ML16133A535
| ML16133A535 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 05/12/2016 |
| From: | Simmons P Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML16133A535 (94) | |
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{{#Wiki_filter:M Tennessee Valley Authority, P.O. Box 2000, Spring City, Tennessee 37381-2000 May 12,2016 10 cFR 50.4 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Units 1 and 2 Facility Operating License Nos. NPF-90 and NPF-96 NRC Docket Nos. 50-390 and 50-391
Subject:
Watts Bar Nuclear Plant - Annual Radiological Environmental Operating Report - 2015 Enclosed is the subject report for the period of January 1,2015, through December 31,2015. This report is being submitted as required by Watts Bar Nuclear Plant (WBN) Units 1 and 2, Technical Specification (TS) 5.9.2, "Annual Radiological Environmental Operating Report," and the WBN Offsite Dose Calculation Manual (ODCM), Administrative Control Section 5.1. This report is required to be submitted to the Nuclear Regulatory Commission (NRC) by May 15 of each year. There are no new regulatory commitments in this letter. lf you have any questions concerning this matter, please contact Gordon Arent, WBN Licensing Director, at (423) 365-2004. Respectfully, Paul Simmons Site Vice President Watts Bar Nuclear Plant
Enclosure:
Annual Radiological Environmental Operating Report - Watts Bar Nuclear Plant 2015 cc: See Page2
U.S. Nuclear Regulatory Commission Page 2 May 12,2016 cc (Enclosure): NRC Regional Administrator - Region Il NRC Project Manager - Watts Bar Nuclear Plant NRC Senior Resident Inspector - Watts Bar Nuclear Plant
ENCLOSURE TEN NESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT Annual Radiological Environmental Operating Report Watts Bar Nuclear Plant 201 5
Annual Radiological Environmental Operating Report Watts Bar Nuclear Plant 2015
A}.INUAL ENVIRONMEX\ITAL RADIOLOGICAL OPERATING REPORT WATTS BAR NUCTEAR PLA}.IT 2015 TENNESSEE VALLEY AUTHORITY April 2016
TABLEOF CONTENTS Table of Contents Executive Sumnrary Introduction 2 Naturally Occuning and Background Radioactivity 2 Electic Power Production 3 S itc/Plant Description Radiological Environmental Monitoring Program. Dircct Radiation Monitoring l1 Measutrment Techniques. . . . . ll Results. 12 Atuospheric Monitoring t4 Sample Collection and Analysis. . . . t4 Results. l5 Terrestrial Monitoring l6 Sample Collection and Analysis. . . . l6 Results. t7 Liquid Pathway Monitoring l8 Sample Collection and Analysis. . . . . l8 Resuls. l9 Assessment and Evaluation. . . 2t Results 2t Conchuions 22 References 23 Table I Comparison of Program Lower Limits of Detection with Regulatory Limits for Maximum Annual Average Effluent Consentrations Released to Unrestricted Areas and Repoming Levels. . . . . . . . . . . 24 Figrue I TennesseeValleyRegton. . .,, . . . . . . . . . r ., . . . . . r . . . . . . .. ., . 25 Figure 2 Environmental Exposure Pathways of Man Due to Releases of Radioactive Materials to the Atrrosphgrgandlake,,., . . . . . . . . . . . . . o . . . . . . . . . . . . . . . . .. 26
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TABLE OF CONTENTS (continued) Appendix A Radiological Environmental Monitoring Program and Sampling Locations. 27 Appendix B Program Modifications. 38 Appendix C Program Deviations. 40 Appendix D Analytical Procedures 43 Appendix E Nominal Lower Limits of DeEction (LLD). 46 Appendix F Quality Assurance/Quality Control Program. 51 Appendix G Land Use Sunrey 56 Appendix H Data Tables and Figures 6l aa
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EX(ECUTM SLTMIVIARY This report describcs th Radiological Enviromental MonitoringProgram (REII{P) coducted by TVA in th vicinity of thc Watts BrNuclear Plant (WBN) duing the monitoring period of 2015. The program is conductod in accordance with regulalory rcquircmen6 to monitorthe environmentper 10 CFR 20 ud 10 CFR 50, ad in accordance with TVA procedures. The REMP inshdes the collection ad su@uent determination ofradioactive mafiedal content in environmcntal samples. Various tlpes of smples are collected within the vicinity of the plmt including air, water, milk, food copo, soil, fish, shoreline scdiment and the measrrement of dircct radiation levels. The radiation levels of these samples arp measured and then compared wi& rsults at contol stations located ouEide the plant's vicinity md dala collecrcd d WBN prior to operations (preoperational data). This report contains an evaluation ofthe poteotial impact of WBN operations on the environment and general public. The vast majority ofradioactivity measurod in environmental samples from the WBN prcgram can be contibuted to naturally occuning radioactine materials. low lerrels of Cesium (Cs)-137 wene measurcd in soil and fish smples. The conccntrations wcre gpical of trc lerrels ocpeoted to be prcseirt in the envfuonment fiom past nrrclear weapons tesftrg or opcration of otk nuclear facilities in the region. The frllout from accidents at the Chernobyl plant in the Ukaine in l9t6 and the Fukushima plant in Japan in 201I may have also contibutod to the low levels of Cs-137 measured in e,nvironmental samples. Trace lerrels oftritium wcrc detected in afuospherio moistlre samples. Tritium at corceirtrations slightly above the malytioal detection limit was alsodetcs:tedin$ratersamplescollectedft,omChiokamatrgaRescrvoh Theselerrelswouldnot represent a significant contibution to the rdiation sxposur to members of tb public. Tritiuor uns detccted in onsite gpound $ratff monitoring wells. The tsitium was fte result of onsite gromd water aontamination from previorsly identified md repafued leaks inplmt systcms. In addition, cobalt (Co>60 ad Cs-I37 wele identified in sediment collected tom the onsite ponds. The level of activity measured in these onsite locations would not preselrt a risk of e{xrsur to tbe general public.
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INIRODUCTION This report describes and summarizes the results of radioactivity measurements madc in the vicinity of WBN and laboratory analyses of samples collected in the area Thc measurements are mad to comply with the requirements of 10 CFR 50, Appendix A Criterion 64 and 10 CFR 50, Appendix I, Section IV.B.2, IV.B.3 and IV.C and to determine potential effects on public heatth and safety. This report satisfies the annual reporting requirements of WBN Technical Specification S.9.2andOffsirc Dose Calculation Maoual (OIrcM) Adminishative Conuol 5.1. In addition to reporting the data prescribed by specific requirements, other information is included to help correlate the significance of results measurpd by this program to the levels of environmental radiation resulting from naturally occuning radioactive materials. Naturally Occunins and Background Radioactivity Most materials iu our world today contain tace amounts of nanually occuning radioactivity. Potassium (K)-40, with a half-life of 1.3 billion yearq is one ofthe major types of radioactive materials found naturally in our environment. Approximately 0.01 perrccnt of all potassium is radioactive potassium-40. Other examples ofnaturally occuning radioactive materials are beryllium (Be)"7, bismuth (Bi)-2l2alndzl4,lead (Pb)-2l2and2l4, thallium Cn>208, actinium (Ac)-228,uranium (U>238 and 235, thorium (Ih)-234,radium (Pa)-226,radon (Rn)-222 and 220, carbon (C) -14, and hydrcgen (H!3 (genera[y called tritium). These naturally occuning radioactive materials are in the soil, our foo4 otu 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 cosrnic rays. It is possible to get an idea of the relative hazard of different tpes of radiation sources by evaluating the amount of radiation the U.S. population rcceives from each gencal tpe of radiation souroe. The information below is primarily adapted from Refetences 2 and 3.
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u.s. GENERAL POPULATION AVERAGE DOSE EQLTMLENT ESTII{ATES Source millirem (mrem)t/Year Per Person Natural background dose equivalent Cosmic 33 Terrestial 2t In the body 29 Radon 228 Total 3ll Medical (effective dose equivalent) 300 Nuclear energy 0.28 Constuner products l3 Total 624 (approximately)
- l. One-thousandth of a Roentgen equivalent man (rem)
As can be seen from the data presented above, natural background radiation dose oquivalent to the U.S. population norrnally exceeds that fiom nuclear plmts by several hundred times. This indicates that nuclear plant operations normally result in a population radiation dose equivalent ufrich is insignificant as compared to the dose from natural hckground radiation. It should be noted that the use of radiation and radioactive materials for medical uses has resulted in a similar effective dose equivalcnt to the U.S. population as that caused by natural background cosmic and terrestial radiation. Electric Power Production Nuclear power planf are similar in many respects to conventional coal buming (or other fossil fuel) electical generating plane. The basic prtrce$ behind electical power production in power 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 planq the fuel is uranium and heat is prcduced in the rcactor through the fission of the uranium. Nuclear plants irclude many complex systems to contrrol the nuclear fission procss and to safeguard agsinst the possibility of reactor malfimction The nuclear reactions produce radionuclides cornmonly refened to as fission and activation products. Vcry small amounts of these fission and activation products are rcleased into the plant systems. This radioactive material can be transported throughout plant systems and somc of it may be released to the environment Paths througfu which radioactivity from a nuclear power plant is routincly released arc monitored. Liquid md gaseous efluent monitors record the radiation levels for each release. These monitors also provide alarm mechanisms to prompt trmination of any rclease above limits. Releases are monitorod at the onsite points of release and through the radiological envimnmental monitoring program which measrues the environmental radiatiott in areas around the plant. In this wan the release ofradioactive materials from the plant is tightly conEolled, md 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 effiuents, as well as limis for doses to the general public from the rclease of these efluents. The dose to a member of the general public from radioactive materials released to unrpstricted arBas, as given in Nuclear Regulatory Commission (NRC) guidelines and the ODCM, is limitcd as follows: LiquidEfluents Total body 53 mrem/Year Any organ <10 rnrern/Year Gaseous Effluents Noble gases: Cranmaradiation <10 millirad (mradlYear Beta radiation <20 mrad/Year Particulates: Any organ <15 mrem/Year 4-
The EPA limib for tb total dose to the public in the vicitrity of a nuclear power plmt establishd in the Environmelrtal Dose Stmdad of 40 CFR 190, are as follows: Total body 5P5 mrcm/year Thyroid 5f5 ruem/year Any otherorgan S25 mrcm/year Appardix B to 10 CFR 20 prescnts annual average linits for the concentations of radioactive marcrials rcleased in gaseous and liErid eflrrcnts at the bormdary of the unrestictcd atcas. Table I of this report presents the annual average conccnhation limits for the pincipal mdionuclides associatcd with nuclear powerplant eflrmts. Thc table also preselrts the concentrations of radioactive mxedals in the environment which would requirc a special rcport to the NRC and the &tection limie for measurpd radionculides. It should be noted that thc levels of radioactive materials measurpd in the environmeot are tpically bclow or only slighdy above the lower limit of detection. SITE/PLA}.IT DESCRIPTION The WBN site is located in Rhea county, Tennessee, on the west bank of the Tennesscc River at Tennessee River Mile (TRM) 528. Figrre I shows the site in relation to other TVA projeots. The WBN site, containing approximarcly 1770 acres on Chickamauga Ldre, is approximarcly 2 miles south of the Watts Bar Dam and approximately 3l miles north-northeast of TVA's SequoyahNuclear Plant (SQN) site. Also locarcd within the reservation are the Watts Bar Dam and Hydro-Electic Plant the lVatts Bar Steam Plant (not in opoation), the TVA Cennal Maintenance Facility, and the Watts BarResortArea Approximately 18,500 people live within l0 miles of the WBN sirc. Morc than 80 percent of these live between 5 and l0 miles from the sirc. Two small tolrms, Spring City and Decafir, are located in this area Spring City, with a population of approximatcly 2200, is northwest and north-northwest from tbe site, while Decatu, with about 1,5fi) people, is south and south-southwest from the plant. The remainder of the area within l0 miles of the site is sparsely populatd consisting primarily of small farms and individual rcsidences. The area betrueen l0 and 50 miles from the site includes portions of the cities of Chatanooga and Knoxville. The largcst urban concentration in this area is the crty of Chattanooga, locatcd to the southwest and south-southwesL The city of Chatanooga bas a population of about 170,000, with approximately E0 perce,nt located betrueen 40 and 50 miles ftom the site and the remainder located beyond 50 miles. The city of Knoxville is located to the east-northeast with not morc than l0 percent of its 185,0ffi plus people living within 50 miles of the sitc. Three smaller urbso areas of grarcr than 2O000 people are located between 30 and 40 miles from the sirc. Oak Ridge is approximarcly 40 miles to the northeast, the twin cities of Alcoa and lvlaryville 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 sf highly controlled multiple-usc rpservoirs whose primary uss are flood control, navigation, and the generation of electic power. Secondary uses include industrial and public water supply and waste disposal, fishiry; and rccrcation. Public access araalr, boat docks, and residential subdivisions have been developed along the reservoir shoreline.
WBN consisB of two prcssudzed watff reactors. WBN Unit I received a low power operating license (MF-20) on November 9,1995 ad achieved initisl criticality in Janury 1996. The firll powcr operating liceose (NPF-90) was rpceived on Febnrary 7,1996. Commercial oporation was aohieved May 25, 1996. WBN Unit2 was deferred Octobcr 24,20@,,in accordmce withthc guidance in Generic tttr 87-15, *Policy Statement on Defenpd Plants.' On Augttst 3 ,2007, TVA provided notice of its intent to reactivate and complete oonstruction of WBN Unit 2. WBN Unit 2 resrmed construstion in late 20['7. octoh n,2015 thc operating liccnse was issued"
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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Most of the radiation and radioactivity generated in a nuclear power reactor is contained within &e reactor systems. Plant effluent radiation monitors are designed to monitor radionuclides released to the environment. Environmental monitoring is a final verification that the systems arc performing as planned. The monitoring program is designod to monitor the pmhways between the plant and the people in the immediate vicinity of the plant Sample ty?es are chose,n so that the poteNrtiat for detection of radioaotivity in tre environment will bc maximized. The Radiological Environmental Monitoring hogram (REt IP) and sampling locations for WBN are ouflined inAppendix A. There are twoprimary pathways by uihich radioactivity canmove throughthe environmentto humans: air and water (see Figrre 2). The air pathway oan be separated into nuo components: thc direct (airborne) pathway and the indircct (gFound or terrestrial) pathway. The dirrect airtome pathway consists of direct radiation and inhalation by humans. In the tenesfiial pathway, radioactive materials may be deposited on the ground or on plants and suboeque,ntly ingested by animals and/or humans. Human exposur through the liquid pathlwy may result from drinking watr, cating fish, or by direct eryxlsur at the shorelinc. Thc tlpes of samples collected in this program are designed to monitor these pathways. A number of frctors werc considered in determining the locations for collectiug environmental ru.pi"r. The locations for the atmospheric monitoring stations were determined firom a critical pathway analysis basd on weatherpatterns, dose projections, population distibution, and land use. Terrestrial smpling stations werc seleoted aftEr rcviewing sush things as the locations of dairy animals aod g;ardens in conjunction with the air pathway analysis. Liquid pathway stations were selected based on dose projections, watcr use information, ard availability of media such as fish and scdiment. Table A-2 (Appendix A Table 2: This notation system is used for all tables and figures gven in the appendices.) lists the sampling stations and the t1ryes of samples collectcd from each. Modifications madc to thc WBN monitoring progam in 2015 are rcported in Appendix B. Deviations to the sanrpling program during 2015 are included in Appendix C. To determine the amount of radioactivity in the environment prior to the openation of WBN, a preoperational radiological environmental monitoring program was initiated in Deccmber 1976 and operated through Decembcr 31, 1995. Measurcments of the same tlpes of radioactive materials that are measured cunently were assessed dudng the preoperational phasc to establish normal brckground levels for variow radionuclides in the environment. Dtuing the 1950s, 1960s, and 1970s, atnospheric nuclear weapons testing releascd radioactive material to the environment causing fluctuations in background radiation levels. trhowledge ofpreexisting radionuclide patterns inthe environment permits a dercrmination" though comparison and tending analyses, of the actual environmental impact of WBN operation. The determination of environmental impact during the operating phase also considers the prcsence of contnol stations that have been established in the envitonment" Results of environmental samples talcen at confiol stations (far fiom the plant) are compared with those from indicator strations (nearthe plant) to aid in thc determination of the impocts from WBN operation. The sample analysis is performed by the Tennessee Valley Authority's (fVA's) Environmental Radiological Monitoring and Instrumentation (ERM&I) group located at the Western Area Radiological Laboratory (WARL) in Muscle Shoals, ahbama, orcept for the shontium (SrF89, 90 analysis of soil samples ufrich is performed by a contract laboratory. Analyses arp conductcd in accordance with unimen and approved procedures and are based on accepted methods. A summary of the analysis rcchniques and methodology is presented in Appendix D. Data tables summarizing the sample analysis results are prcsented in Appendix H. The radiation daection devices and analysis methods used to detcnnine 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 qualrty assurance/quality confiol progran to monitor laboratory performance throughout the year. The program is intended to detect any problems in the measurement prosess as sot)n as possible so they can be cotlected. This program includes equipment checks to ensure that the radiation detection instuments are working properly and the analysis of qulity control samples ufrich are included alongside rcutine environmenal samples. To provide for interlaboratory comparison prcgram, the laboratory participates in an environmental cross-check program administcred by Eckert and Zie$er Analytics. A complete desuiption of the program is presented in Appendix F. DIRECT RADI.ATION MONITORING Dfuect radiation levels are measured at various monitoring points around the plant site. These measgrcments include contributions from cosmic radiation, radioactivity in the groun{ fallout from atuospheric nuclearweapons tesb conducted in the past, and any radioactivity that may be present as a result of plant operations. Becarse of the relatively large variations in background radiation as compared to the small levels from thc planq contibutions from theplantmay be difficult to distinguish" Measureme,nt Technioues The Landauer Intight environmental dosimeter is used in thc rdiological environmental monitoriug program for the measurement of direct radiation. This dosimeter contains fotu elements consisting of aluminum oxide deteotors with open wiodows as well as plastic and copper filrcrs. The dosimeter is processed using optically stimulated luminescence (OSL) technolory to determine the amount of radiation exPosure. The dosimeters are placed approximarcly one meter above the ground, with two at each monitoring location. Sixteen monitoring poinb are located around the plant near the site boundary, one location in each of the 16 compass sectors. One monitoring point is also locatcd in each of the 16 compass scctors at a distaoce of approximately four to five miles fromtheplanr Dosimeters are also placed at additional monitoring locations out to approximately 15 milcs from the sirc. The dosimeters are exchanged every three months. The dosimeterc are sentto Lmdauer Inlight forprocessing ad results reporting. The values are corrected for Eaosit and shielded background e4rcsurc. An average of the two dosimeter results is calculated for each monitoring point. The system meets or exceeds fte performancc spccifications outlined in American National Standards Institutc (AIISD N545-1975 md Halth Physics Society (HPS) Draft Sandard N13.29 for environmental applications of dosimeters. WBN Technical Specification 5.9.2, Annual Radiological Environmental O,peratingReport, requires that the ADnual Radiological Environmental Operating Report identify TLD results that represcnt collocatcd dosimeters in relation to the NRC TLD program and the cxposure period
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associared with each result. The NRC collocatcd TLD program was terminated by the NRC at the end of 199,7, thercfore, therp are no TLD results that represent collocatcd dosimetert included in this rport. Resuls The results forenvironmenal dosimetermcasurpments are normalized to a standard quarter (91.25 days or 2190 hours). The monitoring locations ale grouped according to the distance from the planl The first gloup consists of dl monitoring points within 2 miles of the plant. The second goup is made up of all locations greater than 2 miles from the plant Past data have shown that the average results frrom the locations mote +han 2 miles from the plant are essentially the same. Therefore, for purposes of this rporq
*onsite'stations and monitoring points 2 miles or less from the plant are identified as locations greater than 2 miles ate considercd
*offsite.'
The quarterly gamma radiation levels determined from the dosimeters deployed around WBN in 2015 arc $mmarized in Table H-1. The exposuts arc measured in milliroentgens (mR). For purposes of this rport, one mR, one mrm and one mrad are assumed to be numerically equivalent The rounded average aonual exposurles, as measured in 2015, arp shown below. For comparison purposcs, the average direct radiation measurements made in the preoperational phase of the monitoring program are also shoual Annual WBN Average Direct Radiation Levels mR/Year Preoperational 2015 Average Onsite Stations 61 65 Offsite Sations 55 57 The data in Table H-l indicates trat ttre average quarterly direct radiation levels at the WBN onsite stations are approximarcly 1.4 mR/quarter higher tban levels at the offsite stations. This equates to 5.5 mR/year detected at the onsite locations. This value falls below the EPA limit of 25 mrem/year total body. The difference in onsite and offsite averages is consistent wi& levels measured for the preoperation and construction phases of TVA nuclear powcr plant sites ufiere the average lwels onsite were slightly higherthan levels offsite. Figure H-l compares plots of the data from the onsite stations with those ftrom the offsite stations over the period from 1977 thrcugh 2015. The new Landauer Inlight Opucally Stimulatd Luminescence (OSL) dosimeters rvere deployed since 2fi)7 replacing the Panasonic LJD-814 dosimeters ued during the previous years. The data in Table H-2 contains the results of the individual monitoring sanions. The results reported in 2015 arc coruistent with direct radiation levels identified at locations ufiich arp not influenccd by the operation of WBN. There is no indication that WBN activities increased the background radiation levels normally observed in the areas sunounding the plant. ATMO SPHERIC MONITOR]NG The atnospheric monitoring network is divided iuto thrce grcups ideitified as local, perimeter, and remote. Four local air monitoring sations are located on or adjacent to the plant site in the general directions of greatest wind frequcncy. Four perimeter air monitoring stations are located betureen 6 to I I miles from the plant and two air monitors are located out to 15 miles and uscd as contol or baseline statiotrs. The monitoring program and the locations of monitoring stations are identified in the tables and figures of Appcndix A Resuls from the analysis og samFles in the atmospheric pathway are presated in Tables H-3, H.4, and H-5. Radioaotivity levels identified in this reporting period are consistent with background and preoperational program data. There is no indication of an increase in afrospheric radioactivity as a result of WBN operations. Sample Collection and Analysis Air particulates arc collectcd by continuously sampling air at a flow rate of approximately 2 cubic feet per minute (cfu) through a 2-inch glass fiber filter. The sampling systm consisb of a pump, a rnagnehelio gaugc for measrning the drop in pressure across the system, and a dry gas metr to measure the total volume of air sampled" This system is housed in a building approximately 2 feetby 3 feet by 4 feet. The filter is contained in a sarrpling hpad mounted on the outside of the monitoring building. The filter is replaced weekly. Each filter is analfed for gross beta astivity about 3 days afrer collection to allow time for the radon daughters to decay. Every 4 weeks compositcs ofthe filters from each location arc analped by gamma specfioscopy. Craseous radioiodine is samFled using a commercially available carfiidge containing Triethylenediaminc (TEDA)-impregnated chucoal. This system is designed to collect iodine in both the elemenal form and as organic compounds. The cartridge is located in the same sampling head as the air particulate filter and is doumstreanr of the particularc filtcr. The cartidge is changed at the same time as the particulate filter and samples the same volume of air. Each cartidge is analyzed for I-l3l by gamma spectoscopy analysis.
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Afiospheric moisture sampling is conducted by pulling air at a constant flow ratc through a column loadd with approximarcly 400 grams of silica gel. Evcry two weeks, thc column is exohanged ou the sampler. The atnospheric moisttue is rcmoved from silica gel by heating and anal)rzed fortitium. Results The results from the analysis of air particulate samples are summarized in Table H-3. Gross beta activity in 2015 was consistcnt with levels reported in previous years. The average gross beta activity measurd for air particulaG samples was 0.019 pCi/.3. The annual averages of the goss bea activity in air particulate filtrs at these stations for the period 1977-2015 ue presented in Figrre H-2. Increased levels due to fallout from atnospheric nuclear weapons testing arc evident in the years prior to l98l and a small increase ftom the Chemobyl accident can be seen in 1986. Thcse patterns are consistent with data from monitoring programs conducted by TVA at other nuclear power plant conshrction sircs. Comparison with the same data for the preoperational period of 1990-1995 indicates that &e annual average gross beta activity for air particulates as measured in the 2015 monitoring program was consistent with the preoperational data Only natural radioactive materials were identifid by the monthly gamma spectral analysis of the air particulate samples. As shoum in Table H-4, I-l3l was not detected in any charcoal cartridge samples collected in 2015. The results for atuospheric moisture sampliug are reported in Table H-5. Tritium was measuted, above the nominal LLD vatue of 3.0 pCi/m3, in atmospheric moisturc samples from the indicator and control locations. The highest concentration from the indicator locations rvas 26.4 pCi/m3. The highest conceirtration from the contrrol locations was 5.5 pCi/m3.
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TERRESTRI,AL MONITORING Tenstrial monitoring is accomplishcd by collecting smples of envircnmental mediathat may transport radioactive matsrial fiom the atmosphcre to humans. For examplg radioactive matedal may be dcposited on a vegetable garden and be ingestd along with the vegetables or it may be dposited on pastre grass whu,e dairy cattle are grazing. Whn the cow ingests the radioactive matdal, some of it may be tansfemd to the milk ad consnrmed by humans rryfu drink the milk Therefore, samples of-ilk, soil, ud food crops are collected aDd analyzed to determine poteNrtial impacts ftm exposure through this pathway. The results fiom tbe aoalysis of these samples uc shorrn in Tablcs H-6 thrct4h H-ll. A land use suney is conducted annually behveen April and October to identi& tb location of the neuest milk enimal, the neuest residence, and the nearcst garden of greater tha" 5fi) squrc feet producing fiesh bary vegetables in each of 16 meteorological sstors within a distance of 5 miles from the plant This land use suney satisfies th requirements 10 CFR 50, Appendix I, Sec{ion ry.B.3. From data produced by the land use survey, radiation doses ar projected for individruls living near the plant Doses frrom air submersion are calculaEd for th nearestresidence in each scctor, while doses fron &inlingmilkoreating foodspiroducednear theplant are calculdedfortheareaswithmilk-producing mimals and gpdn$ rcspcctively. These dose projections ue hpothetical exhcmes and do mt represent actul doses to th general public. The resuls of the 2015 land use $rrvey are presented in Appendix G. Sample Collection and Analysis Milk samples ae collected ev,rytnlo rryeeks fiom two indioatordairies ad fiom atleastone contnol dairy. Milk suples are placed on ice for tansport to tre radioualytical labordory. A radiochemical sepantion analysis for I-l3l md a gamma speo:tral analysis ae performed oa each qpmple md Sr-89,90 analysis is performed quutdy. The monitoring prognm includcs a provision for sampling of vegaation fiom locations where milk is being prodrcd and u&en milk sampling camot be conducted" There werc tro pcdods duing this year ufien vegetation smpling was necessary. Soil samples are collected annually from the air monitoring locations. The samples are collected with either a "cookie cuttetor an auger tlpe sampler. After drying and grinding; the sample is anal),zed by eamma spectroscopy and for Sr-89 and Sr-90. Samples representative of food crops raiscd in the arca near the plant are obtained from individual gardens. Types of foods may vary from year to year as a result of changes in the local vegetable gardens. Samples of com, green beans, tomafioes, and tumip grens were collected from local vegetablq gardens and/or fams. Samples of the same food products grown in areas that would not be affected by the plant werc obtained from areaproduce markets as contr:ol samples. The edible ponion 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 I-131 values werc below the established nominal LLD of 0.4 pCi/tircr. The gamma isotopic analysis detected only natrally occurring radionuclides. The results for the quarterly Sr-89 and Sr-fl) analyses were below the established LLD's for these analyses. Consistent with most of the envirormenl Cs-137 was detected in the majority of the soil samples collected in 2015. The maximum concentation of Cs-I37 nnas 0.56 pC;ilg. The concentations were consistent with levels previously reported from falloul All other radionuclides reported werp naturally occuning isotopes. The resulB of the analysis of soil samples are summarized in Table H-7. A plot of the annual average Cs-137 concentrations in soil is presentcd in Figure H-3. Concentrations of Cs-137 in soil are steadily decreasing as a result of the cessation of weapons testing inthc atnosphcre, the 30 year half-life of Cs-l37,aldEa$port through the envirorunent. The radionuclidcs measured in food samples werc naturally occuring. Thc resulg arc reported in Tables H-8 through H-l l.
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LIOUID PATHWAY MONITORING Porcndd exposurcs from the liquid pathrvay can (rccur from drinking watr, ingestion of fish, or from direct radiation exposur from radioactive rnarcrials deposited in the shoreline sodiment The aquatic monitoring program includes the collection of samples of river Gurface) water, ground watr, &inking water supplies, fish, and shoreline sediment. Indicator samples were collected downsheam of the plant and control samples collected within the reservoir upstream of the plant or in the next upstream rcservoir (Watts Bar Lalce). Sample Collection and Analysis Samples of surface water are collected ftom the Tcnnessee River using automatic sampling systemsfromtwodorrynstramstationsandoneupsfieamstation. Atimerturnsonthesystemat least once every two hours. The line is flushed and a sample is collected into a composirc container. A one-gallon sample is rcmoved from the container at 4-week interrrals and the remaining watcr is Oscaraea. Each sample is aoalyzed for gamma-emiuing radionculideq goss beta activity, and Eiti,'m. Samples are also collected by an automatic sarpling system at the first two doumstream drinking water intakes. These samples are collected in fte same manner as the surface water samples. These monthly samples are analyzed for g:amma+mitting radionuclides, gross betaactivity, and uitium. The samples collected by the automatic sampling derrice are taken directly from the river at the intalce structur. Since these samples are untneatod rmter collectcd at plant intake, the ups$eam surface water sa-ple is used as a conEol sample for drinking water. Crround water is sampled firom one onsirc well down gradient from the plan! one onsite well up gradient from the planq and four additional onsite glound watermonitoring wells located along underground discharge lines. The onsite wells are samplcd with a continuous sampling systern. A composite sample is collected from the onsite wells every four weeks and malpcd for garma-mitting radionuclides, grosn beta activity, and titium content Samples of commerpial and game fish species are collected semiannually from each oftwo rcscrvoirs: the rcservoir on which the plant is located (Chickamauga Resenoir) and the
-lt-
upstream rcseryoir (Watts Bar Reservoir). The samples are collectcd using a combination of netting techniques and elecbofishing. The ODCM specifies analysis of the edible portion of the fish To comply with this requirement filleted portions are talcen fiom several fish of each species. 1Xs samFles are analyzed by gam-a spectroscopy. Samples of shoreline sediment are collected from recreation arcas in the vicinity of thc plant The samples are drid, groun4 and analyzed by gamma spechoscopy. Samples of sediment are also collected from the onsite ponds. A total of five samples were collected in 2015. The samples arc drieq grorm( aod analfzd by gamma spechoscopy. Results Gross beta activity was detectable above the nominal LLD in most ofthe surface water semFlos. The gross beta concentrations averaged 2.5 pCi/liter in doumsheam (indicator) samples and2.4 pCi1I- in upsbeam (conrol) samples. These levels wrre consistent with results found during the prcopcrational monitoringprogram. The gammaisotopic analysis of surface watersmples identified only natunlly occuning radionuclides. Low levels of titium were detected in most surface water samples. The highest tritium concenfiation was 1,670 pCi/liter which is signfficantly below the EPA drinlcing water limit of 20,00 pCi/Iiter. A sumrnary trble of the rcsults for surface water samples is shown in Table H-12. The aonual average gross beta activity in surface water samples for the penod 1977 through 2015 are presentod in Figurc H4. No fission or activation products were identified by the gamma analysis of drinking water samples from either oftwo downstream monitoring locations. Average gross beta activity at dorvnstneam (indicator) stations was2.2 pCi/Iiter and the average for the upstram (contol) station was 2.4 pCiniter. Low levels of tritium were detected in most samples collecrcd from the two downstream public watr sampling locations. The highest titium concenfiation was 1,070 pCi/liter. The titiunr levels werc significantly below the EPA drinking water limit of 2O000 pCiAiter. The results arp shown in Table H-13. TrEnd plots of the gross beta activrty in drinking water samples fioml977 through 2015 are presented in Figurc H-5. The g;amma isotopic aoalysis of ground water samples identified only naturally occuning radionuclides. Grcss beta concentrations in samples from the onsite indicator locations averaged 2.9 pCi/Iiter. The average gross beta activity for samples from the confiol locations was 2.8 pCi/titer. Tritium was detectcd in samples from the onsite monitoriag wells located near plant discharge lines. The titium in onsitc glound 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 acrcss the site toward the river. The highest titium conceutration in samples from these monitoring locations was 1,440 pCi/Iiter. There was no titium detected in the onsite up gradientwell orthe offsirc ground water monitoring location. The resule are presented in Table H-14. Cs-137 was identified in one fish sample. The Cs-I37 concentration was 0.03 pCi/g measured in game fish collected at the upsheam location. Other radioisotopes found in fish were naturally occurring, with the most notable being K-{0. The resulg are sumrnarized in Tables H-15 and H-
- 16. Trend plots of the annual aver?ge Cs-137 concentradons measured in fish samples are presented in Figure H{. The Cs-137 activities arp consistent with preoperational results produced by fallout or eflluents from other nuclear facilities.
No fission or activation products were detecte4 above the nominal LLD, by the g;amma analyses performed on shorcline sediment samples. The results for the analysis of shoreline sediment are presented in Table H-17. Trend plots ofthe average concentration of Cs-137 in shorline sediment are presented in Figurc H-7. Consistent with prcvious monitoring conducEd for the onsite pon&, Cs-137 was detected in the sediment samples. The average of the Cs-137 levels measurd in sediment from the onsitc ponds was 0.10 pCi/p. In addition" Co-60 uas also detected in some of the samples collected from the onsite ponds. The average of the Co-60 levels measured in sediment from the onsite ponds was 0.08 p0Ugq. The results for the anatysis of pond sediment samples are provided in Table H-l8. Since these radionuclides wene prBcnt in relatively low concntrations and confind to the ponds located in the owner controlled area not opcn to the general public, the pesence of these radionuclides would not reprcsent an increased risk of exposnrc to the gcneral public. ASSES SMENT A}.ID EVALUATION Potcndal doses to the public are cstimated fiom measurd efluents using oomputer models. These models were developed by TVA and are based on guidance provided by the NRC in Regulatory Guide l.l(D for determining the potential dose to individuals and populations living in the vicinity of the plant. The results of the efluent dose calculations are reported in the Anrusl Radiological Effluent Release ReporL The doses calculatod are a representation of the dose to a"Eardmum exposed individual." Some ofthe factors usd inthese calculations (such as ingestion rates) alE modm"m expected values which will tend to overestimarc the dose to the "hlryothetical'person The calculated maximum dose due to plant cfluents arc small fractions of the applicable regulatory limits. In reality, the expected dose to actual individtuls is significantly lower. Based on the very low concentations of radionuclides actually prcsent in the plant efluents, radioactivity levels measured in the environment as rcsult of plant operations, are expected to be negligible. The results forthe ndiological environmental monitoring conducted for WBN 2015 operations confitm this expectation Results As statd earlier in this rcpoft, the estimated increase in radiation dose equivalent to the general public resulting from the operation of WBN is insignificant when compared to the dose fiom natural background radiation. The results from each environmental sample are compared with the concentrations from the conesponding contnol stations and appropriate preoperational and background data to determine influences from the plant. During this report perio4 Cs-137 was debcrcd in soil and fish collected for the WBN progam. The Cs-137 concentations wete consistent with levels measurod during the preoperational monitoring program. The levels of titium measured in watcrsamplcs from ChickamaugaReservoirrepresented concentations that were a small fraction of the EPA drinking water limit. The levels of tritium detected in the onsirc ground wffer monitoring wells and the radionuclides measured in samples of sediment from the onsirc ponds do not represent an incrEased risk of ab
exposure to the public. These radionuclidcs were limited to the owner contolled area and would not prsnt an exposure pathrvay for the general public. Conchsions It is concluded from the above analysis of cnvironmenal samples and from the hend plots presented in Appendix H, that exposur to membcrs of the general public which may have been attibutable to WBN is negligible. The radioactivity reported herein is prirnarily the result of fallout or natural background. Any activity which may be prsent in the environmcnt as a result of plant operations does not rcprcsent a significant contribution to the oeosure of me,mbers of the public. REFERENCES
- l. Memil Eisenbu4 Environmental Radioactivitv. Academic Press, Inc., New Yorlq NY, 1987.
- 2. National Council on Radiation Protection and MeasuremenB, Report No. 160, "Ionizing Radiation Expoune of the Population of the Unitd Stafs,'March 2009.
- 3. Unitd States Nuclear Regulabry Commission, Regulatory Guide 8.29, "Insfiuction Concerning Risls from Occupational Radiation Exposute,' February 1996.
Table I COMPARISON OF PROGRAM I.oWER LIMITS OF DBTECTION WITII THE REGULATORY LIMITS FOR M.NXIMUM ANNUAL AVERAGE EFFLUENT CONCENTRATIONS RELEASED TO I,'NRESTRICTED AREAS AI{D REFORTING LEVELS ConcenEations in W-ater. pCi/Liter Coneenfrations in Air. pCi/Cubic Meter Effluent Reporting lower limit Efrluent Reponing [ower limit Analvsis Concenhationr Levell of Dercction3 Concenuationl Levell of Detection3
-l-H-3 1,000,000 20,000 270 100,000 -- 3.00 Cr-S1 500,000 .- 45 30,000 -- 0.02 Mn-s4 30,000 1,000 5 1,000 -- 0.005 Co-58 20,000 1,000 5 1,000 -- 0.005 Co-60 3,000 300 5 50 -- 0.005 Zn-65 5,000 l0 400 -- 0.005 Sr-89 8,000 :-oo 5 1,000 - 0.001I Sr-90 s00 2 6 x 0.0004 Nb-95 30,000 iro 5 2,000 .. 0.005 7r-95 20,000 400 l0 400 -. 0.005 Ru-103 30,000 5 900 -- 0.005 Ru-106 3,000 .O 40 20 -- 0.02 l-13 I 1,000 2 0.4 200 0.9 0.03 Cs-134 900 30 5 200 l0 0.005 Cs-131 1,000 50 5 200 20 0.005 Ce-l44 3,000 -- 30 40 -- 0.01 Ba-140 8,000 200 25 2,000 -- 0.015 L.a-140 9,000 200 l0 2,000 -- 0.01 Note: I pCi = 3.7 xl0a Bq.
Note: For drose reporting levels that are blank, Do value is given in the referpnce.
- l. Source: Table 2 of Appendix B to 10 CFR 20.1001?:02401
- 2. Source: WBN Offsite Dose Calculation Manual, Table 2.3A.
- 3. Source: Table E-l of this rEport.
a4-
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trUCLEAR PI-A,IIT SEOUOVAH mrCLEeR PLATIT i \( l I H- - SELLEFO]IITE ilI'CLEAN PLATIT BROUIIS FEffiY ilUCLEAR PLATlT I I I i \
Figure 2 Enl\,IHONn,IENTAL E)(FCIEUHE FAT}Iri,AYA ClF OUE TO FELEABEE OF IIAEISA!:TT\,E ilIATEEIAL ?O T}IE ATtrICIEFHEEE AnlEI LAI(E. Airborno BeleasGs
\f Plume ErDosure Liquid Beleases Diluted By Lahs MAN Gonsumed By ffian AEimals Itillt,teatl Shoreline ExDosulG cooQrru BU Animals Ilrinkins Water Fish Uegetation Uptake From Soil APPENDIXA RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM A}.ID SAIUPLING LOCATIONS a7-
Table A-l WATTS BAR NUCLEAR PLAI{T RADIOLOGI CAL EN VIRON MENTAL MON ITORING PROGRAM. E:rposure Pathway Number of Samples and Sampling and Tlpc and Frcquency and/or Sanrple Locationso Co[ection Freguency of Analysis I. AIRBORNE a Particulates 4 samples from locations (in diftrent Continuou sampler opcration wiflt Analyze for gross beta radioactivity sctors) at or ner llrs sitc boundary samplc collection weekly (more gratsr than or equal to 24 hours (LM-1,2,3, and 4). (tequently ifrequired by dust following filter change. Perform loadi.g). gamma isotopic analysis on each sample if gross bea is greater than l0 times yearly mean of control sample. Composite at least once per 3l days OV location) for gamma scan. 4 eaqples fiom communitics approximatcly 6-10 milcs fiom the plant (PM-2, 3,4, and 5). 2 samples fiom conCIol locations geater ftan l0 miles from the plant (Rtvt-2 and 3).
- b. Radioiodine Samples fiom sarne locations r air Continuors sampler operafion with I- l 3 I at lcast onco pcr 7 days.
particulates. filter collection weekly. Analysis is performed by ganuna specEoscopy.
- c. Abospheric 4 samples from locations (in different Continuous sampleroperation with Analya each sample fortritium.
Moisnnc scctors) at or rcarthe sie bormdary sample colkction biweekly. (LM-I,2,3, andl) 2 sarylcs fiom commrmitics approximately tl-10 miles distance tromtheplant(PM-a 5). a8-
Table A-l WATTS BAR NUCLEAR PLAI.IT RADIOLOGICAL ENVIRONMENTAT MONITORING PROGRAN{. Exposure Pathway Nurnber of Samples and Sampling and Type and Freguency and/or Sample Irqgationsb Collection Frequency of Analysis
- c. Affiospheric 2 samples from control location Moisture (Cont.) greater tlran l0 miles from the plant (RIVI-2 and RM-3).
- d. Soil Samples fiom same location as air Once pcr year. Gamma scarL Sr-89, Sr-90 onoe per particulates. year.
- 2. DIRECT 2 or mons dosimeters placed at or At least once per 92 days. Gamma dose at least once W 92 near the site boundary in eash of the days.
l6 sectors. 2 or more dosirneters placed at stations located approximately 5 miles from the plant in each of the l6 sectors. 2 or morc dosimeters in at least 8 additional locations of special intercsq including at least 2 conEol stations. a9-
Table A-l WATTS BAR NUCLEAR PLA}.IT RADIOLOGICAL EN V IRON MENTAL MON ITORIN G PROGRAIvI' Exposure Pathway
- Number of SamPles and Sarnpling and TWe and Frequency and/or Sample Locationib Collection Frequency of Analysis
- 3. WATERBORNE
- r. Surface 2 samples dormstream from plant Collectcd by automatic sequential- Gross beta, gatnma 8can, and titium discharee (TRM 517.9 and fRM tpe samplef with composite samples analysis of caci sample.
523.1). collected over a period of approximately 3l days. I sample at a confiol locadon upstnesm from the plurtdischarge (TRM s293).
- b. Ground Five sampling locdions from ground Collected by automatic sequential- Grcs bcta, gatnma scu, ud tritium wator monitoring wells a{iac,ent to the tpe saryler with corrpositc samples analysis of eaci sample.
phnt (Wells No. l, & B, C, atrd F). collccled overa peri,od of y3l days. I sample ftom gound water source Same as Well No. l. Gross beta, gamma scan, and tritium up gradient (Well No. 5). analysis of each sample.
- c. Drinking I ourphatthefirsttwopotable Collecrcdbyautomaticscqucndal- Grcsbcta,gammascan,andtridum surfrce water supplies, downstseam t1rye sanrplcf with compositc sample analysis of each samplc.
fromthe plant$RM $3.t andTRM collecedmonthly. 473.0). I omple at a comol locaion TRM 529.3d. Table A-l WATTS BAR NUCLEAR PLA}.IT RADIOLOGICAL MAL MONITORING PROGRAM. Exposure Patrway Number of Samples and Sampling and Ty?e and Frequency and/or Sample LogFtionsD Collection FrcgEpncI of Anqlysie d" Scdirnent from I sarnple dornstcam fiom plam At lcast once per lt4 dap. Gamrna scan of each sarnple. Shorclinc Dischargp (IRM 513.0). I saryle from a control locatiom upsEsam from plant dischargc (TRM 5302).
- e. PondSediment I samphfiommleastdrcelocadons Atleastonceperyear. Gammascmofcadrsample.
in thcYrrd HoldingPmd.
- 5. INGESITION a Milk I sampleftommilkp,roducinganimals Every2wcckr. I-l3l mdgammaanalyeisoneach in eacb of l-3 ms indicred by thc samplc. Sr-t9 and Sr-90 oncc pcr oow ormu! werr &ces are calculmcd $urter.
to be highoce I ormmc sarnplcs fiom oontrol locadons.
- b. Fish otrc sample ofcommaclally iquont At lcast orce pet lta ds! s. Gamna scan or edible portions.
3pccks lnd onc camplc of rcctcadonatty impofint specie. One sample of each spccics fim Chidomeug and nrffB BarRescryoir:.
.3l-
Tablc A-l WATTS BAR NUCLEAR PI.A}.IT RADIOLOGICAL ENVIRONMENT,{L MONITORJNG PROGRAM E:tposurc Pathway Numbu of Saurples and Saryling and Type and Froquency and/or Sample LocationsD Collection Frequency of Analysis
- c. Vegetation' Samplesfiomfrrmsproducingmilk Atleastonccper3l days. I-l3l analysisandEammascanof (Pasturagp ard but not providing a milk saorple. each samplc.
grass)
- d. FoodPnoductr Isamplceachofprirrcipalfood Annuallyattimeofhanrest Thc Gammascanonedibleportion.
products grown atpdvate gmdeos types of foods availabh for sampling and/or frrms in thc immediate will vtry. Following is a list of vicinity of the plant. tlpical foods which may be arnailable: Cabbage, Lettuce and/or Grcens Corn Grcen Beans Potatoes Tomatoes a The sampling program outlinod in this able is that which was in eftct at thc end of 2015.
- b. Sarnple locations arc shown on Figtres A-1, A-2, A-3.
- c. ltamplesshallbecollctedbycollectinsurdlquotatintorvalsnototcocding2hours.
- d. The samples collectcrt at TRMs 503.t and 473.0 are taken fiom the r8w watGr supply, thcrtfott, the rpstream surfroe water samplc will be coosidered the contol sample for &inking rmter.
- e. Vcgetation sampling is applicable only for farms that mect fre crirria for milk sampling and when milk sarnpling canmt be pcrfcd" Tablc iA WATTS BAR NUCLEAR PLAI{T RADIOLOGICAL ENV IRONMENTAL MON ITORIN G PROGRAM SAI,TPLING LOCATTONS Map Approximate Indicator (t)
Location Distance or Samples Numbef- Station Sector (Miles) Conhol (C) Collectcdb-2 PM.2 NW 7.O AP,CF,S,Af,{ 3 PM.3 NNE 10.4 AP,CF,S 4 PM-0 NE/ENEE 7,6 AP,CF,S 5 PM.5 s E.0 AP,CF,SAII{ 6 Rll-2 sw 15.0 c AP,CRS,AII 7 RIvl-3 NNW 15.0 c AP,CRS,AfuI t LM.I ssw 0.5 AP,CF,S,A!t{ 9 LM.2 NNE 0.4 AP,CF,S,AI\,I r0 LM.3 NNE l.g AP,CF,S,AM ll LM4 SE 0.9 AP,CF,S,A[t4 t5 Farm K ENE I1.6 C M It Well #l s 0.6 I w 20 Farm N ESE 4.1 t M 23 Well #5 0.5 c w 25 TRM 517.9 g.f I sw 26 TRM 523.1 4.?n I sw 27 TRM 529.3 : l.5d c sw,Pwo 3l TRM 473.0 54.Ed I PW (C.F. Indus0ies) 32 TRM 513.0 --- l4.gd t SS 33 TRM 530,2 2.4n c ss 35 TRM 503.E 24.0n I PW (Dayton) 37 TRM 522.t-527.E T F (downstrcam of WBN) 38 TRM 471-530 I F (Chickamauga lake) 39 Watts Bar Rcservoir c F 8l Yard Pond ssgslssw Onsitc PS t2 Well A ssE 0.6 w 83 Well B ssE 0.5 w t4 Well C ESE 0.3 w t5 Well F SE 0.3 w t6 Farm HH ssw 1.75 M t7 Fann BB sw 18.6 M a Sce Figures A-1, A-2, and A-3
- b. Sarnple codes:
AItt = Atmosphcric Moisure AP = Air particulate filter PW = Public Watcr SS = Shorcline sedimcnt CF = Charcoal filtcr PS : Pond Sedimcnt SW = Surhe watcr F = Fistt S =t Soil W = Wcll watcr M = Milk G. Station located on the boundary bctrrcen these two ssstots.
- d. Distance fiom ttre plant discharge (TRI{ 527.t)
- e. The nrrfacc watcr sample is also used as r control for public water.
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Table A-3 1T'ATTS BAR NUCLEAR PLAI{T ENVIRONMENTAL DOSIMETERS LOCATIONS Map' Approximatc Onsite (On)b Location Distance or Numbsr Station Scctor (Miles) Otrsitc (Otrt 2 NW-3 NW 7.0 otr 3 NNE-3 NNB 10.4 off 4 ENB3 NETENE 7.6 otr 5 s-3 s 7.9 otr 6 sw-3 sw 15.0 off 7 NNW4 NNW 15.0 off r0 NNE.IA NNE l.g On It SE.IA SE 0.9 On t2 ssw-2 ssw 1.3 On l4 w-2 w 4.E otr 40 N-l N 1,2 On 4l N-2 N 4.7 otr 42 NNE.I NNE 1.2 On 43 NNE-2 NNE 4.1 otr u NE.I NE 0.9 On 45 NE.2 NE 2.9 off 46 NE.3 NE 6.1 otr 47 ENE.I ENE 0.7 On 48 ENE.2 ENE 5.t otr 49 E-t E 1.3 On 50 F-2 E 5.0 off 5l ESE.I ESE 1.2 On 52 ESE-2 ESE 4.4 otr 54 SE.2 SE 5.3 otr 55 ssE-lA ssE 0.6 On 56 ssE-2 ssE 5.8 otr 57 s-l S 0.1 On s8 s-2 s 4.9 off 59 ssw-l ssw 0.E On 60 ssw-3 ssw 5.0 otr O sw-l SW 0.t On 63 sw-2 sw 5.3 off
& wsw-l wsw 0.9 On 65 wsw-2 wsw 3.9 otr 66 w-l w 0.9 On CI wNw-l wNw 0.9 On 6E wNw-2 wNw 4.9 otr 69 NW-l NW l.l On 70 NW-2 NW 4,7 off 7l NNW-I NNW 1.0 On 72 NNW.2 NNW 4.5 otr 73 NNW-3 NNW 7.0 otr 74 ENE.2A ENE 3.5 otr 75 SE.2A SE 3.1 otr 76 s-2A s 2,0 off 7? w-2A w 3.2 otr 7t NW-2A NW 3.0 off
?9 SSE-I SE 0.5 On a Scc Figurcs A-1, A-2, and A3.
- b. Dosimctcrs declgnalcd'onsltc" rrc localcd 2 milcs or lcss from thc plarq,'oftitc' arp locard morc than 2 mllc fromthcplant Figure A-1 Radiological Environmental Sampling Locations Within I Mile ofthe Plant 303.75 56.25 WNW ENE 201.25 78.75 WATTS BAR w NUCLEAR PLANT E 258.75 lo I ,25 w ESE 123.75 Figrrre AA Radiological Environmental Sampling Losations From I to 5 Miles From The Plant
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Figure A-3 Radiological Environmental Sampling Locations Greater Than 5 Miles From the Plant 348.75 lt I1.25
-l-o3tot6e02E lflor
-3?-
APPE}IDD(B PROGRAMMODIFICATIONS Appndix B Radioloqical Environmental Monitoring Program Modification Bacon Farm (Farm BB) was added to the REMP program during 2015 to rrplace the loss of tlre milk sampling location identified as Fam EH. (Farm EH slosed operations duing 2014.) The farm identified as Farm K closed its operation in March, 2015. However, it was officially removcd from the REMP program at a later date. Both Farm EH and Farm K were contol milk locations. The chaoges ane reflected in the Tables and Figrrrcs of Appe,ndix A ofthis rcport APPENDD(C PROGRAN{DEMS AppendixC Prosram Deviations Problems with low moisture rsultcd in 5 missed ahospheric samples. The samples were collected but unable to be analyzed due to the low moisturp content. In addition, 3 sets of dosimeters were missing at the time of change out during 2015. Table C-l provides additional information onthe missed samples. Areviewofthe daails ofthe program deviations didnot identi$ any adversc fiend in equipmentperformance. 4l-
Table C-l Radiological Environmental Monitoring ProEmam Deriations Date Station Location Sample Tlpe Description 0?n3n0r5 3102 1.3 miles SSW Atnospheric Five samples werc unable to be 3106 Moisn[e analyzed due to low moisture contsnl 3109 The problem was identifid in CR 3205 1004980. 05/r Er20 l5 3298 15 miles SW Aunospheric One sanrple was unable to be analyzed Moisture due to low moistutp content. The problem was identified in CR 1035389. 3'd er 2ots r9 Dosimeter While performing quarterly dosimeter WB-NNW-3 change ouq it was discovered that the monitoring station 19 in the NN1V sector had bcen disturbed. The OSLs had been knocked to the ground while Volunteer Elecric was removing a pole about 2 feet alvay ftom the station. The OSLs where later mowed over by ground cnews. One dosimeter was located but suffered damage and the other could not be found. This problem was identified in CR 1095655. 3d er 2ol5 42 Dosimeter Both dosimeterc wert found missing WB.ESEA during the quartef change out and could not be located after extensive search. It appearc the fence that horced ttre dosimeterc had been upgfaded and the dosimeters may have been lost at this time. The issue was documented in cR 1095663. 46 Qtr 2Ot5 38 Dosimeter Two dosimeterc located at station 38 WB.NNEA WB-NNEA were missing. A search of the area did not result in locating the dosimeterts. The cage and protective sleeve that hold the dosimetem wene found approximately 15 feet away from the station. fire station was rrupaired and the new dosimeters werc attached. This issue was identified in CRI 129753. 42-
APPEI{DD(D AI{ALYTICAL PROCEDTJRES 43-
Appendix D Analytical Prosedurcs Analyscs of environmental samples are perfonned by th radioanalytical laboratory located at the Western Area Radiological Laboratory facility in Muscle Shoals, Alabarna, except for the Sr-89, 90 analysis of soil samples which was performed by a contract laboratory. Analysis procedures are bosed on accepted methods. A summary of the analysis techniques and methodology follows. The gross betameasurements are made with an automatic low background counting system. Normal counting times are 50 minutes. Water samples are prepared by evapor*ing 500 mi[iliter (ml) of samples to near drymess, tansfening to a stainless steel planchcg and completing thc evaporation prtrcesll. Air particulatc filters arc cotmted directly in a shallow planchet. The specific analysis of l-l3l in milk is performed by first isolating and puriffing the iodine by radiochemical separation and then counting the final precipitate on a beta-gamma coincidence cormting system. Ihe normal count time is 50 minutes. With the beta-garuna coincidence counting system, backgrormd counts are virtually eliminated and exbemely low levels of activity canbe detected. After a radiochemical separation" milk samples analyzed for Sr-E9, 90 are counted on a low background beta counting system. The sample is counted a second time after a minimum ingowth period of six days. From the two couts, the Sr-89 and Sr-90 concentations can be determined. Water samples are analyzed for titium content by fust distilling a portion of the sample and then counting by liquid scintillation. A commercially available scintillation coclctail is used. Gamma analyscs arc performed in various counting geometries depending on the sample tlpe and volume. All gamma counts arc obtained with germmitrm t1rye detectors inrcrfaced with a high resolution gamma spectnoscopy system. 44-
The charcoal cartridges trsed to sample gaseous radioiodine arc analped by ganrma spectroscopy using a high resolution gamma spechoscopy system with germanium detectors. Atuospheric moisture samples are collectcd 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 cochail. The necessary efficiency values, weight-cfficiency curyes, and geomctrytables are establishedand maintaind on each detector and counting system. A series of daily and periodic qualrty con&ol checlcs are performed to monitor counting instnrmentation. System logbooks and contnol cbarts are used to document the results of the qualrty control checks. 45-
APPEhUDD(E NOMNAL LOWER LIMITS OF DETECTION 46-
Appendix E Nominal l,ower Limits of Detpction A nrmber of factors influence the Lower Limit of Dercction (LLD), including sample size, count time, counting efficienoy, chemical pnooesses, radioactive decay factors, and intcrfering isotopes encountered in the sample. The most probable values for these facton have been evaluated for the various analyses performed in the environmental monitoring program. The nominal LLDs are calculated in accordance with the methodologr prescribed in the ODCM, are presented in Tablc E-1. Thc maximum LLD values forthe lower limits of detection specified in the ODCM arp 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 deterrrining if a measured activity is grearcr than the LLD. In these cases, the LLD value will appear as -1.00E+00 in the data tables in AppendixH. 47-
TABLE E.I Nominal LLD Values A. Radiochemical Procedures Sediment Air Filters Water Milk Wet Vegeution and Soil fuialvsis (pCi/m3) (pCi/L) (pci/L) @Ci/lcg wet) (pCi/g dry) Gross Bea
-a-0.002 l.g -- --
Tritium 3.0 270 -- -- Iodine-l3l 0.4 0.4 6; Snontium-t9 0.001 I 5.0 3.5 31.0 ; Shontium-90 0.0004 2.0 2,0 12.0 0.4 Table E-l Norninal LLD Values B. Gamma fuialyses Foods Particulate Charcoal Water Vegetation Wet Soil and Tomatoes Filter Filter and Milk and Grain Vegetation Sediment Fish Clam Flesh Potatoes, etc. Analysis -pCi/m3- pCi/m3 pCilL pCilg dry pCifts. wct pCilg dry pCi/s dry gQ!b-@ pCitkg wet Ce-14l .005 0.02 l0 .07 35 .35 20 Ce-l44 .01 0.07 30 .15 ils .85 60 Cr-51 .o2 0.15 45 .30 240 2.40 9s l-13 t .005 0.03 l0 .20 60 1.70 20 Ru-103 .005 0.02 5 .03 25 .25 2s Ru-l06 .02 o.l2 40 .t5 190 1.25 90 Cs-I34 .005 0.02 5 .03 30 ,14 l0 Cs-137 .005 0.02 5 .03 25 .15 l0 Zr-95 .005 0.03 l0 .05 45 .45 45 Nb-95 .005 0.02 5 .25 30 .25 l0 Co-5E .005 0.02 5 .03 20 .25 l0 Mn-54 .005 0.02 5 .03 20 .20 l0 Zrrti .005 0.03 l0 .05 45 .40 45 Co-60 .005 0.02 5 .03 20 .20 l0 K40 .04 0.30 r00 .40 400 3.50 250 Ba-140 .015 0.07 25 .30 130 2.40 50 [.a-140 .01 0.04 l0 .20 50 1.40 25 Fe-59 .005 0.04 l0 .08 40 .45 25 Be-? .02 0.15 45 .25 2AO t.90 90 Pb.2I2 .005 0.03 l5 .04 40 .30 40 Pbzl4 .005 0.07 20 .50 80 .10 t0 BiAr4 .005 0.05 20 .10 5s .50 40 Bian .02 0.20 50 .25 250 2.00 130 TlaOE .002 0.02 .o: ,j ,: ,j Rtu'2j]4 l: R*226 -- -- - Ac-?i28 .01 0.07 20 .10 70 .10 .75 50 Pa-234m - 800 49-
Table E-2 Morirnum LLD Values Specified by the WBNOTrcM Airborne Particulate Food Water or Gases Fish Milk Pnoducts Sediment Anal)'sis oCiIL a-pCi/ml oCifte. wet
--I-oCiIL a-nCi/ks. wet a---
uCifte. drv a---- gross beta 4 lxl0{ N.A. NA. N.A. N.A, H-3 2000 N.A. . N.A. N.A. N.A. N.A. Mn-s4 l5 N.A. 130 N.A. N.A. N.A. Fe-59 30 N.A. 260 N.A. N.A. N.A. Co-S8,60 l5 N.A. 130 N.A. N.A. N.A. Zn-65 30 N.A. 260 N.A. N.A. N.A. Zv95 30 N.A. N.A. N.A. N.A. N.A. Nb-95 l5 N.A. N.A. N.A. N.A. N.A. I-l3l lb 7x l0{ N.A. I 60 N.A. Cs-134 l5 5 xl0{ 130 l5 60 150 Cs-137 l8 6 x l0'2 150 lt 80 180 Ba-140 60 N.A. N.A. 60 N.A. N.A. I"a-140 l5 N.A. N.A. l5 N.A. N.A.
- a. If no drinking water pathway exists, a value of 3000 pCi/liter may be used.
- b. lf no drinking water pathway exists, a value of 15 pCi/liter may be used.
APPEI{DD(F QUALrry ASSURAT{CBQUAIITY CONTROL PROGRAT{
-5 l-
AppendixF Ouality Assurmce/Otulity Conhol Procrarl A qulity assuraoce program is employed by the laboratory to ensure that the environmental monitoring data are reliable. This program includes the use of writteq approved procedtres in performing the worlg provisions for stafftaining and certification, intmal self assessments of prcgram performancc, audits by various elcemal organizations, aod a laboratory quality conEol prcgram. The quality contol progam employed by the radioanalytical laboratory is designed to ensulc that the smpling and malysis prcoess is working as intended. The prograrn includes equipment checks and the ualysis of quality conhol samples along with routine samples. Insffim,ent quallty control checks include backgrotrnd count rate and courts 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 devicc and the method it uses to detect radiation or storp the information obtained. Quallty couhol samples of avariety oftypcs are used by the laboratory to vcrify the performance of differcntportions of the analytical prooess. These $ulity contnol samples include blanl<s, replicate samples, analytical knorms, blind samples, and crcss-checks. Blanks are samples which contain no measurable radloactivity or no activity of the tJpe being measured. Such samples ue analyzed to daermine 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 measurpd. Duplicate samples are generated at nndom by the sample computer program which schedules the collection of the routine samples. For examplg ifthe routine program cdls for four milk samples every weeh on a random basis each farm might provide an additional sample several times a year. These duplicate samples are andyzed along with other routine samples. They provide information about the variability of radioactive content in the various sample media If enough sample is available for a particulu anelysis, the laboratory staffcan split it into trro portions. Such a sample pnovides information about the variability of the analytical prrcess since two identical portions of material are analped side by side. Analytical knowns arc another category of quality contol sample. A known amount of radioactivity is added 1e 4 semlrl medium. The lab staffknows the radioactive oontent of the sample. Wheneverpossible, the analytical knowns containthe same amormtofradioactivity eachtimetheyarenrn. Inthiswananalyucalknoumsprcvideimmediatedataonthequlityof the measuremeNrt prooess. Blind spikes are samples containing radioactivity which are introduced into the analysis prccess disguised as ordinary environmental samples. The lab *affdoes not know the sample contains radioactivity. Since the bulk of the ordinary workload ofthe environmental laboratory contains no measurable activity or only naturally occuning radioisotopes, blind spikes can be used to test the deiection capability ofthe taboratory or can be used to test the data review prosess. If an analysis rcutinely generates nume(rus zeros for a particular isotopc, the presence of the isotope is brought to the attention of the laboratory supervisor in the daily review process. Blind spikes test this prooess since the blind spikes contain radioactivity at levels high enough to be ddected. Furthermore, the activity can be put into such samples at the exfrmc limit of detection (near the LLD) to veri$ that the labor*ory can detect very low levels ofactivity. Another category of quality contol samples is the intcrnd cross.checks. These samples have a known amormt of radioactivity added and are presenrcd to the lab stafflabeled as cross-check samples. This means thatthe quality control saffknows the radioactive content or "right answetbut 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 accuraoy of the Eeasurement ptwess. Furttrer information is available about the variability of thc p(rccss if multiple analyses ate rcquested 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 interaal cross-check samples met program performance goals for 2015. To provide for an independent verification ofthe laboratory's ability to make accurate measurments, the labratory participated in an environmental level cross-check program available through Eckert and Ziegler Analytics during 2015. The results of TVA's participation in this cross-check program are prcsented in Table F-I. The resule for these cncss-check samples were all wittrin the program agemeril limits with the exception of the Sr-90 in Milk result for ttre first quarGr cross-checks. The disagreement was documented in CR 110689. All otherSr-fr) results werc iu agreement. The quality contol data are routinely collecte4 examined urd reported to laboratory supervisory personnel. They are checked for trends, proble,m aneas, or other indications that a portion of the anal)tlcal prooess needs correction or imprcvement. The end result is a measurement ploccxts that provides reliable and verifiable data and is sensitive enough to measurc the prcsence of radioactivity far below the levels uftich could be harmful to humans. Table Fl Results For 2015 Extemal Cross Checks ncnrlE Tcil nrhd Snnole TfnrultA&ilyrif f,uu rvA FfoltQ!!ills wrm(DCi/L) (hosr Bar 2.t08+fi1 2.t38+02 ffoil Qurtcr wlg(Dci[) h t.268+O{ t.368+Of Ycs fillQ!ilcr urGc,cl/!,) ott 9.678+0r 9.t38+0t Yer ttch 3.668+(n 3.768+(12 Ycr
-cr t.268+02 1.23E{O2 Ycr
-cs 1.678+04 1.608+fi1 Yer sco 1.808+(tr l.uE+04 Ycs xMn t.598{fil 1.56+O2 Ycs tc t.gltB((a t.E}E+$Z Ycr
*?s 2.1il,8,+& 3.0!)E+m Ycs
'co 3.2t8+ln 3.2t8{fi1 Ycr t.lcc l39E+@ 1.498{.m Ycr fbr Qurilcr SrilbE ic Udne (pCI&)
tr t.438+01 1.468+04 Ycr FiltlQttulcr Milr (firL) Erl 9.908+01 9.088+01 Ycr
'st 9.6t8{Ot t 6lE{Ol Ycr rsr t.328{Ol t.908{O0 No firnQurE Ah FilE (pCi,Fittc!)
ftoct BGtt 1.008+(tr 9.468{0l Ycr IttudAnltcr Wdc, (ICirL) tH 1.328+0{ 1"368+Of Ycr Ttitd(bdcr Sed (pCitgrm) rlce 3.3tEOl 3.loEJ)l Ycr tlo s.54E{ll 8.20801 Yer t'cs 3.36EOl 2.tzF,lll Ycr l'cr {.otB{ll 3.7tE0l Ycr
$co 4.t8EO! f.olE{t Ycr
'h'to tf.6lE0f a.?0E,0l Yer sFc 3.588{t 3.39EOt Ycg 6?s 5.618{11 5.75EOl Ycr oco 5.13E{l Yer
'.?d,E,.l Thild Qrrlg AbfilcrCtGrfinct)
Gmcr Bctr 9.218+Ol 7.708+01 Ycr Third aurilct Ah rillct(DCirftut) rrg, t 3aE{ot &368+0l Ycr
'lcr eltE{tr aolE{oe Ycc lxcl t.298+Ol 6.608+0l Ycr tt'cs g.gEErOl 9JrE{Ol Ycr sco 1.99f,+fi1 9.968{0l Ycr
*Mn l.l{E{O2 l.t9E{t@ Yct tre t.ttfB{Ol 9.qrE+01 Ycr 6?a l.3tE+Gl, 1.508+@ Ycr
'co t.298+(tr t.328{Ol Ycr Itidqffi $yanhcdc usim (pcrL) h t:gE{o{ t.4oE+ot Ycr Fout&atnttcr MiL (Dc-i/L) lilI t.978{Ol 9.3tE{Ot Ycr
?sr 9.0E')01 t.2tE+ot Ycr lsr t-578+01 l.ZrE+o1 Ycr APPENDD(G LAI{DUSESTJRVEY AppendixG Land Use Survev A land use suney was conduotcd in accordance with the provisions of ODCM Conuol l.3.2to identi& the location of the nearest milk aoinal, the nearest residence, and the nearpst garden of greater than 500 squarc fect producing fresh leafr vegetables in each of l6 meteorological sectors withitr a distaoce of 5 miles (8 km) from the plant The land use suryey ums condusted between April 1, 2015, and October l, 2015, using appropriarc techniques such as door-to-door suryey, mail stuvey, telephone survey, aerial survey, or infomation from local agricultural authorities or other reliable !ilrtrces.
Using the survey data, relative radiation doses were projected for individuals nearthe plant. Doses from air submersion werc calculated for the nearest resident in each sector. Doses fiom milk ingestion or vegetable ingestion were calculated for the areas with milk producing animals and gardens, respectively. These doses were calculated using historical meteorological data They also a$ilrme that the effiucnt rcleases are equivalent to the design basis source terms. The calculated doses are relative in nafirc and do not reflect aotual exposures rcceived by individuals living near IVBN. Thc location of nearcst resident changed in one sector dtring 2015. In addition, the location of the nearest garden changed in a total of five sectors. The suruey of milk producing locations performed in 2015 did not identify any new locations. Tables G-I, G-2, and G-3 comparc results of the relative pnojectcd annual dose calculations for 2014 and 2015. Table G-l Watts Bar Nuclear Plant Relative Prcjected Annual Air Submersion Dose to the Ncarest Residence Within E h (5 Miles) of Planf mrem/year 2014 2015 Approximate Approximate Sector Distance (Meters) A$nual Dose Distance (Meten) Annual Dose N 4,474 0.07 4474 0.07 NNE 3,750 0.21 3,750 0.21 NE 3,399 0.27 3,399 0.27 ENE 3,072 0,29 3,072 0.29 E 4,3E8 0.15 4,3tt 0.15 ESE 4,654 0. [4 4,654 0.14 SE 1,409 0.72 1,409 0.72 SSE 1,il6 0.34 l,@6 0.34 s 1,550 0.40 1,550 0.40 ssw 1,832 0.31 1,832 0.31 sw 4,141 0.09 3,784 0.10 wsw 2,422 0.lg 2,422 0.19 w 2,901 0.05 2,901 0.05 wNw 1,44E 0.19 1,44E 0.19 NW 2,065 0.09 2,065 0.09 NNW 4,376 0.02 4,376 0.02
- a. Assunes the effluent releases art equivalent to design basis source terms.
Table GA Watts Bar Nuclear Plant Relative hojes'ted Annual Ingestion Dose to Child's Bone Oqgan ftom lngestion of HomeGrown Foods Nearest Garden Within 8 km (5 Miles) of Planf mrem/year 20t4 2015 Approximate Approximatc Sector Distance (Meters) Annual Dose Disbnce (Meters) Annual llose N 7,188 0.55 629s 4.74 NNE 5,030 2.?g 5,030 2.19 NE 3,793 4.90 3,793 4.90 ENE 3,072 620 5,281 2.27 E 45s6 3.09 4,656 3.09 ESE 7,059 1.66 72e7 1.59 SE 1,409 14.20 1,409 14.20 ssE l,7ll 6.16 l,7l I 6.16 S 2,349 5.29 3,535 2,?9 ssw 7,736 0.61 7,736 0.61 sw 4,566 1.70 3,7W 239 wsw 3,080 2.?? 3,080 2.77 w 3,13E 0.gg 3,138 0.99 wNw 2,963 l.l3 2,956 l.13 NW 2,465 1.64 2,465 1.64 NNW 4,742 0.48 4,742 0.48 a Assumes the effluent releases arc equivalent to dcsign basis source terms.
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Tablc G-3 WatB B$Nucleu Plmt Rcluive Projeded Annud Dose to Roce6or lhyroid fiom Ingestion of MillC (Nearcst Milk-hoducing Animal Wi6in tkn (5 Milcs) of Plam) mrcm/ycar ApproximateDistance AnnualDose )uq location Sector MtGB 2Ol4 2015 s/m' Cows Farm ND ESE 6,706 0.06 0.06 1.35 E-6 Farm P1u'c SSw 2,826 0.19 0.19 1.73 E-6
- a. Assumcs the plant is operating and cfrlucm rclcascs arc equivalcnt to desigp basis soure tems.
- b. Milk being sanplcd at thcsc locadons.
- c. The identification forthis location rvrs revised in 2013 from Farm Ho to Farm HH.
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APPEbIDD(H DATA TABLES AT.ID FIGURES {1-
Table H-I DIRECT MDIATION LB/ELS Average B(emal Gamma Radiation Levele at Various Distances from WatE Bar Nuclear Plentfor Each Quarter- 2015 mR / Quarter o) Averaoe ExtemalGamma Radlation Levels o) 1$ Qf 2nd Qtr 3rd Qtr 4th Qf mR / Yr rcr Average 0-2 miles 14.2 15.3 16.6 14.7 61 (onsite) Average
>2 miles 13.3 13.4 15.1 13.6 55 (otrsite)
(a) Field peilods normalized to one standard quartar (2190 houra) (b) Average of the lndividual measuremEntB ln the set (c) The 5.6 mRlyrbr onslte bcatons falls below the 25 mrem btal body llmlt ln 10 CFR 190. Table H-2 (1 of 2l DI RECT RADIATION LEVELS lndividual Stations at Watts Bar Nuclear Plant Environmential Radiation Levels mR /Quarter Map D,osimeter Approx 1st Qtr Znd Qtr 3rd Qtr 4th Qtr Annual(l) Location Station Directior, Distance, Jan-Mar Apr-lun Jul-Sep Oct-Dec Exposure Number Number degrees miles 2015 2015 2015 2015 mR/Yeaf 40 N-l 10 1.2 15.5 17 .4 18.5 16.4 67.8 41 N-2 350 4.7 16.0 17.3 19.5 13.2 66.0 42 NNE-1 21 1.2 18.7 19.3 18.0 15.5 71.5 10 NNE-IA 22 1.9 12.3 14.0 16.0 15.7 58.0 43 NNE-2 20 4.1 11.7 11.3 14.1 (1) 49.5 3 NNE-3 17 10.4 12.2 12.6 15.0 13.5 53.3 44 NE-l 39 0.9 11.7 15.5 16.1 15.5 58.8 45 NE-2 54 2,9 15.2 12.7 16.5 14.4 58.8 46 NE-3 47 6.1 8.8 11.4 12.1 9,5 41.8 47 ENE-I 74 0.7 17,1 13.6 16.3 13.7 60.7 4g ENE-2 69 5.8 12.9 13.3 14.0 13.1 53.3 74 ENE-2A 69 3.5 11.1 9.9 12.1 10.2 43.3 4 ENE-3 56 7.6 8.8 10.4 11.7 11 .7 42.6 49 E-l 85 1.3 14.5 16.0 16.5 16.6 63.6 50 E-2 92 5.0 15.2 15.0 17.3 14.0 61.5 51 ESE-I 109 .2 1 9.9 10.8 10.2 10.2 41.1 52 ESE-2 106 4.4 18.8 17 .3 (1) 14.7 67.7 11 SE-1A 138 0.9 12.8 13.2 17.4 13.6 57.0 54 SE 128 5.3 10.0 12.2 13.0 12.6 47.7 75 SE 2A 1U 3.1 12.3 14.5 16.6 14.0 57.4 79 SSE-I 146 0.5 16.0 14.5 17.2 15.0 62.7 55 SSE-IA 161 0.6 12.3 11.7 20.0 10.0 54.0 56 SSE-2 15 5.8 13.5 15.9 17.3 16.0 62.7 (1) Sum of available quarterly data normaltred to 1 year for tre annual expoeure ralue.
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Table H-2 (2ot2l DIRECT RADIATION LEVELS lndlvldual Sbtons atWatts Bar Nuclear Hant Envlrcnmental Radiation Levels mR/Quarbr Map Doeimebr Approx lstQtr 2nd QE 3td Qf 4th Qf Annual(r) Locaton Sbtion Direction, Distanoe, Jan-lular Apr-.lun Jutep Oct-Dec Exposure Number Number deoree mlles 2A,1l5 2015 2015 2015 mR/YEar 57 S-1 182 0.7 12.3 13.1 15.8 12.8 54.0 58 S-2 185 4.8 12.3 9.4 10.8 12.3 45.0 70 s-2A 177 2.O 14.0 16.4 16.6 16.3 63.3 5 S-3 185 7.8 10.4 10.8 15.6 12.E 49.6 59 SSW-1 199 0.8 17.6 20.5 19.1 15.3 72.5 12 SSW-2 200 1.3 12.2 12.2 16.6 13.6 54.6 60 ssw-3 199 5.0 11.7 10.3 12.2 11.0 45.2 62 Sr/\r-1 226 0.8 16.0 19.2 19.1 16.2 70.5 63 Srrlr-2 220 5.3 15.8 15.4 2O.O 19.2 7OA 6 S1'\r 225 15.0 11.0 11.3 11.1 11.3 4.7 64 WSI/I -1 255 0.9 13.4 13.1 12.9 13.2 52.6 65 WSI/rr-2 247 3.9 16.9 17.4 18.6 '15.5 68.4 66 W-1 270 0.9 13.9 16.4 15.3 14.1 59.7 14 W-2 277 4.8 11.1 11.8 13.4 11.4 47.7 77 W-2A 268 3.2 12.2 16.0 14,4 14.2 56.8 67 WI.tV\r-l 2% 0.9 21.4 21.2 21.7 22.8 E7.1 68 Wt{^ -2 292 4.9 15.8 17.8 18.9 17.8 70.3 69 Nt r-1 320 1.1 12.8 14.1 14.7 13.2 54.8 70 l.ll l-2 313 1.7 18.3 18.8 17.6 16.4 69.1 78 NW-2A 321 3.0 16.6 11.2 13.8 11.E 53.4 2 ttw 317 7.0 18.0 16.E 18.4 16.0 69.2 71 NI.{V\I-1 340 1.0 10.1 13.6 14.4 13.9 52.O 72 NNVI,-2 333 4.5 13.6 13.1 16.7 15.0 58.4 79 Ni.Mr-3 3il9 7.0 9.4 11.2 (1) 12.2 43.7 7 N}.IW.{ 3i}7 15.0 11.7 12.6 11.2 13.5 49.0 (1) Sum of analhble quartedy data nomalEod to I year forthe annuala:eoours value.
'64'
Tenneesee Valley Authorlty RADIOACNUTY IN AIR FILTER pCUm^3 = 0.037 BCmA3 Name of Fad$tf WATTS BAR NUCLEAR PLANT Do*et Numben 5G380,391 Locatlon of Fadllty: RHEA, TENNESSEE Reportlrg Perlod: 2015 Numbar of Type and Lorer Umlt lndlcalor Locatione LocaUon $rth Hlgheet Annual Mean Control Locationg Norrqrtlne Total Number of Detec0on Mean (F) Mean (F) irean (F) Reported of Analyals (LLD) Range Location Degcrlptlon wlh Rarqe Range Meagurements Peilormed See Nde 1 See Note3 Dlstance and Dlrecfron See Note 2 See NoJe 2 See Note 3 GROSST BETA .520 2.00E{)3 1.92E-02 (416r416) PM5 DECATUR 1.96E-02 (52 t 521 1.89E-Ul (104 104) 2.57E-03 - 4.2#-U 6.2 MILES S 4.54E-03 - 3.23E{2 3.03E-03 - '4.25E-02 GAIIMA SCAN (GELU - 130 AG.A,8 1.00E 02 104 VALUES < LLD Ltil3 13 VALUES < LLD 2O VALUES < LLD 1.9 MILES NNE BE-7 2.008 02 1.01E{1 (1O{ r 104) PM3 1.07E-01 (13 13) 9.86E-fi1 (26 r 26) 6.13E-02 e 1.42t01 10.4 iNlLES NNE - 7.g4lE{/2 ' 1.42E{1 5.49E-02 - 1.34E-01 Bl-214 5.mE{l3 1.99E-02 (102 104) LM-4 t fB 2.58E-O2 (13 13) 2.1OEq2 ett26l 5.40E-03 - '7.16E-02 0.9 MILES SE 6.40E-03 -' 7.16E42 5.20E-03 - 5.66E-02 !-l E' & 104 VALUES < LLD 13 VALUES < LI.D 26 VALUES < LI-O U (^ t K-40 4.00E-02 Plrr4 7.0 MILES NE'ENE o EI P*212 5.00E{3 104 VALUES < LLD Ptr,l4 13 VALUES < LLD 28 VALUES < LLD f.^, 7.8 MILES NE'ENE P*214 5.008{3 1.90E-ff! (100 t lml LM4WB 2.&E-02 (121 13',) 2.13E&, (28 lzgt 5.00E-03 - 7.50E.02 0.9 MILES SE 5.30E-03 - 7.50E-02 5.00E-03 - 5.94E{2 TL-208 2.00E-03 2.20E-03 (i 104) PMs DECATUR 2.20E-03 (1 13) 26 VALUES < LI,D 2,20E-03 '- 2,20e.{Jf3 0.2 MlLEs s 2.208-03 -' 2.20E-03
- l. ilmhd LoE Lml d tbbdbn (uD) a3 Gcribsd rr Table E- I Z ilGm arl Rtngs bad Wot debcbtrb rrauamnb of. Fracdon ddeEcbbb nrcuimntr at rpecfied bca0or lr Hcalgd ln poerrtpasr (D.
- 3. BlEnt! h tit cohnn hdh& m norqmlho moeJlrflldrti
Ten neesco Valley Authority MDIOACTIVITY IN CHARCOAL FILTER pCl,tn^3 = 0.037 Bqrm43 Name of Facility WATTS BAR NUCLEAR PLAlrlT Dodret Numbec 5&300,391 Locatlon of Fadllty: RHEA, TENNESSEE Reportlrg Period: 2015 Number of Type and Lourer Umlt lrdlcator Locaforp Localion wlth Hlghest Arrural Mean Control Locdons Nonrou0ne Total Number of Detedlm Mean (F) ilean (F) Mean (F) Repotted of Analysts (Ll.D) Range Loca0on Descridlon w0th Rarge Rarpe Meastrements Per6rmed See Nole 1 See Note 2 Dlstance ald Dtrcdlsn See N.$e 2 See Note 2 See Note.3 GAMMA SCAN (GELI) - 5i10 Bl-2t4 5.00E-02 1.148-Ol (200 416) LM2 1.40E-01 (28 I 521 1.35E{1 (43 r 1O{) 5.01E-02 ' '6.glE-01 0.5 MILES N 5.03E-02 - 0.818-Ol 5.21E-O2 - 7.50E-01 l-131 3.00E-02 SEE NOTE 4 Kr{0 3.00E-01 3.49E-01 (19 t 416) PMs DECATUR 3.60E-01 (17 l52l 3.78E-01 (19 10{) 3.ff1E-01 7.3llE-01 6.2 MILES S 3.02E-Ol - 7.3ilE-01 3.02E-01 -' 0.13E-01 P*212 3.008-02 416 VALUES < LLD PM2 SPRING CITY 52 VALUES < LU) 104 VALUES < ILD 7.0 MILES ifw P&214 7.00E-02 1.44E-01 (119 I 416) ttiJlz 2.10E 01 (13 52) 1.78E-01 (2$ 1104) t-l t 6 7.00E 6.92E 01 0.5 MILES N - 7.89E-02 ' 6.92E-01 716E52 - 7.40E-01 $ ? TL-ang 2.qlE-02 416 VALUES < LU) t"irl3 52 VALUES < LtD 104 VALUES < LLD 6' 1.9 MILES NNE E A Noba: l. ilflrhd l-ffi lltd of Drbo[on (LLD) c dactocd ln Tr!5 E - I
- 2. l,le.n ad R rl b6d Won debdlDle msrulemstb ooly. Frec[on d&bcldrb mo8rmmeils al lpecltbrl locauon b trrflclH ln pernlhss! (D.
- 3. Cat{tl h 0tb cotumnlndc6 noruuqrrtne nmumn rt
- 4. Ihs mdvlb of Cherod Fllbl! vrrs peftmsd ,y Gamma Specfoacoev. No l-l 31 rE dobctsd. Tha IJD 6r l-l 3f W Garune $ecfoocopy mr 0.8 pqf.uuc rrEb.
Tennoacee Valley Authorlty RADIOACTMTY IN ATMOSPTIERIC MOISTURE pCl'ffi3'0.007 BCm^3 Name of Fadlltf WATTS BAR NUCUAffi PUiIT Dod(stNumDc 500O.3El Locatlon of Fadlity: RHEA, TENNESSEE Rspolfr[ Pedod: aI5 Numborof Type and Lorrer Umit tndlcator Loca$ons LocatbnyrltrHghsstAnrudmm
- Conhol locatms Nmou8ne Total Number of [btecilon Mean (F) lrun(D i/hn(F) -- nspomed of Analysis (LLD) Range Loca0on Dsctip0mwUt neqt Ralpp i[eanmtmntr Perftrmq$ See Note 1 See Note 2 Offsn ald bmcdon Sce !{ae z Se Nda 2 Ss Nole 3 TRMUM .203 3.qlE+(xl 4.$E+00 (15 1153) ulrl 5.54E+qt (1S r 6) 4.00E+00 (18 r 50) 3.(FE+(X) - 2.64E+Ol 0.5 MILES SSW 3.26E+(X) - 2.64E+01 3.04E+fi1 ' 5.t0E+00 hl E.
I trr { ch I 6' F
?Yh t{ole!: l. Nanhat Lmr Lerd ol Dcbcfloo GfD) a dcrdbd h Tebb E' I Z i,htt ad RrEs ba.d UPat &bcbt lo measuenrenb c{y. Fncilqr of debdaua measrortnb at sPednod bcatm b hdcabd ln pannha*l (F).
- 3. Bleilt ln hb cdum trlm m nonlordr mearuturlelilr
Tennessee Val ley Authority RADIOACTIVITY IN MILK pCUL = 0.037 BqlL Name of Fadti$: WATTS BAR NUCLEAR PLANT Dodret Numben fl)-390,391 Locaton of Fadllty RHEA, TENNESSEE Reportlng Perlod: 2015 Number of Type ard Lower Llmit lndtcator LocaUone Loca$on w0tlh Highest Annual Mean Contol Locatons Nonroutine Total Number of Detectlon Mean (F) Mean (F) Mean (F) Reported of Analyslg (LLD) Range Locatlon Decriptton ui0r Range Range Measurements Perbrmed See Note 1 See Note 2 Dlstance and Dlrec{on See Note 2 See Note_? See Note 3 toDtNE-l3l -78 4-00E-01 5E VALUES < TI.D 26 VALUES < LLD GAMMASCAN (GEL]) -78 AC-22E 2.00E+01 52 VALUES < tJ.D 1.73 MILES Ss:tfi' 26 VALUES < LLD 2.59E+Ol (1 ,26) 2,59E+01 - 2.59E+01 Bt-212 5,00E+01 1.84E+02 (1 t 521 1.75 MTLES SSv 1.84E+02 (1 t 26) 26 VALUES < LID 1.&{E+02 1.&dE+02 1.&4E+02 - 1.&4E+02 Bl-z'.,4 2.00E+01 3.UlE+01 (31 t 52l 1.75 MILES Ssltfl, 3.33E+01 (17 126, 3.28E+01 (15 r 2q 2.00E+01 - 6.48E+01 - - I 2.00E+01 6.48E+01 2.12E+O1 6.13E+Ol s' (t 1.31E+03 (25 t gl l h K40 1.00E+@ 1.31E+03 (50 , 52) NORTON FARM 1.32E+03 (26l2gt oo t 1.15E+(E - 1.44E+(Xt 4.1 MILES ESE 1.15E+03 - 1.42E+03 1.18E+03 - 1.44E+03
-t+l o
*.I PA34M 8.00E+02 52 VALUES < LLD 1.75 MILES SSUV 26 VALUES < LtD 26 VALUES < LLD o\
P*212 1.50E+01 52 VALUES < LtD 1.75 MILES Sslrt, 26 VALUES < LLD 26 VALUES < LI..D PB-214 2.008+01 2.93E+01 (21 t 52l 1.75 MILES S$A' 3.07E+01 (8 l2A) 2.94E+01 (14 t 26l 2.01E+01 - 4.908+01 2.14E+01 - 4.90E+01 2.04E+01 - 4.90E+Ol TL-208 1.00E+01 52 VALUES < tLD NORTON FARM 26 VALUES < LLD 26 VALUES < LLD 4.1 MILES ESE sR89 -12 3.50E+00 8 VALUES < LLD 4 VATUES < LtD sRql -12 2.fi)E+00 8 VALUES < LU} 4 VALUES < LtD t{obs: 1. Nomfild LorEr lud of Dsbrthn (l,lD) as dsol0ql ln TaUe E - 1
- 2. lleanrlldRarycbEcduDmdeiedabbmsalurcflrnbmly. Fracilmd(bGctluemeallmentBsts@fadlocatbnbandcabdlnpa'ffieaec(F).
- 3. Blailr ln ltdr odLrnn lrdhdg rc narourdns mas.rgrnh
Tenneeee Valley Authorlty MDIOACTMTY IN SOIL pCug = 0.037 Bq/g (DRY WEIGHT) Name of Fadllty WATTS BAR NUCLEAR PLANT Dodret Number 5$390,391 Locatlon of Facility: RHEA, TENNESSEE Reportlng Perlod: 2015 Number of Type and louBr Umit lndlcator Locatlons Locatbn wtlh Highest Annual Mean Control Localions Nonroufrne Totral Number of Detecilon Mean (F) Mean (F) Mean (F) Reported of Anatyels (Ll.D) Range Loca0on Descrldion wt0r Range Range Measurements Perfgmed See Note I See Note ? Dlstanoe arNd Dlrectlgn See Ngjle 2 See Note 2 See Noh 3 GAMMA SCAN (GELI) - 10 AC*lAI$ 2.glE-01 1.18E+fi) (8 r B) Lill 1.34E+fi) (1 1) 6.25E 01 (21 2l 8.32E-01 - 1.34E+(X) 0.5 MILES SSVI' 1.30Er(X) -' 1.34E+00 6.08E{r1 - 6.42E{1 BE.7 2.50E-01 3.15E{1 (3 r 8) PMs DECATUR 3.84E-01 (1 1) 2 VALUES < LI."D 2.02E{1 3.84E-01 6.2 MILES S 3.E4E-01 ' 3.84E-01 B/,afl 4.50E-01 1.238+00 (8 8) PM3 1.48E+00 (1 ,1) 6.62E-01 (21 4 9.0EE-01 -' 1.48E+fi) 10.4 MILES NNE 1.48E+00 - 1.48E+00 6.62E{1 - 6.62E-01 il.zu 1.508{1 7.64E-01 (8 r 8) L"il3 8.87E-01 (1 1) 6.07E-Ol (2121
- 6.45E-01 5.38E{t1 8.87E{1 1.9 MILES NNE 8.87E-Ol -' 8.87E{1 5.68E{1 c$137 3.00E 02 1.68E{1 (7 8) PM2 SPRING CITY 5.64E.01 (1 / 1) 3.15E-01 (2/,21 Fl p
I - 3,07E-O2 ' 5.64E-01 7.0 Mll-Es !.lw 5.64E Ol - 5.64E'01 1.84E 4.46E-01 ET o\ \o l-o I K-,10 7.50E-01 1.16E+01 (8 r 8) LM.4 WB 2.58E+01 11 I 1' 3.65E+fi) l2l2l tr 3.39E+00 2.58E+Oi 0.9 MILES SE 2.58E+01 - 2.58E+01 3,0EE+00 - 4.23E+fl1 rl 4.fi)E+00 8 VALUES < L[I) Pi,lz SPRING CITY 1 VALUES < LLD 2 VALUES < LLD { a PA"234M 7.0 MILES NW P*212 l.(xrE-ol 1.17E+Ul (E r 8) PM3 1.42E+00 (1 ,1) 6.07E-01 (212}. 8.52E{1 - 1.42f+fi) 10.4 MILES NNE 1.42E+00 - 1.4!f+{10 6.06E-01 - 6.08E-01 P*214 1.30E{1 8.30E-01 (8 r 8) LIriS 9.70E-01 (1 1) 6.76E-01 (214 6.00E{1 9.70E-01 1.9 MILES NNE 9.70E{1 -' 9.70E-01 6.23E 7.29E{1 RA.2B l.qlE ol 7.64E-01 (8 8) LM3 8.87E{1 (1 1) 6.07E-Ol (21 2t 5.38E-01 ' 8.87E-01 1.9 MILES NNE E.g7E-01 -' E.87E-01 5.68E-01 - 6.45E-01 TL-208 6.00E-02 3.93E{1 (8 r 8) PM3 4.61E{tl (1 1) 1.96E-01 (21 4 2.78E51 - 4.61E-01 10.4 M]LES NNE 4.61E-Ol -' 4.61E-01 1.87E 2.058-01 sR89 -10 1.dlE+00 I VALUES < Lt"t) 2 VALUES < IID sR90 -10 4.00E-01 8 VALUES < LI.D 2 VALUES < tI.D t{oEs: t. Nmfid LorEr lsrd ol lrbcdon GfD) a3 d6stbd ln T& E ' 'l Z t esn and ReryF bacdl rfpon d*d& meacumor{r only. Fracfion of &bclaUe mecutolmnts at spodfrod locatlon b Mcated ln paentlEs.r (D.
- 3. Bladc lnthb coftrmn lndcale m nqr]ouiltn meeelcmetils
Tennessee Valley Authority RADIOACTIVITY IN CORN PCI/Kg = 0.037 BqrKg (UVETVt EIGHT) Name of Facllltf WATTS BAR NUCLEAR PI-ANT Dodot Numben 50-390,391 Locaton of Fadt[y RHEA, TENNESSEE RepoillrE Perlod: 2015 Number of Type and Louuer Umlt lndicator Locatlorc Locatlon wlh Hlghert Annual Mean Conlrot Loca0ons Nonroufine Total Ntmber of Detecilon Mean (F) Mean (F) irean (F) RePoiled of AnalyRb (LLD) Range Location Descrlptlon with Range Range Msasurments Performed See Note I See Note 2 Dlstanoe and Dlrecillon Se No,te 2 See Note 2 See Note 3 GAMMA SGAl,l (GELI) -2 B/,.2fi 4.fiIE+01 l VALUES < LLD NORTON FARM 1 VALUES < ILD 1.72E+M, (1 ,1) 4.1 MILES ESE 1.72E+@, - 1.72E+gl2 K-{0 2.50E+02 2.03E+03 (1 1) NORTON FARM 2.03E+03 (1 ,1) 2.21E,*8 t 1) (1 2.038+00 -' 2.038+00 4.1 MILES ESE 2.03E+03 - 2.96f+Gl 2.21E+B - 2.21E+03 PB-214 8.ME+01 l VALUES LLD< NORTON FARM 1 VALUES < LLD 1 VALUES < LID 4.1 MILES ESE Fl D {o a C F tD t lil Ilr I O t{oba: 1. }tortrd Lffi Let d d Oecfim (Lt D) ar &aqlbed ln Tabh E' I
- 2. MeansrdRmgsbarertWqrrHccl6btormasuramltbor{y. FtecUonofdetoctablenmunrmrtral3pecmedbcafmbMcatcdhpacntlasr(D.
- 3. Bhnts h hb cofttmn hdc& m nmu.rdne msuqnil3
Tenneceee Valley Authorlfl RAIXOACTMTY IN GREEN BEAI.IS pciflA = 0.037 Bq,Kg (uvET WEIGHT) Name of Fadllty: WATTS BAR NUCLEAR PLANT Docket Number 50-gg),391 Locallon of Fad[ty RHEA. TENNESSEE Reporting Pedod: 2015 Number of Type and Loruer Umit tndicator LocaUons LocaUon wlh Hlghest Annual Mean Conht Locations Nonrouthe Totral Number of tlgtecilon tulean (D Mean (F) itean (F) RePorted of Analysis (LLD) Range Locatlon Descrlptlon wltlr Range Rarge Meagurements Pefunrrcd See Note I See Note 2 Dtstance and Dlrectlon See Note 2 See Nde 2 See Note 3 GAMMASCAI{ (GELI) -2 Bl-214 4.00E+01 4.17E+01 (1 l) 3.0 MILES NE 4.17E+01 (1 1) 1 VALUES < LLD 4.17E+01 -' 4.17E+01 4.17E+O1 o' 4.17E+01 K.f0 2.50E+02 1.90E+03 (1 , 1) 3.0 MILES NE l.glE{O3 (1 ,1) 2.40E+03 (1 I 1l 1.90E+03 - 1.90E+03 1.90E+03 - l.glE+o3 2.40E+(E - 2.49f+(B PB-214 8.ff}E+01 1 VALUES < LLD 3.0 MILES NE 1 VALUES < LLD 1 VALUES < LLD H D {t U ts J tD I H H
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t{oia: l. f{omhd Low latd of Delcflm (tur) as dslctlbod ln Tdb E' I Z lbmandRqpbasedryonddsddbmasusnenbmly. Frdmddebdauemes$!mil3atgpedlledlocdottblruIcabdhpalsilEses(F).
- 3. Berfu ln hb cdumn lndcab tD ngttourdtE tlptlrronedl
Tenneeeee Valley Authorlty RAOOACTIVITY IN TOMATOES PCi,Kg = 0.037 Bqnq .*ETWEIGH') Name of Faclllty WATTS BAR NUCLEAR PI-ANT Do*et Numben 50-390,391 Locatloct of Fadlitf RHEA, TENNESSEE ReporllrU Pedtd: 2015 Number of Type and Lorer Umit lrdicator LocaUom Locatlon u,!th Hbhest Annual iiean Controt Loca0onE Nonroufilre Total Number of Detecilon Mean (F) Mean (F) Mean (F) Reported of Anatysls (LLD) Range Locatlon Descrlptlon wllh RalPe Range Meaewementa Performed See Note I See Note 2 Dlstiance and Direcillon See Note 2 See Note 2 See NotB 3 GAMMA SCAN (GELI) -2 Bl-214 {.00E+01 4.OgE+01 (1 , 1) 2.5 MILES NE 4.09E+01 (1 1) 4.72E+O1 (1 1) 4.09E+01 - 4.OgE+01 4.09E+01 -' 4.09E+01 4.72E+O1 -' 4.72E.+01 K-,{0 2.50E+02 2.11E+03 (1 , 1) 2.5 MILES NE 2.11E+03 (1 1) 1.9tf+03 (1 1) 2.11E+03 - 2.11E+03 2.11E+03 -' 2.11E+03 1.98E+03 -' 1.gEE+03 P*214 8.OOE+01 1 VALUES < LLD 2.5 MILES NE 1 VALUES < LLD 1 VALUES < LLD Fl pl cr {N t F o
)d I
tr. I F o N&fi l. l{omirlll LouGr lltd of Od.cilm (LlD) a dscosd ln Tade E - I
- 2. lrem atd Rengc bererl rpor dc0adalle rrcannsnenb mly. Frdm of ddecbDle ruaurcmenb at rpecfrd tocaffm b ltdc8bd h paEntrtss.. (D.
& Eard(3 h thb aoltmt mcab no nontu[iltD ttEurwnts
Tennessee Valley Authorlty MDIOACTMTY IN TURNIP GREENS PCl,'lQ = 0.(Xi7 Bq,Kg (WETWEIGHT) Name of Facllltf WATTS BAR NUCLEAR Pl.At{T Do*et Numben 50-390,391 Locatlon of Fadllty: RHEA, TENNESSEE Reportlng Perlod: 2015 Numbr of antt Umlt lndlcator Locatlorc Loca0on u,lth Hlghest Anrual Mean Contnot Localions Nonroutlne llban (F) Type Lonupr RePorted Total Number of Detecffon Mean (F) Mean (F) of Analyrle (lID) Ralge Location Deecrlillon wlth Rarqe Range Measurements Performed See Note 1 Se? Note 2 Dlstanog and Dlredlon See- Note 2 See Note 2 See Note 3 GAMMASGAN (GELI) -2 B,l-214 4.ff)E+01 6.&{E+01 (1 1) 3.0 MILES SE 6.&{E+01 (1 1) 7.34E+01 (1 1) 6.&0E+01 -' 6.&0E+01 6,84E+01 -' 6.84E{Ol 7.34E+01 -' 7.34E+01 K40 2.50E+ff1 2.55E+03 (1 ,l) 3.0 MILES SE 2.55E+03 (1 1) 2.14f+03 (1 1)
-' 2.14E+03 2.55E+03 - 2.55E+03 2.S5E+03 -' 2.56E+03 2.14E+08 P*214 8.OOE+01 1 VALUES < LLD 3.0 MILES SE 1 VALUES < LLD 1 VALUES < L"LD Fl s,
ET f.l H o Ir I ltt i-H tlo6: l. t{omhl Lmrl.etd of Odrcflon$D) ar deccrlbsd ttTaDb E't
- 2. l15at ard Rmgp b6d rpon d66dab6 maanrsnerfr cty. Frac0on d ddecbbb msaurcnreds d rpecllled locdon b lndlcabd ln parsnthe!.s (F).
- 3. t[.da h lhb ootumn hdc& rc nmtflt{hs nEurcmsds
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?-11401 - liE Ol z3lErot - a.?ZErOl 1*iG ' l.G.@ N IL{6 lff.Ol u, rB 5l?.g lavalrEa<u.o l3vaJ.E3<lLo
'VA,rrEa<
tRmtr ., Z.7OE+fiZ, 6.85E+02 (1412f,.1 TRM 543.1 7.31E+02 (8 13) 13 VALUES < LLD 2.98E+fi1 - 1.07E+03 - 3.12E+(n ' 1.67E+03 Nobs: t. ifcn[ral Lmr lrrd d Dsbciion (u-O) as descrlbsd ln Table E' I 2l{3grar5Rengebsqtrpdtdebdeu.msttuElmnt!only. FEdlonofrhEffiemeaalerEricatlpcmdbcatml!hdcebdlnpannthemc(D.
- 3. Eanlls ln U& cdtmn lrdcab m nouuflltre tnea3lmmmb
Tennessee Valley Authorlty RADIOACTMW lN PUBLIC (DRINKING) WATER (l'otal) pCUL = 0.037 BqrL Name of Fadlltf WATTS BAR NUCIfAR PI.ANT Doctret Number: 5().390,391 Locallon of Fadllty RHEA, TENNESSEE Reportlng Period: 2015 Number of torrer Umlt lndlcator Locatbna Loca0on wlth H[hest Annual Mean Conlrol Locdions Nonrouthe Type and Mean (F) Mean (F) Mean (F) Reported Total Nwtber of Detedlon (LlD) Range LocaUon Deecriptlon wlth Range Rarqe Measuremente of Analysis Distane ad Dlrecfron See Note 2 See Note 3 Pe&rmed See Note 1 See Note 2 Qee Note 2 GROSS BETA - 39 1.90E+ff) 2.18E+00 (13 r 26) Ri,I.2 DAYTON TN 2.27E+OO (5 13) 2.41E+00 (8 13) 1.91E+00 - 2.69E+00 17.8 MILES NNE - 2.OOE+00 ' 2.698+00 2.02E+fi)' 2.98E+00 GAMMA SCAN (GELI) -39 AG-228 2.ff)E+01 2.25E+O1 (1 126l CF INDUSTRIES 2.251+01 (1 ,13) 13 VALUES < LLD 2.2SE+01 - 2.29f+01 TRM 473.0 2.25E+O1 - 2.?,5E+O1 Bt-214 2.00E+01 4.33E+01 (14 I frl RltL2 DAYTON TN 5.068+01 (5 / 13) 4.30E+01 ;t I 131 2.16E+01 9.21E+01 17.8 MILES NNE 2.6E+01 - 9.21E+01 2.208+01 l.l lEt{JrZ 26 VALUES < LLD RtI,.2 DAYTON TN 13 VALUES < LLD 13VALUES < LLD K.00 1.fi)E+02 17.8 MILES NNE H pl d {(^ a Pr};212 1.50E+01 2O VALUES < LLD Rii.2 DAYTON TN 13 VALUES < LLD 13 VALUES < LLD
-o I 17.8 MILES NNE 2.@E+01 3.&4E+01 (121 2,1 Rtut2 DAYTON TN 4.60E+Ol (4 13) 5.44E+Ol (4 13)
F t-P&l214 2.04E+01 8.68E+01 17.8 MILES NNE 2.488+01 -' 8.G88+01 3.398+01' 1.028+92 r*) TL-A)8 1.00E+01 26 VALUES < LID RM-2 DAYTON TN 13 VALUES < LIJ) 13VALUES < LLD 17.8 MILES NNE TRITIUM .47 2.7OE+@, 4.74E+02 Ul CF ]NDUSTRIES 4.93E+02 (10 1A 13 VALUES < LI-D 2.8r',E+O2 121
- ' 1.07E+03 TRM 473.0 r 2.UE+O2 ' 9.16E+02
- l. t{qntltl Lm, tul d Dobcilm (LLD) as dccsfred h Teble E' I
- 2. ii n end Rengc De!d Won debclsb measuanentr crty. Frecilor d debddlo mesutgtmlfi d rpcdncd bcadm lr krdcaied ln pann0pret (F).
- 3. Bbr*l h ttt! cdumn lrdcab no nonrurdrp measuFmds
Ten neseee Valley AuthorlU RADIOACTIVITY tN WELL (GROUND) WATER (tota0 pCtL=0.(Xl7Bq/L Name of Fadlltf WATTS BAR NUCLEAR PIANT Docket Number 50-390,391 Location of Fadllty RHEA, TENNESSEE Reporting Period: 2015 Number of Nonroutlne Type and Lorer Umlt lndtcator Locatione Loca0on wih Hlghest Annuat Mean Control Locatlons iilean (D Reported Tota[ Number of Detedion Mean (F] Mean (F) of Anatysls (LLD) Range Locaton Descriptlon wi[r Range Range Measurements See Nde 3 PerbrmeO Se.llole I See Nde 2 See Note 2 Dlstane and Dtrec{on See Note 2 GROSS BETA -78 1.90E+00 2.86E+(P (35 r 65) WBN WEIL#I 3.13E+00 (3, 13) 2.76f+fi) (6 13) 1.91E+fi1 - 5.60E+fi) 0.6 MITES S 2.47Q+OO - 3.O2E+fl) 1.97E+q) -' 4.90E+00 GAMMA SCA}I (GELD -78 2.00E+01 65 VALUES < LJ-D WBNMW 13 VALUES < LLD 13 VALUES < LLD AG22S o.45 MILES SSE) Bl-214 2.00E+01 3.3{iE+01 (43 r 65) WBN MIA/.A 3.95E+01 (11 13) 2.95E+Ol (t I 1gl 2.05E+01 6.69E+01 0.58 MILES SSE) 2.fr1+O1 - ' 5.84E+Ol 2.19E+Ol - 4.15E+01 65 VALUES < LLD WBN ItnW-A 13 VALUES < LLD 13 VALUES < LI.D K.40 1.00E+02 Ft 0.58 MIIES SSE) E cr {Or I PV212 1.50E+01 65 VALUES < tLD WBNMW.A 13 VALUES < UI) 13 VALUES < LLD o H I 0.58 MILES SSE) l-l P&211 g.z]E+ol (3f , 65) WBN IIIW-A 3.88E+01 (11 13) 2.72E,+01 (6, 13) ts 2.fi)E+O1 2.01E+01 - e.21E+01 0.58 MILES SSE) 2,nE+O1 - ' 8.21E+01 2.03E+01 - 3.51E+01 5 TL-208 1.(XlE+01 66 VALUES < LtD wBN iil rf 13VALUES < LLD 13 VALUES < U"D o.30 MITES SE) TRmUM -78 7.7$l+O2 (34 r 65) WBN irfUlr 1.09E+03 (13, 13) 13 VALUES < LLD 2.70E+V 2.748+92 - 1.4{E+(Xl 0.45 MILES SSE) 8.25E+02 - 1.44E+03
- 1. I{olnhl i.oYpf bul dD*dbn (LtD) 8! dcteqt h Tdb E' 1
- 2. lkt ad Rmgg bsd rpon rhbctaDte rpasurmsn03 ody. Fracdm o, debciaue mcauunronb at rpedned bcaton b hdcaled h pdlilElo! (F).
- 3. Bad.t ln thb ohrmn trdcab m tsroulilne rrerugnentr
Ten nessee Val ley Authorlty RADIOACTIVITY IN COMMERCIAL FISH pCUg = 0.037 BCg (DRY WEIGHT) Name of Facility WATTS BAR NUCLEAR PlAl-lT Dodct Number 5&390,391 Locatlon of Fadllty: RHEA, TENNESSEE Repoillr Perlod: 2015 Nurnber of Type and Loner Llmlt lndlcator Locatlons Location u,ith Hlghest Alrnual Mean Conhot Locatlons Nonroufrne Total Number of Detecilon Mean (F) illean (F) Mean (F) Reported of Ana[d8 (LLD) Range Location Descrlptlon wlth Range Range Meaeuroments Perforned See Nole 1 Soe Nolgz Dlstance and Dlrecton See Eote 2 See Note 2 See Note 3 cArrMAscAN(GEU) -6 gt-211 l.mEoi 1.EE{t (3r4) CHEI(AMAUGARES 1.E,rEAt el4 1.tr41 e.t4 t.rzeoi - lne-ot TRu.tzi-qto i.17E41 - z^17g*,1 l.o-rE{l - l.7G{ll K.fo 4.@E{1 l.(EE+Ol (4r4) OOUVNSIREAI,ISTAIONI '1.06E+01 l2l2l 1.G+O1 e,lA e.lte*oo - i.rse.o,t txrwNsTREAM l.@E{rl - l.loEr{tl 1.01E+ol - 1.1'lE+0, P9212 4.qE-Ol /0VALUES < LID CHICIGMAUGARES 2VALUES < LLO 2VALUES< IID TRM471-500 E8l211 S.OOEOI 4VALUES<LU) DOT'VNSTREAMSTANONI 2VALUES<LLD 2VALUES<IID DOt /NSIREAi,I TL.2O8 3.qtE.O2 4VALUES < 1I.T' CHICKAT'AUGARES 2VALUES < lII' 2VALUES < II.O H D TRM471m trr (( t ts o a H H I Fr Q't Nobt l. Nmhd Lcrsr lst d of mc[on GlIr) a (h.ctlled ln Tabb E - I
- 2. lleen a15 Rarge bald Won debdabh msarrqrst a{y. Frdon d d$d.trlo tmsutrlanb at speclfred bcaton Is lldcdd ln pan ilha!s (F).
- 3. Banfa hfiL colttttttt tdhab m nmmldnc meetrunen0s
Tennessee Valley Authortty RADIOACTIVITY lN GAtlrlE FISH pCUg = 0.037 Bqrg (DRY vlrEIGl'fI) Neme of Fadlltf WATTS BAR NUCLEAR PIINT t}ocket Numben 50.390,391 Locatlon of Fadlity: RHEA, TENNESSEE Rebortirp Petud: 2015 Number of Type ard Louer Umtt lndlcator Locations Locallon uith Hlghest Annual [,!ean Control Locdone Nonroullne Total Number of tletecdon Mean (F) Msan (F) irlean (F) Repoilcd of AnalytB (UD) Range Location Dscrlptlon wtth Range Range Measurcments Perfurmed See Note 1 See Note 2 Dlstance and Dlrec0on See Note 2 See Nde 2 See Note,3 GAMMA SCA,II (GELI) .6 Bt-214 1.(pE{l 1.93E-Ol (4 t 4l CHICIIAi'AUGA RES 2.11E-Ol (21 2l 1.23E-01 (21 2) 1.32E-01 2.58E-01 TRM 471-530 1.63E-01 - 2.58E-01 1.07E 1.398-01 c$l37 3.00E{2 4 VALUES < U"D CHICI(AMAI.lGA RES 2 VALUES < TI.D 3.24E.0l2 (1 lz',t TRM 471-53[l 3.24E 3.24E&, K.f0 4.00E{1 1.23E+01 (4 t 4) DOI,I'NSTREAIJl STATION 1 1.25E+01 (2121 1.3tlE+01 (2 t 4 1.18E+01 - 1.25E+01 DOA'NSTREAM 1.24E-'+01 - 1.25E+01 1.31E+01 - 1.35ErOl Pt212 4.00E{2 4 VALUES < LLD CHICK/AMAUGA RES 2 VALUES < LLD 2 VALUES < I.TD TRM 471-530 2 VATUES < LLD Ft P&l214 5.00E{1 4 VALUES < tJ.t) CHICIGMAUGA RES 2 VALUES < LLD E TRM 471-530 tt e -oha a TL-208 3.00E{r2 4 VALUES < LtD DOI^JNSTREAM STATION 1 2 VALUES < tII) 2 VALUES < IID Fk DOWNSTREAM I tra o\
- l. No.ntd LoE lrrd d lrcleodon (Ll,D) I dsct0sl ln TaDb E' 'l Z lrean nd Rmg! ba$d Wm ddrdlbh meaurrmnb mty. Fracilqr d rlebdalle nreaurqrmntr at spednod bodon h hdlcabd ln preldtctcs (F).
3 Elaric h m cofrrmr lndhdr no nffiurntE llEaJrlmqil3
Tenneseee Valley AuthorltY MDIOACTIVITY IN SHORELINE SEDIMENT PCUg = 0.037 Bqrg (DRY vlrElcFff) Name ol Fadllty: WATTS BAR NUCLEAR PI.ANT Dodet Number 50-390,391 Uoqrtlon of FadlltY RHEA. TENNESSEE ReportlrE Period: 2015 r . r a rao, ti Number of Locaflon wlth Hlgheet Annual Mean Controt Locatlons Nonroutlne Type and Lorcr Umit lndlcator LocaUons Mean (F) i*Iean (F) Reported Total Number of Detedlon Mean (R (LLD) Range Locatlon Desdptlon witt Rarqe Range MeasunmenE of Analysls Dlstrane and DirBGtS See Nole 2 See Note 2 See Note 3 Petbrmed See Nde.J Sce Note 2 GAlrfMA SGAN (GELD -4 AC-U,& 2.50E-01 1.19E+00 (2 I 2l COTTON PORT ITARI].lA 1.19E+00 (2/,21 1.15E+00 (21 2) 1.16E+fl1 1.23E+(D TRM 513 1.1$t+(X) - 1.23E+00 5.27E-O1 - 7.77E+fi BE-7 2.50E 01 3.40E-01 (1 l2l COTTON PORT i'ARINA 3.40E-01 (1 l2l 2 VALUES < LLD 3.40E{1 ! 3.40E-Ol TRM 513 3.40E-01 - 3.40E-01 Bl-212 4.50E{1 1.29E+fi1 (212l COTTON PORT MARINA 1.29E+fi) (212' 1.27E+q) (21 2l 1.28E+00 - 1.30E+00 TRM 5'3 1.28E+00 - 1.30E{O0 5.20E{1 2.01E+(n 1.50E{1 5.56E{1 (2121 @TTON PORT ifigPA 5.56E{11 (21 4 7.87E{1 (2 t 4 Ba-214 5.23E{1 - 5.89E-01 TRM 513 5.23E-01 - 5.89E-01 4.47E-O1 - 1.09E+fl) c$l37 3.008{2 2 VALUES < LLD COTTON PORT MARINA 2 VALUES < tID 2 VALUES < tJ.D H s(f TRM 513 {a \o 2.70E+01 (2 t 7.31E+U) (2121 b o lr I K-40 7.508-01 2.70E+01 (2 t 2) COTTON PORT MARI].IA 21 o *rI 2.48E+01 2.&4E+01 TRM 513 z$E+O1 2.9{E+01 2.36E+(P 1.23E+Ol rr Pb212 1.008{1 1.16E+q) e 12) COTTON PORT MARINA 1.16E+00 (2121 1.13E+00 (21 2' \t 1.08E+q) - 1.24E+(X) TRM 5{3 1,08E+00 - 1.24E+00 - 5.13E-01 1.74E+00 PB-214 1.50E-01 6.14E-01 (2121 COTTON PORT MARINA 6.14E{1 (2121 8.01E-ol (21 z',l. 5.&lE{1 - 6.45E-01 TRM 513 5.82E{1 - 6.45E{1 4.74E-01 - 1.13E+d) RA;224 7.508{1 1.34E+q) ( l2l COTTON PORT MARIhIA 1.3{E+00 (1 t 2l 1.70E+00 (1 t 2l 1.34E+(m - 1.t4f+fi) TRM 513 1.34E+00 - 1.34E+U) 1.7$f+@ - 1.76E+00 RA.ZM 1.50E-01 5.88E-01 (21 2' COTTON PORT MARINA 5.58E-01 (21 2l 7.67E-Ol (21 4 5.238-01 5.E98{r1 TRM 513 5.23E-01 ' 5'8gE'Ol 4.47E-O1 - 1.09E+00 TL-208 6.008{2 3.90E{1 t 2l COTTON PORT MARINA 3.90E 01 (21 2' 372E41 (2 t 21 3.E6E-01 12
- 3.948-01 TRM 513 3.86E-01 - 3.94E-01 1.66E{)1 - 5.79E-01
- 1. Nn{nd torFr lltrd ol Mo 0.fD) at dlctlbed h Tabb E - I Z UsanadRangebe$dWondeledaflrhnEarurantadrorly. FraodonddcEdaUomannsnrerGatcpcd[edbcetmblndlcdedlnpannfnaea(F).
- 3. Blsnls h td3 columl tdcab m nmrulillm rrealrlumflb
Tenneesee Valley Authorlty RADIOACTMTY IN POND SEDIMENT pGug o 0.G17 Bq/g (DRYWEIGHT) Name ol Fadlff WATTS BAR NUCLEAR PLANT I)odcet Number 5&390,391 Locatlon of Fadllty: RHEA, TENNESSEE Repordng Period: 2015 Number of Type and Lorer Limlt lndlcator Locdions Loca$on u,ith Hlghest Annual lllban Conbd Locatone Nonrcufins Toial Number ol D$cillon Mean (F) }lean (D Mean (F) Repotud of Analysb (LrD) Range Loca0on Descrlption wlth Range Range ItieagurementE Perfumed See N@ 1 See Nols 2 Diehne and Dtmdion Sea Note 2 See Note 2 See Nob 3 GA,iirim scAN (GELI) -5 AGlZ28 2.SIE-Ol 8.42E{1 (5 r 5) YP.l3 't.01E+@ (1 ,1) VALUES < LU' - 4.88E{1 - 1.01E+00 YARD POND I .01E+00 - 1.01E+(D BE 2.50E{1 2.79E-01 (1 5) YP.l3 2.798-01 (1 1) VALUES < LLD 2.79E-01 - ' 2.79E41 YARD POND 2.79E{ll - ' 2.79E41 Bl-212 4.50E-01 9.18E-01 (5 r 5) YP 1.13E+ff1 (1 ,1) VALUES < LLD 5.79E-01 - 1.13E+00 YARD POND I .1 3E+00 - 1 .13E+00 Bl-214 1.50E-01 6.42E-01 (5 r 5) Y?-5 E.13E-O1 (1 1) VALUES < LID 4.20E-01 - E.13E-O1 YARD POND 8.13E.01 - ' 8.13E-Ol co0 7.83E-AI2 (3 r 5) 1.29E-01 H t O 3.00E-02 4.30E-{r2 - 1.29E-Ol YP.5 YARD POND I .2gE-01 (1 1)
- ' 1.29E-01 VALUES < LLD so F.
o c$l37 9,848{[l LV 1.43E-Ol I 1l a 3.00E-ul 3.10E-0il (4 r 5}
- 1.43E.01 LO/i'VOLWASTE POND 1.43E{1 (1
- 1.41}E-Ol VALUES < LLD *.t h{
lra 6 K-f0 7.SlE-o1 1.07E+01 (5 5) Y?-13 1.54E+01 (1 1) VALUES < LID 5.95E+@ - ' 1.54E+01 YARD POND 1 .54E+01 - ' 1.54E+01 PA.234M 4.dlE+00 5 VATUES < LLD YP 1 VALUES < LtD VALUES < LLD YARD POND Pt212 1.00E-01 8.25E-Ot (5 5) YP.I3 1.05E+00 (1 ,1) VALUES < LLD
$.22EQ1 - ' 1.05E+00 YARD POND 1.05E+00 - 1.05E+ff1 P&l214 1.50E-01 7.(EE-01 (5 5) YP.l3 8.7:tE{1 (1 t 1) VALUES < LLD 4.76E-Ol a' 8.73E-01 YARD POND 8.73E{1 - 8.78E{lt R,';z.4 7.50E{ll 8.91E{1 (3 r5) YP 9.7eE-01 (1 1) VALUES < LLD 8.01E-01 - 9.76E-01 YARD POND 9.76E{1 - ' 9.76E-01 TL-209 6.00E-02 2.90E 01 (5 r 5) YP.I3 3.5ilE-01 (L 1) VATUES < LID 1.68E{l - 3.52E{ll YARD POND 3.54E{11 - 3.silE{ll LoEr: l. lbnlnd Lm]layslolDebcilon (ttD) rderybcd lnTeuc E- I
- 2. llom and RE rgp b8od upon dehdatile nEutlmenb only. Fncilor of d&claDle mear'gnsnb d speclied locdlon b hdhabd h pemnhelc (F).
- 3. Blanh3 ln $b column hdhrb no nonrumllnc m.ururErL
Figure H-l Direct Radiation Direct Radiation Leuels Watts Bar Nuclear Plant Four Quarter Moving Average InLight Dosirneter L gzo DeploYrnent Jan ua w, 2A07 o operation in ct= January, 1996 Eb I EoE I
-o at \15 E
E 2010 2015 Calendar Year
+On-Site --O-Off-Slte Dosimeters are processed quarrcrly. This chart shows fiends in the avemge rcasutement for all dosimeters gouped as "on-siten or 'off-site". The data fiom preoperational phase, prior to non-site" measurcments higher than noff-site" measutments that 1996, show the same hend of is obscrved in curent data indicating that the slightly higfuer "on-site'dirct radiation levels are not related to plant opcations.
- 8l '
Figure H-2 Radioactivity in Air Filters Annual Average Gross Beta Activity in Air Filters Watts Bar Nuclear Plant an E
\r e
L' e I E t a- {E
-# lndlcator +FControt As can be seen in the fiend plot of gtoss beta activity, the gross beta levels in air particularcs have remained relatively constant with the exception of years when the bea activity was elevated due to frllout from ntrclear weapour testing. The data also shows that thcre is no difference in the levels for sampling conductcd at the indicator stations as compared to the control stations. The Wams Barmonitoring Eogram was swpended for one lrear in 1989. The preopcr*ional monitoriag was restafied in 1990.
-t2 -
Figrre H-3 Cs-137 in Soil An nua I Average Activity of G-L37 in Soil Watts Bar Nuclear Plant 1.0 0.9 0.8 Initial WBN Operation in January, 1996 a.7 aE R 0.5 E Y
!0 \
a-0.5 (J B 0.4 I a 0.3 a-t a-o,2 0.1 0.0 197s 1980 1995 2000 2010 2015 Calendar Year
-# lndicator -EFControl Cesium-I37 was produced by past nuclear wcapons testing and is present in alrtost every ncontoln and nindicatorn locations environmental soil sample exposed to the atuosphere. The have generally trcnded downward with year-to-year variation, since the beginniqg ofthe \Vatts Bar monitoring program.
Figure H4 Gross Beta Activity in Surface Water Annual Auerage Gro$ Beta Actlyity ln Surface Water Watts Bar Nuclear Plant lnitial WBN Opsration in January, 19gG
+ lndicator (Downstream)
+F Control (Upstreaml As shown inthe graph, tbe Soss beA activity has ben essentially thc same in samples from tbs dormsheam and upstream locations. The average gross beta activity in thesc samples has becn rcpresentative of tbc levels measured during preoperational monitoring.
- 84'
Figrrre H-5 Gross Beta Activity in Drinking Water Annual Average Groos Beta Activity in Drfnking Water Watts Bar Nuclear Plant 6.00 s.00 Initial WBN Operation ln 4.00 Jarpary, 19gB J
- 9.00 ts a
a P.00 ET rt 1.00 0.00 I 975 1980 1985 1990 1995 2000 20t0 2015 CalsndarYear
+ Doilnstseem (lndicetorl
+ UpeUeam (Contrd)
Thc average gross betaactivity in ddnkingwater samplcs from the uptra.m contol locations has beenessentially the same as thc aotivity level measured in samples from the dormsheam indicator locations. The aonual average goss beta activity has been relatively constant since the swt ofplaot operations in 1996 and is slightly lower than preoperational levels. Figure H-6 Radioactivity in Fish Annua! Average Activity of G-L37 in Commerical Fish Watts Bar Nuclear Plant 0.30 0.25 a- 0.20 L E Y
\!0 f,-
0.15 lnitiat WBN Operation in January, 1996 (J c 0.10 I f
--t 0.05 E
0.00 1975
-F lndicator E Control Annual Average Actlvltyof G-L?7 ln Game Fish Watts Bar Nuclear Plant 0.30 0.25 a- 0.20 B
Y E InitialWEN Operation E 0.15 in Janualy, 1996
\aaa (J
B 0.10 a iY a-a: 0.05 iJ t 0.00 L97S
+ lndicator +Fcontrol Thc concentrations of Cs-137 found in fish are consistent with levcls prcsent in the Tcmessee River due to past afuospheric nuclear weapou testing and operation of other nuclear frcilities inthe upperreaches of the Tennessec River Watershed.
Figure H-T Radioactivity in Shoreline Sediment Annual Avercge ActMW of Cs-137 in Shoreline Sedlment Watts Bar Nuclear Plant 0.60 0.50 0.40 A E
?
U 0.30
\r !0
(, a-ca 0.20 a-t
'E a-0.10 0.00 1990 1995 2000 Calendar Year
+ Indicator +F control Thc Cs-137 prcscnt in the shoreline sodiments ofthe Tennessce River system rvas produced both by rcsting ofnuclear weapour and operation of othcr nuclcar frcilities in the upper reachcs ofthe Tennessee River Waiershed. The amounts of Cs-137 have declined significantly during the coutse of monitoring for the Watts Bar site, so much so that not all samples contain dercctable levels.
M Tennessee Valley Authority, P.O. Box 2000, Spring City, Tennessee 37381-2000 May 12,2016 10 cFR 50.4 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Units 1 and 2 Facility Operating License Nos. NPF-90 and NPF-96 NRC Docket Nos. 50-390 and 50-391
Subject:
Watts Bar Nuclear Plant - Annual Radiological Environmental Operating Report - 2015 Enclosed is the subject report for the period of January 1,2015, through December 31,2015. This report is being submitted as required by Watts Bar Nuclear Plant (WBN) Units 1 and 2, Technical Specification (TS) 5.9.2, "Annual Radiological Environmental Operating Report," and the WBN Offsite Dose Calculation Manual (ODCM), Administrative Control Section 5.1. This report is required to be submitted to the Nuclear Regulatory Commission (NRC) by May 15 of each year. There are no new regulatory commitments in this letter. lf you have any questions concerning this matter, please contact Gordon Arent, WBN Licensing Director, at (423) 365-2004. Respectfully, Paul Simmons Site Vice President Watts Bar Nuclear Plant
Enclosure:
Annual Radiological Environmental Operating Report - Watts Bar Nuclear Plant 2015 cc: See Page2
U.S. Nuclear Regulatory Commission Page 2 May 12,2016 cc (Enclosure): NRC Regional Administrator - Region Il NRC Project Manager - Watts Bar Nuclear Plant NRC Senior Resident Inspector - Watts Bar Nuclear Plant
ENCLOSURE TEN NESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT Annual Radiological Environmental Operating Report Watts Bar Nuclear Plant 201 5
Annual Radiological Environmental Operating Report Watts Bar Nuclear Plant 2015
A}.INUAL ENVIRONMEX\ITAL RADIOLOGICAL OPERATING REPORT WATTS BAR NUCTEAR PLA}.IT 2015 TENNESSEE VALLEY AUTHORITY April 2016
TABLEOF CONTENTS Table of Contents Executive Sumnrary Introduction 2 Naturally Occuning and Background Radioactivity 2 Electic Power Production 3 S itc/Plant Description Radiological Environmental Monitoring Program. Dircct Radiation Monitoring l1 Measutrment Techniques. . . . . ll Results. 12 Atuospheric Monitoring t4 Sample Collection and Analysis. . . . t4 Results. l5 Terrestrial Monitoring l6 Sample Collection and Analysis. . . . l6 Results. t7 Liquid Pathway Monitoring l8 Sample Collection and Analysis. . . . . l8 Resuls. l9 Assessment and Evaluation. . . 2t Results 2t Conchuions 22 References 23 Table I Comparison of Program Lower Limits of Detection with Regulatory Limits for Maximum Annual Average Effluent Consentrations Released to Unrestricted Areas and Repoming Levels. . . . . . . . . . . 24 Figrue I TennesseeValleyRegton. . .,, . . . . . . . . . r ., . . . . . r . . . . . . .. ., . 25 Figure 2 Environmental Exposure Pathways of Man Due to Releases of Radioactive Materials to the Atrrosphgrgandlake,,., . . . . . . . . . . . . . o . . . . . . . . . . . . . . . . .. 26
-i-
TABLE OF CONTENTS (continued) Appendix A Radiological Environmental Monitoring Program and Sampling Locations. 27 Appendix B Program Modifications. 38 Appendix C Program Deviations. 40 Appendix D Analytical Procedures 43 Appendix E Nominal Lower Limits of DeEction (LLD). 46 Appendix F Quality Assurance/Quality Control Program. 51 Appendix G Land Use Sunrey 56 Appendix H Data Tables and Figures 6l aa
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EX(ECUTM SLTMIVIARY This report describcs th Radiological Enviromental MonitoringProgram (REII{P) coducted by TVA in th vicinity of thc Watts BrNuclear Plant (WBN) duing the monitoring period of 2015. The program is conductod in accordance with regulalory rcquircmen6 to monitorthe environmentper 10 CFR 20 ud 10 CFR 50, ad in accordance with TVA procedures. The REMP inshdes the collection ad su@uent determination ofradioactive mafiedal content in environmcntal samples. Various tlpes of smples are collected within the vicinity of the plmt including air, water, milk, food copo, soil, fish, shoreline scdiment and the measrrement of dircct radiation levels. The radiation levels of these samples arp measured and then compared wi& rsults at contol stations located ouEide the plant's vicinity md dala collecrcd d WBN prior to operations (preoperational data). This report contains an evaluation ofthe poteotial impact of WBN operations on the environment and general public. The vast majority ofradioactivity measurod in environmental samples from the WBN prcgram can be contibuted to naturally occuning radioactine materials. low lerrels of Cesium (Cs)-137 wene measurcd in soil and fish smples. The conccntrations wcre gpical of trc lerrels ocpeoted to be prcseirt in the envfuonment fiom past nrrclear weapons tesftrg or opcration of otk nuclear facilities in the region. The frllout from accidents at the Chernobyl plant in the Ukaine in l9t6 and the Fukushima plant in Japan in 201I may have also contibutod to the low levels of Cs-137 measured in e,nvironmental samples. Trace lerrels oftritium wcrc detected in afuospherio moistlre samples. Tritium at corceirtrations slightly above the malytioal detection limit was alsodetcs:tedin$ratersamplescollectedft,omChiokamatrgaRescrvoh Theselerrelswouldnot represent a significant contibution to the rdiation sxposur to members of tb public. Tritiuor uns detccted in onsite gpound $ratff monitoring wells. The tsitium was fte result of onsite gromd water aontamination from previorsly identified md repafued leaks inplmt systcms. In addition, cobalt (Co>60 ad Cs-I37 wele identified in sediment collected tom the onsite ponds. The level of activity measured in these onsite locations would not preselrt a risk of e{xrsur to tbe general public.
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INIRODUCTION This report describes and summarizes the results of radioactivity measurements madc in the vicinity of WBN and laboratory analyses of samples collected in the area Thc measurements are mad to comply with the requirements of 10 CFR 50, Appendix A Criterion 64 and 10 CFR 50, Appendix I, Section IV.B.2, IV.B.3 and IV.C and to determine potential effects on public heatth and safety. This report satisfies the annual reporting requirements of WBN Technical Specification S.9.2andOffsirc Dose Calculation Maoual (OIrcM) Adminishative Conuol 5.1. In addition to reporting the data prescribed by specific requirements, other information is included to help correlate the significance of results measurpd by this program to the levels of environmental radiation resulting from naturally occuning radioactive materials. Naturally Occunins and Background Radioactivity Most materials iu our world today contain tace amounts of nanually occuning radioactivity. Potassium (K)-40, with a half-life of 1.3 billion yearq is one ofthe major types of radioactive materials found naturally in our environment. Approximately 0.01 perrccnt of all potassium is radioactive potassium-40. Other examples ofnaturally occuning radioactive materials are beryllium (Be)"7, bismuth (Bi)-2l2alndzl4,lead (Pb)-2l2and2l4, thallium Cn>208, actinium (Ac)-228,uranium (U>238 and 235, thorium (Ih)-234,radium (Pa)-226,radon (Rn)-222 and 220, carbon (C) -14, and hydrcgen (H!3 (genera[y called tritium). These naturally occuning radioactive materials are in the soil, our foo4 otu 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 cosrnic rays. It is possible to get an idea of the relative hazard of different tpes of radiation sources by evaluating the amount of radiation the U.S. population rcceives from each gencal tpe of radiation souroe. The information below is primarily adapted from Refetences 2 and 3.
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u.s. GENERAL POPULATION AVERAGE DOSE EQLTMLENT ESTII{ATES Source millirem (mrem)t/Year Per Person Natural background dose equivalent Cosmic 33 Terrestial 2t In the body 29 Radon 228 Total 3ll Medical (effective dose equivalent) 300 Nuclear energy 0.28 Constuner products l3 Total 624 (approximately)
- l. One-thousandth of a Roentgen equivalent man (rem)
As can be seen from the data presented above, natural background radiation dose oquivalent to the U.S. population norrnally exceeds that fiom nuclear plmts by several hundred times. This indicates that nuclear plant operations normally result in a population radiation dose equivalent ufrich is insignificant as compared to the dose from natural hckground radiation. It should be noted that the use of radiation and radioactive materials for medical uses has resulted in a similar effective dose equivalcnt to the U.S. population as that caused by natural background cosmic and terrestial radiation. Electric Power Production Nuclear power planf are similar in many respects to conventional coal buming (or other fossil fuel) electical generating plane. The basic prtrce$ behind electical power production in power 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 planq the fuel is uranium and heat is prcduced in the rcactor through the fission of the uranium. Nuclear plants irclude many complex systems to contrrol the nuclear fission procss and to safeguard agsinst the possibility of reactor malfimction The nuclear reactions produce radionuclides cornmonly refened to as fission and activation products. Vcry small amounts of these fission and activation products are rcleased into the plant systems. This radioactive material can be transported throughout plant systems and somc of it may be released to the environment Paths througfu which radioactivity from a nuclear power plant is routincly released arc monitored. Liquid md gaseous efluent monitors record the radiation levels for each release. These monitors also provide alarm mechanisms to prompt trmination of any rclease above limits. Releases are monitorod at the onsite points of release and through the radiological envimnmental monitoring program which measrues the environmental radiatiott in areas around the plant. In this wan the release ofradioactive materials from the plant is tightly conEolled, md 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 effiuents, as well as limis for doses to the general public from the rclease of these efluents. The dose to a member of the general public from radioactive materials released to unrpstricted arBas, as given in Nuclear Regulatory Commission (NRC) guidelines and the ODCM, is limitcd as follows: LiquidEfluents Total body 53 mrem/Year Any organ <10 rnrern/Year Gaseous Effluents Noble gases: Cranmaradiation <10 millirad (mradlYear Beta radiation <20 mrad/Year Particulates: Any organ <15 mrem/Year 4-
The EPA limib for tb total dose to the public in the vicitrity of a nuclear power plmt establishd in the Environmelrtal Dose Stmdad of 40 CFR 190, are as follows: Total body 5P5 mrcm/year Thyroid 5f5 ruem/year Any otherorgan S25 mrcm/year Appardix B to 10 CFR 20 prescnts annual average linits for the concentations of radioactive marcrials rcleased in gaseous and liErid eflrrcnts at the bormdary of the unrestictcd atcas. Table I of this report presents the annual average conccnhation limits for the pincipal mdionuclides associatcd with nuclear powerplant eflrmts. Thc table also preselrts the concentrations of radioactive mxedals in the environment which would requirc a special rcport to the NRC and the &tection limie for measurpd radionculides. It should be noted that thc levels of radioactive materials measurpd in the environmeot are tpically bclow or only slighdy above the lower limit of detection. SITE/PLA}.IT DESCRIPTION The WBN site is located in Rhea county, Tennessee, on the west bank of the Tennesscc River at Tennessee River Mile (TRM) 528. Figrre I shows the site in relation to other TVA projeots. The WBN site, containing approximarcly 1770 acres on Chickamauga Ldre, is approximarcly 2 miles south of the Watts Bar Dam and approximately 3l miles north-northeast of TVA's SequoyahNuclear Plant (SQN) site. Also locarcd within the reservation are the Watts Bar Dam and Hydro-Electic Plant the lVatts Bar Steam Plant (not in opoation), the TVA Cennal Maintenance Facility, and the Watts BarResortArea Approximately 18,500 people live within l0 miles of the WBN sirc. Morc than 80 percent of these live between 5 and l0 miles from the sirc. Two small tolrms, Spring City and Decafir, are located in this area Spring City, with a population of approximatcly 2200, is northwest and north-northwest from tbe site, while Decatu, with about 1,5fi) people, is south and south-southwest from the plant. The remainder of the area within l0 miles of the site is sparsely populatd consisting primarily of small farms and individual rcsidences. The area betrueen l0 and 50 miles from the site includes portions of the cities of Chatanooga and Knoxville. The largcst urban concentration in this area is the crty of Chattanooga, locatcd to the southwest and south-southwesL The city of Chatanooga bas a population of about 170,000, with approximately E0 perce,nt located betrueen 40 and 50 miles ftom the site and the remainder located beyond 50 miles. The city of Knoxville is located to the east-northeast with not morc than l0 percent of its 185,0ffi plus people living within 50 miles of the sitc. Three smaller urbso areas of grarcr than 2O000 people are located between 30 and 40 miles from the sirc. Oak Ridge is approximarcly 40 miles to the northeast, the twin cities of Alcoa and lvlaryville 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 sf highly controlled multiple-usc rpservoirs whose primary uss are flood control, navigation, and the generation of electic power. Secondary uses include industrial and public water supply and waste disposal, fishiry; and rccrcation. Public access araalr, boat docks, and residential subdivisions have been developed along the reservoir shoreline.
WBN consisB of two prcssudzed watff reactors. WBN Unit I received a low power operating license (MF-20) on November 9,1995 ad achieved initisl criticality in Janury 1996. The firll powcr operating liceose (NPF-90) was rpceived on Febnrary 7,1996. Commercial oporation was aohieved May 25, 1996. WBN Unit2 was deferred Octobcr 24,20@,,in accordmce withthc guidance in Generic tttr 87-15, *Policy Statement on Defenpd Plants.' On Augttst 3 ,2007, TVA provided notice of its intent to reactivate and complete oonstruction of WBN Unit 2. WBN Unit 2 resrmed construstion in late 20['7. octoh n,2015 thc operating liccnse was issued"
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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Most of the radiation and radioactivity generated in a nuclear power reactor is contained within &e reactor systems. Plant effluent radiation monitors are designed to monitor radionuclides released to the environment. Environmental monitoring is a final verification that the systems arc performing as planned. The monitoring program is designod to monitor the pmhways between the plant and the people in the immediate vicinity of the plant Sample ty?es are chose,n so that the poteNrtiat for detection of radioaotivity in tre environment will bc maximized. The Radiological Environmental Monitoring hogram (REt IP) and sampling locations for WBN are ouflined inAppendix A. There are twoprimary pathways by uihich radioactivity canmove throughthe environmentto humans: air and water (see Figrre 2). The air pathway oan be separated into nuo components: thc direct (airborne) pathway and the indircct (gFound or terrestrial) pathway. The dirrect airtome pathway consists of direct radiation and inhalation by humans. In the tenesfiial pathway, radioactive materials may be deposited on the ground or on plants and suboeque,ntly ingested by animals and/or humans. Human exposur through the liquid pathlwy may result from drinking watr, cating fish, or by direct eryxlsur at the shorelinc. Thc tlpes of samples collected in this program are designed to monitor these pathways. A number of frctors werc considered in determining the locations for collectiug environmental ru.pi"r. The locations for the atmospheric monitoring stations were determined firom a critical pathway analysis basd on weatherpatterns, dose projections, population distibution, and land use. Terrestrial smpling stations werc seleoted aftEr rcviewing sush things as the locations of dairy animals aod g;ardens in conjunction with the air pathway analysis. Liquid pathway stations were selected based on dose projections, watcr use information, ard availability of media such as fish and scdiment. Table A-2 (Appendix A Table 2: This notation system is used for all tables and figures gven in the appendices.) lists the sampling stations and the t1ryes of samples collectcd from each. Modifications madc to thc WBN monitoring progam in 2015 are rcported in Appendix B. Deviations to the sanrpling program during 2015 are included in Appendix C. To determine the amount of radioactivity in the environment prior to the openation of WBN, a preoperational radiological environmental monitoring program was initiated in Deccmber 1976 and operated through Decembcr 31, 1995. Measurcments of the same tlpes of radioactive materials that are measured cunently were assessed dudng the preoperational phasc to establish normal brckground levels for variow radionuclides in the environment. Dtuing the 1950s, 1960s, and 1970s, atnospheric nuclear weapons testing releascd radioactive material to the environment causing fluctuations in background radiation levels. trhowledge ofpreexisting radionuclide patterns inthe environment permits a dercrmination" though comparison and tending analyses, of the actual environmental impact of WBN operation. The determination of environmental impact during the operating phase also considers the prcsence of contnol stations that have been established in the envitonment" Results of environmental samples talcen at confiol stations (far fiom the plant) are compared with those from indicator strations (nearthe plant) to aid in thc determination of the impocts from WBN operation. The sample analysis is performed by the Tennessee Valley Authority's (fVA's) Environmental Radiological Monitoring and Instrumentation (ERM&I) group located at the Western Area Radiological Laboratory (WARL) in Muscle Shoals, ahbama, orcept for the shontium (SrF89, 90 analysis of soil samples ufrich is performed by a contract laboratory. Analyses arp conductcd in accordance with unimen and approved procedures and are based on accepted methods. A summary of the analysis rcchniques and methodology is presented in Appendix D. Data tables summarizing the sample analysis results are prcsented in Appendix H. The radiation daection devices and analysis methods used to detcnnine 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 qualrty assurance/quality confiol progran to monitor laboratory performance throughout the year. The program is intended to detect any problems in the measurement prosess as sot)n as possible so they can be cotlected. This program includes equipment checks to ensure that the radiation detection instuments are working properly and the analysis of qulity control samples ufrich are included alongside rcutine environmenal samples. To provide for interlaboratory comparison prcgram, the laboratory participates in an environmental cross-check program administcred by Eckert and Zie$er Analytics. A complete desuiption of the program is presented in Appendix F. DIRECT RADI.ATION MONITORING Dfuect radiation levels are measured at various monitoring points around the plant site. These measgrcments include contributions from cosmic radiation, radioactivity in the groun{ fallout from atuospheric nuclearweapons tesb conducted in the past, and any radioactivity that may be present as a result of plant operations. Becarse of the relatively large variations in background radiation as compared to the small levels from thc planq contibutions from theplantmay be difficult to distinguish" Measureme,nt Technioues The Landauer Intight environmental dosimeter is used in thc rdiological environmental monitoriug program for the measurement of direct radiation. This dosimeter contains fotu elements consisting of aluminum oxide deteotors with open wiodows as well as plastic and copper filrcrs. The dosimeter is processed using optically stimulated luminescence (OSL) technolory to determine the amount of radiation exPosure. The dosimeters are placed approximarcly one meter above the ground, with two at each monitoring location. Sixteen monitoring poinb are located around the plant near the site boundary, one location in each of the 16 compass sectors. One monitoring point is also locatcd in each of the 16 compass scctors at a distaoce of approximately four to five miles fromtheplanr Dosimeters are also placed at additional monitoring locations out to approximately 15 milcs from the sirc. The dosimeters are exchanged every three months. The dosimeterc are sentto Lmdauer Inlight forprocessing ad results reporting. The values are corrected for Eaosit and shielded background e4rcsurc. An average of the two dosimeter results is calculated for each monitoring point. The system meets or exceeds fte performancc spccifications outlined in American National Standards Institutc (AIISD N545-1975 md Halth Physics Society (HPS) Draft Sandard N13.29 for environmental applications of dosimeters. WBN Technical Specification 5.9.2, Annual Radiological Environmental O,peratingReport, requires that the ADnual Radiological Environmental Operating Report identify TLD results that represcnt collocatcd dosimeters in relation to the NRC TLD program and the cxposure period
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associared with each result. The NRC collocatcd TLD program was terminated by the NRC at the end of 199,7, thercfore, therp are no TLD results that represent collocatcd dosimetert included in this rport. Resuls The results forenvironmenal dosimetermcasurpments are normalized to a standard quarter (91.25 days or 2190 hours). The monitoring locations ale grouped according to the distance from the planl The first gloup consists of dl monitoring points within 2 miles of the plant. The second goup is made up of all locations greater than 2 miles from the plant Past data have shown that the average results frrom the locations mote +han 2 miles from the plant are essentially the same. Therefore, for purposes of this rporq
*onsite'stations and monitoring points 2 miles or less from the plant are identified as locations greater than 2 miles ate considercd
*offsite.'
The quarterly gamma radiation levels determined from the dosimeters deployed around WBN in 2015 arc $mmarized in Table H-1. The exposuts arc measured in milliroentgens (mR). For purposes of this rport, one mR, one mrm and one mrad are assumed to be numerically equivalent The rounded average aonual exposurles, as measured in 2015, arp shown below. For comparison purposcs, the average direct radiation measurements made in the preoperational phase of the monitoring program are also shoual Annual WBN Average Direct Radiation Levels mR/Year Preoperational 2015 Average Onsite Stations 61 65 Offsite Sations 55 57 The data in Table H-l indicates trat ttre average quarterly direct radiation levels at the WBN onsite stations are approximarcly 1.4 mR/quarter higher tban levels at the offsite stations. This equates to 5.5 mR/year detected at the onsite locations. This value falls below the EPA limit of 25 mrem/year total body. The difference in onsite and offsite averages is consistent wi& levels measured for the preoperation and construction phases of TVA nuclear powcr plant sites ufiere the average lwels onsite were slightly higherthan levels offsite. Figure H-l compares plots of the data from the onsite stations with those ftrom the offsite stations over the period from 1977 thrcugh 2015. The new Landauer Inlight Opucally Stimulatd Luminescence (OSL) dosimeters rvere deployed since 2fi)7 replacing the Panasonic LJD-814 dosimeters ued during the previous years. The data in Table H-2 contains the results of the individual monitoring sanions. The results reported in 2015 arc coruistent with direct radiation levels identified at locations ufiich arp not influenccd by the operation of WBN. There is no indication that WBN activities increased the background radiation levels normally observed in the areas sunounding the plant. ATMO SPHERIC MONITOR]NG The atnospheric monitoring network is divided iuto thrce grcups ideitified as local, perimeter, and remote. Four local air monitoring sations are located on or adjacent to the plant site in the general directions of greatest wind frequcncy. Four perimeter air monitoring stations are located betureen 6 to I I miles from the plant and two air monitors are located out to 15 miles and uscd as contol or baseline statiotrs. The monitoring program and the locations of monitoring stations are identified in the tables and figures of Appcndix A Resuls from the analysis og samFles in the atmospheric pathway are presated in Tables H-3, H.4, and H-5. Radioaotivity levels identified in this reporting period are consistent with background and preoperational program data. There is no indication of an increase in afrospheric radioactivity as a result of WBN operations. Sample Collection and Analysis Air particulates arc collectcd by continuously sampling air at a flow rate of approximately 2 cubic feet per minute (cfu) through a 2-inch glass fiber filter. The sampling systm consisb of a pump, a rnagnehelio gaugc for measrning the drop in pressure across the system, and a dry gas metr to measure the total volume of air sampled" This system is housed in a building approximately 2 feetby 3 feet by 4 feet. The filter is contained in a sarrpling hpad mounted on the outside of the monitoring building. The filter is replaced weekly. Each filter is analfed for gross beta astivity about 3 days afrer collection to allow time for the radon daughters to decay. Every 4 weeks compositcs ofthe filters from each location arc analped by gamma specfioscopy. Craseous radioiodine is samFled using a commercially available carfiidge containing Triethylenediaminc (TEDA)-impregnated chucoal. This system is designed to collect iodine in both the elemenal form and as organic compounds. The cartridge is located in the same sampling head as the air particulate filter and is doumstreanr of the particularc filtcr. The cartidge is changed at the same time as the particulate filter and samples the same volume of air. Each cartidge is analyzed for I-l3l by gamma spectoscopy analysis.
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Afiospheric moisture sampling is conducted by pulling air at a constant flow ratc through a column loadd with approximarcly 400 grams of silica gel. Evcry two weeks, thc column is exohanged ou the sampler. The atnospheric moisttue is rcmoved from silica gel by heating and anal)rzed fortitium. Results The results from the analysis of air particulate samples are summarized in Table H-3. Gross beta activity in 2015 was consistcnt with levels reported in previous years. The average gross beta activity measurd for air particulaG samples was 0.019 pCi/.3. The annual averages of the goss bea activity in air particulate filtrs at these stations for the period 1977-2015 ue presented in Figrre H-2. Increased levels due to fallout from atnospheric nuclear weapons testing arc evident in the years prior to l98l and a small increase ftom the Chemobyl accident can be seen in 1986. Thcse patterns are consistent with data from monitoring programs conducted by TVA at other nuclear power plant conshrction sircs. Comparison with the same data for the preoperational period of 1990-1995 indicates that &e annual average gross beta activity for air particulates as measured in the 2015 monitoring program was consistent with the preoperational data Only natural radioactive materials were identifid by the monthly gamma spectral analysis of the air particulate samples. As shoum in Table H-4, I-l3l was not detected in any charcoal cartridge samples collected in 2015. The results for atuospheric moisture sampliug are reported in Table H-5. Tritium was measuted, above the nominal LLD vatue of 3.0 pCi/m3, in atmospheric moisturc samples from the indicator and control locations. The highest concentration from the indicator locations rvas 26.4 pCi/m3. The highest conceirtration from the contrrol locations was 5.5 pCi/m3.
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TERRESTRI,AL MONITORING Tenstrial monitoring is accomplishcd by collecting smples of envircnmental mediathat may transport radioactive matsrial fiom the atmosphcre to humans. For examplg radioactive matedal may be dcposited on a vegetable garden and be ingestd along with the vegetables or it may be dposited on pastre grass whu,e dairy cattle are grazing. Whn the cow ingests the radioactive matdal, some of it may be tansfemd to the milk ad consnrmed by humans rryfu drink the milk Therefore, samples of-ilk, soil, ud food crops are collected aDd analyzed to determine poteNrtial impacts ftm exposure through this pathway. The results fiom tbe aoalysis of these samples uc shorrn in Tablcs H-6 thrct4h H-ll. A land use suney is conducted annually behveen April and October to identi& tb location of the neuest milk enimal, the neuest residence, and the nearcst garden of greater tha" 5fi) squrc feet producing fiesh bary vegetables in each of 16 meteorological sstors within a distance of 5 miles from the plant This land use suney satisfies th requirements 10 CFR 50, Appendix I, Sec{ion ry.B.3. From data produced by the land use survey, radiation doses ar projected for individruls living near the plant Doses frrom air submersion are calculaEd for th nearestresidence in each scctor, while doses fron &inlingmilkoreating foodspiroducednear theplant are calculdedfortheareaswithmilk-producing mimals and gpdn$ rcspcctively. These dose projections ue hpothetical exhcmes and do mt represent actul doses to th general public. The resuls of the 2015 land use $rrvey are presented in Appendix G. Sample Collection and Analysis Milk samples ae collected ev,rytnlo rryeeks fiom two indioatordairies ad fiom atleastone contnol dairy. Milk suples are placed on ice for tansport to tre radioualytical labordory. A radiochemical sepantion analysis for I-l3l md a gamma speo:tral analysis ae performed oa each qpmple md Sr-89,90 analysis is performed quutdy. The monitoring prognm includcs a provision for sampling of vegaation fiom locations where milk is being prodrcd and u&en milk sampling camot be conducted" There werc tro pcdods duing this year ufien vegetation smpling was necessary. Soil samples are collected annually from the air monitoring locations. The samples are collected with either a "cookie cuttetor an auger tlpe sampler. After drying and grinding; the sample is anal),zed by eamma spectroscopy and for Sr-89 and Sr-90. Samples representative of food crops raiscd in the arca near the plant are obtained from individual gardens. Types of foods may vary from year to year as a result of changes in the local vegetable gardens. Samples of com, green beans, tomafioes, and tumip grens were collected from local vegetablq gardens and/or fams. Samples of the same food products grown in areas that would not be affected by the plant werc obtained from areaproduce markets as contr:ol samples. The edible ponion 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 I-131 values werc below the established nominal LLD of 0.4 pCi/tircr. The gamma isotopic analysis detected only natrally occurring radionuclides. The results for the quarterly Sr-89 and Sr-fl) analyses were below the established LLD's for these analyses. Consistent with most of the envirormenl Cs-137 was detected in the majority of the soil samples collected in 2015. The maximum concentation of Cs-I37 nnas 0.56 pC;ilg. The concentations were consistent with levels previously reported from falloul All other radionuclides reported werp naturally occuning isotopes. The resulB of the analysis of soil samples are summarized in Table H-7. A plot of the annual average Cs-137 concentrations in soil is presentcd in Figure H-3. Concentrations of Cs-137 in soil are steadily decreasing as a result of the cessation of weapons testing inthc atnosphcre, the 30 year half-life of Cs-l37,aldEa$port through the envirorunent. The radionuclidcs measured in food samples werc naturally occuring. Thc resulg arc reported in Tables H-8 through H-l l.
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LIOUID PATHWAY MONITORING Porcndd exposurcs from the liquid pathrvay can (rccur from drinking watr, ingestion of fish, or from direct radiation exposur from radioactive rnarcrials deposited in the shoreline sodiment The aquatic monitoring program includes the collection of samples of river Gurface) water, ground watr, &inking water supplies, fish, and shoreline sediment. Indicator samples were collected downsheam of the plant and control samples collected within the reservoir upstream of the plant or in the next upstream rcservoir (Watts Bar Lalce). Sample Collection and Analysis Samples of surface water are collected ftom the Tcnnessee River using automatic sampling systemsfromtwodorrynstramstationsandoneupsfieamstation. Atimerturnsonthesystemat least once every two hours. The line is flushed and a sample is collected into a composirc container. A one-gallon sample is rcmoved from the container at 4-week interrrals and the remaining watcr is Oscaraea. Each sample is aoalyzed for gamma-emiuing radionculideq goss beta activity, and Eiti,'m. Samples are also collected by an automatic sarpling system at the first two doumstream drinking water intakes. These samples are collected in fte same manner as the surface water samples. These monthly samples are analyzed for g:amma+mitting radionuclides, gross betaactivity, and uitium. The samples collected by the automatic sampling derrice are taken directly from the river at the intalce structur. Since these samples are untneatod rmter collectcd at plant intake, the ups$eam surface water sa-ple is used as a conEol sample for drinking water. Crround water is sampled firom one onsirc well down gradient from the plan! one onsite well up gradient from the planq and four additional onsite glound watermonitoring wells located along underground discharge lines. The onsite wells are samplcd with a continuous sampling systern. A composite sample is collected from the onsite wells every four weeks and malpcd for garma-mitting radionuclides, grosn beta activity, and titium content Samples of commerpial and game fish species are collected semiannually from each oftwo rcscrvoirs: the rcservoir on which the plant is located (Chickamauga Resenoir) and the
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upstream rcseryoir (Watts Bar Reservoir). The samples are collectcd using a combination of netting techniques and elecbofishing. The ODCM specifies analysis of the edible portion of the fish To comply with this requirement filleted portions are talcen fiom several fish of each species. 1Xs samFles are analyzed by gam-a spectroscopy. Samples of shoreline sediment are collected from recreation arcas in the vicinity of thc plant The samples are drid, groun4 and analyzed by gamma spechoscopy. Samples of sediment are also collected from the onsite ponds. A total of five samples were collected in 2015. The samples arc drieq grorm( aod analfzd by gamma spechoscopy. Results Gross beta activity was detectable above the nominal LLD in most ofthe surface water semFlos. The gross beta concentrations averaged 2.5 pCi/liter in doumsheam (indicator) samples and2.4 pCi1I- in upsbeam (conrol) samples. These levels wrre consistent with results found during the prcopcrational monitoringprogram. The gammaisotopic analysis of surface watersmples identified only natunlly occuning radionuclides. Low levels of titium were detected in most surface water samples. The highest tritium concenfiation was 1,670 pCi/liter which is signfficantly below the EPA drinlcing water limit of 20,00 pCi/Iiter. A sumrnary trble of the rcsults for surface water samples is shown in Table H-12. The aonual average gross beta activity in surface water samples for the penod 1977 through 2015 are presentod in Figurc H4. No fission or activation products were identified by the gamma analysis of drinking water samples from either oftwo downstream monitoring locations. Average gross beta activity at dorvnstneam (indicator) stations was2.2 pCi/Iiter and the average for the upstram (contol) station was 2.4 pCiniter. Low levels of tritium were detected in most samples collecrcd from the two downstream public watr sampling locations. The highest titium concenfiation was 1,070 pCi/liter. The titiunr levels werc significantly below the EPA drinking water limit of 2O000 pCiAiter. The results arp shown in Table H-13. TrEnd plots of the gross beta activrty in drinking water samples fioml977 through 2015 are presented in Figurc H-5. The g;amma isotopic aoalysis of ground water samples identified only naturally occuning radionuclides. Grcss beta concentrations in samples from the onsite indicator locations averaged 2.9 pCi/Iiter. The average gross beta activity for samples from the confiol locations was 2.8 pCi/titer. Tritium was detectcd in samples from the onsite monitoriag wells located near plant discharge lines. The titium in onsitc glound 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 acrcss the site toward the river. The highest titium conceutration in samples from these monitoring locations was 1,440 pCi/Iiter. There was no titium detected in the onsite up gradientwell orthe offsirc ground water monitoring location. The resule are presented in Table H-14. Cs-137 was identified in one fish sample. The Cs-I37 concentration was 0.03 pCi/g measured in game fish collected at the upsheam location. Other radioisotopes found in fish were naturally occurring, with the most notable being K-{0. The resulg are sumrnarized in Tables H-15 and H-
- 16. Trend plots of the annual aver?ge Cs-137 concentradons measured in fish samples are presented in Figure H{. The Cs-137 activities arp consistent with preoperational results produced by fallout or eflluents from other nuclear facilities.
No fission or activation products were detecte4 above the nominal LLD, by the g;amma analyses performed on shorcline sediment samples. The results for the analysis of shoreline sediment are presented in Table H-17. Trend plots ofthe average concentration of Cs-137 in shorline sediment are presented in Figurc H-7. Consistent with prcvious monitoring conducEd for the onsite pon&, Cs-137 was detected in the sediment samples. The average of the Cs-137 levels measurd in sediment from the onsitc ponds was 0.10 pCi/p. In addition" Co-60 uas also detected in some of the samples collected from the onsite ponds. The average of the Co-60 levels measured in sediment from the onsite ponds was 0.08 p0Ugq. The results for the anatysis of pond sediment samples are provided in Table H-l8. Since these radionuclides wene prBcnt in relatively low concntrations and confind to the ponds located in the owner controlled area not opcn to the general public, the pesence of these radionuclides would not reprcsent an increased risk of exposnrc to the gcneral public. ASSES SMENT A}.ID EVALUATION Potcndal doses to the public are cstimated fiom measurd efluents using oomputer models. These models were developed by TVA and are based on guidance provided by the NRC in Regulatory Guide l.l(D for determining the potential dose to individuals and populations living in the vicinity of the plant. The results of the efluent dose calculations are reported in the Anrusl Radiological Effluent Release ReporL The doses calculatod are a representation of the dose to a"Eardmum exposed individual." Some ofthe factors usd inthese calculations (such as ingestion rates) alE modm"m expected values which will tend to overestimarc the dose to the "hlryothetical'person The calculated maximum dose due to plant cfluents arc small fractions of the applicable regulatory limits. In reality, the expected dose to actual individtuls is significantly lower. Based on the very low concentations of radionuclides actually prcsent in the plant efluents, radioactivity levels measured in the environment as rcsult of plant operations, are expected to be negligible. The results forthe ndiological environmental monitoring conducted for WBN 2015 operations confitm this expectation Results As statd earlier in this rcpoft, the estimated increase in radiation dose equivalent to the general public resulting from the operation of WBN is insignificant when compared to the dose fiom natural background radiation. The results from each environmental sample are compared with the concentrations from the conesponding contnol stations and appropriate preoperational and background data to determine influences from the plant. During this report perio4 Cs-137 was debcrcd in soil and fish collected for the WBN progam. The Cs-137 concentations wete consistent with levels measurod during the preoperational monitoring program. The levels of titium measured in watcrsamplcs from ChickamaugaReservoirrepresented concentations that were a small fraction of the EPA drinking water limit. The levels of tritium detected in the onsirc ground wffer monitoring wells and the radionuclides measured in samples of sediment from the onsirc ponds do not represent an incrEased risk of ab
exposure to the public. These radionuclidcs were limited to the owner contolled area and would not prsnt an exposure pathrvay for the general public. Conchsions It is concluded from the above analysis of cnvironmenal samples and from the hend plots presented in Appendix H, that exposur to membcrs of the general public which may have been attibutable to WBN is negligible. The radioactivity reported herein is prirnarily the result of fallout or natural background. Any activity which may be prsent in the environmcnt as a result of plant operations does not rcprcsent a significant contribution to the oeosure of me,mbers of the public. REFERENCES
- l. Memil Eisenbu4 Environmental Radioactivitv. Academic Press, Inc., New Yorlq NY, 1987.
- 2. National Council on Radiation Protection and MeasuremenB, Report No. 160, "Ionizing Radiation Expoune of the Population of the Unitd Stafs,'March 2009.
- 3. Unitd States Nuclear Regulabry Commission, Regulatory Guide 8.29, "Insfiuction Concerning Risls from Occupational Radiation Exposute,' February 1996.
Table I COMPARISON OF PROGRAM I.oWER LIMITS OF DBTECTION WITII THE REGULATORY LIMITS FOR M.NXIMUM ANNUAL AVERAGE EFFLUENT CONCENTRATIONS RELEASED TO I,'NRESTRICTED AREAS AI{D REFORTING LEVELS ConcenEations in W-ater. pCi/Liter Coneenfrations in Air. pCi/Cubic Meter Effluent Reporting lower limit Efrluent Reponing [ower limit Analvsis Concenhationr Levell of Dercction3 Concenuationl Levell of Detection3
-l-H-3 1,000,000 20,000 270 100,000 -- 3.00 Cr-S1 500,000 .- 45 30,000 -- 0.02 Mn-s4 30,000 1,000 5 1,000 -- 0.005 Co-58 20,000 1,000 5 1,000 -- 0.005 Co-60 3,000 300 5 50 -- 0.005 Zn-65 5,000 l0 400 -- 0.005 Sr-89 8,000 :-oo 5 1,000 - 0.001I Sr-90 s00 2 6 x 0.0004 Nb-95 30,000 iro 5 2,000 .. 0.005 7r-95 20,000 400 l0 400 -. 0.005 Ru-103 30,000 5 900 -- 0.005 Ru-106 3,000 .O 40 20 -- 0.02 l-13 I 1,000 2 0.4 200 0.9 0.03 Cs-134 900 30 5 200 l0 0.005 Cs-131 1,000 50 5 200 20 0.005 Ce-l44 3,000 -- 30 40 -- 0.01 Ba-140 8,000 200 25 2,000 -- 0.015 L.a-140 9,000 200 l0 2,000 -- 0.01 Note: I pCi = 3.7 xl0a Bq.
Note: For drose reporting levels that are blank, Do value is given in the referpnce.
- l. Source: Table 2 of Appendix B to 10 CFR 20.1001?:02401
- 2. Source: WBN Offsite Dose Calculation Manual, Table 2.3A.
- 3. Source: Table E-l of this rEport.
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trUCLEAR PI-A,IIT SEOUOVAH mrCLEeR PLATIT i \( l I H- - SELLEFO]IITE ilI'CLEAN PLATIT BROUIIS FEffiY ilUCLEAR PLATlT I I I i \
Figure 2 Enl\,IHONn,IENTAL E)(FCIEUHE FAT}Iri,AYA ClF OUE TO FELEABEE OF IIAEISA!:TT\,E ilIATEEIAL ?O T}IE ATtrICIEFHEEE AnlEI LAI(E. Airborno BeleasGs
\f Plume ErDosure Liquid Beleases Diluted By Lahs MAN Gonsumed By ffian AEimals Itillt,teatl Shoreline ExDosulG cooQrru BU Animals Ilrinkins Water Fish Uegetation Uptake From Soil APPENDIXA RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM A}.ID SAIUPLING LOCATIONS a7-
Table A-l WATTS BAR NUCLEAR PLAI{T RADIOLOGI CAL EN VIRON MENTAL MON ITORING PROGRAM. E:rposure Pathway Number of Samples and Sampling and Tlpc and Frcquency and/or Sanrple Locationso Co[ection Freguency of Analysis I. AIRBORNE a Particulates 4 samples from locations (in diftrent Continuou sampler opcration wiflt Analyze for gross beta radioactivity sctors) at or ner llrs sitc boundary samplc collection weekly (more gratsr than or equal to 24 hours (LM-1,2,3, and 4). (tequently ifrequired by dust following filter change. Perform loadi.g). gamma isotopic analysis on each sample if gross bea is greater than l0 times yearly mean of control sample. Composite at least once per 3l days OV location) for gamma scan. 4 eaqples fiom communitics approximatcly 6-10 milcs fiom the plant (PM-2, 3,4, and 5). 2 samples fiom conCIol locations geater ftan l0 miles from the plant (Rtvt-2 and 3).
- b. Radioiodine Samples fiom sarne locations r air Continuors sampler operafion with I- l 3 I at lcast onco pcr 7 days.
particulates. filter collection weekly. Analysis is performed by ganuna specEoscopy.
- c. Abospheric 4 samples from locations (in different Continuous sampleroperation with Analya each sample fortritium.
Moisnnc scctors) at or rcarthe sie bormdary sample colkction biweekly. (LM-I,2,3, andl) 2 sarylcs fiom commrmitics approximately tl-10 miles distance tromtheplant(PM-a 5). a8-
Table A-l WATTS BAR NUCLEAR PLAI.IT RADIOLOGICAL ENVIRONMENTAT MONITORING PROGRAN{. Exposure Pathway Nurnber of Samples and Sampling and Type and Freguency and/or Sample Irqgationsb Collection Frequency of Analysis
- c. Affiospheric 2 samples from control location Moisture (Cont.) greater tlran l0 miles from the plant (RIVI-2 and RM-3).
- d. Soil Samples fiom same location as air Once pcr year. Gamma scarL Sr-89, Sr-90 onoe per particulates. year.
- 2. DIRECT 2 or mons dosimeters placed at or At least once per 92 days. Gamma dose at least once W 92 near the site boundary in eash of the days.
l6 sectors. 2 or more dosirneters placed at stations located approximately 5 miles from the plant in each of the l6 sectors. 2 or morc dosimeters in at least 8 additional locations of special intercsq including at least 2 conEol stations. a9-
Table A-l WATTS BAR NUCLEAR PLA}.IT RADIOLOGICAL EN V IRON MENTAL MON ITORIN G PROGRAIvI' Exposure Pathway
- Number of SamPles and Sarnpling and TWe and Frequency and/or Sample Locationib Collection Frequency of Analysis
- 3. WATERBORNE
- r. Surface 2 samples dormstream from plant Collectcd by automatic sequential- Gross beta, gatnma 8can, and titium discharee (TRM 517.9 and fRM tpe samplef with composite samples analysis of caci sample.
523.1). collected over a period of approximately 3l days. I sample at a confiol locadon upstnesm from the plurtdischarge (TRM s293).
- b. Ground Five sampling locdions from ground Collected by automatic sequential- Grcs bcta, gatnma scu, ud tritium wator monitoring wells a{iac,ent to the tpe saryler with corrpositc samples analysis of eaci sample.
phnt (Wells No. l, & B, C, atrd F). collccled overa peri,od of y3l days. I sample ftom gound water source Same as Well No. l. Gross beta, gamma scan, and tritium up gradient (Well No. 5). analysis of each sample.
- c. Drinking I ourphatthefirsttwopotable Collecrcdbyautomaticscqucndal- Grcsbcta,gammascan,andtridum surfrce water supplies, downstseam t1rye sanrplcf with compositc sample analysis of each samplc.
fromthe plant$RM $3.t andTRM collecedmonthly. 473.0). I omple at a comol locaion TRM 529.3d. Table A-l WATTS BAR NUCLEAR PLA}.IT RADIOLOGICAL MAL MONITORING PROGRAM. Exposure Patrway Number of Samples and Sampling and Ty?e and Frequency and/or Sample LogFtionsD Collection FrcgEpncI of Anqlysie d" Scdirnent from I sarnple dornstcam fiom plam At lcast once per lt4 dap. Gamrna scan of each sarnple. Shorclinc Dischargp (IRM 513.0). I saryle from a control locatiom upsEsam from plant dischargc (TRM 5302).
- e. PondSediment I samphfiommleastdrcelocadons Atleastonceperyear. Gammascmofcadrsample.
in thcYrrd HoldingPmd.
- 5. INGESITION a Milk I sampleftommilkp,roducinganimals Every2wcckr. I-l3l mdgammaanalyeisoneach in eacb of l-3 ms indicred by thc samplc. Sr-t9 and Sr-90 oncc pcr oow ormu! werr &ces are calculmcd $urter.
to be highoce I ormmc sarnplcs fiom oontrol locadons.
- b. Fish otrc sample ofcommaclally iquont At lcast orce pet lta ds! s. Gamna scan or edible portions.
3pccks lnd onc camplc of rcctcadonatty impofint specie. One sample of each spccics fim Chidomeug and nrffB BarRescryoir:.
.3l-
Tablc A-l WATTS BAR NUCLEAR PI.A}.IT RADIOLOGICAL ENVIRONMENT,{L MONITORJNG PROGRAM E:tposurc Pathway Numbu of Saurples and Saryling and Type and Froquency and/or Sample LocationsD Collection Frequency of Analysis
- c. Vegetation' Samplesfiomfrrmsproducingmilk Atleastonccper3l days. I-l3l analysisandEammascanof (Pasturagp ard but not providing a milk saorple. each samplc.
grass)
- d. FoodPnoductr Isamplceachofprirrcipalfood Annuallyattimeofhanrest Thc Gammascanonedibleportion.
products grown atpdvate gmdeos types of foods availabh for sampling and/or frrms in thc immediate will vtry. Following is a list of vicinity of the plant. tlpical foods which may be arnailable: Cabbage, Lettuce and/or Grcens Corn Grcen Beans Potatoes Tomatoes a The sampling program outlinod in this able is that which was in eftct at thc end of 2015.
- b. Sarnple locations arc shown on Figtres A-1, A-2, A-3.
- c. ltamplesshallbecollctedbycollectinsurdlquotatintorvalsnototcocding2hours.
- d. The samples collectcrt at TRMs 503.t and 473.0 are taken fiom the r8w watGr supply, thcrtfott, the rpstream surfroe water samplc will be coosidered the contol sample for &inking rmter.
- e. Vcgetation sampling is applicable only for farms that mect fre crirria for milk sampling and when milk sarnpling canmt be pcrfcd" Tablc iA WATTS BAR NUCLEAR PLAI{T RADIOLOGICAL ENV IRONMENTAL MON ITORIN G PROGRAM SAI,TPLING LOCATTONS Map Approximate Indicator (t)
Location Distance or Samples Numbef- Station Sector (Miles) Conhol (C) Collectcdb-2 PM.2 NW 7.O AP,CF,S,Af,{ 3 PM.3 NNE 10.4 AP,CF,S 4 PM-0 NE/ENEE 7,6 AP,CF,S 5 PM.5 s E.0 AP,CF,SAII{ 6 Rll-2 sw 15.0 c AP,CRS,AII 7 RIvl-3 NNW 15.0 c AP,CRS,AfuI t LM.I ssw 0.5 AP,CF,S,A!t{ 9 LM.2 NNE 0.4 AP,CF,S,AI\,I r0 LM.3 NNE l.g AP,CF,S,AM ll LM4 SE 0.9 AP,CF,S,A[t4 t5 Farm K ENE I1.6 C M It Well #l s 0.6 I w 20 Farm N ESE 4.1 t M 23 Well #5 0.5 c w 25 TRM 517.9 g.f I sw 26 TRM 523.1 4.?n I sw 27 TRM 529.3 : l.5d c sw,Pwo 3l TRM 473.0 54.Ed I PW (C.F. Indus0ies) 32 TRM 513.0 --- l4.gd t SS 33 TRM 530,2 2.4n c ss 35 TRM 503.E 24.0n I PW (Dayton) 37 TRM 522.t-527.E T F (downstrcam of WBN) 38 TRM 471-530 I F (Chickamauga lake) 39 Watts Bar Rcservoir c F 8l Yard Pond ssgslssw Onsitc PS t2 Well A ssE 0.6 w 83 Well B ssE 0.5 w t4 Well C ESE 0.3 w t5 Well F SE 0.3 w t6 Farm HH ssw 1.75 M t7 Fann BB sw 18.6 M a Sce Figures A-1, A-2, and A-3
- b. Sarnple codes:
AItt = Atmosphcric Moisure AP = Air particulate filter PW = Public Watcr SS = Shorcline sedimcnt CF = Charcoal filtcr PS : Pond Sedimcnt SW = Surhe watcr F = Fistt S =t Soil W = Wcll watcr M = Milk G. Station located on the boundary bctrrcen these two ssstots.
- d. Distance fiom ttre plant discharge (TRI{ 527.t)
- e. The nrrfacc watcr sample is also used as r control for public water.
'33-
Table A-3 1T'ATTS BAR NUCLEAR PLAI{T ENVIRONMENTAL DOSIMETERS LOCATIONS Map' Approximatc Onsite (On)b Location Distance or Numbsr Station Scctor (Miles) Otrsitc (Otrt 2 NW-3 NW 7.0 otr 3 NNE-3 NNB 10.4 off 4 ENB3 NETENE 7.6 otr 5 s-3 s 7.9 otr 6 sw-3 sw 15.0 off 7 NNW4 NNW 15.0 off r0 NNE.IA NNE l.g On It SE.IA SE 0.9 On t2 ssw-2 ssw 1.3 On l4 w-2 w 4.E otr 40 N-l N 1,2 On 4l N-2 N 4.7 otr 42 NNE.I NNE 1.2 On 43 NNE-2 NNE 4.1 otr u NE.I NE 0.9 On 45 NE.2 NE 2.9 off 46 NE.3 NE 6.1 otr 47 ENE.I ENE 0.7 On 48 ENE.2 ENE 5.t otr 49 E-t E 1.3 On 50 F-2 E 5.0 off 5l ESE.I ESE 1.2 On 52 ESE-2 ESE 4.4 otr 54 SE.2 SE 5.3 otr 55 ssE-lA ssE 0.6 On 56 ssE-2 ssE 5.8 otr 57 s-l S 0.1 On s8 s-2 s 4.9 off 59 ssw-l ssw 0.E On 60 ssw-3 ssw 5.0 otr O sw-l SW 0.t On 63 sw-2 sw 5.3 off
& wsw-l wsw 0.9 On 65 wsw-2 wsw 3.9 otr 66 w-l w 0.9 On CI wNw-l wNw 0.9 On 6E wNw-2 wNw 4.9 otr 69 NW-l NW l.l On 70 NW-2 NW 4,7 off 7l NNW-I NNW 1.0 On 72 NNW.2 NNW 4.5 otr 73 NNW-3 NNW 7.0 otr 74 ENE.2A ENE 3.5 otr 75 SE.2A SE 3.1 otr 76 s-2A s 2,0 off 7? w-2A w 3.2 otr 7t NW-2A NW 3.0 off
?9 SSE-I SE 0.5 On a Scc Figurcs A-1, A-2, and A3.
- b. Dosimctcrs declgnalcd'onsltc" rrc localcd 2 milcs or lcss from thc plarq,'oftitc' arp locard morc than 2 mllc fromthcplant Figure A-1 Radiological Environmental Sampling Locations Within I Mile ofthe Plant 303.75 56.25 WNW ENE 201.25 78.75 WATTS BAR w NUCLEAR PLANT E 258.75 lo I ,25 w ESE 123.75 Figrrre AA Radiological Environmental Sampling Losations From I to 5 Miles From The Plant
'36'
Figure A-3 Radiological Environmental Sampling Locations Greater Than 5 Miles From the Plant 348.75 lt I1.25
-l-o3tot6e02E lflor
-3?-
APPE}IDD(B PROGRAMMODIFICATIONS Appndix B Radioloqical Environmental Monitoring Program Modification Bacon Farm (Farm BB) was added to the REMP program during 2015 to rrplace the loss of tlre milk sampling location identified as Fam EH. (Farm EH slosed operations duing 2014.) The farm identified as Farm K closed its operation in March, 2015. However, it was officially removcd from the REMP program at a later date. Both Farm EH and Farm K were contol milk locations. The chaoges ane reflected in the Tables and Figrrrcs of Appe,ndix A ofthis rcport APPENDD(C PROGRAN{DEMS AppendixC Prosram Deviations Problems with low moisture rsultcd in 5 missed ahospheric samples. The samples were collected but unable to be analyzed due to the low moisturp content. In addition, 3 sets of dosimeters were missing at the time of change out during 2015. Table C-l provides additional information onthe missed samples. Areviewofthe daails ofthe program deviations didnot identi$ any adversc fiend in equipmentperformance. 4l-
Table C-l Radiological Environmental Monitoring ProEmam Deriations Date Station Location Sample Tlpe Description 0?n3n0r5 3102 1.3 miles SSW Atnospheric Five samples werc unable to be 3106 Moisn[e analyzed due to low moisture contsnl 3109 The problem was identifid in CR 3205 1004980. 05/r Er20 l5 3298 15 miles SW Aunospheric One sanrple was unable to be analyzed Moisture due to low moistutp content. The problem was identified in CR 1035389. 3'd er 2ots r9 Dosimeter While performing quarterly dosimeter WB-NNW-3 change ouq it was discovered that the monitoring station 19 in the NN1V sector had bcen disturbed. The OSLs had been knocked to the ground while Volunteer Elecric was removing a pole about 2 feet alvay ftom the station. The OSLs where later mowed over by ground cnews. One dosimeter was located but suffered damage and the other could not be found. This problem was identified in CR 1095655. 3d er 2ol5 42 Dosimeter Both dosimeterc wert found missing WB.ESEA during the quartef change out and could not be located after extensive search. It appearc the fence that horced ttre dosimeterc had been upgfaded and the dosimeters may have been lost at this time. The issue was documented in cR 1095663. 46 Qtr 2Ot5 38 Dosimeter Two dosimeterc located at station 38 WB.NNEA WB-NNEA were missing. A search of the area did not result in locating the dosimeterts. The cage and protective sleeve that hold the dosimetem wene found approximately 15 feet away from the station. fire station was rrupaired and the new dosimeters werc attached. This issue was identified in CRI 129753. 42-
APPEI{DD(D AI{ALYTICAL PROCEDTJRES 43-
Appendix D Analytical Prosedurcs Analyscs of environmental samples are perfonned by th radioanalytical laboratory located at the Western Area Radiological Laboratory facility in Muscle Shoals, Alabarna, except for the Sr-89, 90 analysis of soil samples which was performed by a contract laboratory. Analysis procedures are bosed on accepted methods. A summary of the analysis techniques and methodology follows. The gross betameasurements are made with an automatic low background counting system. Normal counting times are 50 minutes. Water samples are prepared by evapor*ing 500 mi[iliter (ml) of samples to near drymess, tansfening to a stainless steel planchcg and completing thc evaporation prtrcesll. Air particulatc filters arc cotmted directly in a shallow planchet. The specific analysis of l-l3l in milk is performed by first isolating and puriffing the iodine by radiochemical separation and then counting the final precipitate on a beta-gamma coincidence cormting system. Ihe normal count time is 50 minutes. With the beta-garuna coincidence counting system, backgrormd counts are virtually eliminated and exbemely low levels of activity canbe detected. After a radiochemical separation" milk samples analyzed for Sr-E9, 90 are counted on a low background beta counting system. The sample is counted a second time after a minimum ingowth period of six days. From the two couts, the Sr-89 and Sr-90 concentations can be determined. Water samples are analyzed for titium content by fust distilling a portion of the sample and then counting by liquid scintillation. A commercially available scintillation coclctail is used. Gamma analyscs arc performed in various counting geometries depending on the sample tlpe and volume. All gamma counts arc obtained with germmitrm t1rye detectors inrcrfaced with a high resolution gamma spectnoscopy system. 44-
The charcoal cartridges trsed to sample gaseous radioiodine arc analped by ganrma spectroscopy using a high resolution gamma spechoscopy system with germanium detectors. Atuospheric moisture samples are collectcd 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 cochail. The necessary efficiency values, weight-cfficiency curyes, and geomctrytables are establishedand maintaind on each detector and counting system. A series of daily and periodic qualrty con&ol checlcs are performed to monitor counting instnrmentation. System logbooks and contnol cbarts are used to document the results of the qualrty control checks. 45-
APPEhUDD(E NOMNAL LOWER LIMITS OF DETECTION 46-
Appendix E Nominal l,ower Limits of Detpction A nrmber of factors influence the Lower Limit of Dercction (LLD), including sample size, count time, counting efficienoy, chemical pnooesses, radioactive decay factors, and intcrfering isotopes encountered in the sample. The most probable values for these facton have been evaluated for the various analyses performed in the environmental monitoring program. The nominal LLDs are calculated in accordance with the methodologr prescribed in the ODCM, are presented in Tablc E-1. Thc maximum LLD values forthe lower limits of detection specified in the ODCM arp 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 deterrrining if a measured activity is grearcr than the LLD. In these cases, the LLD value will appear as -1.00E+00 in the data tables in AppendixH. 47-
TABLE E.I Nominal LLD Values A. Radiochemical Procedures Sediment Air Filters Water Milk Wet Vegeution and Soil fuialvsis (pCi/m3) (pCi/L) (pci/L) @Ci/lcg wet) (pCi/g dry) Gross Bea
-a-0.002 l.g -- --
Tritium 3.0 270 -- -- Iodine-l3l 0.4 0.4 6; Snontium-t9 0.001 I 5.0 3.5 31.0 ; Shontium-90 0.0004 2.0 2,0 12.0 0.4 Table E-l Norninal LLD Values B. Gamma fuialyses Foods Particulate Charcoal Water Vegetation Wet Soil and Tomatoes Filter Filter and Milk and Grain Vegetation Sediment Fish Clam Flesh Potatoes, etc. Analysis -pCi/m3- pCi/m3 pCilL pCilg dry pCifts. wct pCilg dry pCi/s dry gQ!b-@ pCitkg wet Ce-14l .005 0.02 l0 .07 35 .35 20 Ce-l44 .01 0.07 30 .15 ils .85 60 Cr-51 .o2 0.15 45 .30 240 2.40 9s l-13 t .005 0.03 l0 .20 60 1.70 20 Ru-103 .005 0.02 5 .03 25 .25 2s Ru-l06 .02 o.l2 40 .t5 190 1.25 90 Cs-I34 .005 0.02 5 .03 30 ,14 l0 Cs-137 .005 0.02 5 .03 25 .15 l0 Zr-95 .005 0.03 l0 .05 45 .45 45 Nb-95 .005 0.02 5 .25 30 .25 l0 Co-5E .005 0.02 5 .03 20 .25 l0 Mn-54 .005 0.02 5 .03 20 .20 l0 Zrrti .005 0.03 l0 .05 45 .40 45 Co-60 .005 0.02 5 .03 20 .20 l0 K40 .04 0.30 r00 .40 400 3.50 250 Ba-140 .015 0.07 25 .30 130 2.40 50 [.a-140 .01 0.04 l0 .20 50 1.40 25 Fe-59 .005 0.04 l0 .08 40 .45 25 Be-? .02 0.15 45 .25 2AO t.90 90 Pb.2I2 .005 0.03 l5 .04 40 .30 40 Pbzl4 .005 0.07 20 .50 80 .10 t0 BiAr4 .005 0.05 20 .10 5s .50 40 Bian .02 0.20 50 .25 250 2.00 130 TlaOE .002 0.02 .o: ,j ,: ,j Rtu'2j]4 l: R*226 -- -- - Ac-?i28 .01 0.07 20 .10 70 .10 .75 50 Pa-234m - 800 49-
Table E-2 Morirnum LLD Values Specified by the WBNOTrcM Airborne Particulate Food Water or Gases Fish Milk Pnoducts Sediment Anal)'sis oCiIL a-pCi/ml oCifte. wet
--I-oCiIL a-nCi/ks. wet a---
uCifte. drv a---- gross beta 4 lxl0{ N.A. NA. N.A. N.A, H-3 2000 N.A. . N.A. N.A. N.A. N.A. Mn-s4 l5 N.A. 130 N.A. N.A. N.A. Fe-59 30 N.A. 260 N.A. N.A. N.A. Co-S8,60 l5 N.A. 130 N.A. N.A. N.A. Zn-65 30 N.A. 260 N.A. N.A. N.A. Zv95 30 N.A. N.A. N.A. N.A. N.A. Nb-95 l5 N.A. N.A. N.A. N.A. N.A. I-l3l lb 7x l0{ N.A. I 60 N.A. Cs-134 l5 5 xl0{ 130 l5 60 150 Cs-137 l8 6 x l0'2 150 lt 80 180 Ba-140 60 N.A. N.A. 60 N.A. N.A. I"a-140 l5 N.A. N.A. l5 N.A. N.A.
- a. If no drinking water pathway exists, a value of 3000 pCi/liter may be used.
- b. lf no drinking water pathway exists, a value of 15 pCi/liter may be used.
APPEI{DD(F QUALrry ASSURAT{CBQUAIITY CONTROL PROGRAT{
-5 l-
AppendixF Ouality Assurmce/Otulity Conhol Procrarl A qulity assuraoce program is employed by the laboratory to ensure that the environmental monitoring data are reliable. This program includes the use of writteq approved procedtres in performing the worlg provisions for stafftaining and certification, intmal self assessments of prcgram performancc, audits by various elcemal organizations, aod a laboratory quality conEol prcgram. The quality contol progam employed by the radioanalytical laboratory is designed to ensulc that the smpling and malysis prcoess is working as intended. The prograrn includes equipment checks and the ualysis of quality conhol samples along with routine samples. Insffim,ent quallty control checks include backgrotrnd count rate and courts 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 devicc and the method it uses to detect radiation or storp the information obtained. Quallty couhol samples of avariety oftypcs are used by the laboratory to vcrify the performance of differcntportions of the analytical prooess. These $ulity contnol samples include blanl<s, replicate samples, analytical knorms, blind samples, and crcss-checks. Blanks are samples which contain no measurable radloactivity or no activity of the tJpe being measured. Such samples ue analyzed to daermine 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 measurpd. Duplicate samples are generated at nndom by the sample computer program which schedules the collection of the routine samples. For examplg ifthe routine program cdls for four milk samples every weeh on a random basis each farm might provide an additional sample several times a year. These duplicate samples are andyzed along with other routine samples. They provide information about the variability of radioactive content in the various sample media If enough sample is available for a particulu anelysis, the laboratory staffcan split it into trro portions. Such a sample pnovides information about the variability of the analytical prrcess since two identical portions of material are analped side by side. Analytical knowns arc another category of quality contol sample. A known amount of radioactivity is added 1e 4 semlrl medium. The lab staffknows the radioactive oontent of the sample. Wheneverpossible, the analytical knowns containthe same amormtofradioactivity eachtimetheyarenrn. Inthiswananalyucalknoumsprcvideimmediatedataonthequlityof the measuremeNrt prooess. Blind spikes are samples containing radioactivity which are introduced into the analysis prccess disguised as ordinary environmental samples. The lab *affdoes not know the sample contains radioactivity. Since the bulk of the ordinary workload ofthe environmental laboratory contains no measurable activity or only naturally occuning radioisotopes, blind spikes can be used to test the deiection capability ofthe taboratory or can be used to test the data review prosess. If an analysis rcutinely generates nume(rus zeros for a particular isotopc, the presence of the isotope is brought to the attention of the laboratory supervisor in the daily review process. Blind spikes test this prooess since the blind spikes contain radioactivity at levels high enough to be ddected. Furthermore, the activity can be put into such samples at the exfrmc limit of detection (near the LLD) to veri$ that the labor*ory can detect very low levels ofactivity. Another category of quality contol samples is the intcrnd cross.checks. These samples have a known amormt of radioactivity added and are presenrcd to the lab stafflabeled as cross-check samples. This means thatthe quality control saffknows the radioactive content or "right answetbut 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 accuraoy of the Eeasurement ptwess. Furttrer information is available about the variability of thc p(rccss if multiple analyses ate rcquested 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 interaal cross-check samples met program performance goals for 2015. To provide for an independent verification ofthe laboratory's ability to make accurate measurments, the labratory participated in an environmental level cross-check program available through Eckert and Ziegler Analytics during 2015. The results of TVA's participation in this cross-check program are prcsented in Table F-I. The resule for these cncss-check samples were all wittrin the program agemeril limits with the exception of the Sr-90 in Milk result for ttre first quarGr cross-checks. The disagreement was documented in CR 110689. All otherSr-fr) results werc iu agreement. The quality contol data are routinely collecte4 examined urd reported to laboratory supervisory personnel. They are checked for trends, proble,m aneas, or other indications that a portion of the anal)tlcal prooess needs correction or imprcvement. The end result is a measurement ploccxts that provides reliable and verifiable data and is sensitive enough to measurc the prcsence of radioactivity far below the levels uftich could be harmful to humans. Table Fl Results For 2015 Extemal Cross Checks ncnrlE Tcil nrhd Snnole TfnrultA&ilyrif f,uu rvA FfoltQ!!ills wrm(DCi/L) (hosr Bar 2.t08+fi1 2.t38+02 ffoil Qurtcr wlg(Dci[) h t.268+O{ t.368+Of Ycs fillQ!ilcr urGc,cl/!,) ott 9.678+0r 9.t38+0t Yer ttch 3.668+(n 3.768+(12 Ycr
-cr t.268+02 1.23E{O2 Ycr
-cs 1.678+04 1.608+fi1 Yer sco 1.808+(tr l.uE+04 Ycs xMn t.598{fil 1.56+O2 Ycs tc t.gltB((a t.E}E+$Z Ycr
*?s 2.1il,8,+& 3.0!)E+m Ycs
'co 3.2t8+ln 3.2t8{fi1 Ycr t.lcc l39E+@ 1.498{.m Ycr fbr Qurilcr SrilbE ic Udne (pCI&)
tr t.438+01 1.468+04 Ycr FiltlQttulcr Milr (firL) Erl 9.908+01 9.088+01 Ycr
'st 9.6t8{Ot t 6lE{Ol Ycr rsr t.328{Ol t.908{O0 No firnQurE Ah FilE (pCi,Fittc!)
ftoct BGtt 1.008+(tr 9.468{0l Ycr IttudAnltcr Wdc, (ICirL) tH 1.328+0{ 1"368+Of Ycr Ttitd(bdcr Sed (pCitgrm) rlce 3.3tEOl 3.loEJ)l Ycr tlo s.54E{ll 8.20801 Yer t'cs 3.36EOl 2.tzF,lll Ycr l'cr {.otB{ll 3.7tE0l Ycr
$co 4.t8EO! f.olE{t Ycr
'h'to tf.6lE0f a.?0E,0l Yer sFc 3.588{t 3.39EOt Ycg 6?s 5.618{11 5.75EOl Ycr oco 5.13E{l Yer
'.?d,E,.l Thild Qrrlg AbfilcrCtGrfinct)
Gmcr Bctr 9.218+Ol 7.708+01 Ycr Third aurilct Ah rillct(DCirftut) rrg, t 3aE{ot &368+0l Ycr
'lcr eltE{tr aolE{oe Ycc lxcl t.298+Ol 6.608+0l Ycr tt'cs g.gEErOl 9JrE{Ol Ycr sco 1.99f,+fi1 9.968{0l Ycr
*Mn l.l{E{O2 l.t9E{t@ Yct tre t.ttfB{Ol 9.qrE+01 Ycr 6?a l.3tE+Gl, 1.508+@ Ycr
'co t.298+(tr t.328{Ol Ycr Itidqffi $yanhcdc usim (pcrL) h t:gE{o{ t.4oE+ot Ycr Fout&atnttcr MiL (Dc-i/L) lilI t.978{Ol 9.3tE{Ot Ycr
?sr 9.0E')01 t.2tE+ot Ycr lsr t-578+01 l.ZrE+o1 Ycr APPENDD(G LAI{DUSESTJRVEY AppendixG Land Use Survev A land use suney was conduotcd in accordance with the provisions of ODCM Conuol l.3.2to identi& the location of the nearest milk aoinal, the nearest residence, and the nearpst garden of greater than 500 squarc fect producing fresh leafr vegetables in each of l6 meteorological sectors withitr a distaoce of 5 miles (8 km) from the plant The land use suryey ums condusted between April 1, 2015, and October l, 2015, using appropriarc techniques such as door-to-door suryey, mail stuvey, telephone survey, aerial survey, or infomation from local agricultural authorities or other reliable !ilrtrces.
Using the survey data, relative radiation doses were projected for individuals nearthe plant. Doses from air submersion werc calculated for the nearest resident in each sector. Doses fiom milk ingestion or vegetable ingestion were calculated for the areas with milk producing animals and gardens, respectively. These doses were calculated using historical meteorological data They also a$ilrme that the effiucnt rcleases are equivalent to the design basis source terms. The calculated doses are relative in nafirc and do not reflect aotual exposures rcceived by individuals living near IVBN. Thc location of nearcst resident changed in one sector dtring 2015. In addition, the location of the nearest garden changed in a total of five sectors. The suruey of milk producing locations performed in 2015 did not identify any new locations. Tables G-I, G-2, and G-3 comparc results of the relative pnojectcd annual dose calculations for 2014 and 2015. Table G-l Watts Bar Nuclear Plant Relative Prcjected Annual Air Submersion Dose to the Ncarest Residence Within E h (5 Miles) of Planf mrem/year 2014 2015 Approximate Approximate Sector Distance (Meters) A$nual Dose Distance (Meten) Annual Dose N 4,474 0.07 4474 0.07 NNE 3,750 0.21 3,750 0.21 NE 3,399 0.27 3,399 0.27 ENE 3,072 0,29 3,072 0.29 E 4,3E8 0.15 4,3tt 0.15 ESE 4,654 0. [4 4,654 0.14 SE 1,409 0.72 1,409 0.72 SSE 1,il6 0.34 l,@6 0.34 s 1,550 0.40 1,550 0.40 ssw 1,832 0.31 1,832 0.31 sw 4,141 0.09 3,784 0.10 wsw 2,422 0.lg 2,422 0.19 w 2,901 0.05 2,901 0.05 wNw 1,44E 0.19 1,44E 0.19 NW 2,065 0.09 2,065 0.09 NNW 4,376 0.02 4,376 0.02
- a. Assunes the effluent releases art equivalent to design basis source terms.
Table GA Watts Bar Nuclear Plant Relative hojes'ted Annual Ingestion Dose to Child's Bone Oqgan ftom lngestion of HomeGrown Foods Nearest Garden Within 8 km (5 Miles) of Planf mrem/year 20t4 2015 Approximate Approximatc Sector Distance (Meters) Annual Dose Disbnce (Meters) Annual llose N 7,188 0.55 629s 4.74 NNE 5,030 2.?g 5,030 2.19 NE 3,793 4.90 3,793 4.90 ENE 3,072 620 5,281 2.27 E 45s6 3.09 4,656 3.09 ESE 7,059 1.66 72e7 1.59 SE 1,409 14.20 1,409 14.20 ssE l,7ll 6.16 l,7l I 6.16 S 2,349 5.29 3,535 2,?9 ssw 7,736 0.61 7,736 0.61 sw 4,566 1.70 3,7W 239 wsw 3,080 2.?? 3,080 2.77 w 3,13E 0.gg 3,138 0.99 wNw 2,963 l.l3 2,956 l.13 NW 2,465 1.64 2,465 1.64 NNW 4,742 0.48 4,742 0.48 a Assumes the effluent releases arc equivalent to dcsign basis source terms.
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Tablc G-3 WatB B$Nucleu Plmt Rcluive Projeded Annud Dose to Roce6or lhyroid fiom Ingestion of MillC (Nearcst Milk-hoducing Animal Wi6in tkn (5 Milcs) of Plam) mrcm/ycar ApproximateDistance AnnualDose )uq location Sector MtGB 2Ol4 2015 s/m' Cows Farm ND ESE 6,706 0.06 0.06 1.35 E-6 Farm P1u'c SSw 2,826 0.19 0.19 1.73 E-6
- a. Assumcs the plant is operating and cfrlucm rclcascs arc equivalcnt to desigp basis soure tems.
- b. Milk being sanplcd at thcsc locadons.
- c. The identification forthis location rvrs revised in 2013 from Farm Ho to Farm HH.
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APPEbIDD(H DATA TABLES AT.ID FIGURES {1-
Table H-I DIRECT MDIATION LB/ELS Average B(emal Gamma Radiation Levele at Various Distances from WatE Bar Nuclear Plentfor Each Quarter- 2015 mR / Quarter o) Averaoe ExtemalGamma Radlation Levels o) 1$ Qf 2nd Qtr 3rd Qtr 4th Qf mR / Yr rcr Average 0-2 miles 14.2 15.3 16.6 14.7 61 (onsite) Average
>2 miles 13.3 13.4 15.1 13.6 55 (otrsite)
(a) Field peilods normalized to one standard quartar (2190 houra) (b) Average of the lndividual measuremEntB ln the set (c) The 5.6 mRlyrbr onslte bcatons falls below the 25 mrem btal body llmlt ln 10 CFR 190. Table H-2 (1 of 2l DI RECT RADIATION LEVELS lndividual Stations at Watts Bar Nuclear Plant Environmential Radiation Levels mR /Quarter Map D,osimeter Approx 1st Qtr Znd Qtr 3rd Qtr 4th Qtr Annual(l) Location Station Directior, Distance, Jan-Mar Apr-lun Jul-Sep Oct-Dec Exposure Number Number degrees miles 2015 2015 2015 2015 mR/Yeaf 40 N-l 10 1.2 15.5 17 .4 18.5 16.4 67.8 41 N-2 350 4.7 16.0 17.3 19.5 13.2 66.0 42 NNE-1 21 1.2 18.7 19.3 18.0 15.5 71.5 10 NNE-IA 22 1.9 12.3 14.0 16.0 15.7 58.0 43 NNE-2 20 4.1 11.7 11.3 14.1 (1) 49.5 3 NNE-3 17 10.4 12.2 12.6 15.0 13.5 53.3 44 NE-l 39 0.9 11.7 15.5 16.1 15.5 58.8 45 NE-2 54 2,9 15.2 12.7 16.5 14.4 58.8 46 NE-3 47 6.1 8.8 11.4 12.1 9,5 41.8 47 ENE-I 74 0.7 17,1 13.6 16.3 13.7 60.7 4g ENE-2 69 5.8 12.9 13.3 14.0 13.1 53.3 74 ENE-2A 69 3.5 11.1 9.9 12.1 10.2 43.3 4 ENE-3 56 7.6 8.8 10.4 11.7 11 .7 42.6 49 E-l 85 1.3 14.5 16.0 16.5 16.6 63.6 50 E-2 92 5.0 15.2 15.0 17.3 14.0 61.5 51 ESE-I 109 .2 1 9.9 10.8 10.2 10.2 41.1 52 ESE-2 106 4.4 18.8 17 .3 (1) 14.7 67.7 11 SE-1A 138 0.9 12.8 13.2 17.4 13.6 57.0 54 SE 128 5.3 10.0 12.2 13.0 12.6 47.7 75 SE 2A 1U 3.1 12.3 14.5 16.6 14.0 57.4 79 SSE-I 146 0.5 16.0 14.5 17.2 15.0 62.7 55 SSE-IA 161 0.6 12.3 11.7 20.0 10.0 54.0 56 SSE-2 15 5.8 13.5 15.9 17.3 16.0 62.7 (1) Sum of available quarterly data normaltred to 1 year for tre annual expoeure ralue.
-63'
Table H-2 (2ot2l DIRECT RADIATION LEVELS lndlvldual Sbtons atWatts Bar Nuclear Hant Envlrcnmental Radiation Levels mR/Quarbr Map Doeimebr Approx lstQtr 2nd QE 3td Qf 4th Qf Annual(r) Locaton Sbtion Direction, Distanoe, Jan-lular Apr-.lun Jutep Oct-Dec Exposure Number Number deoree mlles 2A,1l5 2015 2015 2015 mR/YEar 57 S-1 182 0.7 12.3 13.1 15.8 12.8 54.0 58 S-2 185 4.8 12.3 9.4 10.8 12.3 45.0 70 s-2A 177 2.O 14.0 16.4 16.6 16.3 63.3 5 S-3 185 7.8 10.4 10.8 15.6 12.E 49.6 59 SSW-1 199 0.8 17.6 20.5 19.1 15.3 72.5 12 SSW-2 200 1.3 12.2 12.2 16.6 13.6 54.6 60 ssw-3 199 5.0 11.7 10.3 12.2 11.0 45.2 62 Sr/\r-1 226 0.8 16.0 19.2 19.1 16.2 70.5 63 Srrlr-2 220 5.3 15.8 15.4 2O.O 19.2 7OA 6 S1'\r 225 15.0 11.0 11.3 11.1 11.3 4.7 64 WSI/I -1 255 0.9 13.4 13.1 12.9 13.2 52.6 65 WSI/rr-2 247 3.9 16.9 17.4 18.6 '15.5 68.4 66 W-1 270 0.9 13.9 16.4 15.3 14.1 59.7 14 W-2 277 4.8 11.1 11.8 13.4 11.4 47.7 77 W-2A 268 3.2 12.2 16.0 14,4 14.2 56.8 67 WI.tV\r-l 2% 0.9 21.4 21.2 21.7 22.8 E7.1 68 Wt{^ -2 292 4.9 15.8 17.8 18.9 17.8 70.3 69 Nt r-1 320 1.1 12.8 14.1 14.7 13.2 54.8 70 l.ll l-2 313 1.7 18.3 18.8 17.6 16.4 69.1 78 NW-2A 321 3.0 16.6 11.2 13.8 11.E 53.4 2 ttw 317 7.0 18.0 16.E 18.4 16.0 69.2 71 NI.{V\I-1 340 1.0 10.1 13.6 14.4 13.9 52.O 72 NNVI,-2 333 4.5 13.6 13.1 16.7 15.0 58.4 79 Ni.Mr-3 3il9 7.0 9.4 11.2 (1) 12.2 43.7 7 N}.IW.{ 3i}7 15.0 11.7 12.6 11.2 13.5 49.0 (1) Sum of analhble quartedy data nomalEod to I year forthe annuala:eoours value.
'64'
Tenneesee Valley Authorlty RADIOACNUTY IN AIR FILTER pCUm^3 = 0.037 BCmA3 Name of Fad$tf WATTS BAR NUCLEAR PLANT Do*et Numben 5G380,391 Locatlon of Fadllty: RHEA, TENNESSEE Reportlrg Perlod: 2015 Numbar of Type and Lorer Umlt lndlcalor Locatione LocaUon $rth Hlgheet Annual Mean Control Locationg Norrqrtlne Total Number of Detec0on Mean (F) Mean (F) irean (F) Reported of Analyals (LLD) Range Location Degcrlptlon wlh Rarqe Range Meagurements Peilormed See Nde 1 See Note3 Dlstance and Dlrecfron See Note 2 See NoJe 2 See Note 3 GROSST BETA .520 2.00E{)3 1.92E-02 (416r416) PM5 DECATUR 1.96E-02 (52 t 521 1.89E-Ul (104 104) 2.57E-03 - 4.2#-U 6.2 MILES S 4.54E-03 - 3.23E{2 3.03E-03 - '4.25E-02 GAIIMA SCAN (GELU - 130 AG.A,8 1.00E 02 104 VALUES < LLD Ltil3 13 VALUES < LLD 2O VALUES < LLD 1.9 MILES NNE BE-7 2.008 02 1.01E{1 (1O{ r 104) PM3 1.07E-01 (13 13) 9.86E-fi1 (26 r 26) 6.13E-02 e 1.42t01 10.4 iNlLES NNE - 7.g4lE{/2 ' 1.42E{1 5.49E-02 - 1.34E-01 Bl-214 5.mE{l3 1.99E-02 (102 104) LM-4 t fB 2.58E-O2 (13 13) 2.1OEq2 ett26l 5.40E-03 - '7.16E-02 0.9 MILES SE 6.40E-03 -' 7.16E42 5.20E-03 - 5.66E-02 !-l E' & 104 VALUES < LLD 13 VALUES < LI.D 26 VALUES < LI-O U (^ t K-40 4.00E-02 Plrr4 7.0 MILES NE'ENE o EI P*212 5.00E{3 104 VALUES < LLD Ptr,l4 13 VALUES < LLD 28 VALUES < LLD f.^, 7.8 MILES NE'ENE P*214 5.008{3 1.90E-ff! (100 t lml LM4WB 2.&E-02 (121 13',) 2.13E&, (28 lzgt 5.00E-03 - 7.50E.02 0.9 MILES SE 5.30E-03 - 7.50E-02 5.00E-03 - 5.94E{2 TL-208 2.00E-03 2.20E-03 (i 104) PMs DECATUR 2.20E-03 (1 13) 26 VALUES < LI,D 2,20E-03 '- 2,20e.{Jf3 0.2 MlLEs s 2.208-03 -' 2.20E-03
- l. ilmhd LoE Lml d tbbdbn (uD) a3 Gcribsd rr Table E- I Z ilGm arl Rtngs bad Wot debcbtrb rrauamnb of. Fracdon ddeEcbbb nrcuimntr at rpecfied bca0or lr Hcalgd ln poerrtpasr (D.
- 3. BlEnt! h tit cohnn hdh& m norqmlho moeJlrflldrti
Ten neesco Valley Authority MDIOACTIVITY IN CHARCOAL FILTER pCl,tn^3 = 0.037 Bqrm43 Name of Facility WATTS BAR NUCLEAR PLAlrlT Dodret Numbec 5&300,391 Locatlon of Fadllty: RHEA, TENNESSEE Reportlrg Period: 2015 Number of Type and Lourer Umlt lrdlcator Locaforp Localion wlth Hlghest Arrural Mean Control Locdons Nonrou0ne Total Number of Detedlm Mean (F) ilean (F) Mean (F) Repotted of Analysts (Ll.D) Range Loca0on Descridlon w0th Rarge Rarpe Meastrements Per6rmed See Nole 1 See Note 2 Dlstance ald Dtrcdlsn See N.$e 2 See Note 2 See Note.3 GAMMA SCAN (GELI) - 5i10 Bl-2t4 5.00E-02 1.148-Ol (200 416) LM2 1.40E-01 (28 I 521 1.35E{1 (43 r 1O{) 5.01E-02 ' '6.glE-01 0.5 MILES N 5.03E-02 - 0.818-Ol 5.21E-O2 - 7.50E-01 l-131 3.00E-02 SEE NOTE 4 Kr{0 3.00E-01 3.49E-01 (19 t 416) PMs DECATUR 3.60E-01 (17 l52l 3.78E-01 (19 10{) 3.ff1E-01 7.3llE-01 6.2 MILES S 3.02E-Ol - 7.3ilE-01 3.02E-01 -' 0.13E-01 P*212 3.008-02 416 VALUES < LLD PM2 SPRING CITY 52 VALUES < LU) 104 VALUES < ILD 7.0 MILES ifw P&214 7.00E-02 1.44E-01 (119 I 416) ttiJlz 2.10E 01 (13 52) 1.78E-01 (2$ 1104) t-l t 6 7.00E 6.92E 01 0.5 MILES N - 7.89E-02 ' 6.92E-01 716E52 - 7.40E-01 $ ? TL-ang 2.qlE-02 416 VALUES < LU) t"irl3 52 VALUES < LtD 104 VALUES < LLD 6' 1.9 MILES NNE E A Noba: l. ilflrhd l-ffi lltd of Drbo[on (LLD) c dactocd ln Tr!5 E - I
- 2. l,le.n ad R rl b6d Won debdlDle msrulemstb ooly. Frec[on d&bcldrb mo8rmmeils al lpecltbrl locauon b trrflclH ln pernlhss! (D.
- 3. Cat{tl h 0tb cotumnlndc6 noruuqrrtne nmumn rt
- 4. Ihs mdvlb of Cherod Fllbl! vrrs peftmsd ,y Gamma Specfoacoev. No l-l 31 rE dobctsd. Tha IJD 6r l-l 3f W Garune $ecfoocopy mr 0.8 pqf.uuc rrEb.
Tennoacee Valley Authorlty RADIOACTMTY IN ATMOSPTIERIC MOISTURE pCl'ffi3'0.007 BCm^3 Name of Fadlltf WATTS BAR NUCUAffi PUiIT Dod(stNumDc 500O.3El Locatlon of Fadlity: RHEA, TENNESSEE Rspolfr[ Pedod: aI5 Numborof Type and Lorrer Umit tndlcator Loca$ons LocatbnyrltrHghsstAnrudmm
- Conhol locatms Nmou8ne Total Number of [btecilon Mean (F) lrun(D i/hn(F) -- nspomed of Analysis (LLD) Range Loca0on Dsctip0mwUt neqt Ralpp i[eanmtmntr Perftrmq$ See Note 1 See Note 2 Offsn ald bmcdon Sce !{ae z Se Nda 2 Ss Nole 3 TRMUM .203 3.qlE+(xl 4.$E+00 (15 1153) ulrl 5.54E+qt (1S r 6) 4.00E+00 (18 r 50) 3.(FE+(X) - 2.64E+Ol 0.5 MILES SSW 3.26E+(X) - 2.64E+01 3.04E+fi1 ' 5.t0E+00 hl E.
I trr { ch I 6' F
?Yh t{ole!: l. Nanhat Lmr Lerd ol Dcbcfloo GfD) a dcrdbd h Tebb E' I Z i,htt ad RrEs ba.d UPat &bcbt lo measuenrenb c{y. Fncilqr of debdaua measrortnb at sPednod bcatm b hdcabd ln pannha*l (F).
- 3. Bleilt ln hb cdum trlm m nonlordr mearuturlelilr
Tennessee Val ley Authority RADIOACTIVITY IN MILK pCUL = 0.037 BqlL Name of Fadti$: WATTS BAR NUCLEAR PLANT Dodret Numben fl)-390,391 Locaton of Fadllty RHEA, TENNESSEE Reportlng Perlod: 2015 Number of Type ard Lower Llmit lndtcator LocaUone Loca$on w0tlh Highest Annual Mean Contol Locatons Nonroutine Total Number of Detectlon Mean (F) Mean (F) Mean (F) Reported of Analyslg (LLD) Range Locatlon Decriptton ui0r Range Range Measurements Perbrmed See Note 1 See Note 2 Dlstance and Dlrec{on See Note 2 See Note_? See Note 3 toDtNE-l3l -78 4-00E-01 5E VALUES < TI.D 26 VALUES < LLD GAMMASCAN (GEL]) -78 AC-22E 2.00E+01 52 VALUES < tJ.D 1.73 MILES Ss:tfi' 26 VALUES < LLD 2.59E+Ol (1 ,26) 2,59E+01 - 2.59E+01 Bt-212 5,00E+01 1.84E+02 (1 t 521 1.75 MTLES SSv 1.84E+02 (1 t 26) 26 VALUES < LID 1.&{E+02 1.&dE+02 1.&4E+02 - 1.&4E+02 Bl-z'.,4 2.00E+01 3.UlE+01 (31 t 52l 1.75 MILES Ssltfl, 3.33E+01 (17 126, 3.28E+01 (15 r 2q 2.00E+01 - 6.48E+01 - - I 2.00E+01 6.48E+01 2.12E+O1 6.13E+Ol s' (t 1.31E+03 (25 t gl l h K40 1.00E+@ 1.31E+03 (50 , 52) NORTON FARM 1.32E+03 (26l2gt oo t 1.15E+(E - 1.44E+(Xt 4.1 MILES ESE 1.15E+03 - 1.42E+03 1.18E+03 - 1.44E+03
-t+l o
*.I PA34M 8.00E+02 52 VALUES < LLD 1.75 MILES SSUV 26 VALUES < LtD 26 VALUES < LLD o\
P*212 1.50E+01 52 VALUES < LtD 1.75 MILES Sslrt, 26 VALUES < LLD 26 VALUES < LI..D PB-214 2.008+01 2.93E+01 (21 t 52l 1.75 MILES S$A' 3.07E+01 (8 l2A) 2.94E+01 (14 t 26l 2.01E+01 - 4.908+01 2.14E+01 - 4.90E+01 2.04E+01 - 4.90E+Ol TL-208 1.00E+01 52 VALUES < tLD NORTON FARM 26 VALUES < LLD 26 VALUES < LLD 4.1 MILES ESE sR89 -12 3.50E+00 8 VALUES < LLD 4 VATUES < LtD sRql -12 2.fi)E+00 8 VALUES < LU} 4 VALUES < LtD t{obs: 1. Nomfild LorEr lud of Dsbrthn (l,lD) as dsol0ql ln TaUe E - 1
- 2. lleanrlldRarycbEcduDmdeiedabbmsalurcflrnbmly. Fracilmd(bGctluemeallmentBsts@fadlocatbnbandcabdlnpa'ffieaec(F).
- 3. Blailr ln ltdr odLrnn lrdhdg rc narourdns mas.rgrnh
Tenneeee Valley Authorlty MDIOACTMTY IN SOIL pCug = 0.037 Bq/g (DRY WEIGHT) Name of Fadllty WATTS BAR NUCLEAR PLANT Dodret Number 5$390,391 Locatlon of Facility: RHEA, TENNESSEE Reportlng Perlod: 2015 Number of Type and louBr Umit lndlcator Locatlons Locatbn wtlh Highest Annual Mean Control Localions Nonroufrne Totral Number of Detecilon Mean (F) Mean (F) Mean (F) Reported of Anatyels (Ll.D) Range Loca0on Descrldion wt0r Range Range Measurements Perfgmed See Note I See Note ? Dlstanoe arNd Dlrectlgn See Ngjle 2 See Note 2 See Noh 3 GAMMA SCAN (GELI) - 10 AC*lAI$ 2.glE-01 1.18E+fi) (8 r B) Lill 1.34E+fi) (1 1) 6.25E 01 (21 2l 8.32E-01 - 1.34E+(X) 0.5 MILES SSVI' 1.30Er(X) -' 1.34E+00 6.08E{r1 - 6.42E{1 BE.7 2.50E-01 3.15E{1 (3 r 8) PMs DECATUR 3.84E-01 (1 1) 2 VALUES < LI."D 2.02E{1 3.84E-01 6.2 MILES S 3.E4E-01 ' 3.84E-01 B/,afl 4.50E-01 1.238+00 (8 8) PM3 1.48E+00 (1 ,1) 6.62E-01 (21 4 9.0EE-01 -' 1.48E+fi) 10.4 MILES NNE 1.48E+00 - 1.48E+00 6.62E{1 - 6.62E-01 il.zu 1.508{1 7.64E-01 (8 r 8) L"il3 8.87E-01 (1 1) 6.07E-Ol (2121
- 6.45E-01 5.38E{t1 8.87E{1 1.9 MILES NNE 8.87E-Ol -' 8.87E{1 5.68E{1 c$137 3.00E 02 1.68E{1 (7 8) PM2 SPRING CITY 5.64E.01 (1 / 1) 3.15E-01 (2/,21 Fl p
I - 3,07E-O2 ' 5.64E-01 7.0 Mll-Es !.lw 5.64E Ol - 5.64E'01 1.84E 4.46E-01 ET o\ \o l-o I K-,10 7.50E-01 1.16E+01 (8 r 8) LM.4 WB 2.58E+01 11 I 1' 3.65E+fi) l2l2l tr 3.39E+00 2.58E+Oi 0.9 MILES SE 2.58E+01 - 2.58E+01 3,0EE+00 - 4.23E+fl1 rl 4.fi)E+00 8 VALUES < L[I) Pi,lz SPRING CITY 1 VALUES < LLD 2 VALUES < LLD { a PA"234M 7.0 MILES NW P*212 l.(xrE-ol 1.17E+Ul (E r 8) PM3 1.42E+00 (1 ,1) 6.07E-01 (212}. 8.52E{1 - 1.42f+fi) 10.4 MILES NNE 1.42E+00 - 1.4!f+{10 6.06E-01 - 6.08E-01 P*214 1.30E{1 8.30E-01 (8 r 8) LIriS 9.70E-01 (1 1) 6.76E-01 (214 6.00E{1 9.70E-01 1.9 MILES NNE 9.70E{1 -' 9.70E-01 6.23E 7.29E{1 RA.2B l.qlE ol 7.64E-01 (8 8) LM3 8.87E{1 (1 1) 6.07E-Ol (21 2t 5.38E-01 ' 8.87E-01 1.9 MILES NNE E.g7E-01 -' E.87E-01 5.68E-01 - 6.45E-01 TL-208 6.00E-02 3.93E{1 (8 r 8) PM3 4.61E{tl (1 1) 1.96E-01 (21 4 2.78E51 - 4.61E-01 10.4 M]LES NNE 4.61E-Ol -' 4.61E-01 1.87E 2.058-01 sR89 -10 1.dlE+00 I VALUES < Lt"t) 2 VALUES < IID sR90 -10 4.00E-01 8 VALUES < LI.D 2 VALUES < tI.D t{oEs: t. Nmfid LorEr lsrd ol lrbcdon GfD) a3 d6stbd ln T& E ' 'l Z t esn and ReryF bacdl rfpon d*d& meacumor{r only. Fracfion of &bclaUe mecutolmnts at spodfrod locatlon b Mcated ln paentlEs.r (D.
- 3. Bladc lnthb coftrmn lndcale m nqr]ouiltn meeelcmetils
Tennessee Valley Authority RADIOACTIVITY IN CORN PCI/Kg = 0.037 BqrKg (UVETVt EIGHT) Name of Facllltf WATTS BAR NUCLEAR PI-ANT Dodot Numben 50-390,391 Locaton of Fadt[y RHEA, TENNESSEE RepoillrE Perlod: 2015 Number of Type and Louuer Umlt lndicator Locatlorc Locatlon wlh Hlghert Annual Mean Conlrot Loca0ons Nonroufine Total Ntmber of Detecilon Mean (F) Mean (F) irean (F) RePoiled of AnalyRb (LLD) Range Location Descrlptlon with Range Range Msasurments Performed See Note I See Note 2 Dlstanoe and Dlrecillon Se No,te 2 See Note 2 See Note 3 GAMMA SGAl,l (GELI) -2 B/,.2fi 4.fiIE+01 l VALUES < LLD NORTON FARM 1 VALUES < ILD 1.72E+M, (1 ,1) 4.1 MILES ESE 1.72E+@, - 1.72E+gl2 K-{0 2.50E+02 2.03E+03 (1 1) NORTON FARM 2.03E+03 (1 ,1) 2.21E,*8 t 1) (1 2.038+00 -' 2.038+00 4.1 MILES ESE 2.03E+03 - 2.96f+Gl 2.21E+B - 2.21E+03 PB-214 8.ME+01 l VALUES LLD< NORTON FARM 1 VALUES < LLD 1 VALUES < LID 4.1 MILES ESE Fl D {o a C F tD t lil Ilr I O t{oba: 1. }tortrd Lffi Let d d Oecfim (Lt D) ar &aqlbed ln Tabh E' I
- 2. MeansrdRmgsbarertWqrrHccl6btormasuramltbor{y. FtecUonofdetoctablenmunrmrtral3pecmedbcafmbMcatcdhpacntlasr(D.
- 3. Bhnts h hb cofttmn hdc& m nmu.rdne msuqnil3
Tenneceee Valley Authorlfl RAIXOACTMTY IN GREEN BEAI.IS pciflA = 0.037 Bq,Kg (uvET WEIGHT) Name of Fadllty: WATTS BAR NUCLEAR PLANT Docket Number 50-gg),391 Locallon of Fad[ty RHEA. TENNESSEE Reporting Pedod: 2015 Number of Type and Loruer Umit tndicator LocaUons LocaUon wlh Hlghest Annual Mean Conht Locations Nonrouthe Totral Number of tlgtecilon tulean (D Mean (F) itean (F) RePorted of Analysis (LLD) Range Locatlon Descrlptlon wltlr Range Rarge Meagurements Pefunrrcd See Note I See Note 2 Dtstance and Dlrectlon See Note 2 See Nde 2 See Note 3 GAMMASCAI{ (GELI) -2 Bl-214 4.00E+01 4.17E+01 (1 l) 3.0 MILES NE 4.17E+01 (1 1) 1 VALUES < LLD 4.17E+01 -' 4.17E+01 4.17E+O1 o' 4.17E+01 K.f0 2.50E+02 1.90E+03 (1 , 1) 3.0 MILES NE l.glE{O3 (1 ,1) 2.40E+03 (1 I 1l 1.90E+03 - 1.90E+03 1.90E+03 - l.glE+o3 2.40E+(E - 2.49f+(B PB-214 8.ff}E+01 1 VALUES < LLD 3.0 MILES NE 1 VALUES < LLD 1 VALUES < LLD H D {t U ts J tD I H H
\o a
t{oia: l. f{omhd Low latd of Delcflm (tur) as dslctlbod ln Tdb E' I Z lbmandRqpbasedryonddsddbmasusnenbmly. Frdmddebdauemes$!mil3atgpedlledlocdottblruIcabdhpalsilEses(F).
- 3. Berfu ln hb cdumn lndcab tD ngttourdtE tlptlrronedl
Tenneeeee Valley Authorlty RAOOACTIVITY IN TOMATOES PCi,Kg = 0.037 Bqnq .*ETWEIGH') Name of Faclllty WATTS BAR NUCLEAR PI-ANT Do*et Numben 50-390,391 Locatloct of Fadlitf RHEA, TENNESSEE ReporllrU Pedtd: 2015 Number of Type and Lorer Umit lrdicator LocaUom Locatlon u,!th Hbhest Annual iiean Controt Loca0onE Nonroufilre Total Number of Detecilon Mean (F) Mean (F) Mean (F) Reported of Anatysls (LLD) Range Locatlon Descrlptlon wllh RalPe Range Meaewementa Performed See Note I See Note 2 Dlstiance and Direcillon See Note 2 See Note 2 See NotB 3 GAMMA SCAN (GELI) -2 Bl-214 {.00E+01 4.OgE+01 (1 , 1) 2.5 MILES NE 4.09E+01 (1 1) 4.72E+O1 (1 1) 4.09E+01 - 4.OgE+01 4.09E+01 -' 4.09E+01 4.72E+O1 -' 4.72E.+01 K-,{0 2.50E+02 2.11E+03 (1 , 1) 2.5 MILES NE 2.11E+03 (1 1) 1.9tf+03 (1 1) 2.11E+03 - 2.11E+03 2.11E+03 -' 2.11E+03 1.98E+03 -' 1.gEE+03 P*214 8.OOE+01 1 VALUES < LLD 2.5 MILES NE 1 VALUES < LLD 1 VALUES < LLD Fl pl cr {N t F o
)d I
tr. I F o N&fi l. l{omirlll LouGr lltd of Od.cilm (LlD) a dscosd ln Tade E - I
- 2. lrem atd Rengc bererl rpor dc0adalle rrcannsnenb mly. Frdm of ddecbDle ruaurcmenb at rpecfrd tocaffm b ltdc8bd h paEntrtss.. (D.
& Eard(3 h thb aoltmt mcab no nontu[iltD ttEurwnts
Tennessee Valley Authorlty MDIOACTMTY IN TURNIP GREENS PCl,'lQ = 0.(Xi7 Bq,Kg (WETWEIGHT) Name of Facllltf WATTS BAR NUCLEAR Pl.At{T Do*et Numben 50-390,391 Locatlon of Fadllty: RHEA, TENNESSEE Reportlng Perlod: 2015 Numbr of antt Umlt lndlcator Locatlorc Loca0on u,lth Hlghest Anrual Mean Contnot Localions Nonroutlne llban (F) Type Lonupr RePorted Total Number of Detecffon Mean (F) Mean (F) of Analyrle (lID) Ralge Location Deecrlillon wlth Rarqe Range Measurements Performed See Note 1 Se? Note 2 Dlstanog and Dlredlon See- Note 2 See Note 2 See Note 3 GAMMASGAN (GELI) -2 B,l-214 4.ff)E+01 6.&{E+01 (1 1) 3.0 MILES SE 6.&{E+01 (1 1) 7.34E+01 (1 1) 6.&0E+01 -' 6.&0E+01 6,84E+01 -' 6.84E{Ol 7.34E+01 -' 7.34E+01 K40 2.50E+ff1 2.55E+03 (1 ,l) 3.0 MILES SE 2.55E+03 (1 1) 2.14f+03 (1 1)
-' 2.14E+03 2.55E+03 - 2.55E+03 2.S5E+03 -' 2.56E+03 2.14E+08 P*214 8.OOE+01 1 VALUES < LLD 3.0 MILES SE 1 VALUES < LLD 1 VALUES < L"LD Fl s,
ET f.l H o Ir I ltt i-H tlo6: l. t{omhl Lmrl.etd of Odrcflon$D) ar deccrlbsd ttTaDb E't
- 2. l15at ard Rmgp b6d rpon d66dab6 maanrsnerfr cty. Frac0on d ddecbbb msaurcnreds d rpecllled locdon b lndlcabd ln parsnthe!.s (F).
- 3. t[.da h lhb ootumn hdc& rc nmtflt{hs nEurcmsds
TdilD\r.fytuahodu luDlolgllvlrY rl sJf,F cEw rBO..r) F,L. 0.6rEq,L r.tr.dF.& tll^Tl83lRiltrctE Rrum rt*.alrlll!.r tOIO,r'l t .dotd@ ncArEtliGssGE Rtatlalit.it ax6 iltnrc Il'r.fa L llrlI ldc.Eldlol. lrc.ilcltlorltnAnfiararl contd Lc.bi. t'crtlL Tdfltrlt. orD.lclcr kr{R 5tO hrG) thal n-^naa- [rD irr.' Loc.rbolLqFaclsr R.ra - RT.
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!4ille ra.Jdir. gir-Siz E--d &.6- bx-2 8aNd.2 nilhi.l GRNSETA -C r.Grql z-G{O (t.r20 lfi[ol?.e 2,5./EruJ 0t1,, 2alE o Grlq r.G+oo - !!lc+oo z0cr{lo - !.t0Gr,00 2.@Ero . zeG+O oltraSc raGGlo -r t& 2.oErol U.D ',l @!.1 i3vrr.tEa < U.o llv LLEs < tLo
'VAIJEa<
*2l. 2G.0t 8.t7E+Ot 0rrr) rRr !ar.l !.2!Erol or'19 a'!G.ol ort9 zG+01 - !.#.rot eqlErol ' a.sro! l'r(E+G ' l.ltE+E r{O l.(Ern 2!V UlEl< LLo r !!llt llv lJ.E8.U-O IIVA.IES < LU' H
tr cr .l,l Fe.l2 LG{ot tvallES<u.o r !z!.t 13v uJEs.tLD lavllJCa<uD Hl o t ha lr{
?*t1 aoc{or r4io1 or2o lElt?!.1 Lc.o,t (alt, t,l.lE+ot (,lrlo f-t
?-11401 - liE Ol z3lErot - a.?ZErOl 1*iG ' l.G.@ N IL{6 lff.Ol u, rB 5l?.g lavalrEa<u.o l3vaJ.E3<lLo
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tRmtr ., Z.7OE+fiZ, 6.85E+02 (1412f,.1 TRM 543.1 7.31E+02 (8 13) 13 VALUES < LLD 2.98E+fi1 - 1.07E+03 - 3.12E+(n ' 1.67E+03 Nobs: t. ifcn[ral Lmr lrrd d Dsbciion (u-O) as descrlbsd ln Table E' I 2l{3grar5Rengebsqtrpdtdebdeu.msttuElmnt!only. FEdlonofrhEffiemeaalerEricatlpcmdbcatml!hdcebdlnpannthemc(D.
- 3. Eanlls ln U& cdtmn lrdcab m nouuflltre tnea3lmmmb
Tennessee Valley Authorlty RADIOACTMW lN PUBLIC (DRINKING) WATER (l'otal) pCUL = 0.037 BqrL Name of Fadlltf WATTS BAR NUCIfAR PI.ANT Doctret Number: 5().390,391 Locallon of Fadllty RHEA, TENNESSEE Reportlng Period: 2015 Number of torrer Umlt lndlcator Locatbna Loca0on wlth H[hest Annual Mean Conlrol Locdions Nonrouthe Type and Mean (F) Mean (F) Mean (F) Reported Total Nwtber of Detedlon (LlD) Range LocaUon Deecriptlon wlth Range Rarqe Measuremente of Analysis Distane ad Dlrecfron See Note 2 See Note 3 Pe&rmed See Note 1 See Note 2 Qee Note 2 GROSS BETA - 39 1.90E+ff) 2.18E+00 (13 r 26) Ri,I.2 DAYTON TN 2.27E+OO (5 13) 2.41E+00 (8 13) 1.91E+00 - 2.69E+00 17.8 MILES NNE - 2.OOE+00 ' 2.698+00 2.02E+fi)' 2.98E+00 GAMMA SCAN (GELI) -39 AG-228 2.ff)E+01 2.25E+O1 (1 126l CF INDUSTRIES 2.251+01 (1 ,13) 13 VALUES < LLD 2.2SE+01 - 2.29f+01 TRM 473.0 2.25E+O1 - 2.?,5E+O1 Bt-214 2.00E+01 4.33E+01 (14 I frl RltL2 DAYTON TN 5.068+01 (5 / 13) 4.30E+01 ;t I 131 2.16E+01 9.21E+01 17.8 MILES NNE 2.6E+01 - 9.21E+01 2.208+01 l.l lEt{JrZ 26 VALUES < LLD RtI,.2 DAYTON TN 13 VALUES < LLD 13VALUES < LLD K.00 1.fi)E+02 17.8 MILES NNE H pl d {(^ a Pr};212 1.50E+01 2O VALUES < LLD Rii.2 DAYTON TN 13 VALUES < LLD 13 VALUES < LLD
-o I 17.8 MILES NNE 2.@E+01 3.&4E+01 (121 2,1 Rtut2 DAYTON TN 4.60E+Ol (4 13) 5.44E+Ol (4 13)
F t-P&l214 2.04E+01 8.68E+01 17.8 MILES NNE 2.488+01 -' 8.G88+01 3.398+01' 1.028+92 r*) TL-A)8 1.00E+01 26 VALUES < LID RM-2 DAYTON TN 13 VALUES < LIJ) 13VALUES < LLD 17.8 MILES NNE TRITIUM .47 2.7OE+@, 4.74E+02 Ul CF ]NDUSTRIES 4.93E+02 (10 1A 13 VALUES < LI-D 2.8r',E+O2 121
- ' 1.07E+03 TRM 473.0 r 2.UE+O2 ' 9.16E+02
- l. t{qntltl Lm, tul d Dobcilm (LLD) as dccsfred h Teble E' I
- 2. ii n end Rengc De!d Won debclsb measuanentr crty. Frecilor d debddlo mesutgtmlfi d rpcdncd bcadm lr krdcaied ln pann0pret (F).
- 3. Bbr*l h ttt! cdumn lrdcab no nonrurdrp measuFmds
Ten neseee Valley AuthorlU RADIOACTIVITY tN WELL (GROUND) WATER (tota0 pCtL=0.(Xl7Bq/L Name of Fadlltf WATTS BAR NUCLEAR PIANT Docket Number 50-390,391 Location of Fadllty RHEA, TENNESSEE Reporting Period: 2015 Number of Nonroutlne Type and Lorer Umlt lndtcator Locatione Loca0on wih Hlghest Annuat Mean Control Locatlons iilean (D Reported Tota[ Number of Detedion Mean (F] Mean (F) of Anatysls (LLD) Range Locaton Descriptlon wi[r Range Range Measurements See Nde 3 PerbrmeO Se.llole I See Nde 2 See Note 2 Dlstane and Dtrec{on See Note 2 GROSS BETA -78 1.90E+00 2.86E+(P (35 r 65) WBN WEIL#I 3.13E+00 (3, 13) 2.76f+fi) (6 13) 1.91E+fi1 - 5.60E+fi) 0.6 MITES S 2.47Q+OO - 3.O2E+fl) 1.97E+q) -' 4.90E+00 GAMMA SCA}I (GELD -78 2.00E+01 65 VALUES < LJ-D WBNMW 13 VALUES < LLD 13 VALUES < LLD AG22S o.45 MILES SSE) Bl-214 2.00E+01 3.3{iE+01 (43 r 65) WBN MIA/.A 3.95E+01 (11 13) 2.95E+Ol (t I 1gl 2.05E+01 6.69E+01 0.58 MILES SSE) 2.fr1+O1 - ' 5.84E+Ol 2.19E+Ol - 4.15E+01 65 VALUES < LLD WBN ItnW-A 13 VALUES < LLD 13 VALUES < LI.D K.40 1.00E+02 Ft 0.58 MIIES SSE) E cr {Or I PV212 1.50E+01 65 VALUES < tLD WBNMW.A 13 VALUES < UI) 13 VALUES < LLD o H I 0.58 MILES SSE) l-l P&211 g.z]E+ol (3f , 65) WBN IIIW-A 3.88E+01 (11 13) 2.72E,+01 (6, 13) ts 2.fi)E+O1 2.01E+01 - e.21E+01 0.58 MILES SSE) 2,nE+O1 - ' 8.21E+01 2.03E+01 - 3.51E+01 5 TL-208 1.(XlE+01 66 VALUES < LtD wBN iil rf 13VALUES < LLD 13 VALUES < U"D o.30 MITES SE) TRmUM -78 7.7$l+O2 (34 r 65) WBN irfUlr 1.09E+03 (13, 13) 13 VALUES < LLD 2.70E+V 2.748+92 - 1.4{E+(Xl 0.45 MILES SSE) 8.25E+02 - 1.44E+03
- 1. I{olnhl i.oYpf bul dD*dbn (LtD) 8! dcteqt h Tdb E' 1
- 2. lkt ad Rmgg bsd rpon rhbctaDte rpasurmsn03 ody. Fracdm o, debciaue mcauunronb at rpedned bcaton b hdcaled h pdlilElo! (F).
- 3. Bad.t ln thb ohrmn trdcab m tsroulilne rrerugnentr
Ten nessee Val ley Authorlty RADIOACTIVITY IN COMMERCIAL FISH pCUg = 0.037 BCg (DRY WEIGHT) Name of Facility WATTS BAR NUCLEAR PlAl-lT Dodct Number 5&390,391 Locatlon of Fadllty: RHEA, TENNESSEE Repoillr Perlod: 2015 Nurnber of Type and Loner Llmlt lndlcator Locatlons Location u,ith Hlghest Alrnual Mean Conhot Locatlons Nonroufrne Total Number of Detecilon Mean (F) illean (F) Mean (F) Reported of Ana[d8 (LLD) Range Location Descrlptlon wlth Range Range Meaeuroments Perforned See Nole 1 Soe Nolgz Dlstance and Dlrecton See Eote 2 See Note 2 See Note 3 cArrMAscAN(GEU) -6 gt-211 l.mEoi 1.EE{t (3r4) CHEI(AMAUGARES 1.E,rEAt el4 1.tr41 e.t4 t.rzeoi - lne-ot TRu.tzi-qto i.17E41 - z^17g*,1 l.o-rE{l - l.7G{ll K.fo 4.@E{1 l.(EE+Ol (4r4) OOUVNSIREAI,ISTAIONI '1.06E+01 l2l2l 1.G+O1 e,lA e.lte*oo - i.rse.o,t txrwNsTREAM l.@E{rl - l.loEr{tl 1.01E+ol - 1.1'lE+0, P9212 4.qE-Ol /0VALUES < LID CHICIGMAUGARES 2VALUES < LLO 2VALUES< IID TRM471-500 E8l211 S.OOEOI 4VALUES<LU) DOT'VNSTREAMSTANONI 2VALUES<LLD 2VALUES<IID DOt /NSIREAi,I TL.2O8 3.qtE.O2 4VALUES < 1I.T' CHICKAT'AUGARES 2VALUES < lII' 2VALUES < II.O H D TRM471m trr (( t ts o a H H I Fr Q't Nobt l. Nmhd Lcrsr lst d of mc[on GlIr) a (h.ctlled ln Tabb E - I
- 2. lleen a15 Rarge bald Won debdabh msarrqrst a{y. Frdon d d$d.trlo tmsutrlanb at speclfred bcaton Is lldcdd ln pan ilha!s (F).
- 3. Banfa hfiL colttttttt tdhab m nmmldnc meetrunen0s
Tennessee Valley Authortty RADIOACTIVITY lN GAtlrlE FISH pCUg = 0.037 Bqrg (DRY vlrEIGl'fI) Neme of Fadlltf WATTS BAR NUCLEAR PIINT t}ocket Numben 50.390,391 Locatlon of Fadlity: RHEA, TENNESSEE Rebortirp Petud: 2015 Number of Type ard Louer Umtt lndlcator Locations Locallon uith Hlghest Annual [,!ean Control Locdone Nonroullne Total Number of tletecdon Mean (F) Msan (F) irlean (F) Repoilcd of AnalytB (UD) Range Location Dscrlptlon wtth Range Range Measurcments Perfurmed See Note 1 See Note 2 Dlstance and Dlrec0on See Note 2 See Nde 2 See Note,3 GAMMA SCA,II (GELI) .6 Bt-214 1.(pE{l 1.93E-Ol (4 t 4l CHICIIAi'AUGA RES 2.11E-Ol (21 2l 1.23E-01 (21 2) 1.32E-01 2.58E-01 TRM 471-530 1.63E-01 - 2.58E-01 1.07E 1.398-01 c$l37 3.00E{2 4 VALUES < U"D CHICI(AMAI.lGA RES 2 VALUES < TI.D 3.24E.0l2 (1 lz',t TRM 471-53[l 3.24E 3.24E&, K.f0 4.00E{1 1.23E+01 (4 t 4) DOI,I'NSTREAIJl STATION 1 1.25E+01 (2121 1.3tlE+01 (2 t 4 1.18E+01 - 1.25E+01 DOA'NSTREAM 1.24E-'+01 - 1.25E+01 1.31E+01 - 1.35ErOl Pt212 4.00E{2 4 VALUES < LLD CHICK/AMAUGA RES 2 VALUES < LLD 2 VALUES < I.TD TRM 471-530 2 VATUES < LLD Ft P&l214 5.00E{1 4 VALUES < tJ.t) CHICIGMAUGA RES 2 VALUES < LLD E TRM 471-530 tt e -oha a TL-208 3.00E{r2 4 VALUES < LtD DOI^JNSTREAM STATION 1 2 VALUES < tII) 2 VALUES < IID Fk DOWNSTREAM I tra o\
- l. No.ntd LoE lrrd d lrcleodon (Ll,D) I dsct0sl ln TaDb E' 'l Z lrean nd Rmg! ba$d Wm ddrdlbh meaurrmnb mty. Fracilqr d rlebdalle nreaurqrmntr at spednod bodon h hdlcabd ln preldtctcs (F).
3 Elaric h m cofrrmr lndhdr no nffiurntE llEaJrlmqil3
Tenneseee Valley AuthorltY MDIOACTIVITY IN SHORELINE SEDIMENT PCUg = 0.037 Bqrg (DRY vlrElcFff) Name ol Fadllty: WATTS BAR NUCLEAR PI.ANT Dodet Number 50-390,391 Uoqrtlon of FadlltY RHEA. TENNESSEE ReportlrE Period: 2015 r . r a rao, ti Number of Locaflon wlth Hlgheet Annual Mean Controt Locatlons Nonroutlne Type and Lorcr Umit lndlcator LocaUons Mean (F) i*Iean (F) Reported Total Number of Detedlon Mean (R (LLD) Range Locatlon Desdptlon witt Rarqe Range MeasunmenE of Analysls Dlstrane and DirBGtS See Nole 2 See Note 2 See Note 3 Petbrmed See Nde.J Sce Note 2 GAlrfMA SGAN (GELD -4 AC-U,& 2.50E-01 1.19E+00 (2 I 2l COTTON PORT ITARI].lA 1.19E+00 (2/,21 1.15E+00 (21 2) 1.16E+fl1 1.23E+(D TRM 513 1.1$t+(X) - 1.23E+00 5.27E-O1 - 7.77E+fi BE-7 2.50E 01 3.40E-01 (1 l2l COTTON PORT i'ARINA 3.40E-01 (1 l2l 2 VALUES < LLD 3.40E{1 ! 3.40E-Ol TRM 513 3.40E-01 - 3.40E-01 Bl-212 4.50E{1 1.29E+fi1 (212l COTTON PORT MARINA 1.29E+fi) (212' 1.27E+q) (21 2l 1.28E+00 - 1.30E+00 TRM 5'3 1.28E+00 - 1.30E{O0 5.20E{1 2.01E+(n 1.50E{1 5.56E{1 (2121 @TTON PORT ifigPA 5.56E{11 (21 4 7.87E{1 (2 t 4 Ba-214 5.23E{1 - 5.89E-01 TRM 513 5.23E-01 - 5.89E-01 4.47E-O1 - 1.09E+fl) c$l37 3.008{2 2 VALUES < LLD COTTON PORT MARINA 2 VALUES < tID 2 VALUES < tJ.D H s(f TRM 513 {a \o 2.70E+01 (2 t 7.31E+U) (2121 b o lr I K-40 7.508-01 2.70E+01 (2 t 2) COTTON PORT MARI].IA 21 o *rI 2.48E+01 2.&4E+01 TRM 513 z$E+O1 2.9{E+01 2.36E+(P 1.23E+Ol rr Pb212 1.008{1 1.16E+q) e 12) COTTON PORT MARINA 1.16E+00 (2121 1.13E+00 (21 2' \t 1.08E+q) - 1.24E+(X) TRM 5{3 1,08E+00 - 1.24E+00 - 5.13E-01 1.74E+00 PB-214 1.50E-01 6.14E-01 (2121 COTTON PORT MARINA 6.14E{1 (2121 8.01E-ol (21 z',l. 5.&lE{1 - 6.45E-01 TRM 513 5.82E{1 - 6.45E{1 4.74E-01 - 1.13E+d) RA;224 7.508{1 1.34E+q) ( l2l COTTON PORT MARIhIA 1.3{E+00 (1 t 2l 1.70E+00 (1 t 2l 1.34E+(m - 1.t4f+fi) TRM 513 1.34E+00 - 1.34E+U) 1.7$f+@ - 1.76E+00 RA.ZM 1.50E-01 5.88E-01 (21 2' COTTON PORT MARINA 5.58E-01 (21 2l 7.67E-Ol (21 4 5.238-01 5.E98{r1 TRM 513 5.23E-01 ' 5'8gE'Ol 4.47E-O1 - 1.09E+00 TL-208 6.008{2 3.90E{1 t 2l COTTON PORT MARINA 3.90E 01 (21 2' 372E41 (2 t 21 3.E6E-01 12
- 3.948-01 TRM 513 3.86E-01 - 3.94E-01 1.66E{)1 - 5.79E-01
- 1. Nn{nd torFr lltrd ol Mo 0.fD) at dlctlbed h Tabb E - I Z UsanadRangebe$dWondeledaflrhnEarurantadrorly. FraodonddcEdaUomannsnrerGatcpcd[edbcetmblndlcdedlnpannfnaea(F).
- 3. Blsnls h td3 columl tdcab m nmrulillm rrealrlumflb
Tenneesee Valley Authorlty RADIOACTMTY IN POND SEDIMENT pGug o 0.G17 Bq/g (DRYWEIGHT) Name ol Fadlff WATTS BAR NUCLEAR PLANT I)odcet Number 5&390,391 Locatlon of Fadllty: RHEA, TENNESSEE Repordng Period: 2015 Number of Type and Lorer Limlt lndlcator Locdions Loca$on u,ith Hlghest Annual lllban Conbd Locatone Nonrcufins Toial Number ol D$cillon Mean (F) }lean (D Mean (F) Repotud of Analysb (LrD) Range Loca0on Descrlption wlth Range Range ItieagurementE Perfumed See N@ 1 See Nols 2 Diehne and Dtmdion Sea Note 2 See Note 2 See Nob 3 GA,iirim scAN (GELI) -5 AGlZ28 2.SIE-Ol 8.42E{1 (5 r 5) YP.l3 't.01E+@ (1 ,1) VALUES < LU' - 4.88E{1 - 1.01E+00 YARD POND I .01E+00 - 1.01E+(D BE 2.50E{1 2.79E-01 (1 5) YP.l3 2.798-01 (1 1) VALUES < LLD 2.79E-01 - ' 2.79E41 YARD POND 2.79E{ll - ' 2.79E41 Bl-212 4.50E-01 9.18E-01 (5 r 5) YP 1.13E+ff1 (1 ,1) VALUES < LLD 5.79E-01 - 1.13E+00 YARD POND I .1 3E+00 - 1 .13E+00 Bl-214 1.50E-01 6.42E-01 (5 r 5) Y?-5 E.13E-O1 (1 1) VALUES < LID 4.20E-01 - E.13E-O1 YARD POND 8.13E.01 - ' 8.13E-Ol co0 7.83E-AI2 (3 r 5) 1.29E-01 H t O 3.00E-02 4.30E-{r2 - 1.29E-Ol YP.5 YARD POND I .2gE-01 (1 1)
- ' 1.29E-01 VALUES < LLD so F.
o c$l37 9,848{[l LV 1.43E-Ol I 1l a 3.00E-ul 3.10E-0il (4 r 5}
- 1.43E.01 LO/i'VOLWASTE POND 1.43E{1 (1
- 1.41}E-Ol VALUES < LLD *.t h{
lra 6 K-f0 7.SlE-o1 1.07E+01 (5 5) Y?-13 1.54E+01 (1 1) VALUES < LID 5.95E+@ - ' 1.54E+01 YARD POND 1 .54E+01 - ' 1.54E+01 PA.234M 4.dlE+00 5 VATUES < LLD YP 1 VALUES < LtD VALUES < LLD YARD POND Pt212 1.00E-01 8.25E-Ot (5 5) YP.I3 1.05E+00 (1 ,1) VALUES < LLD
$.22EQ1 - ' 1.05E+00 YARD POND 1.05E+00 - 1.05E+ff1 P&l214 1.50E-01 7.(EE-01 (5 5) YP.l3 8.7:tE{1 (1 t 1) VALUES < LLD 4.76E-Ol a' 8.73E-01 YARD POND 8.73E{1 - 8.78E{lt R,';z.4 7.50E{ll 8.91E{1 (3 r5) YP 9.7eE-01 (1 1) VALUES < LLD 8.01E-01 - 9.76E-01 YARD POND 9.76E{1 - ' 9.76E-01 TL-209 6.00E-02 2.90E 01 (5 r 5) YP.I3 3.5ilE-01 (L 1) VATUES < LID 1.68E{l - 3.52E{ll YARD POND 3.54E{11 - 3.silE{ll LoEr: l. lbnlnd Lm]layslolDebcilon (ttD) rderybcd lnTeuc E- I
- 2. llom and RE rgp b8od upon dehdatile nEutlmenb only. Fncilor of d&claDle mear'gnsnb d speclied locdlon b hdhabd h pemnhelc (F).
- 3. Blanh3 ln $b column hdhrb no nonrumllnc m.ururErL
Figure H-l Direct Radiation Direct Radiation Leuels Watts Bar Nuclear Plant Four Quarter Moving Average InLight Dosirneter L gzo DeploYrnent Jan ua w, 2A07 o operation in ct= January, 1996 Eb I EoE I
-o at \15 E
E 2010 2015 Calendar Year
+On-Site --O-Off-Slte Dosimeters are processed quarrcrly. This chart shows fiends in the avemge rcasutement for all dosimeters gouped as "on-siten or 'off-site". The data fiom preoperational phase, prior to non-site" measurcments higher than noff-site" measutments that 1996, show the same hend of is obscrved in curent data indicating that the slightly higfuer "on-site'dirct radiation levels are not related to plant opcations.
- 8l '
Figure H-2 Radioactivity in Air Filters Annual Average Gross Beta Activity in Air Filters Watts Bar Nuclear Plant an E
\r e
L' e I E t a- {E
-# lndlcator +FControt As can be seen in the fiend plot of gtoss beta activity, the gross beta levels in air particularcs have remained relatively constant with the exception of years when the bea activity was elevated due to frllout from ntrclear weapour testing. The data also shows that thcre is no difference in the levels for sampling conductcd at the indicator stations as compared to the control stations. The Wams Barmonitoring Eogram was swpended for one lrear in 1989. The preopcr*ional monitoriag was restafied in 1990.
-t2 -
Figrre H-3 Cs-137 in Soil An nua I Average Activity of G-L37 in Soil Watts Bar Nuclear Plant 1.0 0.9 0.8 Initial WBN Operation in January, 1996 a.7 aE R 0.5 E Y
!0 \
a-0.5 (J B 0.4 I a 0.3 a-t a-o,2 0.1 0.0 197s 1980 1995 2000 2010 2015 Calendar Year
-# lndicator -EFControl Cesium-I37 was produced by past nuclear wcapons testing and is present in alrtost every ncontoln and nindicatorn locations environmental soil sample exposed to the atuosphere. The have generally trcnded downward with year-to-year variation, since the beginniqg ofthe \Vatts Bar monitoring program.
Figure H4 Gross Beta Activity in Surface Water Annual Auerage Gro$ Beta Actlyity ln Surface Water Watts Bar Nuclear Plant lnitial WBN Opsration in January, 19gG
+ lndicator (Downstream)
+F Control (Upstreaml As shown inthe graph, tbe Soss beA activity has ben essentially thc same in samples from tbs dormsheam and upstream locations. The average gross beta activity in thesc samples has becn rcpresentative of tbc levels measured during preoperational monitoring.
- 84'
Figrrre H-5 Gross Beta Activity in Drinking Water Annual Average Groos Beta Activity in Drfnking Water Watts Bar Nuclear Plant 6.00 s.00 Initial WBN Operation ln 4.00 Jarpary, 19gB J
- 9.00 ts a
a P.00 ET rt 1.00 0.00 I 975 1980 1985 1990 1995 2000 20t0 2015 CalsndarYear
+ Doilnstseem (lndicetorl
+ UpeUeam (Contrd)
Thc average gross betaactivity in ddnkingwater samplcs from the uptra.m contol locations has beenessentially the same as thc aotivity level measured in samples from the dormsheam indicator locations. The aonual average goss beta activity has been relatively constant since the swt ofplaot operations in 1996 and is slightly lower than preoperational levels. Figure H-6 Radioactivity in Fish Annua! Average Activity of G-L37 in Commerical Fish Watts Bar Nuclear Plant 0.30 0.25 a- 0.20 L E Y
\!0 f,-
0.15 lnitiat WBN Operation in January, 1996 (J c 0.10 I f
--t 0.05 E
0.00 1975
-F lndicator E Control Annual Average Actlvltyof G-L?7 ln Game Fish Watts Bar Nuclear Plant 0.30 0.25 a- 0.20 B
Y E InitialWEN Operation E 0.15 in Janualy, 1996
\aaa (J
B 0.10 a iY a-a: 0.05 iJ t 0.00 L97S
+ lndicator +Fcontrol Thc concentrations of Cs-137 found in fish are consistent with levcls prcsent in the Tcmessee River due to past afuospheric nuclear weapou testing and operation of other nuclear frcilities inthe upperreaches of the Tennessec River Watershed.
Figure H-T Radioactivity in Shoreline Sediment Annual Avercge ActMW of Cs-137 in Shoreline Sedlment Watts Bar Nuclear Plant 0.60 0.50 0.40 A E
?
U 0.30
\r !0
(, a-ca 0.20 a-t
'E a-0.10 0.00 1990 1995 2000 Calendar Year
+ Indicator +F control Thc Cs-137 prcscnt in the shoreline sodiments ofthe Tennessce River system rvas produced both by rcsting ofnuclear weapour and operation of othcr nuclcar frcilities in the upper reachcs ofthe Tennessee River Waiershed. The amounts of Cs-137 have declined significantly during the coutse of monitoring for the Watts Bar site, so much so that not all samples contain dercctable levels.
}}