ML17135A145
| ML17135A145 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 05/15/2017 |
| From: | Simmons P Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML17135A145 (84) | |
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{{#Wiki_filter:Tennessee Valley Authority, P.O. Box 2000, Spring City, Tennessee 37381-2000 May 15, 2017 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 - 2016 Enclosed is the subject report for the period of January 1,2016, through December 31,2016. 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 Kim Hulvey, WBN Licensing Manager, at (423) 365-7720. Respectfully, Paul Simmons Site Vice President Watts Bar Nuclear Plant
Enclosure:
Annual Radiological Environmental Operating Report - Watts Bar Nuclear Plant 2016 cc: See Page 2
U.S. Nuclear Regulatory Commission Page 2 May 15, 2017 cc (Enclosure): NRC Regional Administrator - Region ll NRC Project Manager - watts Bar Nuclear Plant NRC Senior Resident lnspector - Watts Bar Nuclear Plant
ENCLOSURE TEN NESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT Annual Radiological Environmental Operating Report Watts Bar Nuclear Plant 2016
Annual Radiological Environmental Operating Report Watts Bar Nuclear Plant 2016
AI{NUAL ENVIRONMEN'TAL RADIOLOGICAL OPERATING REPORT WATTS BAR NUCLEAR PLA}{T 2016 TENNESSEE VALLEY AUTHORITY April 2017
TABLE OF CONTENTS Table of Contents Executive Summary lnfroduction. . . . 2 Naturally Occuning and Background Radioactivity 2 Electric Power Production 3 Site/Plant Description Radiological Environmental Monitoring Program. Direct Radiation Monitoring l1 Measurement Techniques 11 Results. t2 Atnospheric Monitoring t4 SampleCollectionandAnalysis.... .... i..... t4 Results. 15 Terrestial Monitoring t6 Sample Collection and Analysis. . . . . l6 Results t7 Liquid Pathway Monitoring r8 Sample Collection and Analysis. . . . l8 Results l9 Assessment and Evaluation. . . 2t Results .:.... 2T Conclusions.. . .. 22 References. 23 Table I Comparison of Prograrn Lower Limits of Detection with Regulatory Limits for Maximum Annual Average Effluent Concentrations Released to Unrestricted Areas and Reporting Levels. . . . . . . . . . . 24 Figrre I TennesseeValleyRegiofl. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 25 Figrrre 2 Environmental Exposure Pathways of Man Due to Releases of Radioactive Materials to the Atrrosphereandlakg. . . . . . r . .. . . . . . . . . . . . . . . . . . . r . . . o . . . 26
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TABLE OF CONTENTS (continued) Appendix A Radiological Environmental Monitoring Program and Sampling Locations. 27 38 Appendix C Program Deviations. 40 Appendix D Analytical Procedures 43 Appendix ENominal lower Limits ofDetection (LLD). 46 Appendix F Quality Assurance,/Quality Control Program. 5l Appendix G Irnd Use Survey 56 Appendix H Data Tables and Figures 61
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DGCUTIVE
SUMMARY
This report describes the Radiological Environmental Monitoring Program (RElrfP) conducted by TVA in the vicinity of the Watts BarNuclear Plant (WBN).during the monitoring period of 2016. The program is conducted in accordance with regulatory requirements to monitor the environment per 10 CFR 20 and 10 CFR 50, and in accordance with TVA procedures. The REMP includes the collection and subsequent determination of radioactive material content in environmental samples. Various tlpes of sanrples are collected within the vicinity of the planL including air, water, milk, food crops, soil, fislr, shoreline sedimen! and the measurement of direct radiation levels. The radiation levels of these samples are measured and then compared with results at control stations located outside the plant's vicinity and data collected at WBN prior to operations (preoperationd data). This report contains an evaluation of the potential impact of WBN operations on the environment and general public. The vast majority of radioactivity measured in environmental samples from the WBN Fogram can be contributed to naturally occurring radioactive materials. Low levels of Cesium (Cs)-137 were measurd in soil, shoreline sediment, and fish samples. The concentrations wer typical of the levels expected to be present in the environment from past nuclear weapons testing or operation of other nuclear facilities in the regron. The fallout from accidents at the Chernobyl plant in the Ukraine in 1986 and the Fukushima plant in Japan in 201I may have also contibuted to the low levels of Cs-137 measured in environmental sarnples. Trace levels of titium were detected in atnospheric moisture samples. Also, titium, at a fraction of the EPA drinking water limit was detected in water samples collected from Chickamauga Reservoir. These levels would not represent a significant contibution to the radiation exposur to members of&e public. Tritium was detected in onsite Sound water monitoring wells. The titium was the result of onsite gromd water contamination from previously identified and repafued leaks in plant systems. In addition, cobalt (Co)-60 and Cs-137 were identified, above the nominal LLD, in sediment collected from the onsite ponds. The level of activity measurd in these onsite locations would not present a risk of expostre to the general public.
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INTRODUCTION This report describes and summarizes the resulrc of radioactivity measurements made in the vicinity of WBN and laboratory analyses of samples collected in the area The measurements are made to comply with the requirements of 10 CFR 50, Appendix A" Criterion 64 and 10 CFR 50, Appendix I, Section IV.B.2, IV.B.3 and IV.C and to determine potential effects on public health and safety. This report satisfies the annual reporting requirements of WBN Technical Specification 5.9.2 and Offsite Dose Calculation Manual (ODCM) Administrative Contol5.l. In addition to reporting the data prescribed by specific requirements, other information is included to help correlate the significance of results measnred by this monitoring program to the levels of environmental radiation resulting from naturally occurring radioactive materials. Naturallv Occunine aod Backeround Radioactivitv Most materials in our world today contain tace amounts of nattually occurring radioactivity. Potiusium (K)-40, with a half-life of 1.3 billion years, is one of the major tpes of radioactive materials formd naturally in our environment. Approximately 0.01 percent of all potassium is radioactive potassium-4O. Other examples ofnaturally occur.ring radioactive materials are beryllinm (Be)-7, bismuth (Bi)-212 and2l4,lead (Pb)-212 and 214, thallium (Tl)-208, actiniun (Ac)-228,uranium (U)-238 and,23l,thoritrm CIh)-234, radium (Ra)-226,radon (Rn)-222 and 220, carbon (C) -14, and hydrogen (H)-3 (generally called titium). These naturally occuning radioactive materials are in the soil, our food our drinking water, and our bodies. The radiation from these materials makes up a part of the lowJevel natural background radiation. The remainder of the natural background radiation results from cosmic rays. It is possible to get an idea of the relative hazud of different types of radiation sources by evaluating the amount of radiation the U.S. population receives from each general tlpe of radiation sounce. The information below is primarily adapted from References 2 and 3. U.S. GENERAL POPULATION AVERAGE DOSE EQUIVALENT ESTIMATES Source millirem (mrem)'/Year Per Person Nattual background dose equivalent Cosmic 33 Tenestrial 2t In the body 29 Radon 228 Total 3ll Medical (effective dose equivalent) 300 Nuclear energy a.2g Consumer products l3 Total 624 (approximately)
- l. One-thousandth of a Roentgen equivalent man Gem)
As can be seen from the datapresented above, natural background radiation dose equivalelrt to the U.S. population normally exceeds that from nuclear plants by several hundred times. This indicates that nuclear plant operations normally result in a population radiation dose equivaleirt u&ich is insignificant as compared to the dose from natual background radiation. It should be noted that the use of radiation and radioactive materials for medical uses has resulted in a similar effective dosc equivalent to the U.S. population as that cansed by natural backgrormd cosmic and terrestial radiation. Electic Power Production Nuclear power plants are simifus in many respects to conventional coal burning (or other fossil fuel) electical generating plants. The basic prooess behind electical power production in power plants is that fuel is used to heat water to produce steam which provides the force to tunr trubines and generators. In a nuclear power planL the fuel is uranium and heat is produced in the reactor though the fission of the uranium. Nuclear plants include many complex systems to control the nuclear fission process and to safeguard against the possibility of reactor malfirnction. The nuclear reactions produce radionuclides commonly referred to as fission and activation products. Very small amounts of these fission and activation products are released into the plant systems. This radioactive material can be tansported throughout plant systems and some of it may be released to the environment. Paths through which radioactivity from a nuclear power plant is routinely released are monitored. Liquid and gaseous efluent monitors record the radiation levels for each release. These monitors also provide alam mechanisms to prompt tnnination of any nelease above limits. Releases are monitored at the onsite points of release and through the radiological environmental monitoring progam which measures the environmental radiation in areas around the plant In . this way, the release of radioactive materials from the plant is tightly contolled, and 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 Spccifications, prescribes limits for the release of radioactive efluents, as well as limih for doses to the general public from the release of these effiuents. The dose to a member of the general public from radioactive materials released to unresEicted arEas, as given in Nuclear Regulatory Commission (NRC) guidelines and the ODCM, is limited as follows: LiouidEfluents Total body <3 mrem/Year Any organ Gaseous Effluents Noble gases: Gamma radiation <10 millirad (mrad)/Year Beta radiation <20 mrad/Year Particulates: Any organ <15 rnrem/Year 4-
The EPA limits for the total dose to the public in the vicinity of a nuclear power planq established in the Environmental Dose Standard of 40 CFR 190, are as follows: Total body <25 mrern/year Thyroid s/5 mrem/year Any other organ <25 mrern/year Appendix B to 10 CFR 20 presents annual average limits for the concentations of radioactive materials released in gaseous and liquid efluents at the boundary of the unresticted areas. Table I of this report presents the annual average concentration limits for the principal radionuclides associated with nuclear power plant efluents. The table also presents the concentations of radioactive materials in the environment which would requirc a special rport to the NRC and the detection limits for measured radionculides. It should be noted that the levels of radioactive materials measured in the environment are typically below or only slightly above the lower limit of detection. SITE/PLA}.IT DESCRIPTION The WBN site is located in Rhea @uU, Tehnessee, on the west bank of the Teonessee River at Tennessee Nver Mile (TRM) 528. Figure I shows the site in relation to other TVA projects. The WBN site, containing approximately 1770 acres on Chickamauga Laken is approximaGly 2 miles souttr of the Watts Bar Dam and approximately 3l miles north-northeast of TVA's Sequoyah Nuclear Plant (SQN) site. Also located wiein the resenration are the Wans Bar Dam and Hydro-Electic Plant, the Watts Bar Steam Plant (not in operation), the TVA Cental Maintenance Facility, and the Watts Bar Resort Area Approximately 18,500 people live within l0 miles of the WBN site. More than 80 pencent of these live between 5 and l0 miles from the site. Two small towns, Spring City and Decatur, are located in this area Spring City, with apopulation of approximately 2,200, is northwest and north-northwest from the site, while Decatur, with about 1,500 people, is south and south-southwest from the plant The remainder of the area within l0 miles of the site is sparsely populated, consisting primarily of small farms and individual residences. The area between l0 and 50 miles fiom the site includes portions of the cities of Chattanooga and l(noxville. The largest urban concenfration in this area is the city of Chattanoogq located to the southwest and south-southwest. The city of Chattanooga has a population of about 170,000, with approximately 80 percent located between 40 and 50 miles fiom the site and the remainder located beyond 50 miles. The city of Knoxville is located to the east-northeast with not more than l0 percent of its 185,000 phs people living within 50 miles of the site. Three smaller urban areas of greater than 20,000 people are located betlveen 30 and 40 miles from the site. Oalc Ridge is approximately 40 miles to the northeast, the trnin cities of Alcoa and Maryville are located 45 to 50 miles to the east-northeasL and Cleveland is located about 30 miles to the south. Chickamauga Rescrvoir is one of a series of highly controlled multiple-rse reservoirs whose primary uaes are flood contol, navigation, and the generation of electric power. Secondary uses include industrial and public water supply and waste disposal, fishing, and recreation. Public ac@ss areiasr, boat docks, and residential subdivisions have been developed along the resenroir shoreline.
WBN consists of two pressurized water reactors. WBN Unit I received a low power operating Iicense (NPF-20) on November 9,1995 and achieved initial criticality in January 1996. The full power operating license (NPF-90) was received on February 7,1996. Commercial operation was achieved May 25,1996. WBN Unit 2 was deferred October 24,2OOO,in accordance with the guidance in Generic Letter 87-15, '?olicy Statement on Deferred Plaots.' On Augtst 3,2W7, TVA provided notice of ie intent to reactivate and complete constrtrction of WBN Unit 2. WBN Unit 2 resuned conshrction in late 2007. October 22,2015 the operating license was issued. Initial criticality was achieved on May 23,2016 and commercial operation was achieved on October 19,2016.
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Most of the radiation and radioactivity generated in a nuclear power reactor is contained within the reactor systems. Plant efluent radiation monitors are designed to monitor radionuclides released to the environment. Environmental monitoring is a final verification that the systems are performing as plaoned. The monitoring program is designed to monitor the pathways between the plant and the people in the immediate vicinity of the plant. Sample tlpes are chosen so that the potential for detection of radioactivity in the environment will be maximized. The Radiological Environmental Monitoring Program (RElt{P) and sampling locations for WBN are outlined in Appendix A. There are two primary pathways by which radioactivity can move through the environment to hnmans: air and water (see Figrue 2). The air pathway can be separated into two components: the direct (airbome) pathway and the indirect (ground or (errestrial) pathway. The direct airbome pathway consists of direct radiation and inhalation by humans. ln the terrestrial pathunay, mdioactive materials may be deposited on the ground or on plants and subsequently ingesrcd by animals and/or hunans. Human exposure througlr the liquid pathway may result from &inking water, eating fish, or by direct exposure at the shoreline. The tlpes of sarrples collected in this progrcno are designed to monitor these pathways. A number of factors were considered in determining the locations for collecting elrvironmental samples. The locations for the atmospheric monitoring stations were detennined from a critical pathway analysis based on weather patterns, dose projections, population distibution, and land use. Terrestrial sampling stations were selected after reviewing susfu things as the locations of dairy enimals and gardens in conjunction with the air pathuay analysis. Liquid pathnay stations were selected based on dose projections, water use informatio& and availability of media such as fish and sediment. Table A-2 (Appendix A, Table 2: This notation system is used for all tables and figures given in the appendices.) lists the sampling stations and the tyryes of samples collected from each. Modifications rnade to the WBN monitoring program in 2016 are reported in Appendix B. Deviations to the sampling program during 2016 are included in Appeirdix C. To daermine the amount of radioactivity in the environment pnor to the operation of WBN, a preoperatiooal radiological environmental monitoring program was initiarcd in Docember 1976 and operated through December 31, 1995. Measurements of the same types of radioactive materials that are measured currently were assessed duing the preoperational phase to establish normal background levels for various radionuclides in the environment. During the 1950s, 1960s, and 1970s, atnospheric nuclear weapons testing released radioactive material to the environment causing fluctuations in backgrormd radiation levels. Ifuowledge of preexisting radionrclide patterns in the environment pemrits a determination, through comparison and hending analyses, ofthe actual environmental impact of WBN operation. The determination of environmental impact during the operating phase also considers the presence of control stations that have been established in the environment. Results of environmental samples taken at contol stations (far from the plant) are compared with those from indicator stations (near the plan$ to aid in the determination of the impacts from WBN operation. 1[s samfle analysis is performed by the Tennessee Valley Auttrority's (TVA's) Environmental Radiological Monitoring and Instnrmentation (ERIvI&I) group located at the Western Area Radiological Laboratory (WARL) in Muscle Shoals, Alabama, except for the sfrontium (Sr)-89, 90 analysis of soil samples which is performed by a contract laboratory. Analyses are conducted in accordance with written and approved procedures and are based on accepted mefhods. A summary of the analysis techniques and methodology is presented in Appendix D. Data tables summarizing the sample analysis results are presented in Appendix H. The radiation detection devices and analysis methods used to determine the radionuclide content of sarnples collected in the environment are very sensitive to small amounts of radioactivity. The sensitivity of the measurement plocess is defined in terms of the lower limit of detection (LLD). A description of the nominal LLDs for the ERM&I laboratory is presented in Appendix E.
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The ERM&I laboratory operates under a comprehensive quality assnrance/quality contol program to monitor laboratory performance throughout the year. The program is intended to detect any problems in the measurement process as soon as possible so they can be corrected. This program includes equipment checks to ensure that the radiation detection instruments are working properly and the analysis of quality control samples which are included alongside routine environmental samples. To provide for interlaboratory comparison program, the laboratory participates in an environmental cross-check program administered by Eckert and Ztegler Analytics. A complete description ofthe program is presented in Appendix F.
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DIRECT RADIATION MONITORING Dircct radiation levels are measured at various monitoring points around the plant site. These measurements include contibutions fiom cosmic radiation, radioactivity in the ground, fallout from afuospheric nuclear weapons tests conducted in the past, and any radioactivity that may be present as a result of plant operations. Because of the relatively large variations in background radiation as compared to the small levels from the plan! contibutions from the plant may be difficult to distinguish. Measurement Techniques The Landauer Inlight environmental dosimeter is used in the radiological environmental monitoring progam for the measurement of direct radiation. This dosimeter contains four elments consisting of aluminum oxide detectors with open windows as well as plastic and copper filters. The dosimeter is processed using optically stimulated luminessense (OSL) technology to determine the amount of radiation exposure. The dosimeters are placed approximately one meter above the ground, with trryo at each monitoring location. Sbrcn monitoring points are located around the plant near the site boundary, one location in each of the 16 compass sectors. One monitoring point is also located in each ofthe 16 compass sectors at a distance of approximately four to five miles from the plant. Dosimeters are also placed at additional monitoring locations out to approximately 15 miles from the site. The dosimeters are exchanged every three months. The dosimeters are sent to Iandauer Inligbt for processing and results reporting. The values are corrected for tansit and shielded background exposure. An average of the two dosimeter results is calculated for each monitoring point. The system meets or exceeds the performance specifications outlined in American National Standards lnstitute (AI.ISI) N545-I975 and Health Physics Society GPS) Drafr Standard N13.29 for environmental applications of dosimeters. WBN Technical Specification 5.9.2,Anrua1Radiological Environmental Operating Report requires that the Annual Radiological Environmental Operating Report identify TLD results that represent collocated dosimeters in relation to the NRC TLD program and the exposure period
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associated with eaph result. The NRC collocated TLD program was terminated by the NRC at the end of 1997,therefore, there are no TLD results that represent collocated dosimeters included in this rport Results The resulg for environmental dosimeter measurements are norrralizqdto a standard quarter (91.25 days or 2190 hours). The monitoring locations are grouped according to the distance from the plant The first group consists of all monitoring points within 2 miles of the plant The second group is made up of all locations greater than 2 miles from the plant Past data have shown that the average results from the locations more than 2 miles from the plant are essentially the same. Therefore, forpurposes of this rporq monitoring points 2 miles or less from the plant are identified as "onsite" stations and locations greater than 2 miles are considered "offsite." The quarterly gamma radiation levels determined from the dosimeters deployed arormd WBN in 2016 are summarizednTable H-1. The exposurcs are measured in milliroentgens (mR). For purposes of this rpo$ one mR, one ilum and one mrad are assumed to be numerically equivalent The rounded average annual exposures, as measured lm20l6,are shonm below. For comparison purlDses, the average direct radiation measurements made in the prmperational phase ofthe monitoringprogram are also shown. Annual WBN Average Direct Radiation Levels mR/Year Preoperational 2016 Average Onsite Stations 69 65 Offsite Stations 65 57
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The data in Table H-l indicates that the average quarterly direct radiation levels at the WBN onsite stations are approximately 0.9 mR/quarter higher than levels at the offsite stations. This equates to 3.7 mR/year detected at the onsite locations. This value falls below the EPA limit of 25 mrem/year total body. The difference in onsite and offsite averages is consistent with Ievels measured for the preoperational and construction phases of TVA nuclear power plant sites where the average levels onsite were slightly higher than levels offsite. Figure H-l compares plots of the data from the onsite stations with those from the offsite stations over the period from 1977 through 2016. The new Landauer Inlight Optically Stimulated Luminescence (OSL) dosimeters were deployed since 2007 replacing the Panasonic UD-814 dosimeters used during the previous yearc. The data in Table H-2 contains the results of the individual monitoring stations. The results reported in 2016 are consistent with direct radiation levels identified at locations which are not influenced by the operation of WBN. There is no indication that WBN activities increased the background radiation levels normally observed in the areas surrounding the plant. ATMOSPHERIC MONITORING The atnospheric monitoring network is divided into three groups identified as local, perimeter, and remote. Four local air monitoring stations are located on or adjacent to the plant site in the general directions of greatest wind frequency. Four perimeter air monitoring stations are located between 6 to l l miles from the plang'and two air monitors are located out to 15 miles and used as control or baseline stations. The monitoring program and the locations of monitoring stations are identified in the tables and figures of Appendix A. Results from the analysis of samples in the atuospheric pathway are prcsented in Tables H-3, H-4, and H-5. Radioactivity levels identified in this reporting period are consis"tent with background and preoperational program data. There is no indication of an increase in atuospheric radioactivity as a result of WBN operations. Sample Collection and Analysis Air particulates are collected by continuously sampling air at a flow rate of approximately 2 cubic feet per minute (cfo) tbrough a 2-inch glass fiber filter. The saurpling system consists of a Vacuum Florescent Display (VFD), a bnrshless motor, and a precision-machined mechanical ditrerential pressure flow sensor. It is equipped with automatic flow control, on-board data storage, and alarm notifications for flow, P, T, and higher filter DP. This system is housed in a weather resistant environnrental enclosure approximately 3 feet by 2 feet by 4 feet. The filter is contained in a sampling head mounted on the outside of the monitoring building. The filter is replaced weekly. Each filter is analped for gross beta activity about 3 days after collection to allowtime forthe radon daughters to decay. Every 4 weeks composites ofthe filters fiom each location are analyzed by gamma spectroscopy. Gaseous radioiodine is sampled using a cominercially available cartidge containing Triethylenediamine (TEDA)-impregnated charcoal. This system is designed to collect iodine in both the elemental form and as organic compounds. The cartridge is located in the sarne sampling head as the air particulate filter and is downsteam of the particulate filter. The cartridge is changed at the same time as the particulate filter and samples the same volume of air. Each cartidge is analped for I-l3l by gamma spectroscopy analysis. Atuospheric moisture sampling is conducted by pulling air at a constant flow rate through a column loaded with approximately 400 grams of silica gel. Every two weeks, the column is exchanged on the sampler. The atmospheric moisture is removed from silica gel by heating and analyzed fortitium. Results The resuls from the analysis of air particulsts samples are strmmarized in Table H-3. Gross beta activity in 2016 was consistent with levels reporrcd in previous years. The average gross beta activity measured for air particulate samples was 0.020 pCi/m3. The annual averages of the gross beta activrty in air particulate filters at these stations for the period 1977-2016 arc presented in Figurc H-2. lncreased lerrels due to fallout from atuospheric nuclear weaporur testing are evident in the years prior to l98l and a small increase from the Chernobyl accident can be seen in 1986. These patterns are consistent with data from monitoring programs conducted by TVA at other nuclear power plant construction sites. Comparison with the same data for the preoperational period of 1990-1995 indicats that the annual average gross beta activity for air particulates as measured in the 2016 monitoring program was consistent with the preoperational data Only natural radioactive materials were identified by the monthly gamma spectal analysis of the air particulate samples. As shorm in Table H4, I-l3l was not detected in any charcoal cartridge samples collected in 2016. The results for atnospheric moisture sarrpling are reported in Table H-5. Tritium was measured, above the nominal LLD value of 3.0 pCi/m3, in affiospheric moisture samples from both the indicator and contol locations. The highest concentration from the indicator locations was 7.4pCilm3 and the highest concenfration from the confrol locations was 5.2 pCi/m3.
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TERRESTRIAL MONITORING Terrestial monitoring it apssmFlished by collecting samples of environmental media that may tansport radioactive material from the atnosphere to humans. For example, radioactive material may be deposited on a vegetable garden and be ingested along with the vegetables or it may be deposited on pasture grass where dairy caule are grazing. When the cow ingests the radioactive material, some of it may be hansfened to the milk and consumed by humans who drink the milk. Therefore, samples of milk, soil, and food crops are collected and analyzed to determine potential impacs from exposure through this pathway. The results from the analysis of these samples are shown in Tables H-6 through H-l l. A land use survey is conducted annually between April and October to identify the location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 5fi) square feet producing fresh lea$ vegetables in each of 16 meteorological sectors within a distance of 5 miles from the plant. This land use surrey satisfies the requirements 10 CFR 50, Appendix I, Section IV.B.3. From data produced by the land use suwey, radiation doses are projected for individuals living near the plant Doses from air submersion are calculated for the nearest residence in each s@tor, while doses from drinking milk or eating foods produced near the plant are calculated for the areas with milk-producing animals and gardens, respectively. These dose projectioru are hypothetical extremes and do not represent actual doses to the general public. The results of the 2016 land use survey are presented in Appendix G. Sample Collection and Analvsis Milk samples ar collected every two weeks from two indicator dairies and from at least one contol dairy. Milk samples af,e placed on ice for transport to the radioanalytical laboratory. A radiochemical separation analysis for I-l3l and a gamma spectral analysis are performed on each sample and Sr-89,90 analysis is perfomred quarterly. The monitoring program includes a provision for sampling of vegctation from locations where milk is being produced and when milk sampling cannot be condusted. There were no periods during this year when vegetation sampling was necessary.
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Soil samples are collected annually from the air monitoring locations. The samples are collected with either a "cookie cutter'or an auger tlpe sampler. After drying and grinding the sample is analyzed by gamma spectoscopy and for Sr-89 and Sr-90.
$amples representative of food crops raised in the area near the plant are obtained from individual gardens. Tlryes of foods may vary fiom year to year as a result of changes in the local vegetable gardens. $amples of cabbage, conl green beans, and tomatoes were collected from local vegetable gardens and/or farms. $emfles of the same food products gtown in areas that would not be atrectd by the plant were obtained from area produce markets as contol samples.
The edible portion of each sample is analyzed by gamma spectoscopy. Results The rcsults from the analysis of milk samples are presented in Table H-6. No radioactivity attributable to WBN Plant operations was identified. All I-l3l values were below the established nominal LLD of 0.4 pCi/liter. The gamma isotopic analysis detected only nahrally occurring radionuclides. The results for the quarterly Sr-89 and Sr-90 analyses were below the established LLD's for these analyses. Consistent with most of the environnen! Cs-137 was detected in the majority of the soil samples collected in 2016. The maximrrm corctrtotion of Cs-137 was 0.38 pCi/g. The concentations werp consistent with levels previously reported from fallout All other radionuclides reported were naturally occurring isotopes. The results ofthe analysis of soil samples are summarized in Table H-7. Aplot of the aonual average Cs-137 concentrations in soil is presented in Figure H-3. Concentrations of Cs-137 in soil are steadily decreasing as a result of the cessation of weapons testing in the atuosphere, the 30 year half-life of Cs-137, and tansportthrough the environment. The radionuclides measured in food samples were naturally occurring. The results are reported in Tables H-8 through H-l l. LIOUID PATHWAY MONITORING Potential exposures from the liquid pathway can occur from drinlcing water, ingestion of fis[ or from direct radiation exposue from radioactive materials deposited in the shoreline sediment. The aquatic monitoring program includes thc collection of samples of river (surface) watcr, ground water, drinking water supplies, fislU and shoreline sediment Indicator samples were collected dortnstream of the plant and conEol samples collected within the reservoir upsteam of the plant or in the next upsteam resewoir (Watts Bar Lalce). Sample Collection and Analvsis
$amfles of surface water are collected from the Tennessee River using automatic sampling systems from two doumstneam stations and one upsteam station. A timer firms on the system at least once every two hours. The line is flushed and a sample is collected into a composite container. A one-gallon sample is removed from the container at 4-week intervals and the remaining water is discarded. Each sample is analyzed for gamma-emiuing radionculides, gnoss beta activity, and titium.
Samples are also collected by an automatic sampling system at the first truo downstream drinking water intakes. These samples are collected in the same manner as the surface water samples. These monthly samples are analyzed for gamma-emitting radionuclides, gross beta activity, and titium. The samples collected by the automatic sampling device are taken directly from the river at the intake structure. Since these samples are unteated water collected at plant intalce, the upstream surface water sample is used as a contol sample for drinking water. Cnound nater is sampled from one onsite well down gradient from the plan! one onsite well up gradient from the planq and four additional onsirc ground water monitoring wells located along underground discharge lines. The onsite wells are sampled with a continuous sampling system. A composite sample is collected from the onsite wells every four weeks and analped for gamma-emitting radionuclides, gross beta activity, and tritium content. Samples of commercial and game fish species are collected semiannually from each of trno reservoirs: the reservoir on which the plant is located (Chickamauga Reservoir) and the
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upsteam rcservoir (Watts Bar Reservoir). The samples are collected using a combination of netting techniques and electrofishing. The ODCM spwifies analysis of the edible portion of the fish. To comply with this requiremen! filleted portions are taken from several fish of each species. The samples are analped by gamma specfioscopy. Samples of shoreline sediment are collected from reueation arsas in the vicinity of the plant The samples are dried, grormd, and analyzed by gamma spectoscopy. Samples of sediment are also collected from the onsite ponds. A total of five samples were collected in 2016. The samples are dried, ground, and analped by gamma spectoscopy. Results Crloss beta activity was detectable above the nominal LLD in most ofthe surface water samples. The gross treta concentations averaged 3.0 pCi/titer in dormsteam (indicator) samples and 2.3 pCilLin upsfream (control) samples. These levels were consistent with results found during the preoperational monitoring program. The gammz isotopic analysis of surface water samples identified only naturally occurring radionuclides. Low levels of Eitium were detected in some strrfrce water samples. The highest tritium concentration was 1,620 pCrlliter which is significantly below the EPA &inking water limit of 20,000 pCi/liter. A summary table of the results for surface water samples is shown in Table H-12. The annual average gross beta activity in snrface water samples for the period 1977 through 2016 aepresented in Figur H4. No fission or activation products were identffied by the gamma analysis of &inking wakr samples from the two downstream monitoring locations. Average gross beta activity at downstream (indicator) stations was 2.3 pCi/liter and the average for the upsteam (contnol) station was 2.3 pCi/liter. Low levels of titium were detected in approximately half of the samples collected from the two downstream public water sampling locations. The highest tritium concentration was 1,010 pCifliter. The titium levels were significantly below the EPA drinking water limit of 20,000 pCi/liter. The results are shown in Table H-l3. Trend plots of the gross beta activity in drinking water samples from1977 through 2015 are presented in Figure H-5.
-l9-
The gamma isotopic analysis of ground water samples identified only nafirally occurring radionuclides. Gross beta concentrations in samples from the onsite indicator locations averaged 3.1 pCi/liter. The average gross beta activrty for samples from the contol locations was 2.3 pCilhter. Trititim was detected in samples from the onsite monitoring wells located near plant discharge lines. The titium in onsite ground water was the result of previously identified leaks from plant systems. Repairs were made to resolve the leaks but ttre plume of contaminated ground water continues to move slowly acnoss the sirc toward the river. The highest titium concentration in samples from these monitoring locations was 1,130 pCi/liter. There was no tritium detected in the onsite up gradient well. The results are presented in Table H-14. Cs-137 was identified in one 6sh samFle. The Cs-l3Z concentation was 0.03 pcilg measrned in game fish collected at the upstream location. Other radioisotopes found in fish were naturally occurring, with the most notable being K40. The results arc surnmarized in Tables H-15 and H-
- 16. Trend plots of the annual ayerage Cs-I37 concentations measured in fish samples are presented in Figure H-6. The Cs-137 activities are consistent with preoperational results produced by fallout or efluents from other nuclear facilities.
Cs-I37, consistent with the concentations present in the environment as the result of past nuclear weapons testing or other nuclear operations in the area, was measured in one shoreline sediment sample. The results for the analysis of shoreline sediment are presented in Table H-I7. Trend plots of the average concentation of Cs-137 in shoreline sediment arre presented in Figure H-7. Consis'tent with previous monitoring conducted for the onsite ponds, Cs-137 was detected in the sediment samples. The average of the Cs-137 levels measurcd in sediment from the onsite ponds was 0.09 pCi/gm. In addition, Co-60 was 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 pCi/gm. The results for the analysis of pond sediment samples are provided in Table H-18. Since these radionuclides were present in relatively low concentrations and confined to the ponds located in the owner conEolled area not open to the general public, the presence of these radionuclides would uot represent an increased risk of exposure to the general public. ASSESSMENT Al.lD EVALUATION Potential doses to the public are estimated from measured effluents using computer models. These models were developed by TVA and are based on guidance provided by the NRC in Regulatory Guide 1.109 for determining the potential dose to individuals and populations living in the vicinity of the plant. The results of the effIuent dose calculations are reported in the annuat Radiological Efluent Release Report. The doses calculated are a representation of the dose to a "maximum exposed individual." Some of the factors used in these calculations (such as ingestion rates) are manimum expected values which will tend to overestimate the dose to the "hypothetical" person. The calculated ma:rimum dose due to plant efluents are small fractions of the applicable regulatory limits. In reality, the expected dose to actual individuals is significantly lower. Based on the very low concentations of radionuclides actually present in the plant effluents, radioactivity levels measured in the environmen! as result of plant olrcrations, are expected to be negligible. The results for the radiological environmental monitoring conducted for WBN 2016 operations confirm this expectation. Results As staGd earlier in this repoft, the estimated increase in radiation dose equivalent to the general public resulting from the operation of WBN is insignificant when compared to the dose from natral background radiation. The results from each environmental sample are compared with the concentations from the corresponding contol stations and appropriate preoperational and background datato determine influences from the plant. During this report period, Cs-137 was detected in soil, sediment and fish collected forthe WBN program. The Cs-137 concentations were consistent with levels measured during the preoperational monitoring program. The levels of titium measured in water samples from Chickamauga Reservoir represented concentrations that were a mall fraction ofthe EPA drinking water limit. The levels of tritium detected in the onsite ground water monitoring wells and the radionuclides measured in samples of sediment from the onsite ponds do not represent an increased risk of
-2t-
exlrosure to the public. These radionuclides werie limited to the owner confiolled area and would not prcsent an exposur pathway for the general public. Conclusions It is concluded fiom the above analysis of environmental samples and from the tend plots presented in Appendix H, that exposure to members ofthe general public which may have bcen attributable to WBN is negligible. The radioactivity reported herein is primarily the result of fallout or natural backgound. Any activity which may be present in the environment as a result ofplant operations does not rcpresent a significant contribution to the exposure of members of the public. a2-
REFERENCES
- l. Menil Eisenbud, Environmental Radioactivitv. Academic Press, Inc., New Yorlq NY, 1987.
- 2. National Council on Radiation Protection and Measnrements, Report No. 160, "Ionizing Radiation Exposure of the Population of the United States,,'March 2009.
- 3. United States Nuclear Regulatory Comnissio& Regulatory Guide 8.29, "Instruction Concerning Risks from Occupational Radiation Exposnt," Febnrary t996.
Tablc I COMPARISON OF PROGRAM LOWER UMITS OF DETECTION WITH THE REGULATORY LIMITS TOR MAXIMUM ANNUAL AVERAGB EFFLUENT CONCENTRATIONS RELEASED TO I.'NRESTRICTED AREAS AND REPORTING LEVELS Concentrations in Water. pCi/Liter Concentrations in Air. pCi/Cubic Meter EffIuent Reporting Lower limit Effluent Reporting Lower limit Analysis Concenhationl Lrvel2- of Detection3 Concentrationl I**t'- of Delgction3 H-3 1,000,000 20,000 270 100,000 Cr-51 500,000 45 30,000 Mn-54 30,000 1,000 5 1,000 Co-S8 20,000 1,000 5 1,000 Co-60 3,000 300 5 50 Zn-65 5,000 300 400 Sr-89 8,000 1,000 Sr-90 500 1 6 Nb-9s 30,000 400 5 2,000 -- 0.005 k-95 20,000 l0 400 0.005 Ru-103 30,000 3', 5 900 -- 0.005 Ru-106 3,000 40 20 -- 0.02 I-13 I 1,000 2 0.4 200 0.9 0.03 Cs-134 900 30 5 200 l0 0.005 Cs-137 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 La-140 9,000 200 l0 2,000 0.01 Note: I pCi : 3.7 xl0'2 Bq. Note: For thoc rcporting levels and lower limits of detection that re blank, no value is given in the reference.
- l. Source: Table 2 of Appendix B to 10 CFR 20. 100 I -20J/i01
- 2. Sonrce: WBN Oftite Dose Calculation Manual, Table2.3-2.
- 3. Source: Table Bl of this reporl I
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Figure 2 EN\,I]TCINMENTAL E)(PC!BL,FE PATHI,VAYA ClF MAN EIUE TCl FIELEASEE ClF FIAEIICIACTI\,E MATEHIAL TCl THE ATMCISPHE]IE ANE' LAKE. Airborne Beleases PI um8 Exposure D Liquid Beleases Diluted By lake MAN Consumed By illan Animals tililk,teatl Shoreline Exposule Gofirro By Animals Drinking Water Fish Uegetation Uptake From Soi! APPENDXA RADIOLOGICAL W MOMTORING PROGRAIU A}ID SAIVIPLING LOCATIONS a7-
Table A-l WATTS BAR NUCLEAR PLANT RADIOLOGIC AL E}-TIYIRONMENTAL MOMTORING PROGRAM" Exposure Pathway Number of Samples and Sampling and Ty?e and Frequency and/or Sample Locationsb Collection Frequency ofAnalYsis I. AIRBORNE
- a. Particulates 4 samples from locations (in differcnt Continuous sampler operation with -
Analyze for gross beta radioactivity sectors) at or near the site boundary sample collection weekly (more greater than or equal to 24 hours (LM-1,2,3, and 4). (frequently if required by dust following filter change. Perform loading). gamma isotopic analysis on each sample if gross beta is greater than l0 times yearly mean of control sample. Composite at least once per 3l days (bV location) for gamma scan. 4 samples from communities approximately 6-10 miles from the plant (PM-2, 3,4, and 5). 2 samples from control locations greater than l0 miles from the plant (RlvI-2 and 3).
- b. Radioiodine Samples from same locations as air Continuous sampler operation with I- 13 I at least once per 7 days.
particulates. filter collection weekly. Analysis is performed by gamma spectroscopy.
- c. Atmospheric 4 samples from locations (in different Continuous sampler operation with Analyze each sample for tritium.
Moismre sectors) at or near the site boundary sample collection biweekly. (LM-lr2r 3, and 4) 2 samples from communities approximately 4-10 miles distance from the plant (PM-Z,5). Table A-l WATTS BAR NUCLEAR PLAI{T RADIOLOGICAL EIWIRONMENTAL MOMTORING PROGRAM" Exposure Pathway Number of Samples and Sampling and Type and Frequency and/or Sample Locationsb Collection Frequency of Analvsis
- c. Atmospheric 2 samples from control location Moisture (Cont.) greater than t0 miles from the plant (RIVI-2 and RM-3).
- d. Soil Samples from same location as air Once per year. Gamma scan, Sr-89, Sr-90 once per particulates. year.
- 2. DIRECT 2 or more dosimeters placed at or At least once per 92 days. Gamma dose at least once per 92 near the site boundary in each of the days.
16 sectors. 2 or more dosimeters placed at stations located approximately 5 miles fiom the plant in each of the 16 sectors. 2 or mone dosimeters in at least 8 additional locations of special interesf including at least 2 control stations. Table A-l WATTS BAR NUCLEAR PLANT RADIOLOGI CAL E}WIRONMENTAL MONITORING PROGRAM" Exposure Pathway Number of Samples and Sampling and Type and Frequency and/or Sample Locationsb Collection Frequency of Analysis
- 3. WATERBORNE a Surface 2 samples downstneam from plant Collected by automatic sequential- Gross baq gamma scan, and tritium discharge (TRM 517.9 and TRM type samplef witr composirc mmples analysis of each sample.
523.1). collected over a period of approximately 3l days. I sample at a contol location upstream from the plant discharge (rRM 529.3).
- b. Ground Five sampling locations from ground Collected by automatic sequcntial- Gross beta, gamma scan, and tritium rvater monitoring wells adjacent to thc tlrye sampler with composite samples analysis of each samplc.
plant (Wclls No. l, A, B, C, and F). collected over a period of approximatly 3l days. I sample from ground water soutre Same as Well No. l. Gross beta, gEmma scan, and tritium up gradient (Well No. 5). analysis of each sample.
- c. Ihinking I sample at the first two poable Collected by automatic sequential- Gross baa, gamma scan, and tritium surface water supplies, downstneam tpe samplef with composirc sample analysis of each sample.
from thc plant (TRM 503.t and TRM collected monthly. 473.0). I sample at a control loc*ion TRM 529.3d. Table A-l WATTS BAR NUCLEAR PLANT RADIOLOGI CAL ETWIRONMENTAL MONITORING PROGRAM' Exposure Pathway Number of Samples and Sampling and Type and Frequency and/or Sample Locationsb Collection Frequency of Analysis
- d. Sediment from I sample downsneam from plant At least once per 184 days. Gamma scan of each sample.
Shoreline Discharge (TRM 513.0). I sample fiom a confirol location upsfream fiom plant discharge (TRM 530.2).
- e. PondSediment I samplefiomatleastttrcelocations Atleastonceperyear. Gammascanofeachsample.
in the Yard Holding Pond.
- 5. INGESTION a- Milk I samplefrommilkproducinganimals Every2weeks. I-l3l andgammaanalysisoneach in each of l-3 areas indicated by the sample. Si-gg anA Sr-b0 once per cow census were doses are calculated quarter.
to be highest I ormorc samples from control locations.
- b. Fish One sample of commetcially important At least once per t84 days. Gamma scan on edible portions.
species and one sample of reoeationally important species. One sample of each species ftom Chickamauga and Watts Bar Reservoirs.
-3 l-
Table A-l WATTS BAR NUCLEAR PLA}.IT RADIOLOGICAL EWAL MONITORING PROGRAM Exposure Pathway Number of Samples and Sampling and Type and Frequency and/or Sample Locationsb Collection Freguency of Analvsis Vegetation" Samples from farms producing milk At least once per 3l days. I-l3l analysis and gamma scan of
@asturage and but not providing a milk sample. each sample.
grass)
- d. Food Products I sample each of principal food Annually at time of harvest. The Gamma scan on edible portion.
products grown at private gardens bpes of foods available for sampling and/or farms in the immediate will vary. Following is a list of vicinity of the plant. tlpical foods which may be available: Cabbage, Lettuce and/or Greens Corn Green Beans Potatoes Tomatoes
- a. The sampling ptogram outlined in this table is that which was in effect at the end of 2016.
- b. Sample locations are shown on Figures A-1, A-2,A-3.
- c. Samples shall be collected by collecting an aliquot at interrrals not exceeding 2 hotns.
- d. The samples collected d TRMs 503.t and 473.0 arc taken fiom the raw uratcr suppln thereforc, the upstneam surface nater sample will be considered ttre control sample for drinking water.
- e. Vegetation sampling is applicable only for farms that meet the criteria for milk sampling and when milk sampling cannot be performed.
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Table A-2 WATTS BAR NUCLEAR PLAI{T RADI OLOGICAL EN V IRON MENTAL MON TTORIN G PROGRAT{ SAI\4PLING LOCATIONS Map Approxirnate lndicator (l) location Distancc or Samples Numbef- Station Sector (Miles)_ Conuol (C) Collectedb-2 PM.2 NW 7,0 AP,CF,S,AM 3 PM.3 NNE 10.4 AP,CF,S 4 PM-4 NE/ENE" 7,6 AP,CF,S 5 PM-5 S 8.0 AP,CF,S,AI\,I 6 RM-2 SW 15.0 C AP,CF,S,AId 7 RM-3 NNW 15.0 C AP,CF,S,AlvI E LM-I ssw 0.5 AP,CF,S,AI\{ 9 LM-2 NNE 0.4 AP,CF,S,AI\d r0 LM-3 NNE t.9 AP,CRS,AI\d ll LM4 SE 0.9 AP,CF,S,Atrt l8 Well #l S 0.6 w 20 Farm N ESE 4.1 M c 23 25 Well #5 TRM 517.9 I 0.5 e.* I w SW 26 TRM 523.1 -- 4.7d I SW 27 TRM 529.3 -- l.5d c sw,Pw' 3l TRI\{ 473.0 54.9d I PW (C. F. Industries) 32 TRM 513.0 l4.gd I SS 33 TRM 530.2 2.4d c SS 35 TRM 503.9 :: 24.0d I PW (Dayton) 37 TRM 522.9-527.9 F (dovmsheam of WBN) 38 TRM 471-530 F (Cltickamauga Lake) 39 TRM 530-602 c F (Watts Bar Rescrvoir) EI Yard Pond SSE/SISSW Onsite PS E2 Well A SSE 0.6 w 83 Well B SSE 0.5 w E4 Well C ESE 0.3 w 85 Well F SE 0.3 w 86 Farm FIII SSW 1.75 M 87 Farm BB SW 18.6 M & See Figures A-1, A-\ and A-3
- b. Sample codes:
Alvl : Atmoqpheric Moisturs AP = Air particulate filter PW= Public Watcr SS : Shorcline sediment CF = Charcoal filter PS: Pond Sediment SW = Surfacc watcr F- Fistt S: Soil W : Wcll water M: Milk
- c. Station located on the boundary bctwcen thesc two scctors.
- d. Distance ftom the plant discharge (TRM 527.8)
- e. The surface water saurple is also used as a control for public water.
Table A-3 WATTS BAR NUCLEAR PLANIT ENVIRONMENTAL DOSIMETERS LOCATIONS Map" Approximate Onsite (Onf Location Distancc or Number Station Sector (Miles) offsirc (ofin 2 NW-3 NW 7.0 otr 3 NNE-3 NNE 10.4 otr 4 ENE.3 NE/ENE '1.6 otr 5 s-3 s 7,8 otr 6 sw-3 SW 15.0 otr 7 NNW-f NNW 15.0 otr l0 NNE-IA NNE 1.9 On ll SE-IA SE 0.9 On l2 ssw-2 ssw 1.3 On l4 w-2 w 4.9 off 40 N-l N t.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 otr 46 NE-3 NE 6.1 otr 47 . ENE.I ENE 0,7 On 48 ENE-2 ENE 5.8 otr 49 E-l E 1.3 On 50 E-2 E 5.0 otr 5l ESE-I ESE 1.2 On 52 ESE.2 ESE 4,4 off 54 SE-2 SE 5.3 otr 55 SSE-IA SSE 0.6 On 56 SSE.2 SSE 5.9 otr 57 S-T S 0.7 On 5E s-2 s 4.9 off 59 SSW-I ssw 0.9 On 60 ssw-3 ssw 5.0 otr 62 sw-l sw 0.9 On 63 sw-2 SW 5.3 off 64 wsw-l wsw 0.9 On 65 wsw-2 wsw 3.9 otr 66 w-l w 0.9 On 67 wNw-l wNw 0.9 On 68 wNw-2 wNw 4.9 otr 69 NW-l NW l.l On 7A NW-2 NW 4.7 otr 7t NNW.I NNW 1.0 On 72 NNW.2 NNW 4.5 off 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 77 w-2A w 3.2 otr 78 NW-2A NW 3.0 off 79 SSE.I SE 0.5 On a Scc Figurcs A-1, A-a and A-3.
- b. Ilosimctsrs &signatcd'onsitc' arc locarcd 2 miles or less from thc plar4 "offsitc' arp locatcd rnorc 0ran 2 milcs fiomlhcplant
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Figure A-l Radiological Environmental Sarnpling Locations Within I Mile of the Plant 303.75 56.25 wNw ENE 287.25 78.75 WATTS BAB w NUGLEAR PLANT E 258.75 to I ,26 ws ESE
.r'mr 14 123.75 191.25 S Figure A-2 Radiological Environmental Sampling Locations From I to 5 Miles From The Plant wArrs BAR NucLeee p[ur l I Pd:
Figure A-3 Radiological Environmental Sarnpling Locations Greater Than 5 Miles From the Plant APPENDD(B PRO GRAN{ MODIFICATIONS Appendix B Radiological Envirorunental Monitorine Prosram Modification The farm identified as Farm K closed its operation in 2015 and was replaced by Bacon Farm. However, it was not removed from the REMP collection schedule until January of 2016. Farm K was a control milk location. The change is reflected in the Tables and Figures of Appendix A of this report. There were no other modifcations to the WBN REMP program during 2016. APPENDIXC PROGRAI\{ DEVIATIONS
-,40-
Appendix C ProEram Deviations Problems with equipment resulted in missed air samples from three locations during 2016. Problems with low moisture resulted in 2 missed atrrospheric samples. The samples were collected but unable to be analped due to the low moisture content. The low moisture from one of the samples was due to damaged equipment. Table C-l provides additional information on the missed samples. A review of the details of the program deviations did not identi& any adverse tend in equipment performance. 4l-
Table C-l Radiological Environmental Monitoring Progrram Deviations Date Station Location Sample TWe Dessription 0912012016 PI&d-z 7.0 MilesNW AF/CF While performing the routine REMP collection, it was discovered that the motor at PM-2 (station 3106, Spring City) had failed, which resulted in missed air samples. The entire unit was replaced on 9120116. The issue was documented in CR 1214561. tolt4l20t6 LM-t 0.5 Miles SSW AF/CF Chemistry was informed that the LM-l REMP air monitoring statiotr, located near the MET tower, was not running. Upon investigation, the monitor was found off. Attempts to restart the monitor failed. The issue was documented in CR 1222800. tolra2u6 RI\d.3 15 MilesNNW AF/CF While performing the routine REMP collection, it was discovered that RM-3 (station 3205, Alloway) air sampler had failed before obtaining the minimum required volume. The issue was documented in CR 1223692. r l/1 5120t6 PM-5 8.0 Miles S Afrnospheric A canister was broken during Moisture shipment causing the sample to have low moisture content. The sample was analyzed but unable to be calculated. The problem was identified in CR 1234087. tu29l20r6 PM-5 8.0 Miles S Atnospheric The sample was collected but unable Moistue to be analyzed due to low rnoisture content. The problem was identified in CR 1241477. APPEI{DD(D AI{ALYTICAL PROCEDI JRES 43-
Appendix D Analytical Procedures Analyses of environmental samples ar performed by the radioanalytical laboratory located at the Western Area Radiological Laboratory facility in Muscle Shoals, Alabama, except for the Sr-89, 90 aaalysis of soil samFles which was performed by a contract laboratory. Analysis procedures are based on accepted methods. A sunrmary ofthe analysis techniques and methodology follows. The gross betameasurements are made with an automatic lowbackground counting systertr. Normal counting times are 50 minutes. Water samples are prepared by evaporating 500 milliliter (ml) of samples to near drymess, tansferring to a stainless steel plancha, and completing the evaporation process. Air particulate filters are counted directly in a shallow planchet The specific analysis of I-l3l in milk is performed by first isolating and ptui$ing the iodine by radiochemical separation and then counting the final precipitate on a beta-gamma coincidence counting system. The normal count time is 50 minutes. With the beta-gamma coincidence counting system, background counts are virtually sliminated and e:rtemely low levels of activity can be detcted. After a radiochemical separation, milk samples analyzed for Sr-89, 90 are counted on a low background bAa counting system. The sample is counted a second time after a minimum ingrowlt period of six days. From the two counts, the Sr-89 and Sr-90 concentrations can be determined. Water samples are analyzed for titium content by first distilling a portion of the sample and then counting by liquid scintillation. A cornmercially available scintillation cocltail is used. Gamma analyses are performed in various counting geometries depending on the sample tlpe and volume. All gamma counts are obtained with germanium type detectors interfrced with a high resolution gamma spectroscopy system. The charcoal cartidges used to sample gaseous radioiodine are analyzed by gamma spectroscopy using a high resolution gamma spectroscopy system with germanium detectors. Atuospheric moisture samples are collected on silica gel from ametered air flow. The moisture is released from the silica gel by heating and a portion of the distillate is counrcd by liquid scintillation fortitium using commercially available scintillation cocktail. The necessary efficiency values, weight-efficiency cunres, and geometry tables are established and maintained on each detector and counting system. A series of daily and periodic quality contol checks are perfonned to monitor counting instnrmentation. System logbooks and contol charts are used to document the results of the quality contol checks.
'45'
APPENDIXE NOMINAL LOWER LIMITS OF DETECTION 46-
Appendix E Norninal lower Limits of Detection A number of factors influence the Lower Limit of Detection (LLD), including sample size, count time, cormting efficiency, chemical prooesss, radioactive decay factors, and interfering isotopes encormtered in the sample. The most probable values for these factors have been evaluated for the various analyses performed in the environmental monitoring program. The nominal LLDs are calculated in accordance with the methodology prescribed in the ODCM, are presented in Table E-1. The maximum LLD values for the lower limits of detection specified in the ODCM ane 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 establishe4 an LLD of zero is assumed in determining if a measued activity is greater than the LLD. In these cases, the LLD value will appear as -1.00E+00 in the data tables in Appendix H. 47-
TABLEE-I Nominal LLD Values A. Radiochemical Procedures Sediment Air Water Mitk Wet Vegetation and Soil Analvsis (pCi/m3) (pCi/L) (pGi/L) (pCi/kg wet) (pci/g dry) Gross Beta
-l-0.002 1.9 --
Tritium 270 Iodine-l31 1: 0.4 6.0 -- Strontium-89 Strontium-90
- l 3.5 2.0 1.6 0.4 48-
Table E-l Nominal LLD Vatues B. Gamma Analyses Foods Air Charcoat Water Wet Soil and Tomatoes Particutate Filter and Milk Vegetation Sediment Fish Potatoes, etc. Analysis JrCi/m3- pCi/m3 pC;ilL pCi/kg, wet pCi/g. dry pCi/g. dry oCifte. wet Ce-l4l .005 0.02 l0 35 .10 .07 20 Ce-144 .01 0.07 30 ll5 .24 .15 60 Cr-51 .02 0.15 45 200 .35 .30 95 I-131 .005 0.03 l0 60 .25 .20 2A Ru-103 .005 0.02 5 25 .03 .03 25 Ru-106 .02 0.12 40 r90 .20 .15 90 Cs-134 .005 4.02 5 30 .03 .03 l0 Cs-l37 .005 0.02 5 25 .03 .03 l0 Zr-95 .005 0.03 t0 45 .05 .05 45 hlb-95 .005 0.02 5 30 .04 ' .25 l0 Co-58 .005 0.02 5 20 .03 .03 t0 Mn-54 .005 0.02 5 20 .03 .03 l0 Zn-65 .005 0.03 l0 45 .05 .05 45 Co-60 .005 0.02 5 20 .03 .03 l0 K40 .04 0.30 100 400 .75 .4A 2s0 Ba-140 .015 0.07 25 r30 .30 .30 s0 La-140 .01 0.04 l0 50 .20 .20 25 Fe-S9 .005 0.M l0 40 .05 .08 25 Be-7 .02 0.15 45 204 .25 .25 90 Pb-212 .005 0.03 t5 40 .10 .04 40 Pb-i2t4 .005 0.07 20 80 .15 .10 80 Bi-214 .005 0.05 2A 55 .15 .10 40 Bi-212 .42 0.20 50 250 .45 .25 t30 TI-208 .002 ,:, .06 .03 Ra-224 i: :3 .75 :3 Ra-226 .15 -- Ac-228 .01 0.07 20 70 .25 .10 50 Pa-234m 800 4.0 Table EA Maximum LLD Values Specified by the WBNODCM Airborne Particulate Food Water or Gases Fish Milk Products Sediment Analysis pCtlL pCi/m3 pCi&g. w.e! oCdL a-oCi/ks. wet
!a-lr-nCi/ks. drv F-L-<b gross beta 4 Ix l0-2 N.A. N.A. N.A. N.A.
H-3 2000" N.A. N.A. N.A. N.A. N.A. Mn-54 l5 N.A. 130 N.A. N.A. N.A. Fe-59 30 N.A. 260 N.A. N.A. N.A. Co-58,60 l5 N.A. t30 N.A. N.A. N.A. Zn-65 30 N.A. 260 N.A. N.A. N.A. k-95 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-13 I lb 7 x l0-2 N.A. I 60 N.A. Cs-134 l5 5 xl0-2 130 l5 60 ls0 Cs-137 l8 6 x t0'2 150 t8 80 180 Ba-140 60 N.A. N.A. 60 N.A. N.A. La-I40 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. If no drinking water pattrway exists, I value of 15 pCi/liter may be used.
APPEhTDIXF QUATITY AS STJRA}.ICBQUALITY CONTROL PROGRAN{
-5 l-
Appendix F Oualiry AssurancdOualiB Contol Procram A quality assurance pogram is ernployed by the laboratory to ensure that the environmental data are reliable. This program includes the use of written, approved procedures in performing the work" provisions for staffhaining and certification, internal self assesments of program performance, atrdits by various external organizations, and a laboratory quality contol progam.
The quality control prosam ernployed by the radioanalytical laboratory is designed to ensure that the sampling and analysis process is working as intended. The program includes checks and the analysis of quality control samples along with routine samples. Instrument qtnltty contol checks include backgroturd count rate and counts reproducibillty. In addition to these two general checks, other qtrality control checks are perfomred on the variety of detectors used in the laboratory. The exact nafirrc of these checks depends on the tlpe of device and the method it uses to detect radiation or store the information obtained.
Qualtty control samples of a variety of t1ryes are used by the laboratory to verifo the performance of differentportions of the analytical process. These qualrty control samples include blanks, replicate samples, aoalyhcal knowns, blind samples, and cross-checks.
Blaol2 miles 16.2 15.5 17.2 16.0 65 (otrsite)
(a) Field periods normalized to one standard quarter (2190 houre)
(b) Average of the lndividual measurements in the set (c) The 3.7 mR/yr fur onsite locations falls below the 25 mrem totial body limit in 10 CFR 190.
Table H-2(1 of 2)
DIRECT MDIATION LEVELS lndividual Stations at Watb Bar Nuclear Plant Environmental Radiation Levels mR /Quarter Map Dosimeter Approx 1st Qf 2nd Qt 3rd Qtr 4th Qtr Annual(l)
Location S-tation Dircction, Distance, Jan-Mar Apr.lun Jul-Sep Oct-Dec Exposure Number Number deorces miles 2016 2016 2016 2016 mRlfear 40 N-1 10 1.2 21.7 19.3 16.5 17.9 75.4 41 N-2 350 4.7 17.8 19.1 17.2 17.6 71.7 42 NNE-1 21 1.2 17.1 17.3 19.9 17.9 72.2 10 NNE-IA 22 1.9 15.9 12.9 16.6 15.2 60.6 43 NNE-2 20 4.'t 16.2 13.0 17.0 14.6 60.9 3 NNE-3 17 10.4 16.7 15.9 16.1 16.8 65.5 44 NE-1 39 0.9 18.1 15.3 19.4 19.6 72.4 45 NE-2 U 2.9 15.9 17.1 19.2 17.9 70.0 46 NE 47 6.1 13.4 11.5 12.7 13.6 51.2 47 ENE-1 74 0.7 16.6 13.3 13.1 17.9 60.9 48 ENE-2 69 5.8 15.4 10.9 16.8 14.5 57.6 74 ENE-24 69 3.5 13.8 12.0 16.3 1 1.3 53.4 4 ENE-3 56 7.6 13.9 12.0 15.4 10.7 52.0 49 E-1 85 1.3 17.6 15.3 16.5 16.3 65.7 50 E-2 92 5.0 14.3 2'1.2 21.1 20.5 77.1 51 ESE-I 109 1.2 14.4 11.8 14.0 14.6 54.9 52 ESE-2 106 4.4 17.8 19.7 22.1 17.2 76.8 11 SE-1A 138 0.9 15.5 11.3 17.4 17.4 61.6 il sE-2 128 5.3 14.3 14.5 15.9 14.5 59.2 75 SE-24 144 3.1 16.3 16.5 16.9 18.9 68.6 79 SSE-I 146 0.5 17.1 17.8 18.5 16.7 70.1 55 SSE-1A 161 0.6 15.0 12.8 15.6 12.4 55.9 56 SSE-2 156 5.8 20.2 16.1 17.3 16.7 70.3 (1) Sum of available quarterly data normalized to 1 year br the annual exposurc value.
Table H-2 (2 of 2)
DIRECT RADIATION LEVELS lndividual Stations at Watts Bar Nuclear Plant Environmental Radiation Levels mR /Quarter Map Dosimeter Approx 1st Qtr 2nd Qtr 3rd Qtr 4th Qr Annual(l)
Location S-tation Directior, Distance, Jan-Mar Apr-Jun Jul-Sep Oct-Dec Exposure Number Number degrees miles 201A 2016 2016 2016 mRAfear 57 S-1 192 0.7 16.3 16.3 14.1 15.1 61 .8 58 S-2 195 4.9 13.9 13.0 14.9 1 1.9 53.5 76 S-2A 177 2.0 '17.5 17.3 16.0 19.4 70.2 5 S-3 195 7.9 13.9 14.4 13.0 15.3 56.6 59 ssw-1 1gg 0.9 21 .1 24.6 21 .5 18.3 85.5 12 SSW-2 200 1.3 14.9 13.8 19.4 17.2 64.3 60 ssw-3 1gg 5.0 14.3 13.0 14.0 17.4 58,7 62 SW-1 226 0.9 19.3 21 .0 20.5 18.9 78.7 63 SW-2 22A 5.3 19.6 21 .2 1g.g 20.1 79.8 6 SW-3 225 15.0 15.1 11 .5 14.6 14.6 55.8 64 WSW-1 255 0.9 15.6 15.4 16.6 13.4 61.0 65 WSW-2 247 3.9 17.6 17.0 20.9 19.0 74.4 66 W-1 270 0.9 17.2 18.5 17.6 17.9 71 .1 14 W-2 277 4.8 16.6 14.4 15.9 12.? 59.2 77 W-2A 269 3.2 19.2 17 .0 19.4 16.3 70.9 67 WNW-1 294 0.9 24.3 25.4 25.7 25.1 100.5 6g wNW-2 292 4.9 20.2 18.8 22.5 17.8 79.3 69 NW-1 320 1.1 14.5 17.3 19.7 14.7 65.2 70 NW-2 31 3 4.7 17.3 18.8 19.3 20.5 75.9 78 NW-2A 321 3.0 17.1 17.8 19.7 14.2 67.8 2 NW-3 317 7.0 17.9 19.0 23.5 17.4 77.7 71 NNW-1 340 1.0 15.4 14.4 16.0 17.4 63.2 72 NNW-2 333 4.5 17.8 15.6 15.8 19.2 67.4 73 NNW-3 329 7.0 14.0 9.4 11.7 13.0 48.1 7 NNW.4 337 15.0 15.2 13.9 14.5 '13.7 57.3 (1) Sum of available quarterly data normalized to 1 year fur the annual exposure value.
Tennessee Valley Authorlty RADIOACTIVITY IN AIR FILTER pCi/m^3 = 0.037 Bg/m^3 Name of Facility: WATTS BAR NUCLEAR PLANT Docket Numben 50-390,391 Location of Facility: RHEA, TENNESSEE Reporting Period: 2016 Number of Type and Loner Limit lndicator Locations Location with Highest Annual Mean Control Locations Nonroutine Total Number of Detection Mean (F) Mean (F) Mean (F) Reported of Analysis (LLD) Range Location Description with Range Range Measurements Performed See Note 1 See Note 2 Distance and Direction See Note 2 See Note 2 See Note 3 GROSS BETA - 527 2.00E43 2.C/rE-02 (422 I 422') PMs DECATUR 2.16E-02 (53 / 53) 1 .96E-02 (105 / 105) 6.01E-03 - 5.16E-02 6.2 MILES S 6.01E-03 - 4.gE-02 5.69E 3.95E42 GAMMA SCAN (GELl) - 140 AC-228 1.00E-02 1.94E-02 (1 I 112',) LM2 1.94E-02 (1 I 141 28 VALUES < LLD 1.94E-02 1.94E-02 0.5 MILES N 1.948-02 - 1.94E-02 BE-7 2.00E-02 1.15E-01 (1 12 I 1121 PM5 DECATUR 1.20E-01 (14 I 14) 1.16E-01 (28 t 281 6.66E-02 1.65E-01 6.2 MILES S 8.10E-02 1.59E-01 6.47E42 - 1.918-01 Bl-214 5.00E-03 2.77E-02 (109 t 1121 PM4 3.63E-02 (13 I '.t4',) 2.65E42 (27 t28l 5.40E-03 - 1.32E-01 7.6 MILES NE/ENE 7.10E-03 - 1.32E-01 5.60E-03 - 1.05E-01 H t
K-,40 4.00E-02 5.25E-02 (1 t 112) p o\ PM3 5.25E-02 (1 I 14) 28 VALUES < LLD er Ut I 5.25E-02 5.25E-02 10.4 MILES NNE 5.25E-02 - 5.25E-02 (!
)d hra PB-212 5.00E-03 6.80E-03 (6 t 1121 8.50E-03 (1 I tt{
6.00E-03 9.50E-03 L[,12 0.5 MILES N 8.50E-03 - 14',t 9.50E-03 9.40E-03 (2 I 281 7.00E 1 .1gE-02 (,t P&214 5.00E-03 2.80E-02 (103 I 1121 PM5 DECATUR 3.69E-02 (13 I 141 2.45E-A2 Q6 t 28l 5.20E-03 1.38E{1 6.2 MILES S 5.60E-03 1.34E-01 5.20E-03 6.73E-02 TL-209 2.00E-03 5.28E-03 (4 t 112) LM2 5.50E-03 (1 t 141 6.90E-03 (1 t28) 3.908-03 6.70E-03 0.5 MILES N 5.50E-03 - 5.50E-03 6.90E-03 6.90E-03 Notes: l. ],lominal Lovuer Lgvgl of Debdlon (LLD) ae doacribed in Table E - 1
- 2. ilean and Range baaed upon dtectable meagurcmsntg only. Fraction of detedable masurements at spoclfled tocation b indlcatod in panntheses (F).
- 3. Blankr ln thic column lndlceto no nonrountine mcaaurBment!
Tennessee Valley Authority RADIOACTIVIW IN CHARCOAL FILTER pCi/m^3 = 0.037 Bq/m^3 Name of FacilitY: WATTS BAR NUCLEAR PTANT Docket Number: 50-390,391 Location of FacilitY: RHEA, TENNESSEE Reporting Period: 2016 Number of Type and Lower Limit lndicator Locations Location with Highest Annual Mean Control Locations Nonroutine Total Number of Detection tvlean (F) Mean (F) Mean (F) Reported of Analysis (LLD) Range Location Elescription with Range Range Measurements Performed See Note 1 See Note 2 Distance and Direction See Note 2 See Note 2 See Note 3 GAMMA SCAN (GELl) - 527 Bt-214 5.00E-02 9.6 E-02 (178 t 422) LM1 1.05E-01 (17 I 52) s.29E{2 (3e / 105) 5.02E-02 2.66E-01 0.5 MILES SSW 5.1EE-02 - 1.92E-01 5.04E-02 2.36E-01 t-131 3.00E-02 SEE NOTE 4 K40 3.00E-01 3,65E-01 (71 I 4221 LM1 3.94E-01 (5 l52l 3.48E-01 (15 / 105) 3.02E-01 6.96E-01 0.5 MILES SSW 3.12E-01 6.96E-01 3.02E 5.25E-01 PB-212 3.00E{2 422 VALUES < LLD LM3 53 VALUES < LLD 105 VALUES < LLD 1.9 MILES NNE PB-214 7.00E-02 1.16E-01 (1 14 I 4221 PM3 1.36E-01 (16 / 53) 1 .1 7E-01 (1 9 / 105) H I 7.02E-O2 3.95E-01 10.4 MILES NNE 7.06E-02 7.25E-02 D o\ o\ 3.95E-01 2,gtE-01 tf I TL-209 2.00E-02 422 VALUES < LLD PMz SPRING CITY 52 VALUES < LLD 105 VALUES < LLD (! lEl 7.0 MILES NW H f*{ 5I Notes: 1. Nominal Lryer Lerol of DeGclbn (LLD) as d$cribed in Tabte E - I
- 2. liban and Rango basd upon detoctable measuEment3 only. Fnac{ion of dctedabb measurmcnt3 at spcct'ficd location b lndacebd in paontheses (F).
- 3. Blanks ln thls column indlcab no nonrounline masur"mentg
- 4. Thc analyais of Charcoal Filters was poilomad by Gamma Spoctroscopv. No l-131 wes dtoded. The LLD for l-131 bv Gamma SpsctrolcoDy wae 0.03 DcUcublc mct r.
Tennessee Valley Authority RADIOACTIVIW IN ATMOSPHERIC MOISTURE pCi/m^3 = 0.037 Bq/m^3 Name of Facility: WATTS BAR NUCLEAR PLANT Docket Number: 5G390,391 Location of Facility: RHEA, TENNESSEE Reporting Period: 2016 Number of Type and Loupr Limit lndicator Locations Location with Highest Annual Mean Control Locations Nonroutine Total Number of Detection Mean (F) Mean (F) Mean (F) Reported of Analysis (LLD) Range Location Description with Range Range Measurements Performed See Note 1 See Note 2 Distance and Direction See Note 2 See Note 2 See Note 3 TRTTIUM - 206 3.00E+00 3.98E+00 (47 t 130) LM2 4.45E+00 (14 126) 3.89E+OO (11 I 52') 3.03E+OO 7.42E+OO 0.5 MILES N 3.24E+00 - 7,42E+00 3.19E+OO 5.23E+00 I sd-l { o\ I tD iir-F t*{ t L'I Notes: l. Norninal Lovyer Level of Detection (LLD) as descdbed ln Table E - 1
- 2. liban and Range based upon dstcdabb measurgmenE only. Fraction of detedable msasurpmsnig at opccificd locatkm b lndlcated in paentheses (F).
- 3. Bbnks in this column indbab no nonrcuntino mcaaurments
Tennessee Valley Authority RADIOACT]VITY IN MILK pCi/L = 0.037 Bq/L Name of Facility: WATTS BAR NUCLEAR PLANT Docket Number: 50-390,391 Locatlon of Facility: RHEA, TENNESSEE Reporting Period: 20t6 Number of Type and Lourer Limit lndicator Locations Location with Highest Annual Mean Control Locations Nonroutine Total Number of Detection Mean (F) Mean (F) Mean (F) Reported of Analysis (LLD) Range Location Desoiption with Range Range Measurements Performed See Note I See Note 2 Distance and Direction See Note 2 See Note 2 See Note 3 toDtNE-l31 -78 4.00E-01 52 VALUES < LLD 26 VALUES < LLD GAIUMA SCAN (GELl) -78 AC-228 2.00E+0t 52 VALUES < LLD NORTON FARM 26 VALUES < LLD 2.03E+01 (1 t26l 4.1 MILES ESE 2.038+01 - 2.03E+01 Bl-214 2.00E+01 3.94E+01 (28 I 521 1.75 MILES SSW 4.35E+01 (1 4t261 3.93E+01 (13 t 26l 2.04E+01 1.14E+02 2.33E+01 - 1j4E+02 2.13E+01 - 1.05E+02 K.00 1.00E+02 1.30E+03 (52 t 521 1.75 MILES SSW 1.30E+03 ee t 261 1 .31E+03 (26 I 261 8.95E+02 1.44E+03 8.95E+0e - 1.42E+03 1.18E+03 - 1.48E+03 t.l t D o\ 6 PBA12 1.50E+01 52 VALUES < LLD 1.75 MILES SSW 26 VALUES < LLD 26 VALUES < LLD cr t-I o
,ra P&l214 2.00E+01 3.76E+01 (19 t t&
521 1.75 MILES SSW 3.88E+01 (10 I 26) 4.20E+01 (7 I 26) t 2.01E+01 8.48E+01 2.01E+01 8.4EE+0t - o\ 2.29E+A1 E.27E+01 TL-202 -1.00E+00 2.37E+00 (1 I 52) NORTON FARM 2.37E+00 (1 t 261 26 VALUES < LLD 2.37E+00 2.37E+00 4.1 MILES ESE 2.37E+00 2,37E+00 TL-208 1.00E+01 S?VALUES < LLD NORTON FARM 26 VALUES < LLD 26 VALUES < LLD 4.1 MILES ESE sR89 -12 3.50E+00 8 VALUES < LLD 4 VALUES < LLD sR90 -12 2.00E+00 8 VALUES < LLD 4 VALUES < LLD Notes: 1. Nominal Lower Level of Detestion (LLD) as described in Table E-1
- 2. Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).
- 3. Blanks in this column indicate no nonrountine measurements
Tennessee Valley Authority RADIOACTIVIW IN SOIL pCi/g = 0.037 Bq/g (DRY WEIGHT) Name of Facility: WATTS BAR NUCLEAR PISNT Docket Number: 50-390,391 Location of Facility: RHEA, TENNESSEE Reporting Period: 2016 Number of Type and Lower Limit lndicator Locations Location with Highest Annual Mcan Control Locations Nonroutine Total Number of Detection lUban (F) Mean (F) Mean (F) Reported of Analysis (LLD) Range Location Description with Range Range Measurements Perfurmed See Note 1 See Note 2 Distance and_Direction See Note 2 See Note 2 See Note 3 GAMMA SCAN (GELl) - 10 AG228 2.s0E-01 1.08E+00 (8 / 8) PMs DECATUR 1.33E+00 (1 t 1l 6.66E-01 (2 t 2l
. 6.60E-01 - 1.33E+00 6.2 MILES S 1.33E+00 - 1.33E+OO 6.40E 6.91E-01 BE.7 2.50E-01 8.52E-01 (3 / 8) PMz SPRING CITY 1.63E+00 (1 / 1) 4.26E-01 (1 t 2) 3.75E-01 1.63E+00 7.0 MILES NW 1.63E+00 1.63E+00 4.26E{1 - 4.26E41 san 4.50E-01 1.19E+00 (8 / 8) LMl 1.51E+00 (1 t 1l 717E-01 (2 I 2) 6.38E-01 - 1.51E+00 0.5 MILES SSW 1 .51E+00 1.51E+00 6.25E-01 - g.0gE-01 Bt-214 1.50E-01 7.54E-01 (g / 8) LM3 9.14E-01 (1 I 1) 6.57E-01 (2 I 2')
5.33E-01 - 9.14E-01 1.9 MILES NNE 9.14E41 - 9.14E-01 5.98E 7.16E-01 cs-l37 3.008-02 1.33E-01 (6 / 8) LM2 2.96E-01 (1 I 1) 3.84E-01 (1 I 2) F.l a 4.69E-02 2.96E-01 0.5 MILES N 2.96E-01 - 2.96E-01 3.84E 3.94E-01 p o\ \o d lEa I K40 7.50E-01 1.07E+01 (8 / 8) LfrI4 WB 2.678+01 (1 / 1) 4,58E+00 (2 I 2l t! 3.86E+00 - 2.67E+01 0.9 MILES SE 2.67E+01 - 2.67E+O1 4.54E+00 4.62E+00 -r t4. PA-234M 4.00E+00 8 VALUES < LLD LM2 1 VALUES < LLD
\tI 2 VALUES < LLD 0.5 MILES N PB-212 1.00E-01 1.04E+00 (8 / 8) PMs DECATUR 1.30E+00 (1 t 1l 6.81E-01 (2 t 2) 6.24E{1 - 1.30E+00 6.2 MILES S 1.30E+00 1.30E+00 5.90E 7.728-01 P*214 1.50E-01 8.40E-01 (g / g) LM3 1.03E+00 (1 / 1) 7.17E.o1 (2 t 2) 6.31E-01 - 1.03E+00 1.9 MILES NNE 1.03E+OO 1.03E+00 6.24E 9.10E-01 RA-226 1.50E-01 7.54E-01 (8 / g) LIr/l3 9.14E-01 (1 I 1) 6.57E-01 (2 t 2) 5.33E-01 - 9.14E-01 1.9 MILES NNE 9.14E-01 - 9.14E-01 5.98E 7.16E-01 TL-z06 6.00E-02 3.47E-01 (8 / 8) LM-4 WB 4.25E-01 (1 I 1l 2.20E-01 (2 I 2l 2.11E-01 4.25E-01 0,9 MILES SE 4.25E-01 - 4.25E-01 2.04E-01 2.37E-01 sR89 -10 1.60E+00 8 VALUES < LLD 2 VALUES < LLD sR90 -10 4.00E{1 8 VALUES < LLD 2 VALUES < LLD Notca: 1. Nominal Lo*ur lsvel of Detcction (LLD) as dscribcd in Tablc E - I
- 2. i/ben and Range basd upott dctectable measulcmonts only. Fractlon of dstc0abb mcasupmentB at spscmod bcatlon b indlcated in parunthcses (F).
- 3. Blanks in thb column indlcat! no nonountlnc measurumcntg
Tennessee Valley Authority RADIOACTIVIW IN CABBAGE PCi/Kg = 0.037 Bq/Kg WET WEIGHT) Name of Facility: WAfiS BAR NUCLEAR PIANT DocketNumber: 50-390,391 Location of Facility: RHEA, TENNESSEE Reporting Period: 2016 Number of Type and Lower Limit lndicator Locations Location with H(;hest Annual Mean Control Locations Nonroutine Total Number of Detection Mean (F) Mean (F) Mean (F) Reported of Analysis (LLD) Range Location Desoiption with Range Range Measurements Perbrmed See Note 1 See Note 2 Distance and Direction See Note-2 See Note 2 See Note 3 GAMMA SCAN (GELl) -3 Bl-214 4.00E+01 6.58E+01 (1 / 1) 3.0 MILES SE 6.58E+01 (1 / 1) 2 VALUES < LLD 6.58E+01 - 6.58E+01 6.58E+01 - 6.58E+01 K.40 2.50E+02 2.54E+03 (1 t 1) 3.0 MILES SE 2.&4E+03 (1 I 1) 2.32E+03 (2 t 2l 2.54E+03 2.54E+03 2.54E+03 2.54E+03 2.07E+03 2.57E+03 PB-212 4.00E+01 1 VALUES < LLD 3.0 MILES SE 1 VALUES < LLD 2 VALUES < LLD PB-214 8.00E+01 1 VALUES < LLD 3.0 MILES SE 1 VALUES < LLD 2 VALUES < LtD
-l g,
{o I C' t - (D t+l t4{ I oo Notes: 1. Nominal Lorer lowl of Debctbn (LLD) as described in Table E - 1
- 2. i/lean hnd Rango based upon dcbctabb moesurrmcnt8 only. Fraction of dctacfable mcasurcmcntg at specifisd location b indicated ln parcnthcrs (F).
- 3. Blanks ln thi! column lndbate no nonrountino masuromontB
Tennessee Valley Authority RADIOACTIVITY IN CORN PCi/Kg = 0.037 Bq/Kg WET WEIGHT) Name of Facility: WATTS BAR NUCLEAR PISNT Docket Number: 50-390,391 Location of Facility: RHEA, TENNESSEE Reporting Period: 2016 Number of Type and Lower Limit lndicator Locations Location with Highest Annual Mean Control Locations Nonroutine Total Number of Detection Mean (F) Mean (F) Mean (F) Reported of Analysis (LLD) Range Location Description with Range Range Measurements Performed See Note I See Note 2 Distance and Direction See Note 2 See Note 2 See Note 3 GAI GAMMA SCAN (GELI) - 2 Bl-214 4.00E+0't 6.72E+01 (1 / 1) NORTON FARM 6.72E+01 (1 t 1) 1 VALUES < LLD 6.72E+01 - 6.72E+0t 4.1 MILES ESE 6.72E+01 - 6.72E+01 K-,40 2.50E+02 1.69E+03 (1 / 1) NORTON FARM 1 .69E+03 (1 / 1) 2.16E+03 (1 t 1l 1.69E+03 1.69E+03 4.1 MILES ESE 1.69E+03 1.69E+Og 2.16E+03 2.16E+03 PB-212 4.00E+01 1 VALUES < LLD NORTON FARM 1 VALUES < LLD 1 VALUES < LLD 4.1 MILES ESE PB-214 8.00E+01 1 VALUES < LLD NORTON FARM 1 VALUES < LLD 1 VALUES < LLD 4.1 MILES ESE TL-209 3.00E+01 1 VALUES < LLD NORTON FARM 1 VALUES < LLD 4.1 MILES ESE 1 VALUES < LLD d E {t\, I t
\t cr E
I I tT ld tJr I
\o Nol$: 1. Nominal Lwucr Lcvol of Dotaction (LLD) aB d$cdbed ln Table E - 1 2' Mean end Renge basad upon rteteciabls rnsasuEmnta only. Fraction of detectabb moasurmonts st specified location is indicated in parntho3e3 (F).
3, Blanks ln thB column indicete no nonrountans moesulrments
Tennessee Valley Authority RADIOACTIVITY IN GREEN BEANS PCi/Kg = 0.037 Bq/Kg WET WEIGHT) Name of Facili$: WATTS BAR NUCLEAR PI,ANT Docket Number: 5G3g0,39l Location of Facility: RHEA, TENNESSEE Reporting Period: 2016 Number of Type and Lower Limit lndicator Locations Location with Highest Annual Mean Control Locations Nonroutine Total Number of Detection Mean (F) Mean (F) Mean (F) Reported of Analysis (LLD) . Range Location Description with Range Range Measurements Performed See Note I See l$ote 2 Distanoe and Direction See Note 2 See Note 2 See Note 3 GAMMA SCAN (GELI) -2 Bl-214 4.00E+01 9.72E+01 (1 I 1') 3.0 MILES SE 9.72E+01 (1 / 1) 5.53E+01 (1 t 1) 9.72E+01 - 9.72E+01 9.72E+01 - 9.72E+0t 5.53E+01 - 5.53E+01 K.00 2.50E+02 1.90E+03 (1 t 1l 3.0 MILES SE 1.90E+03 (1 t 1l 3.70E+03 (1 I 1l 1.90E+03 - 1.90E+03 1.90E+03 - 1.90E+03 3.708+03 - 3.70E+03 PB-l214 8.00E+01 9.61E+01 (1 / 1) 3.0 MILES SE 9.61E+01 (1 t 1l 1 VALUES < LLD 9.61E+01 9.61E+01 9.61E+01 9.61E+01
-l st a
\t cr t\) tT
-a I f+l FL I
hJ o
],lotes: 1. Nominal Lomr Lewl of Dctedion (LLD) as desqibe<t in Table E - 1
- 2. iiean and Rang basd upon detedable measurcmnts only. Fraction of detsctabl msasurmont3 at spocifid locatbn is indicatsd ln parentheces (F).
- 3. Blanks in this column andlcato no nonrountinc mcalurcmentg
Tennessee Valley Authority RADIOACTIVITY IN TOMATOES PCi/Kg = 0.037 Bq/Kg WET WEIGHT) Name of Facility: WATTS BAR NUCLEAR PIANT Docket Number: 5G390,391 Location of Facility: RHEA, TENNESSEE Reporting Period: 2016 Number of Type and Louer Limit lndicator Locations Location with Highest Annual Mean Control Locations Nonroutine Total Number of Detection Mean (F) Mean (F) lVlean (F) Reported of Analysis (LLD) Range Location Description with Range Range Measurements Performed See Note 1 See Note 2 Distance and Direction See Note 2 See Note 2 See Note 3 GAMMA SCAN (GELl) -2 Bl-214 4.00E+01 4.94E+01 (1 / 1) 3.0 MILES SE 4.94E+01 (1 t U 4.05E+01 (1 t 1) 4.94E+01 - 4.94E+0t 4.94E+01 - 4.94E+01 4.05E+01 - 4.05E+01 K-40 2.50E+02 2.01E+03 (1 / 1) 3.0 MILES SE 2.01E+03 (1 I 1) 1.90E+03 (1 I 1l 2.01E+03 - 2.01E+03 2.01E+03 2.01E+03 1.90E+09 1.90E+03 Pt214 8.00E+01 1 VALUES < LLD 3.0 MILES SE 1 VALUES < LLD 1 VALUES < LLD TL-209 3.fr)E+Ot 1 VALUES < LLD 3.0 MILES SE 1 VALUES < LLD 1 VATUES < LLD H F' { ! f.Al C ha o I l+f rl I td H Notes: 1. Norninal Louuer Level of Detection (LLD) as deecribed in Table E-1
- 2. Mean and Range based upon detectable measurements only. Fraction of detectable rneasurements at specified location is indicated in parentheses (F).
- 3. Blanks in this column indicate no nonrountine measurements
Ten nessee Valley Authority RADIOACTIVIW lN SURFACE WATER Cl'otal) pCi/L = 0.037 BqlL Name of Facility: WATTS BAR NUCLEAR PIANT Docket Number: 50-390,391 Location of Facility: RHEA, TENNESSEE Reporting Period: 2016 Number of Type and Lourcr Limit lndlcator Locations Location with Highest Annual Mean Control Locations Nonroutine Total Number of Detection Mean (F) Mean (F) Mean (F) Reported of Analysls (LLD) Range Location Description with Range Range Measurements Performed See Note 1 See Note 2 Distance and Direction See Note 2 See Note 2 See Note 3 GROSS BETA - 39 1.90E+00 2.95E+OO (18 / 26) TRM 517.9 3.1 1E+00 (8 / 13) 2.33E+00 (7 t 13) 2.08E+OO - 5.78E+00 2.08E+00 4.34E+00 1.928+fi) 3.24E+00 GAMMA SCAN (GELl) - 3e Ae-229 2.00E+01 26 VALUES < LLD TRM 523.1 I3 VALUES < LLD 13 VALUES < LLD Bt-214 2.00E+01 4.88E+01 (1 4126) TRM 517.9 5.55E+01 (7 / 13) 5.96E+01 (5 / 13) 2.18E+01 - 1.37E+02 2.62E+A1 - 1.37E+O2 2.42E+0t 1.3llE+O2 K,40 1.(DE+02 26 VALUES < LLD TRM 523.1 13 VALUES < LLD 13 VALUES < LLD
*l s
(r {5 t PB-212 1.50E+01 26 VALUES < LLD TRM 517.9 13 VALUES < LLD 13 VALUES < LLD ha o I :r lr{ P*214 2.00E+01 4.75E+01 (10 I 26) TRM 517.9 5.10E+01 (6 / 13) 4.92E+01 (5 / 13) I hJ 2.18E+01 - 1.19E+02 2.18E+01 - 1.19E+02 2.01E+01 1.12E+02 hJ TL-208 1.00E+01 26 VALUES < LLD TRM 523.1 13 VALUES < LLD 13 VALUES < LLD TRITIUM - 39 2.70E+02 7.22E+02 (8 I 26') TRM s23.1 7.30E+02 (4 t 13) 13 VALUES < LLD 3.11E+02 - 1.62E+03 4,97E+02 - 1.15E+03 Notes: 1. Nominal Louuer Level of Detec{ion (LLD) as described in Table E-1
- 2. Mean and Range based upon detectable measurements only. Fraction of detectable measuriements at specified location is indicated in parentheses (F).
- 3. Blanks in this column indicate no nonrountine measurements
Tenneaaee Valley Authority RADIOACTMITY lN PUBLIC (DRINKING) WATER (Totat) pCi/L = 0.037 Bq/L Name of Facility: WATTS BAR NUCLEAR PLANT Docket Number: 50-390,391 Location of Facility: RHEA, TENNESSEE Reporting Period: 2016 Number of Type and Lower Limit lndicator Locations Location with Highest Annual Mean Control Locations Nonroutine Total Number of Detection Mean (F) Mean (F) Mean (F) Reported of Analysis (LLD) Range Location Description with Rangc Range ft/leasurements Performed Sqg Note 1 See Note 2 Distance and Direction See Note 2 See Note 2 See Note 3 GROSS BETA - 39 1.90E+00 2.28E+00 (10 / 26) CF INDUSTRIES 2.39E+00 (6 / 13) 2.33E+00 (7 t 13) 2.06E+00 3.32E+00 TRlvl 473.0 2.06E+00 - 3.32E+00 1.92E+00 3.24E+00 GAMMA SCAN (GELI) - 39 AC-228 2.00E+01 5.80E+01 (4 t26l RM.z DAYTON TN 8.05E+01 (2/ 13) 13 VALUES < LLD 3.34E+01 - 1.24E+02 17.8 [/llLES NNE 3.69E+01 - 1.24E+A2 Bl-214 2.00E+01 3.47E+01 (1 1126) RM-2 DAYTON TN 3.77E+01 (5 / 13) 5.96E+01 (5 / 13) 2.05E+01 - 6.08E+Ot 17,8 MILES NNE 2.80E+01 - 6.05E+01 2,42E+01 - 1.34E+02 Kr{0 1.00E+02 26 VALUES < LLD RM-2 DAYTON TN 13 VALUES < LLD 13 VALUES < LLD 17.8 ]I/IILES NNE *l s(r { t u PB-212 1.50E+01 26 VALUES < LLD RM-2 DAYTON TN 13 VALUES < LLD 13 VALUES < LLD b o I 17.8 MILES NNE t#
)r{
PBlzl4 2.00E+01 3.37E+01 (7 t 26) CF INDUSTRIES 3.59E+01 (3 I 13') 4.92E+01 (5 I 13) I 2.07E+01 - 5.42E+01 TRM 473.0 2.66E+01 - 5.26E+01 2.01E+01 1.12E+02 (, F{ A TL-209 1.00E+01 26 VALUES < LLD CF INDUSTRIES 13 VALUES < LLD 13 VALUES < LLD TRM 473.0 TRITIUM - 47 2.74E+02 5.73E+02 (16 / 34) RM.z DAYTON TN 5.91E+02 (7 t 171 13 VALUES < LLD 2.82E+02 - 1.01E+03 17.8 MILES NNE 3.50E+02 - 9.85E+02 NotBE: 1. l{ominal Lowsr Lcrrol of Dotectaon (LLD) as dcscrlbd ln Table E - 1
- 2. Ilean and Range barcd upon detcdable meatullmcnE only. Fradion of dstcctabb mcalurrmcnt3 at rpccilicd location ia lndicated ln paonthegar (F).
3, Blenkc in thb column indlcab no nonrpuntine mcasutEmGnt!
Tennessee Valley Authority RADIOACTIVIil lN WELL (GROUND) WATER Ootal) pCi/L = 0.037 Bq/L Name of Facility: WATTS BAR NUCLEAR PIANT Docket Number: 50-390,391 Location of Facllity: RHEA, TENNESSEE Reporting Period: 2016 Number of Type and Loupr Limit lndicator Locations Location with Hlghest Annual Mean. Control Locations Nonroutine Total Number of Detection Mean (F) Mean (F) Mean (F) Reported of Analysis (LLD) Range Location Description with Range Range Measurements Performed See Note 1 See.Note 2 Distance and Direction See Note 2 See Note 2 See Note 3 GROSS BETA .84 1.90E+00 3.11E+00 (40 / 70) WBN I/II/V-B 4.05E+00 (14 t 14) 2.26E+00 (9 / 14) 1.91E+00 5.918+00 0.4s MTLES SSE) . 2.42E+OA 5.91E+00 1.91E+00 3.04E+00 GAMMA SCAN (GELl) - 84 AC-228 2.00E+01 3.17E+01 (2 I 7A) WBN i,,IW-F 3.38E+01 (1 I 14) 14 VALUES < LLD 2.96E+01 3.38E+01 o.30 MlLES SE) 3.38E+01 - 3.38E+01 Bl-214 2.00E+01 3.72E+O1 (42 t70t WBN MW-A 4.47E+01 (12 t 14, 3.83E+01 (5 t 141 2.06E+01 1.18E+02 0.58 MlLES SSE) 2.11E+01 1.18E+02 2.02E+Al - 5.52E+01 K-,40 1.00E+02 70 VALUES < LLD WBN WELL #1 14 VALUES < LLD 14 VALUES < LLD 0.6 MILES S H s, { I Pb212 1.50E+01 1.90E+01 (2 t 70) WBN MW-F 2.25E+01 (1 I 14) 14 VALUES < LLD cr ld o\ 1.548+01 - 2.25E+O1 o.30 MlLES SE) 2.25E+01 - 2.25E+0't t! I )+{
*{
t PB-214 2.00E+0t 3.83E+01 (28 t70) WBN ]ITIA,-A 4.83E+01 (10 t 14) 3.71E+01 (3 t 14) t-2.00E+Ot - 1.20E+02 0.58 MTLES SSE) 2.05E+01 - 1.2AE+02 2.05E+01 - 4.72E+O1 5 TL-208 1.00E+01 1.198+01 (1 I 7Ol WBN MW.F 1.19E+01 (1 I 14'l 14 VALUES < LLD 1.19E+01 - 1.19E+01 o.30 MlLES SE) 1.19E+01 - 1.19E+01 TRITIUM .84 2.70E+02 5.86E+02 (41 t70) WBN [\,llru.B 7.90E+02 (14 t 141 14 VALUES < LLD 2.78E+02 1.13E+03 0.4s MTLES SSE) 4.12E+OZ 1.13E+Og Nobs: l. l,lominal Lwsr Lcwl of Detecffon (tLD) aE dsEcribod in Table E - 1
- 2. tlcan and Range based upon detctable measuEments only. Fraction of detectable meeour nenE at spcified location is andacated in parentheses (F).
- 3. Blanks in this column indicatc no nonrountine mca3uGmcnt3
Tenneasee Valley Authority RADIOACTIVITY IN COMMERCIAL FISH pCi/g = 0.037 Bdg (DRY WEIGHT) Name of Facility: WAfiS BAR NUCLEAR PLANT Docket Number: 5G390,391 Location of Facility: RHEA, TENNESSEE Reporting Period: 201 6 Number of Type and Lower Limit lndicator Locations Location with Highest Annual Mean Control Locations Nonroutine Total Number of Detection Mean (F) Mean (F) Mean (F) Reported of Analysis (LLD) Range Location Description with Range Range Measurements Performed See Note 1 See Note 2 Distance and Direction See Note 2 See Note 2 See Note 3 GAMMA SCAN (GELl) -6 Bl-214 1.00E-01 4 VALUES < LLD DOWNSTREAM STATION 1 2 VALUES < LLD 1.19E-01 (1 I 2l DOWNSTREAM 1 .1 gE-01 - 1 .1gE-01 K,{0 4.00E-01 8.62E+00 (4 I 4, DOWNSTREAM STATION 1 9.16E+OO (2 t2) 1.21E+01 (2 t 2l 6.57E+00 9.61E+00 DOWNSTREAM 9.01E+00 9.31E+00 1.10E+01 ' 1.32E+01 Pt212 4.00E-02 4 VALUES < LLD CHICKAMAUGA RES 2 VALUES < LLD 2 VALUES < LLD TRM 471-530 PB-214 1.00E-01 4 VALUES < LLD DOWNSTREAM STATION 1 2 VALUES < LLD 1.16E-01 (1 I 2l DOWNSTREAM 1.16E 1.16E-01 TL-208 3.00E-02 4 VALUES < LLD CHICKAMAUGA RES 2 VALUES < LLD 2 VALUES < LLD -l TRM 471-530 p I -{ cr { H (D I
)+a
)+{
I ld L,I Notes: 1. Nominal Lower Level of Detection (LLD) as described in Table E-1
- 2. Mean and Range based upon detectable measurements only. Fraction of detedable measurements at specified location is indicated in parentheses (F).
- 3. Blanke in this column indicate no nonrountine measuremente}}