable measurements only.3. Blanks in this column indicate no nonrountine measurementsE-1Fraction of detectable measuriements at specified location is indicated in parentheses (F).Notes: Name of Facility: WATTS BAR NUCLEAR PLANTLocation of Facility: RHEA, TENNESSEETenneaaee Valley AuthorityRADIOACTMITY lN PUBLIC (DRINKING) WATER (Totat)pCi/L = 0.037 Bq/LLocation with Highest Annual MeanType andTotal Numberof AnalysisPerformedGROSS BETA - 39GAMMA SCAN (GELI) - 39AC-228Bl-214Kr{0PB-212PBlzl4TL-209TRITIUM - 47Lower Limitof Detection(LLD)Sqg Note 11.90E+002.00E+012.00E+011.00E+021.50E+012.00E+011.00E+012.74E+02lndicator LocationsMean (F)RangeSee Note 22.28E+00 (10 / 26)2.06E+00 3.32E+005.80E+01 (4 t26l3.34E+01 - 1.24E+023.47E+01 (1 1126)2.05E+01 - 6.08E+Ot26 VALUES < LLD26 VALUES < LLD3.37E+01 (7 t 26)2.07E+01 - 5.42E+0126 VALUES < LLD5.73E+02 (16 / 34)2.82E+02 - 1.01E+03Location Description withDistance and DirectionCF INDUSTRIESTRlvl 473.0RM.z DAYTON TN17.8 [/llLES NNERM-2 DAYTON TN17,8 MILES NNERM-2 DAYTON TN17.8 ]I/IILES NNERM-2 DAYTON TN17.8 MILES NNECF INDUSTRIESTRM 473.0CF INDUSTRIESTRM 473.0RM.z DAYTON TN17.8 MILES NNEMean (F)RangcSee Note 22.39E+00 (6 / 13)2.06E+00 - 3.32E+008.05E+01 (2/ 13)3.69E+01 - 1.24E+A23.77E+01 (5 / 13)2.80E+01 - 6.05E+0113 VALUES < LLD13 VALUES < LLD3.59E+01 (3 I 13')2.66E+01 - 5.26E+0113 VALUES < LLD A5.91E+02 (7 t 1713.50E+02 - 9.85E+02Docket Number:Reporting Period:50-390,3912016Control LocationsMean (F)RangeSee Note 22.33E+00 (7 t 13)1.92E+00 3.24E+0013 VALUES < LLD5.96E+01 (5 / 13)2,42E+01 - 1.34E+0213 VALUES < LLD13 VALUES < LLD4.92E+01 (5 I 13)2.01E+01 1.12E+0213 VALUES < LLD13 VALUES < LLDNumber ofNonroutineReportedft/leasurementsSee Note 3*ls(rbot#)r{IF{(,t{uINotBE: 1. l{ominal Lowsr Lcrrol of Dotectaon (LLD) as dcscrlb*d ln Table E - 12. Ilean and Range barcd upon detcdable meatullmcnE only. Fradion of dstcctabb mcalurrmcnt3 at rpccilicd location ia lndicated ln paonthegar (F).3, Blenkc in thb column indlcab no nonrpuntine mcasutEmGnt! Name of Facility: WATTS BAR NUCLEAR PIANTLocation of Facllity: RHEA, TENNESSEETennessee Valley AuthorityRADIOACTIVIil lN WELL (GROUND) WATER Ootal)pCi/L = 0.037 Bq/LLocation with Hlghest Annual Mean.Type andTotal Numberof AnalysisPerformedGROSS BETA .84GAMMA SCAN (GELl) - 84AC-228Bl-214K-,40Pb212PB-214TL-208TRITIUM .84Loupr Limitof Detection(LLD)See Note 11.90E+002.00E+012.00E+011.00E+021.50E+012.00E+0t1.00E+012.70E+02lndicator LocationsMean (F)RangeSee.Note 23.11E+00 (40 / 70)1.91E+00 5.918+003.17E+01 (2 I 7A)2.96E+01 3.38E+013.72E+O1 (42 t70t2.06E+01 1.18E+0270 VALUES < LLD1.90E+01 (2 t 70)1.548+01 - 2.25E+O13.83E+01 (28 t70)2.00E+Ot - 1.20E+021.198+01 (1 I 7Ol1.19E+01 - 1.19E+015.86E+02 (41 t70)2.78E+02 1.13E+03Location Description withDistance and DirectionWBN I/II/V-B0.4s MTLES SSE)WBN i,,IW-Fo.30 MlLES SE)WBN MW-A0.58 MlLES SSE)WBN WELL #10.6 MILES SWBN MW-Fo.30 MlLES SE)WBN ]ITIA,-A0.58 MTLES SSE)WBN MW.Fo.30 MlLES SE)WBN [\,llru.B0.4s MTLES SSE)Mean (F)RangeSee Note 24.05E+00 (14 t 14). 2.42E+OA 5.91E+003.38E+01 (1 I 14)3.38E+01 - 3.38E+014.47E+01 (12 t 14,2.11E+01 1.18E+0214 VALUES < LLD2.25E+01 (1 I 14)2.25E+01 - 2.25E+0't4.83E+01 (10 t 14)2.05E+01 - 1.2AE+021.19E+01 (1 I 14'l1.19E+01 - 1.19E+017.90E+02 (14 t 1414.12E+OZ 1.13E+OgDocket Number:Reporting Period:50-390,3912016Control LocationsMean (F)RangeSee Note 22.26E+00 (9 / 14)1.91E+00 3.04E+0014 VALUES < LLD3.83E+01 (5 t 1412.02E+Al - 5.52E+0114 VALUES < LLD14 VALUES < LLD3.71E+01 (3 t 14)2.05E+01 - 4.72E+O114 VALUES < LLD14 VALUES < LLDNumber ofNonroutineReportedMeasurementsSee Note 3Hs,crldt!)+{*{tt-5I{o\INobs: l. l,lominal Lwsr Lcwl of Detecffon (tLD) aE dsEcribod in Table E - 12. tlcan and Range based upon det*ctable measuEments only. Fraction of detectable meeour* nenE at sp*cified location is andacated in parentheses (F).3. Blanks in this column indicatc no nonrountine mca3uGmcnt3 Name of Facility: WAfiS BAR NUCLEAR PLANTLocation of Facility: RHEA, TENNESSEETenneasee Valley AuthorityRADIOACTIVITY IN COMMERCIAL FISHpCi/g = 0.037 Bdg (DRY WEIGHT)Location with Highest Annual MeanType andTotal Numberof AnalysisPerformedGAMMA SCAN (GELl)Bl-214K,{0Pt212PB-214TL-208Lower Limitof Detection(LLD)See Note 1-61.00E-014.00E-014.00E-021.00E-013.00E-02lndicator LocationsMean (F)RangeSee Note 24 VALUES < LLD8.62E+00 (4 I 4,6.57E+00 9.61E+004 VALUES < LLD4 VALUES < LLD4 VALUES < LLDLocation Description withDistance and DirectionDOWNSTREAM STATION 1DOWNSTREAMDOWNSTREAM STATION 1DOWNSTREAMCHICKAMAUGA RESTRM 471-530DOWNSTREAM STATION 1DOWNSTREAMCHICKAMAUGA RESTRM 471-530Mean (F)RangeSee Note 22 VALUES < LLD9.16E+OO (2 t2)9.01E+00 9.31E+002 VALUES < LLD2 VALUES < LLD2 VALUES < LLDDocket Number:Reporting Period:5G390,391201 6Control LocationsMean (F)RangeSee Note 21.19E-01 (1 I 2l1 .1 gE 1 .1gE-011.21E+01 (2 t 2l1.10E+01 ' 1.32E+012 VALUES < LLD1.16E-01 (1 I 2l1.16E 1.16E-012 VALUES < LLDNumber ofNonroutineReportedMeasurementsSee Note 3-lpcrH(D)+a)+{IldL,II-{{INotes: 1.2.3.Nominal Lower Level of Detection (LLD) as described in TableMean and Range based upon detectable measurements only.Blanke in this column indicate no nonrountine measurementeE-1Fraction of detedable measurements at specified location is indicated in parentheses (F).}}