ML18135A255
| ML18135A255 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 05/15/2018 |
| From: | Simmons P Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18135A255 (67) | |
Text
Tennessee Valley Authority, P.O. Box 2000, Spring City, Tennessee 37381-2000 May 15, 2018 10 cFR 50.4 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001
Subject:
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 Watts Bar Nuclear Plant - Annual Radiological Environmental Operating Report - 2017 Enclosed is the subject report for the period of January 1,2017, through December 31,2017. 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.
Paul Simmons Site Vice President Watts Bar Nuclear Plant
Enclosure:
Annual Radiological cc: see Page 2
/
Respectfully, Environmental Operating Report - Watts Bar Nuclear Plant 2017
U.S. Nuclear Regulatory Commission Page 2 May 15, 2018 cc (Enclosure):
NRC Regional Administrator - Region ll NRC Project Manager - Watts Bar Nuclear Plant NRC Senior Resident lnspector - Watts Bar Nuclear Plant
ENCLOSURE TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT Annual Radiological Environmental Operating Report Watts Bar Nuclear Plant 2A17
Annual Radiological Envi ronmenta I Operating Report Watts Bar Nuclear Plant 2017 Ten nessee Va I ley Authority May 2Ot8 Laboratories r i {l a mr*nber cf The GEL Group r,,r[.
@(hestpenke Huclear Seruices
TABLE OF CONTENTS Naturally Occurring and Background Radioactivity...........
...........2 Electric Power Production..
...................3 Site and Plant Description.............
..,.........5 Radiological EnvironmentalMonitoring Program
........7 Direct Radiation Monitoring.............
...... 10 Measurement Techniques
..................10 Atmospheric Monitoring..
....................... 13 Sample Collection and Analysis
..........13 Sample Collection and Analysis
..........15 Liquid Pathway Monitorin9..................
.......................L7 Sample Collection and Analysis
..........17 Assessment and Evaluation,..............
..................,......2O Appendix A Radiological Environmental Monitoring Program and Sampling Locations.......................22 Appendix B Program Modifications.................
......32 Appendix C Program Deviations...
......34 Appendix D Analytical Procedures
.........................3g Appendix E Lower Limits Of Detection
..................40 Appendix F Quality Assurance / Quality Control Program......
....................... r14 ApRendix G Land Use Survey.........
....r...............
.........................47 l
.i^- ^-r ti-..-^-
I ApOendix H Data Tables and Figures
.1..................
......................50 tiI
Appendix !
Errata to Previous Annual EnvironmentalOperating Reports....
....................60 li iI
EXECUTIVE
SUMMARY
This report describes the Radiological Environmental Monitoring Program (REMP) conducted by the Tennessee Valley Authority (WA) near the Watts Bar Nuclear Plant (WBN) during the 2OL7 monitoring period. The program is conducted in accordance with regulatory requirements to monitor the environment per 10 CFR 20, 10 CFR 50, and TVA procedures. The REMP includes the collection and subsequent determination of radioactive material content in environmental samptes. Various types of samples are collected within the vicinity of the plant, including air, water, food crops, soil, fish and shoreline sediment, and direct radiation levels are measured, The radiation levets of these samples are measured and compared with results at control stations located outside the plant's vicinity and data collected at Watts Bar Nuclear Plant prior to operations (preoperational data). This report contains an evaluation of the potential impact of WBN operations on the environment and the general public.
Most of the radioactivity measured in environmental samples in the WBN program can be attributed to naturally occurring radioactive materials. ln 2017, trace quantities of Cesium-137 (Cs-137) were measured in soil samples. The concentrations were typical of the levels expected to be present in the environment from past nuclear weapons testing. The fallout from accidents at the Chernobyl plant in the Ukraine in 1985 and the Fukushima plant in Japan in 2011 may have also contributed to the low levels of G-137 measured in environmental samples. Tritium (H-3) was detected in water samples collected from Washington Ferry and Breedenton Ferry and in drinking water samples from TRM 503.8 (Dayton, TN) and TRM 473 (East Side Utilities). Tritium was also detected in onsite groundwater wells. Similar levels of tritium were detected in both control and indicator locations, indicating that any plant contribution to the natural background level is small. The measured levels were a small fraction of the EpA drinking water limit These levels of radioactive elements detected do not represent a significant contribution to the radiation exposure to members of the public.
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INTRODUCTION This report describes and summarizes the results of radioactivity measurements made near WBN and laboratory analyses of samples collected in the area. The measurements are made to comply with the requirements of 10 CFR 50, Appendix 4 Criterion 54 and 10 CFR 50, Appendix l, Section lV.B.2, lV.B.3 and lV.C and to determine potential effects on public health and safety. This report satisfies the annual reporting requirements of WBN TechnicalSpecification 5.9.2 and Offsite Dose Calculation Manual(ODCM)
Administrative Control 5.1. ln addition to reporting the data prescribed by specific requirements, other information is included to help correlate the significance of results measured by this monitoring program to the levels of environmental radiation resulting from naturally occurring radioactive materials Naturallv Occurrins and Backsround Radioactivitv Most materials in our world today contain trace amounts of naturally occurring radioactive materials.
Potassium 40 (K40), with a half-life of 1.3 billion years, is one of the most common radioactive materials found naturally in our environment. Approximately 0.01 percent of all potassium is radioactive K-40.
Other examples of naturally occurring radioactive materials include isotopes of beryllium, bismuth, lead, thallium, thorium, uranium and radium, among others. Carbon-14 (C-14) and Hydrogen-3 (H-3, commonly called Tritium") exist in the environment naturally but also as a result of nuclear power plant operations.
These naturally occurring radioactive materials are in the soil, our food, our drinking water, and our bodies. The radiation from these materials makes up a part of the low-level natural background radiation.
The remainder of the natural background radiation results from cosmic rays.
It is possible to get an idea of the relative hazard of different types of radiation sources by evaluating the amount of radiation the U.S. population receives from each general type of radiation source. The information below is primarily adapted from Reference 1 and Reference 2.
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Natural Background Dose Equivalent Cosmic 33 Terrestria I 2L ln the body 29 Radon 228 Tota I 311 Medical (effective dose equivalent) 300 Nuclear energy 0.28 Consumer Products 13 TOTAL 624,28 Table 1 - U.S. General Populatian Averoge Dose Equivalent Estimates i One-thousandth of a Roentgen Equivalent Man (rem). By comparison, the NRCs annual radiation dose limit for the public from any licensed activity, such as a nuclear plant, is 100 mrem As can be seen from the data presented above, natural background radiation dose equivalent to the U.S.
population exceeds that normally received from nuclear plants by several hundred times. This indicates that nuclear plant operations normally result in a population radiation doses which are insignificant as compared to the dose from natural background radiation. lt should be noted that the use of radiation and radioactive materials for medical uses has resulted in a similar effective dose equivalent to the U.S.
population as that caused by natural background cosmic and terrestrial radiation.
Electric Power Production Nuclear power plants are similar in many respects to conventional coal burning (or other fossil fuel) electrical generating plants. The basic process behind electrical power production in power plants is that fuel is used to heat water to produce steam which provides the force to turn turbines and generators. ln a nuclear power plant, the fuel is uranium and heat is produced in the reactor through the fission of the uranium. Nuclear plants include many complex systems to control the nuclear fission process and to safeguard against the possibility of reactor malfunction. The nuclear reactions produce radionuclides commonly referred to as fission and activation products. Very small amounts of these fission and activation products are released into the plant systems. This radioactive material can be transported throughout plant systems and some of it may be released to the environment.
Paths through which radioactivity from a nuclear power plant is routinely released are monitored. Liquid and gaseous effluent monitors record the radiation levels for each release. These monitors also provide alarm mechanisms to prompt termination of any release above limits.
Releases are monitored at the onsite points of release. The radiological environmental monitori4g program, which measures the environmJntal radiation in areas around the plant, provides a confirmatiln t3l
that releases are being properly controlled and monitored in the plant and that any resulting levels in the environment are within the established regulatory limits and a small fraction of the natural background radiation levels. ln this way, the release of iadioactive materials from the ptant is tightly controtted, and verification is provided that the public is not exposed to significant levels of radiation or radioactive materials as the result of plant operations.
The WBN ODCM, which describes the program required by the plant technical specifications, prescribes limits for the release of radioactive effluents, as well as limits for doses to the general public from the release of these effluents.
TheNRCsannualdoselimittoamemberofthepublicforalllicenseesisl00mrem.
TheNRC'sregulations for nuclear power plants contain additional operational constraints, impiementing the philosophy of "as low as reasonably achievable, where there the dose to a member of the general public from radioactive materials released to unrestricted areas is limited as follows:
Liquid Effluents Total body Any organ Gaseous Effluents
< 3 m rem/yr
< 10 mrem/yr
< 10 millirad (mrad)/yr
< 20 mrad/yr
< 15 mrem/yr Noble gases:
Gamma radiation Beta radiation Pa rticu lates:
Any organ In addition to NRC's regulations, the EPA standard forthe total dose to the public in the vicinity of a nuclear power plant, established in the Environmental Dose Standard of 40 CFR 19Q are as follows:
Total body Thyroid Any other organ 3 25 mrem/yr
<75 mrem/yr s 25 mrem/yr Table 6 of this report presents the compares the nominal lower limits of detection (LLD) for the WBN monitoring program with the regulatory Iimits for maximum annual average concentration released to unrestricted areas. The table also presents the concentrations of radioactive materials in the environment which would require a special report to the NRC and the detection limits for measured radionuclides. lt should be noted that the levels of radioactive materials measured in the environment are typically below or only slightly above the lower limit of detection.
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SITE AND PLANT DESCRIPTION The WBN site is in Rhea county, Tennessee, on the west bank of the Tennessee River at Tennessee River Mile (TRM) 528. Figure 1 shows the site in relation to other WA projects. The WBN site, containing approximately L770 acres on Chickamauga Lake, is approximately 2 miles south of the Watts Bar Dam and approximately 31 miles north-northeast of WA's Sequoyah Nuclear plant (SeN) site. Also located within the reservation are the Watts Bar Dam and Hydro-Electric Plant, the Watts Bar Steam plant (not in operation), the wA central Maintenance Facility, and the watts Bar Resort Area.
Approximately 18,500 people live within 10 miles of the WBN site. More than 80 percent of these live between 5 and 10 miles from the site. Two smalltowns, Spring City and Decatur, are located in this area.
Spring City, with a population of approximately 2,200, is northwest and north-northwest from the site, while Decatur, with about 1,500 people, is south and south-southwest from the plant. The remainder of the area within 10 miles of the site is sparsely populated, consisting primarily of small farms and individual residences.
The area between 10 and 50 miles from the site includes portions of the cities of Chattanooga and Knoxville. The largest urban concentration in this area is the city of Chattanooga, located to the southwest and south-southwest. The city of Chattanooga has a population of about 17O,OOO, with approximately g0 percent located between 40 and 50 miles from the site and the remainder located beyond 50 miles. The city of Knoxville is located to the east-northeast, with not more than 10 percent of its 185,000 plus people living within 50 miles of the site. Three smaller urban areas of greater than 20,000 people are located between 30 and 40 miles from the site. Oak Ridge is approximately 40 miles to the northeast, the twin cities of Alcoa and Maryville are located 45 to 50 miles to the east-northeast, and Cleveland is located about 30 miles to the south.
Chickamauga Reservoir is one of a series of highly controlled multiple-use reservoirs whose primary uses are flood control, navigation, and the generation of electric power. Secondary uses include industrial and public water supply and waste disposal, fishing, and recreation. Public access areas, boat dock, and residential subdivisions have been developed along the reservoir shoreline.
WBN consists of two pressurized water reactors. WBN Unit 1 received a low power operating license (NPF-20) on November 9, 1995 and achieved initial criticality in January 199G. The full power operating license (NPF-90) was received on February 7, Lgg6. Commercial operation was achieved May 25, 19gG.
WBN Unit 2 was deferred October 24,2000, in accordance with the guidance in Generic Letter g7-15, "Policy Statement on Deferred Plants." On August 3,2OO7,WA provided notice of its intent to reactivate and complete construction of WBN Unit 2. WBN Unit 2 resumed construction in late 2007. October 22, 2015 the operating license was issued. lnitial criticality was achieved on May 23,20L6 and commercial operation was achieved on October !9,2016.
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RADIOLOGICAL ENVI RON M ENTAL M ON ITORI NG PROG RAM Most of the radiation and radioactivity generated in a nuclear power reactor is contained within the reactor systems. Plant effluent radiation monitors are designed to monitor radionuclides released to the environment. Environmental monitoring is a finalverification that the systems are performing as planned.
The monitoring program is designed to monitor the pathways between the plant and the people in the immediate vicinity of the plant. Sample types are chosen so that the potential for detection of radioactivity in the environment will be maximized. The Radiological Environmental Monitoring Program (REMP) and sampling locations for WBN are outlined in Appendix A.
There are two primary pathways by which radioactivity can move through the environment to humans:
air and water (see Figure 2). The air pathway can be separated into two components: the direct (airborne) pathway and the indirect (ground or terrestrial) pathway. The direct airborne pathway consists of direct radiation and inhalation by humans. ln the terrestrial pathway, radioactive materials may be deposited on the ground or on plants and subsequently ingested by animals and/or humans. Human exposure through the liquid pathway may result from drinking water, eating fish, or by direct exposure at the shoreline. The types of samples collected in this program are designed to monitor these pathways.
Many factors were considered in determining the locations for collecting environmental samples. The locations for the atmospheric monitoring stations were determined from a critical pathway analysis based on weather patterns, dose projections, population distribution, and land use. Terrestrialsampling stations were selected after reviewing such things as the locations of dairy animals and gardens in conjunction with the air pathway analysis. Liquid pathway stations were selected based on dose projections, water use information, and availability of media such as fish and sediment. Table 4 lists the sampling stations and the types of samples collected from each. Modifications made to the WBN monitoring program in 2Ot7 are reported in Appendix B. Deviations to the sampling program during 2OL7 are included in Appendix C.
To determine the amount of radioactivity in the environment prior to the operation of WBN, a preoperational radiological environmental monitoring program was initiated in December L976 and operated through December 31, 1995. Measurements of the same types of radioactive materials that are measured currently were assessed during the preoperational phase to establish normal background levels for various radionuclides in the environment.
The preoperational monitoring program is a very important part of the overall program. Duringthe 1950s, 1960s, and 1970s, atmospheric nuclear weapons testing released radioactive materialto the environment causing fluctuations in background radiation levels. Knowledge of preexisting radionuclide patterns in the environment permits a determination, through comparison and trending analyses, of the actual environmental impact of WBN operation.
The determination of environmental impact during the operating phase also considers the presence of control stations that have been established in the environment. Results of environmental samples taken at control stations (far from the plant) are compared with those from indicator stations (near the plant) to aid in the determination of the impacts from WBN operation.
17)
ln 20L7, the sample analysis was performed by two separate laboratories. Samples collected prior to June 30,2OL7 were analyzed by Tennessee Valley Authorit/s (WA's) Environmental Radiological Monitoring and lnstrumentation'(ERM&I) group located at the Western Area Radiological LiUoratory {WARL) in Muscle Shoals, Alabama, except for the Strontium-89/90 (Sr-89, Sr-90) analysis of soil samples which is performed by a contract laboratory. Beginning in July 2Ot7, GEL Laboratories, LLC based in Charleston, SC performed all the radiochemistry analyses of the WBN REMP samples. Analyses are conducted in accordance with written and approved procedures and are based on industry established standard analytical methods. A summary of the analysis techniques and methodology is presented in Appendix D.
The radiation detection devices and analysis methods used to determine the radionuclide content of samples collected in the environment are very sensitive and capable of detecting 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 nomina! LLDs for the ERM&I laboratory and GEL is presented in Appendix E.
The laboratory applies a comprehensive quality assurance/quality contro! program to monitor laboratory performance throughout the year. One of the key purposes of the AA/AC program is to provide early identification of any problems in the measurement process so they can be corrected in a timely manner.
This program includes instrument check, to ensure that the radiation detection instruments are working properly, and the analysis of quality controlsamples. As part of an interlaboratory comparison program, the laboratory participated in a blind sample program administrated by Eckert & Ziegler Analytics. A complete description of the program is presented in Appendix F. Data tables summarizing the sample analysis results are presented in Appendix H.
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Figure 2 - Environmental Expasure Pothwoys EN\\,ITIC,NMENTAL E)<PIIEUHE FATHWAYA ClF lYlAN EIUE TCl ]IELEAtsEE ElF HAEIICIAETIVE lvlATEHIAL TCl THE AT]VICIEPHEHE ANEI LA!(E.
Airborne Beleases L
PIume Erposure Liquid Beleases Diluted By Lake Animals Itilk,teatl con*rru Gonsumed Bytan\\
Shoreline ExposurG By Animals Drinking Water tish Vegetation Uptake From Soil MAN teI
DI RECT RADIATION MON ITORING Direct radiation levels are measured at various monitoring points around the plant site. These measurements include contributions from cosmic radiation, radioactivity in the ground, fallout from atmospheric nuclear weapons tests conducted in the past, and any radioactivity that may be present from plant operations. Because of the relatively large variations in background radiation as compared to the small levels from the plant, contributions from the plant may be difficult to distinguish.
Measurement Techniques The Landauer lnLight environmental dosimeter is used in the radiological environmental monitoring program for the measurement of direct radiation. This dosimeter contains four elements consisting of aluminum oxide detectors with open windows as well as plastic and copper filters. The dosimeter is processed using optically stimulated luminescence (OSL) technology to determine the amount of radiation exposure.
The dosimeters are placed approximately one meter above the ground, with two at each monitoring location. Sixteen monitoring points are located around the plant nearthe site boundary, one location in each of the 16 compass sectors. One monitoring point is also located in each of the 15 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 Landauer lnlight for processing and results reporting. The values are corrected for transit and shielded background exposure.
An average of the two dosimeter results is calculated for each monitoring point. The system meets or exceeds the performance specifications outlined in American National Standards lnstitute (ANSI) N545-1975 and Health Physics Society (HPS) Draft Standard N13.29 for environmental applications of dosimeters.
WBN Technical Specification 5.9.2, Annual Radiological Environmental Operating Report, requires that the Annual Radiological Environmental Operating Report identify TLD results that represent collocated dosimeters in relation to the NRC TLD program and the exposure period associated with each result. The NRC collocated TLD program was terminated by the NRC at the end of L997, therefore, there are no TLD results that represent collocated dosimeters included in this report.
Results The results for environmental dosimeter measurements are normalized to a standard quarter (91.25 days or 2190 hours0.0253 days <br />0.608 hours <br />0.00362 weeks <br />8.33295e-4 months <br />). 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, for purposes of this report, monitoring points 2 miles or less from the plant are identified as "onsite" stations and locations greater than 2 miles are considered "offsite."
[10]
The quarterly and annualgamma radiation levels determined from the dosimeters deployed around WBN in2ot7 are summarized in Table 2. For comparison purposes, the average direct radiation measurements made in the preoperationat phase of the monitoiing program are also shown.
Table 2 ' Average Externol Gamma Radiation Levels ot Vorious Distdnces from Wotts Bor Nucleor plont lor Eoch Quorter - 2017 Average External Gamma Radiation Levels jl'Jffi,ffi, !28 Q1' Q2 (mrem lqtrl (mrem lqtrl Q3 Q4 (mrem /qtrl (mrem lqtr)
L7,g 13.5 L7.O L2.3 Annual Preoperational (mrem lVrl (mR/yr) 61.5c 65 55.3 57 11.5 L7.3 15.4 Average >2 miles (offsite)b NOTES
- a. Field periods normalized to one standard quarter(2190 hourc)
- b. Average of the individual measurements in the set
- c. The 5.2 mrem/yr excess for onsite locations falls below the 25 mrem total body limit for 40 CFR 190.
The data in Table 2 indicates that the average quarterly direct radiation levels at the WBN onsite stations are approximately 1.3 mrem/quarter higher than levels at the offsite stations. This equates to 5.2 mrem/year detected at the onsite locations. This vatue falls betow the EPA limit of 25 mremlyear total body. The difference in onsite and offsite averages is consistent with levets measured for the preoperational and construction phases of WA nuclear power plant sites where the average levets onsite were slightly higher than levels offsite. Figure 3 compares plots of the data from the onsite stations with those from the offsite stations over the period from L977 through 2OLl. The new Landauer lnLight optically Stimulated Luminescence (oSL) dosimeters were deployed since 2007 reptacing the panasonic UD-814 dosimeters used during the previous years.
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Figure 3 - Average Direct Rodioiton Resu/fs Direct Radiation Levels Watts Bar Nuclear Plant Four Quarter Moving Average
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-<FOff-Site The data in Table 13 contains the results of the individual monitoring stations. The results reported in 2OL7 are consistent with historical and preoperational results, indicating that the direct radiation levets are not influenced by the operation of WBN. There is no indication that WBN activities increased the background radiation levels normally observed in the areas surrounding the plant.
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aTtuosP H E R I C MO NITOR I NG The atmospheric monitoring network is divided into three groups identified as tocal, perimeter, and remote. Four local air monitoring stations are located on or adjacent to the plant site in the general directions of greatest wind frequency. Four perimeter air monitoring stations are located between 6 to 11 miles from the plant, and two air monitors are located out to 15 miles and used as control or baseline stations. The monitoring program and the locations of monitoring stations are identified in the tables and figures of Appendix A.
Results from the analysis of samples in the atmospheric pathway are presented in Table 14 through Table L7. Radioactivity levels identified in this reporting period are consistent with background and preoperational program data. There is no indication of an increase in atmospheric radioactivity due to WBN operations.
Sample Collection and Analvsis Air particulates are collected by continuously sampling air at a flow rate of approximately 2 cubic feet per minute (cfm) through a 2-inch glass fiber filter. The sampling system consists of a Vacuum Florescent Display (VFD), an oil-less carbon vane vacuum pump and a precision-machined mechanical differential pressure flow sensor. lt is equipped with automatic flow controt, on-board data storage, and alarm notificaflons for flow, P, T, and higher filter DP. This system is housed in a weather resistant environmental 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 analyzed for gross beta activity about 3 days after collection to allow time for the radon daughters to decay. Every 4 week composites of the filters from each location are analyzed by gamma spectroscopy.
Gaseous radioiodine is sampled using a commercially available cartridge containing Triethylenediamine (TEDA)-impregnated charcoal. This system is designed to collect iodine in both the elemental form and as organic compounds. The cartridge is in the same sampling head and downstream of the air particulate filter. The cartridge is changed at the same time as the particulate filter and samples the same volume of air. Each cartridge is analyzed for l-131 by gamma spectroscopy.
Atmospheric moisture sampling is conducted by pulling air at a constant flow rate through a column loaded with approximately 400 grams of silica gel. Every two weeks, the column is exchanged on the sampler. The atmospheric moisture is removed from silica gel by heating and analyzed for tritium.
Results The results from the analysis of air particulate samples are summarized in Table 14. Gross beta activity in 2017 was consistent with levels reported in previous years. The average gross beta activity measured for air particulate samples was0.027 pCi/m3. The annualaverages of the gross beta activity in air particutate filtersatthesestationsfortheperiodT9TT-2OLTarepresentedinFigurel0. lncreasedlevelsduetofallout from atmospheric nuclear weapons testing are evident in the years prior to 1981 and a small increase from the chernobyl accident can be seen in 1986. These patterns are consistent with data from monitoring programs conducted by WA at other nuclear power plant co4struction sites. ln 2OL7,the tlrl
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annual average gross beta particulate activity has increased. However, this increase is consistent across both control and indicator locations, so is not considered a result of any WBN operationa! activities.
Only natural radioactive materials were particulate samples. As shown in Table collected in 20L7.
identified by the monthly gamma spectral analysis of the air 15, f-131 was not detected in any charcoal cartridge samples The results for atmospheric moisture sampling are reported in Table 17. Tritium was measured, above the nominal LLD value of 3.0 pCi/m3, in atmospheric moisture samples from both the indicator and control locations. The highest concentration from the indicator locations was 4.95 pClm3 and the highest concentration from the control locations was 2.54 pCi/m3.
[14]
rE R R ESTR tAL M O N tTO R tl_\\S Terrestrial monitoring is accomplished by collecting samples of environmental media that may transport radioactive material from the atmosphere to humans. For example, radioactive material may be deposited on a vegetable garden and be ingested along with the vegetables or it may be deposited on pasture grass where dairy cattle are grazing. When the cow ingests the radioactive material, some of it may be transferred to the milk and consumed by humans who drink the milk. Therefore, samples of milk, soil, and food crops are collected and analyzed to determine potential impacts from exposure through this pathway. The results from the analysis of these samples are shown in Table 18 through Table 20.
A land use survey is conducted annually between Apriland Octoberto identifythe location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 square feet producing fresh leafy vegetables in each of 15 meteorotogical sectors within 5 miles from the plant. This land use survey satisfies the requirements 10 CFR 50, Appendix l, Section lV.B.3. From data produced by the land use survey, radiation doses are projected for individuals living near the plant. Doses from air submersion are calculated for the nearest residence in each sector, while doses from drinking milk or eating foods produced near the plant are calculated for the areas with milk-producing animals and gardens, respectively. These dose projections are hypothetical extremes and do not represent actual doses to the general public. The results of the 2017 land use survey are presented in Appendix G.
Sample Collection and Analvsis Milk samples are collected every two weeks from two indicator dairies and from at least one control dairy.
Milk samples are placed on ice fortransport to the radioanalytical taboratory. A radiochemicalseparation analysis for l-131 and gamma spectroscopy are performed on each sample and a Sr-89 and Sr-90 analysis is performed quarterly.
The monitoring program includes a provision for sampling of vegetation from tocations where milk is being produced and when milk sampling cannot be conducted. There were no periods during this year when vegetation sampling was necessary.
Soil samples are collected annually from the air monitoring locations. The samples are collected with either a "cookie cutte/' or an auger type sampler. After drying and grinding, the sample is analyzed by gamma spectroscopy and for Sr-89 and Sr-90.
Samples representative of food crops raised in the area near the plant are obtained from individual gardens. Types of foods may vary from year to year due to changes in the local vegetable gardens.
Samples of cabbage, corn, green beans, and tomatoes were collected from local vegetable gardens and/or farms' Samples of the same food products grown in areas that would not be affected by the plant were obtained from area produce markets as control samples. The edible portion of each sample is analyzed by gamma spectroscopy.
Results The results from the analysis of milk samples are presented in Table 18. No radioactivity attributable to WBN Plant operations was iderlrtified. All l-131 values were below the established nominal Lto of r.o pCi/liter. The gamma isotopic aha[sis detected only naturally occurring radionuclides. Milk sJmp]es are
[1s]
analyzed quarterly for Sr-89 and Sr-90. No analyses identified any positive resutts for Sr-g9 or Sr-90.
However, the third quarter sample from one indicator location (Norton Farm) was not completed. The third quarter control location was inilyzed for Sr-8g but the nominal LLD was not achieved. '-:' -'-
Consistent with most of the environment, Cs-137 was detected in most of the soil samples coltected in 2OL7. The maximum concentration of Cs-137 was 255 pC;/y,g, but this was identified at a control location.
The concentrations were consistent with levels previously reported from failout. All other radionuclides reported were naturally occurring isotopes. The results of the analysis of soil samples are summarized in Table 19.
A plot of the annual average Cs-137 concentrations in soil is presented in Figure 4. Concentrations of Cs-137 in soil are steadily decreasing as a result of the cessation of weapons testing in the atmosphere, the 30-year half-life of G-137, and transport through the environment.
Figure 4 An nual Average Activity of Cs-137 in Soil Watts Bar Nuclear plant 1.0 r
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0.9 0.8 o.7 0.5 0.5 0.4 0.3 0.2 0.0 0.1
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L -r 2015 1975 2010 The radionuclides measured in food samples were naturally occurring.
in Table 20.
I I
Calendar Year
--*- lndicator
- l*Control The results are reported I
lnitial WBN Operation in January, 1996 t16I
LIQU I D PATHWAY MON ITORI NG Potential exposures from the liquid pathway can occur from drinking water, ingestion of fish, or from direct radiation exposure from radioactive materials deposited in the shoreline sediment. The aquatic monitoring program includes the collection of samples of river (surface) water, ground water, drinking water supplies, fish, and shoreline sediment. lndicator samples were collected downstream of the plant and controlsamples collected within the reservoir upstream of the plant or in the next upstream reservoir (Watts Bar Lake).
Sample Collection and Analvsis Samples of surface water are collected from the Tennessee River using automatic sampling systems from two downstream stations and one upstream station. A timer turns on the system at least once every two hours. The line is flushed and a sample 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-emitting radionuclides and tritium.
Samples are also collected by an automatic sampling system at the first two downstream drinking water intakes. These samples are collected in the same manner as the surface water samples. These monthly samples are analyzed for gamma-emitting radionuclides, gross beta activity, and tritium. The samples collected by the automatic sampling device are taken directly from the river at the intake structure. Since these samples are untreated water collected at plant intake, the upstream surface water sample is used as a control sample for drinking water.
Ground water is sampled from one onsite well down gradient from the plant, one onsite well up gradient from the plant, and four additional onsite ground water monitoring wells located along underground discharge lines. The onsite wells are sampled with a continuous sampling system. A composite sample is collected from the onsite wells every four weeks and analyzed for gamma-emitting radionuclides, gross beta activity, and tritium content.
Samples of commercial and game fish species are collected semiannually from each of two reservoirs: the reservoir on which the plant is located (Chickamauga Reservoir) and the upstream reservoir (Watts Bar Reservoir). The samples are collected using a combination of netting techniques and electrofishing. The ODCM specifies analysis of the edible portion of the fish. To comply with this requirement, filleted portions are taken from several fish of each species. The samples are analyzed by gamma spectroscopy.
Samples of shoreline sediment are collected from recreation areas near the plant. The samples are dried, ground, and analyzed by gamma spectroscopy.
Results The gamma isotopic analysis of all surface water samples identified only naturally occurring radionuclides.
Low levels of tritium were detected in some surface water samples. The highest tritium concentration was 846 pCi/liter at a control location. This tritium concentration is considered background and represent only a small fraction of the Environmental Protection Agency (EPA) drinking water limit of 20,000 pCi/liter.
A summary table of the results for surface water safnples is shown in Table 21.
I lLTl
No fission or activation products were identified by the gamma analysis of drinking water samples from the two downstream monitoring locations. Average gross beta activity at downstream (indicator) stations was 2.98 pCi/liter and the average for the upstream icbntrol) station was 3.08 pCi/liter. Low levets of tritium were detected in one third of the samples collected from the two downstream public water sampling locations. The highest tritium concentration was 1,031 pCi/liter. The tritium levels were significantly below the EPA drinking water limit of 20,000 pCi/liter. The results are shown in Table 22.
The gamma isotopic analysis of ground water samples identified only naturally occurring radionuclides.
Gross beta concentrations in samples from the onsite indicator locations averaged 2.2 pCi/liter. No samples from control locations identified any positive results for gross beta activity. Tritium was detected in samples from the onsite monitoring wells located near plant discharge tines. The tritium in onsite ground water was the result of previously identified leaks from plant systems. Repairs were made to resolve the leak but the plume of contaminated ground water continues to move slowty across the site toward the river. The highest tritium concentration in samples from these monitoring locations was 498 pCi/liter' There was no tritium detected in the onsite up gradient well. The results are presented in Table 23.
Cs-137 was identified in three fish samples, two indicator and one control. The G-137 concentration averaged 0.021 pCi/ke measured in game fish collected at indicator tocations and 0.018 pCi/kg at the control location. Other radioisotopes found in fish were naturally occurring. The results are summarized in Table 24. Trend plots of the annual average Cs-137 concentrations measured in fish samptes are presented in Figure 5. The Cs-137 activities are consistent with preoperational resutts produced byfatlout or effluents from other nuclear facilities.
t18I
Figure 5 Annual Average Activity of Cs-L37 in Game Fish Watts Bar Nuclear Plant 0.30 0.25 0.20 0.15 0.10 0.05 lnitial WBN Operation in Janfrary, 1996 I
I 0.00 L975 1980 1985 1990 1995 2000 Calendar Year 2010 2015
--+- lndicator +- Control ln past years, Cs-137 activities consistent with the concentrations present in the environment as the resutt of past nuclear weapons testing or other nuclear operations in the area was measured in shoreline sediment samples. ln 2OL7, no plant related nuclides were identified in shoretine sediment samples.
Consistent with previous monitoring conducted forthe onsite ponds, G-137 was detected in the sediment samples. The average of the Cs-137 levels measured in sediment from the onsite ponds was 133 pci/kg.
This radioactivity was present in relatively low concentrations and confined to the ponds tocated in the owner-controlled area not open to the general public so the presence of this radioactivity does not represent an increased risk of exposure to the general public.
A LEI Y
u0\\
II(,
CL I
+,'t o-flC'
[1s]
ASSESSM E NT AN D EVALUATION Potential doses to the public are estimated from measured effluents using computer models. These models were developed byWA and are based on guidance provided bythe NRC in Regulatory Guide 1.109 for determining the potential dose to individuals and populations living near the plant. The results of the effluent dose calculations are reported in the Annual Radiological Effluent Release Report. The doses calculated are a representation of the dose to a "maximum exposed individual." Some of the factors used in these calculations (such as ingestion rates) are maximum expected values which will tend to overestimate the dose to the "hypothetical" person. The calculated maximum dose due to plant effluents are smallfractions of the applicable regulatory limits. ln reality, the expected dose to actual individuals is significantly lower.
Based on the very low concentrations of radionuclides present in plant effluent and radioactivity levels measured in the environment, doses as a result of plant operations are negligible. The results for the radiological environmental monitoring conducted for WBN in 2OL7 operations confirm this expectation.
Results As stated earlier in this report, the estimated increase in radiation dose equivalent to the general public resulting from the operation of WBN is insignificant when compared to the dose from natural background radiation. The results from each environmental sample are compared with the concentrations from the corresponding control stations and appropriate preoperational and background data to determine influences from the plant. During this report period, Cs-137 was detected in soil, on-site pond sediment and fish collected for the WBN program. The Cs-137 concentrations were consistent with levels measured during the preoperational monitoring program. The levels of tritium measured in water samples from Chickamauga Reservoir represented concentrations that were a smallfraction of the EpA drinking water limit.
The levels of tritium detected in the onsite ground water monitoring wells and the radionuclides measured in samples of sediment from the onsite ponds do not represent an increased risk of exposure to the public.
These radionuclides were limited to the owner-controlled area and would not present an exposure pathway for the general public.
Conclusions It is concluded from the above analysis of environmental samples and from the trend ptots presented, that exposure to members of the general public which may have been attributable to WBN is negligible.
The radioactivity reported herein is primarily the result of fallout or natural background. Any activity which may be present in the environment as a result of plant operations does not represent a significant contribution to the exposure of members of the public.
[20]
REFERENCES
- 1. NCRP. (March 2009). Repon No. 76Q lonizing Rodiotion Exposure olthe Populotion of the united Stotes. NCRP, Washington, D.C.
- 2. USNRC. (February 1995). lnstruction Concerning Risk lrom Occupotional Exposure. USNRC, Washington, D.C.
[21]
APPENDIX A RADIOLOG ICAL ENVI RON M ENTAL MON ITORI NG PROGRAM AND SAMPLING LOCATIONS l22l
APPENDIX A Toble 3 - Watts Bor Nucleor Power Plant Rodiologicol Environmental Monitoring Program Exposure Pathwav and r Sample'
- 1. AIRBORNE
- a. Pa rticu lates Number of Samples and Locationsb 4 samples from locations (in different sectors) at or nearthe site boundary (LM-l, 2,3 and 4) 4 samples from communities approximately 5-t0 miles from plant (PM-2,3, 4 and 5) 2 samples from control locations > 10 miles from the plant (RM-2 and 3)
- b. Radioiodine Samples from same locations as air particulates 4 samples from locations (in different sectors) at or near the site boundary (LM-l, 2,3, and 4) 2 samples from communities approximately 4-10 miles distance from the plant (PM-2, 5).
2 samples from control location greater than 10 miles from the plant (RM-2 and RM-3).
Samples from same location as air particulates
- d. Soil
- c. Atmospheric Moisture Samplins and Collection Frequencv Continuous sam pler operation with sample collection weekly (more frequently if required by dust loadine)
Continuous sam ple operation with filter collection weekly.
Conti nuous sam pler operation with sample collection biweekly.
Annually Tvpe and Frequencv of Analvsis Analyze for gross beta radioactivity 2 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following filter change.
Perform gamma isotopic analysis on each sample if gross beta > 10 times yearly mean of contro! sample.
Composite at least oqice per 31 days (by location) for gamma spectroscopy.
l-131 at least once per 7 days.
Analysis is performed by gamma spectroscopy.
Analyze each sample for tritium.
Ga mma spectroscop% Sr-89, Sr-90 annually
[23]
t-APPENDIX A Sampline and Collection Tvpe and Frequencv of Exposure Pathwav and r Sample'
- 2. DIRECT
- a. Dosimeters Number of Samples and Locationsb Frequencv Analvsis 2 or more dosimeterc placed at or nearthe site euarterly (once per 92 days) Gamma dose quarterty (at boundary in each of the 15 sectors.
2 or more dosimeters placed at stations located approximately 5 miles from the plant in each of the 15 sectors.
2 or more dosimeters in at least 8 additional locations of special interest, including at least 2 control stations.
Ieast once per 92 days)
- 3. WATERBORNE
- a. Surface Water 2 samples downstream from plant discharge Collected by automatic Gross beta, gamma (TRM 517.9 and TRM 523.1).
sequential-type samplef with spectroscopy, and tritium composite samples collected analysis of each sample.
1 sample at a control location upstream from over a period of approximately the plant discharge (TRM 529.3).
31days.
- b. Ground water Five sampling locations from ground water Cotlected by automatic Gross beta, gamma monitoring wells adjacent to the plant (Wells sequential-type sampler" with spectroscopy, and tritium No. 1, A, B, C, and F).
composite samples collected analysis of each sample.
1 sampre from ground water source up gradien, ;l]#riod of approximately (WellNo.5).
- c. Drinking Water 1 sample at the first two potable surface water Collected by automatic Gross beta, gamma scan, and supplies, downstream from the plant (TRM sequential-type sampler. with tritium analysis of each 503.8 and TRM 473.0).
composite sample collected sample.
monthly.
l sample at a control location FnM SZg.Sld 124l
APPENDIXA Exoosurc Pathwav end/or l{umber of SamoLs and tocationsb Sampllnr and colleation Tvoe atld Frouer6, of SamplC Frcouencv Analssis "
d-lfiorcllne Scdlment l sample downslream from pl.m dischaGe ScmlAnnually(.t le.st once c.mm. spectioscopy of e.ch (IRM 513,0) per 144 days) sample 1 sample frcm a control location upstream fiom plait dircha,r fiRM 530.2)
- e. Pond Sediment l sample from at least three locations in the Annually Yard Holding Pond Gamma spectroscopy of each sample l-131and gamma spectroscopy on each sample.
Sr-89 and Sr-90 quarterly.
- 4. !NGESTION
- a. Milk 1 sample from milk producing animals in each Every 2 weeks of 1-3 areas indicated by the cow census where doses are calculated to be highest.
1 or more samples from control locations
- b. Fish One sample of commercially important species Semi-Annualty (at least once Gamma spectroscopy on and one sample of recreationally important per 184 days) edible portions species. One sample of each species from Chickamauga and Watts Bar Reservoirs.
- c. Vegetatione Samples from farms producing milk but not Monthly (at least once per 31 l-131analysis and gamma (Pasturage and grass) providing a milk sample days) spectroscopy of each sample
[2s]
APPENDIXA EroosutE Pathwav and/or Number ofsamoles and Locatlonsb Seinplinr and Colleatbn Tvoe and FEduen6, of Samole' FrEouencr A!!EE
- d. Food Products l sample e.ch of principalfood poducts &own At least once per 365 days.t Gamm. scrn on edible
.t prlv.te gardens and/or farms in thc vhinity the time of harvest. The types portions ofthephnt.
of hodswillrary, Followiry is A contror s.mpre fiom srm a, food products a flstvof typkal foods whkh mty tt*
- t
-T l:-d,lInt ln th' least
. GbbaSe ind/or lettuce prvalentwlnd dlGction.
. iorn Grecn Beans Potatoes
. Tomatoes
'The samplint progrem outlined ln thts teble is that whlch wes in affect at the nd ot m17.
b Sample lo.atlons are shdn on Figure 6 through Ftgul &
'S.mples lhall be coll.cled by collectlnS en aliquot at lnteruals not excdlng 2 hou6 c Thc sampls collected at TRMS g):l.8 and 473.0 are taken from thc rew watar supily, thncfore, the upstream suface w.ter s.mpl. will be consrd.rd the contrcl sample ior drinklng wat r.
'vegetation sampllng ls epplicable only tor fafins that m.t the diterla tor mlll srmpling and when milk sampllng cannot be perform.d
[26]
Table 4 - Wstts pqy Nuclear Pawer Plont REMP Sompling Lacotions APPENDIX A lndicator (l) or Control lCl Samples Collectedb Map location Numbera 2
3 4
5 5
7 8
9 10 11 18 20 23 25 26 27 31 32 33 35 37 38 39 81 82 83 84 85 85 87 Sector NW NNE NE/Erue '
ESE N
Distance lmilesl 7.0 10.4 7.5 8.0 15.0 15.0 0.5 0.4 1.9 0.9 0.6 4.L 0.5 g.gd 4.7d 1.5d 54.9d 14.9d 2.4d 24.0d Onsite 0.5 0.5 0.3 0.3 L.75 18.6 AP, CF, S, AM AP, CF, S AP, CF, S AP, CF, S, AM AP, CF, S, AM AP, CF, S, AM AP, CF, S, AM AP, CF, S, AM AP, CF, S, AM AP, CF, S, AM W
M W
F F
PS W
W W
W M
M Station PM-2 PM-3 PM-4 PM-5 RM-2 RM-3 LM-1 LM-2 LM-3 LM-4 Well #1 Farm N Well #5 TRM 517.9 TRM 523.1 TRM 529.3 TRM 473.0 (C. F. lndustries)
TRM 513.0 TRM 530.2 TRM 503.8 (Dayton)
TRM 522.9-527.9 (downstream of WBN)
TRM 471-530 (Chickamauga Lake)
TRM 530-502 (Watts Bar Reservoir)
Yard Pond Well A Well B Well C Well F Farm HH Farm BB c
I I
c I
ssE/s/ssw SSE SSE ESE SE SSW SW
'See Figure 5 through Figure 8 b Sample Codes:
AM = Atmospheric moisture AP = Air particulate filter p = Fish ffi = Milk SS=
SW=
\\/[=
PW=
PS=
S-Public water Pond sediment Soil Shoreline sediment Surface water Well water
'Station located on the boundary between these two sectors.
d Distance from the plant discharge at Tennessee River Mile (TRM) SZI.B
'The surface water sample is also used as a control for public water.
l27l
APPENDIX A Toble 5 - wotts Bar Nucleor Power Plont Environmentol Dosimeter Locations Map Location Numbera 2
3 4
5 6
7 10 11 L2 L4 40 4L 42 43 44 45 46 47 48 49 50 51 52 54 55 56 57 58 59 60 62 53 64 65 55 67 58 59 70 7L 72 73 74 75 76 77 78 79 Station NW-3 NNE-3 ENE-3 s-3 SW-3 NNW-4 NNE-lA SE-1A SSW.2 w-2 N-1 N-2 NNE.1 NNE.2 NE-1 N E-2 NE-3 EN E-1 EN E-2 E-1 E-2 ESE-1 ESE-2 sE-2 SSE-1A SSE-2 s-1 s-2 ssw-1 SSW.3 SW-1 sw-2 WSW-1 WSW-2 w-1 WNW-1 WNW.2 NW-1 NW.2 NNW-1 NNW-2 NNW-3 ENE-2A SE-2A S-2A W-2A NW.2A ssE-1 Sector NW NNE NE/ENE s
N N
NNE NNE NE NE NE ENE ENE E
WNW WNW NW NW NNW NNW NNW ENE SE S
W NW SE Distance lmilesl 7,0 10.4 7,6 7.8 15.0 15.0 1.9 0.9 1.3 4,9 L.2 4.7 L.2 4.L 0.9 2.9 6.1 0.7 5.8 1.3 5.0 L.2 4.4 5.3 0.5 5.8 o.7 4.9 0.8 5.0 0.8 s.3 0.9 3.9 0.9 0.9 4.9 1.1 4.7 1.0 4.5 7.0 3.5 3.1 2.0 3.2 3.0 0.5 Onsite or OffsiteF off off off off off off On On On off On off On off On off off On off On off On off off On off On off On off On off On off On
.On off On off On off off off off off off off On
'See Figure 6 through Figure 8 l28I
APPENDIX A b Dosimeters designated "onsite" are located 2 miles or less from the plan! "offsite" are located more than 2 miles Figure 6 - Rodiologicol Environmentol Sampling Locotions Within 1 Mile of the Ptont WNW 28t "25 78,7S 258.75 to t.?5 wsw 19 1.25 S
168.7S
$crb 326.25 123.7S SE r 46.?5 16z \\
\\ \\}*ro-/
,/:'i WATTS BAR NUCLEAR PLANT
\\ii./
ii lN./
.irl1
- t#
Iea /
12sI
APPENDIX A Figure 7 - Rodiologicol Environmentol Sompling Locations from 7 to 5 Miles from the Plont I
130I WATTS BAR NUCLEAR PLANTi
APPENDIX A Figure 8 - Rodiologicol Environmentol Sompling Locotions Greoter Than 5 Miles from the Plant 281.25 78.75 258.75 t0 15 Miles 11.25 326.25 33.75 56.25 LE
[31]
APPENDIX B PROGRAM MODIFICATIONS
[32]
APPENDIX B Radiological Environmental Monitoring Program Modifications In June 20L7, a GEL Laboratories LLC began performing all radioanalytical services in support of the Watts Bar REMP, replacing WAs Western Areal Radiological Laboratory (WARL) based in Muscle Shoals, AL.
ln2OL7, there were no modification to the Radiological Environmental Monitoring Program sampling locations, analysis types or frequency.
t33I
APPENDIX C PROGRAM DEVIATIONS
[341
APPENDIX C Media Location Date CR Issue Direct Radiation Station #7 r2854L9 while performing 0-oDt-ggg-02 euarterly Direct Radiation TLD Collection, the TLDs at Deploy #7 Station WB-NNW-2 could not be located. This area had recently been disturbed by Volunteer Electric while installing a new power pole. A search of the area was performed and nothing was found.
New TLDs were placed in the field.
1308950 REMP air monitoring station in 310G pM-2, Spring City is a missed particulate/charcoal filter sample for week 24. Volume thru unit was 119.1 which is less than the required volume of 250 cubic meters. Technician noted pump flow will not maintain proper flow and unit was replaced with upgraded unit with carbon vane pump. Unit is now operating properly and maintaining flow.
Known issue with units in field and are currently being replaced with new units.
arou nd 6lIL/L7 to 6/LglI7.
L254L82 while performing 0-oDt-9gg-05 REMP, r found the station 3IO7 PM-3 Cedine Bible Camp air sampler had failed. This is a missed sample. Please refer to CR1252263 (not a missed sample) for the same sampler issue from the previous week. Troubleshooting has found that when there is a power failure, the sampler does not restart as it is designed to do. Sampler will be repaired or a spare sampler will be installed in its place, when available.
L267054 while performing O-oDt-ggg-0s REMP, r found the air sampler at station 3107 Cedine Bible Camp had failed to obtain the minimum required sample volume. This is a missed sample. The sample motor runs at a slow speed and at times will accelerate only to drop back to slow. The software shows no sample being obtained. A volume of 101.9 rn3 was obtained before failure and a minimum of 250 m3 is required.
I I
[3s]
4lL$l20L7 Air Filter and Charcoal Cartridge 6lLLlzOr7 Ll2sl2OL7 2l2Sl2OL7 PM-2 3106 PM-3 3ro7 PM-3 3LO7
APPENDIX C Media Location Date CR lssue Atmospheric Moisture PM-3 3LO7 PM-5 3109 PM-5 3109 PM-5 3109 LM-4 3204 3105 320s 6lLel2OL7 612612Or7 130895s 8lLOl2OL7 L337785 LlLel2OrT L252259 3/27120L7 L277588 WBN is in processing of swapping out faulty pumps in the REMP air monitoring stations.
The pump failures of two units resulted in missed samples. Vendor has provided motor swaps which were being performed every two weeks for swapping. These were one of the last few to get replaced.
While performing 0-OD!-999-05 REMP, I found that the air sampler at station 3109 PM-s, Decatur was not operating correctly.
Even though the motor was running no sample was being obtained. I could not find the source of the problem. The sampler was removed from the field and a spare put in its place. lt will be sent to F&J for repair.This is a missed sample While performing 0-ODl-999-05 REMP, the air sampler at station 3109 PM-5 Decatur TN had failed to obtain the minimum sample required. A minimum of 250 m3 needs to be sampled, the sampler was running but had drawn only 83.9 m3. This is a missed sample.
Filters were changed and sent to WARL.
REMP air monitoring station in 3109 PM-s, Decatur is a missed particulate/charcoal filter sample. No volume obtained thru unit.
Unit was powered on but motor was not operating. Unit was removed and shipped 6119117 tor replacement with upgraded unit with carbon vane pump. Known issue with units in field and are currently being replaced with new units.
WBN is in processing of swapping out faulty pumps in the REMP air monitoring stations.
The pump failures of two units resulted in missed samples. Vendor has provided motor swaps which were being performed every two weeks for swapping. These were one of the last few to get replaced.
Missed sample due to not enough moisture from the samples to analyze.
Missed sample due to not enough moisture from the samples to analyze.
8/LslzOL7 L337785 LzlLslzOrT LOl24l2lr7 t36I
APPENDIX C Media Location Date CR Issue MiIK 3119 Q3 3119 7lr7l2ur7 332L 617120L7 332L 8l2el2gL7 and LzlLelzOLT Well (Ground) 3L21 Well 9l5l2OL7 Water
- 1 Surface Water 3L34 8lLSlzOI7 Missing Sr-89 and Sr-90 analysis. Not performed by laboratory.
Missing milk sample. No analysis performed by laboratory Missing milk sample. No analysis performed by laboratory.
Sr-89 analysis was performed, but analysis resulted in an MDC above the nominal LLD of 3.5 pCi/l. Analysis did not result in any positive indication of Sr-89.
Water bottle received by GEL was broken and empty. No gamma scan, gross beta or Tritium result.
Water bottle received by GEL was broken and empty. No gamma scan or Tritium resu lt.
1371
APPENDIX D ANALYTICAL PROCEDURES
[38]
APPENDIX D Analvtical Procedures Analyses of environmental samples are performed by GEL Laboratories, LLC in Charlestor?, SC. Analysis procedures are based on accepted methods. A summary of the analysis techniques and methodology follows.
The gross beta measurements are made with an automatic low background counting system. Normal counting times are 50 minutes. Water samples are prepared by evaporating 400 miltititer (mL) of samples to near dryness, transferring to a stainless steel planche! and completing the evaporation process. Air particulate filters are counted directly in a shallow planchet.
The specific analysis of l-131 in milk is performed by first isolating and purifying the iodine by radiochemicat separation and then counting the final precipitate on a beta-gamma coincidence counting system. The normal count time is 480 minutes. When the l-131 counted in a gamma spectroscopy utilizing high resolution Hp-Ge detectors.
After a radiochemical separation, milk samples anatyzed for Sr-89, 90 are counted on a low background beta counting system. The sample is counted a second time after a minimum ingrowth period of six days.
From the two counts, the Sr-89 and Sr-90 concentrations can be determined.
Water samples are analyzed for tritium content by first distilling a portion of the sample and then counting by liquid scintittation. A commercially availabte scintitlation cocktail is used.
Gamma analyses are performed in various counting geometries depending on the sample type and volume. Allgamma counts are obtained with germanium type detectors interfaced with a high resolution Samma spectroscopy system.
The charcoalcartridges used to sample gaseous radioiodine are analyzed by gamma spectroscopy using a high resolution gamma spectroscopy system with germanium detectors.
Atmospheric moisture samples are coltected on sitica gel from a metered air ftow. 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 cockail.
The necessary efficiency values, weight-efficiency curves, and geometry tables are established and maintained on each detector and counting system. A series of daily and periodic quality control check are performed to monitor counting instrumentation. System logbook and control charts are used to document the results of the quality contro! check.
[3s]
APPENDIX E LOWER LIMITS OF DETECTION
[40]
APPENDIX E Lower Limits of Detection A number of factors influence the Lower Limit of Detection (LLD)for a specific analysis method, including sample size, count time, counting efficiency, chemical processes, radioactive decay factors, and interfering isotopes encountered in the sample. The most probable values for these factors have been evaluated for the various analyses performed in the environmental monitoring program. The nominal LLDs are calculated from these values, in accordance with the methodology prescribed in the ODCM. The current nominal LLD values achieved by the radioanalytical lab are listed in Table 7 and Table 8. For comparison, the maximum values for the lower limits of detection specified in the ODCM are given in Table 9.
Toble 6 - Comporison of Program Lower Limits of Detection with the Regulatory Limits for Moximum Annuol Averaqe Effluent Concentration Released to lJnrestricted Areas ond Reporting Levels Concentrations in Water (pCi'/Liter)
Concentrations in Air (pCi 'm3)
Effluent Analvsis Concentrationb H-3 1,000,000 Cr-51 500,000 Mn-54 30,000 Fe-59 10,000 Co-58 20,000 Co-50 3,000 Zn-65 5,000 Sr-89 8,000 Sr-90 500 N b-95 30,000 Zr-95 20,000 Ru-103 30,000 Ru-105 3,000 l-131 1,000 Cs-134 900 Cs-137 1,000 Ce-L44 3,000 Ba-L4O 8,000 La-140 9,000 Lower Reporting Limit of Effluent Level' d Detectione Concentration 20,000 270 100,000 45 30,000 1000 5
1,000 400 10 500 1000 5
1,000 300 s
s0 300 10 400 1,000 5
400 5
2,000 400 10 400 s
900
- o3 o;
30 5
200 50 s
200 30 40 200 25 2,000 200 10 2,000 Lower Reporting Limit of Levcl ry*
0.02 0.005 0.005 0.005 0.005 0.005 0.0005 0.005 0.005 0.02 0.9 0.03 10 0.005 20 0.005 0.0L 0.015 0.01
" 1 pCi = 3.7 x10-2 Bq b Source: Table 2 of Appendix B to 10 CFR 2O.1OO1-2O.240L
" For those reporting levels and lower limits of detection that are blan( no value is given in the reference d Source: WBN Offsite Dose Calculation Manual, Table 2.3-2
" Source: Table 7 and Table 8 of this report I
I I
[41]
APPENDIX I Table 7 - Nominal LLD Volues - Radiochemical Airborne Particulate or Gases (PCi 3l 0.002 3.0 Water (pCi 'l 1.9 270 0.4 0.4 3.5 2.O Water Wet Airborne Charcoal and Vesetation Analvsis Gross beta H-3 I-131 Sr-89 Sr-90 Analvsis Ce-141 Ce-L44 Cr-S1 t-131 Ru-103 Ru-106 Cs-134 Cs-137 Zr-95 Nb-gs Co-58 Mn-54 Zn-55 Co-60 K-40 Ba-140 La-140 Fe-59 Be-7 Pb-2L2 Pb-2L4 Bi-2r4 Ba-2L2 Tl-208 Ra-224 Ra-226 Pa rticu late (pCi 3l 0.005 0.01 0.02 0.005 0.005 0.02 0.005 0.005 0.005 0.005 0.005 0.005 0.005 0.005 0.04 0.015 0.01 0.005 0.02 0.005 0.005 0.005 0.02 0.002 Filter (pCi 3l 0.02 o.o7 0.15 0.03 0.02 o.L2 0.02 0.02 0.03 0.02 0.02 0.02 0.03 0.02 0.30 o.o7 0.04 0.04 0.15 0.03 0.07 0.05 0.20 0.02 Milk (oCi /L) 10 30 45 10 5
40 5
5 10 5
5 5
10 5
100 25 10 10 45 15 20 20 50 10 (PCi --
wetl 35 115 200 50 25 190 30 25 45 30 20 20 45 20 400 130 50 40 200 40 80 55 2s0 30 l--
t-_
I l42l Sediment and Soil (pCi tu) 0.10 0.20 0.35 0.25 0.03 0.20 0.03 0.03 0.05 0.04 0.03 0.03 0.05 0.03 o.75 0.30 0.20 0.05 0.25 0.10 0.15 0.15 0.45 0.05 0.75 0.15 Milk lpglltl Wet Vesetation ry 6.0 Sediment and Soilry 1.6 0.4 Toble 8 - Nominal LLD Values - Gamma Anolysis Fish Food Products (PCi/kg. (PCi '-.
wet) wet) o.o7 20 0.15 60 0.30 95 0.20 20 0.03 25 0.15 90 0.03 10 0.03 10 0.05 45 0.25 10 0.03 10 0.03 10 0.05 45 0.03 10 0.40 250 0.30 50 0.20 25 0.08 25 0.25 90 0.04 40 0.10 80 0.10 40 0.25 130 0.03 30
Analvsis Ac-228 Pa-234m Analvsis Gross beta H-3 Mn-54 Fe-59 Co-58, 50 Zn-65 Zr-95 Nb-gs r-131 Cs-134 Cs-137 Ba-140 La-140 Airborne Particulate (pCi 3l 0.01 Water Charcoal and Filter Milk (pCi 3l (pCi " I 0.07 20 800 Wet Veeetation (pCi/ke.
wet) 70 Sediment and Soil
'u- (pCi/ke.
drr) 0.25 4.0 APPENDIX E Food Products (pCi/ks.
wet) 50 Fish (pCi/ke.
wetl 0.10 Toble 9 - Maximum Values for Lower Limits of Detection (LLD)
Water (pCi/L) 4 2000.
15 30 15 30 30 15 1u 15 18 60 15 Airborne Particulate or Gases (pCi 3l 0.01 o.o, 0.05 0.05 Fish (pCi ' -.
we!)
130 260 130 260 150 Food Products ry Sediment ry 180 Milk (Ei/t) 15 18 60 15 50 60 80 Notes
- a. lf no drinking water pathway exists, a value of 3000 pCi/L may be used
- b. lf no drinking water pathway exists, a value of 15 pCi/L may be used.
[43]
APPENDIX F QUALITY ASSURANCE / QUALIW CONTROL PROGRAM 1441
APPENDIX F Qualitv Assurance / QualiW Control Prosram A quality assurance program is employed by the laboratory to ensure that the environ'mental monitoring data are reliable. This program includes the use of written, approved procedures in performing the work, provisions for staff training and certification, internal self-assessments of program performance, audits by various external organizations, and a laboratory quality control program The quality control program employed by the radioanalytical laboratory is designed to ensure that the sampling and analysis process is working as lntended. The program includes equipment checks and the analysis of quality control samples, along with routine field samples. lnstrument quality control check include background count rate and counts reproducibility. ln addition to these two general check, other quality control check are performed on the variety of detectors used in the laboratory. The exact nature of these checla depends on the type of device and the method it uses to detect radiation or store the information obtained.
Quality controt samples of a variety of types are used by the laboratory to verify the performance of different portions of the analytical process. These quality controlsamples include blanks, field duplicates, process duplicates, matrix spikes, laboratory controlsamples, and independent cross-check.
BIank are samples which contain no measurable radioactivity or no activity of the type being measured.
Such samples are analyzed to determine whether there is any contamination or cross-contamination of equipment, reagents, processed samples, or interferences from isotopes other than the ones being measured.
Duplicate field samples are generated at random by the sample computer program which schedules the collection of the routine samples. For example, if the routine program calls for four milk samples every week, on a random basis each farm might provide an additional sample several times a year. These duplicate samples are analyzed along with other routine samples. They provide information about the variability of radioactive content in the various sample media. lf enough sample is available for a particular analysis, the laboratory staff can spiit the sample taking two individual aliquots, known as process duplicates. Duplicate samples provide information about the variability of the entire sampling and analytical process.
Matrix spikes are field samples that have been spiked with known low levels of specific target isotopes.
Recovery of the known amount allow the analyst to determine if any interferences are exhibited from the field sample's matrix.
Laboratory control samples are another type of quality control sample. A known amount of radioactivity is added to a sample medium are processed along with the other QC and field samples in the analytical batch. Laboratory control samples provide the assurance that all aspects of the process have been successfully completed within the criteria established by Standard Operating Procedure.
Another category of quality control samples are cross-checks. The laboratory procures single-blind performance evaluation samples from Eckert & Ziegler Analytics to verify the analysis of sample matrices processed at the laboratory. Samples are received on a quarterly basis. The laborato4y's Third-Party Cross-Check Program provides environmental matrices encountered in a typical nuclear utitity REMP.
Once performance ev{luation samples have been prepared in accordance with the inftructions provided by the PT provider, safnples are managed and analyzed in the same manner as enviNonmental samples.
[4s]
APPENDIX F These samples have a known amount of radioactivity added and are presented to the lab staff labeled as cross-check samples. The labor-atory does not know the true value of the amount of known adlgd to the sample. Such samples test the best -performance of the laboratory by determining if the laboratory can find the "right answer." These samples provide information about the accuracy of the measurement process. Further information is available about the variability of the process if multiple analyses are requested on the same sample. Like matrix spikes or laboratory control samples, these samples can also be spiked with low levels of activity to test detection limits. The analysis results for interna! cross-check samples met program performance goals for 2017.
The quality control data are routinely collected, examined and reported to laboratory supervisory personnel. They are checked fortrends, problem areas, or other indications that a portion of the analytical process needs correction or improvement. The end result is a measurement process that provides reliable and verifiable data and is sensitive enough to measure the presence of radioactivity far below the levels which could be harmfulto humans.
[46]
APPENDIX G LAND USE SURVEY l47l
APPENDIX G Land Use Survev A land use survey was conducted in accordance with the provisions of ODCM Control 1.3.2 to identify the location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 sguare feet producing fresh leafy vegetables in each of 15 meteorological sectors within a distance of 5 miles {8 km)from the plant.
The Iand use survey was conducted between April 1, 2OL7, and October L,2OL7, using appropriate techniques such as door-to-door survey, mail survey, telephone survey, aerial survey, or information from local agricultural authorities or other reliable sources.
There were no changes to the nearest resident or garden in2OL7. The survey of milk producing locations performed in 2Ot7 did not identify any new locations. As a result, there are no changes required to the REMP sampling or analysis program.
Toble 70 - Projected AnnualAir Suhmersion Dose to the Neorest Residence (mrem/yr)
Sector 20L6 Distance Dose (meters) (mrem lVrl 2017 Distance Dose (meters)
(mrem lyrl N
NNE NE ENE E
ESE SE ssE S
WNW NW NNW 4474 3750 3399 3072 4388 4654 1409 1645 1550 1832 8100 2422 290L L448 2065 4376 5.80E-02 1.59E-01 2.LfiE-OL 2.27E-Or 1.18E-01 1.10E-01 5.47E-OL 2.63E-01 3.19E-01 2.54f-01 2.07E-02 1.45E-01 4.01E-02 1.44E-01 6.09E-02 L.87E-02 I
[48]
4474 3750 3399 3072 4388 4654 1409 L546 1550 L832 8100 2422 290L L448 2065 4376 5.80E-02 1.69E-01 2,T4E-OL 2.27E-OL 1.18E-01 1.10E-01 5.47E-OL 2.53E-01 3.19E-01 2.54E-01 2.O7E-O2 1.45E-01 4.01E-02 1.44E-01 6.09E-02 L.87E-Oz
APPENDIX G Toble 77 - Projected Annuol lngestion Dose to Child's Bone from Home-Grown Foods (mrem/yr)
Sector 20L6 Distance Dose (meters) (mrem lVrl nr 2017 Distance Dose (meters)
(mrem/yr)
N NNE NE ENE E
ssw SW WSW W
WNW NW NNW 6295 5030 3561 3072 4656 7297 1409 LTLL 2349 2286 8100 3080 3138 2956 206s 4742 4.31E-01 L.77E+OO 2.82E+00 3.12E+00 1.49E+00 7.58E-01 7.85E+00 4.15E+00 3.60E+00 3.89E+00 3.64E-01 1.58E+00 5.38E-01 6.L7 E-01 9.38E-01 2.63E-01 6295 5030 3561 3072 4655 7297 1409 LTLL 2349 2285 8100 3080 3138 2956 2065 4742 4.66E-01 1.89E+00 3.09E+00 3.48E+00 1.58E+00 8.53E-01 8.58E+00 4.46E+00 3.79E+00 4.08E+00 3.95E-01 1.72E+00 5.89E-01 6.76E-01 1.02E+00 2.88E-01 20L7 Dose (mrem lVrl x/q (s/m')
Toble 72 - Relotive Projected Annuol Dose to ReceptorThyroid from lngestion oI Milk Distance 2OL6 Dose Cows Location Sector (meters) (mrem /Vrl Farm N Farm HH ESE SSW 6706 2826 7.73E-OL 4.13E+00 8.36E-01 4.21E+00 1.35E-06 L.73E-05
[4s]
APPENDIX H DATA TABLES AND FIGURES ts0I
Map Loc.
No.
Station Number Dir.
(degreesl Distance (milesl q1 20L7 Q2 20t7 Q3 20L7 q4 2017 Annual Exposure (mrem/yrl
{mrem/qtr}
2 NW-3 317 7.0 14.8 17.8 19.5 15.9 67.9 3
NNE-3 L7 LO.4 9.2 15.0 14.9 L2.9 51.8 4
EN E-3 s5 7.6 7.4 13.3 15.4 9.1 45.2 5
s-3 185 7.8 10.9 L2.9 LO.7 8.3 42.8 6
SW.3 22s 15.0 9.2 11.8 10.1 10.9 4L.9 7
NNW-4 337 15.0 L1.9 L4.2 L4.8 L2.4 53.3 10 N N E-1A 22 1.9 12.5 15.5 15.9 L4.3 58.4 11 SE-1A 138 0.9 14.5 18.3 20.5 14.8 58.2 72 SSW-2 200 1.3 L2.6 L7.L 15.9 11.9 58.5 L4 w-2 277 4.8 8.7 L3.2 15.s 9.5 45.9 40 N-1 10 L,2 L5.5 L7.8 19.9 L5.2 58.s 4L N-2 350 4.7 L2.6 19.4 19.5 13.8 55.1 42 NNE-1 2L L.2 12.5 19.3 L7.O L5.2 54.0 43 NNE-2 20 4.L 10.4 14.6 L7.O 10.5 52.s 44 N E-1 39 0.9 12.0 L6.7 15.5 L5.7 59.9 45 N E-2 54 2.9 L4,2 15.6 16.8 13.8 50.4 46 N E-3 47 6.1 9.9 11.9 L4,6 L1.5 47.8 47 EN E-1 74 o.7 13.0 L7.4 L6.2 11.0 57.7 48 EN E-2 59 5.8 11.1 14.5 18.2 11.5 55.2 49 E-1 85 1.3 11.5 L5.4 L3.2 11.9 53.0 50 E-2 92 5.0 13.6 15.6 18.9 L2.9 61.0 51 ESE.1 109 L,2 8.9 L3.7 13.9 11.9 48.5 52 ESE.2 106 4.4 L4.7 L7.9 2L.8 L7.6 7L.9 54 SE-2 L28 5.3 10.0 13.3 L7.3 13.3 53.9 55 SSE-1A 161 0.6 10.0 14.8 L7.7 11.5 53.9 55 SSE-2 155 5.8 13.1 L7.5 15.4 L4.3 50.3 57 s-1 182 0,7 t2.o 15.3 17.7 L7.9 57.9 58 s-2 185 4.8 11.6 L4.8
- 15. s L2.4 54.3 59 SSW-1" 199 0.8 15.1 2L.2 24.2 L5.7 76.2 60 SSW.3 199 5.0 9.1 L4.L 12.6 9.1 45.0 62 SW-1 226 0.8 12.5 19.3 23.s 15.6 7 L.9 63 sw-2 220 5.3 16.6 19.8 19.5 L7.3 73.L 64 WSW-1 255 0.9 L2.O 15.5 15.5 L2.9 55.9 55 WSW-2 247 3.9 13.1 L7,8 22.O 14.8 67.7 55 w-1 270 0.9 10.0 L7.4 19.g 11.5 58.7 67 WNW-1 294 0.9 2L.5 24.O 22.s 2L.3 89.4 68 WNW-2 292 4.9 15.3 18.5 20.6 14.3 68.7 69 NW-1 320 1.1 11.5 15.8 L8.2 11.5 58.0 70 NW-2 313 4,7 14.5 L7.O 21.3 L4.3 67.O 7L NNW-1 340 1.0 11.5 L5.2 16.8 11.0 54.5 72 NNW-2 333 4.5 5.3 L7.4 20.6 L4.3 57.6 73 NNW-3 329 7.0 10.5 13.3 14.8 8.8 47.4 APPENDIX H Toble 1i - lndividuol Dosirneter Stafions of Watts Bor Nuclear Plont
[s 1]
APPENDIX H 74 ENE.2A 69 3.5 9.0 13.3 12.5 9.1 43.9 75 SE-2A L44 3.1 L2.L L7,L 2L.8 11.9 62.9 76 s-2A L77 2.0 13.6 t7.9 L7.5 13.3 62.4 77 W-2A 268 3.2 13.1 15.8 16.8 9.5 55.2 78 NW-2A 32r 3.0 10.9 15.3 18.4 11.0 55.5 79 SSE-1 L46 0.5 L2.O 16.3 L6.2 11.0 55.5
[s2]
APPENDIX H Table 14 - Weekly Airborne Particulate Gross Beta Figure 9 - Average Gross Beta in Air Filters
{fi E
H 0.10 a
3-t aa IJ Annual Average Gross Beta Activity in Air Filters Watts Bar Nuclear Plant lnitial Operefion of WBNP in January. 19go
--+- tndicator
-#-Cofird Is3]
0.a27 (408/408)
(0.oog - 0.075)
PM-3, 10.4 Mi. NNE 0.029 lszlszl (0.009 - 0.069) a,027 (104/104)
(0.009 - 0.070)
IU sa APPENDIX H Tsble 75 - Weekly Rodiaiodine t-731 Activity NOTESa. This tgble eummarlzes the weekly air iodlne-l3l caftridge data above the MDL lodln+li}l has an Sday half-lifcr. Wtth rcac&rshutdownn it k no longera radionudide attrtbutable to SONGS
- h. Ll"D is the a priorl llmtt as prcscrtbed by the ODCM.
c' The Term <LLD as used meansthat r$ults had ns detesable actr'vity abore the mlllmum detecAble.
Toblel$ - Qaarterly Composite Airbarne Psrticulate Gnmma Activlty NOIES Natural occuning radlonudldes (B.7, Pb-212, 8F214 and othenl were observed in quartedy composlte air samphs h n017.
< LLD. (0/+ng1
< LLD (0/1041
< LLD (o/zsl ts4I
APPEIilDIX H G't Table 77 - Biweekly Atmospheric Moisture Rodiooctivity 2.70 (20/155)
LM-z, 0.4 mi NNE 3.70 15126l 2.47 - 4.95 1.39 (2l51.l 0.24 - 2.54 Tsble 78 - Biweekly Milk Rodioactivitlr Milk lrrgestion
--teci/LI
< LLD (0ls3l
< LLD (0/4)
< LLD l0l4l
< LLD (sl7l
< LLD (o/Sr}
< LLD (o/2sl NOTESa. l{atural occunlng radionuclides (K"40, Pb-214 Bi-214 and othersl were observed in mllk samples tn 2017.
Iss]
APPENDIX H Table 1 Annuol Soil Rodiosctivity 108 (sl8l 70.7 - L73 LM-z,0.4 mi NNE L73 (rlLl L73-L73 Table 20
- Annual LocalCrops Rsdioactivity Cabbage lngestion (pG/el Garnma Isotopic 2
Various
< LLD (o/u
< LLD
< LLD
< LLD (o/U 0
Corn lngestion
-(pc/el Gamma lsotopic 2
Various
< LLD (o/1)
< LLD
< LLD
< LLD (OlLl 0
Green Beans Ingestion (pfi/gl Gamma lsotopic 2
Various
< LLD (0/11
< LLD
< LLD
< LLD (0/11 0
TomEiffi-lngestion (pfi/el Gamma lsotopic z
Various
< LLD (o/11
< LLD
< LLD
< LLD (oAl d
0 ls6l
APPENDIX H NOTES
- a. Natural occurring radionuclides (Pb-2!2, Bi-214 and others) were observed in surface water samples in 2017.
Toble 22 - Monthly Public Drinking Woter Rodioactivity Table 21
- Monthty Surface Water Rodioactivity NOTES
- a. Natural occurring radionuclides (Pb-212, Bi-214 and others) were observed in public drinking water samples in 2017.
Is7]
Pathway
[Measurement Unit]
Type and Number of Analysis Performed Lower Limit of Detection (LLDI All lndicator Locations Mean (Rangel Location with Highest Annual Mean fantral I amfinns Non-routine Reported Measuyements d
Name, Distance and Direction Mean (Rangel Mean (Range!
Surface Water Direct Exposure (pci/tl Gamma 3g
!sotopic Va rious
< LLD (0/2s)
< LLD
< LLD
< LLD (0/13) 0 Surface Water Direct Exposure (pci/Ll Tritium 39 2000 6e6 (7lzsl 230 - t7L0 TRM 517.9 (Washington Ferry) 9.9 miles 846 (3/721 410 - ].TLO
< LLD (0/13) 0 Pathway (Measurement Unit!
Type and Number of Analysis Performed Lower Limit of Detection (rLD)
All lndicator Locations Mean (Rangel Location with Highest Annual Mean Control Locations Mean (Range!
Non-routine Reported Measurements Name, Distance and Direction Mean (Range)
Drinking Water lngestion (pci/L)
Gross Beta 4L 4.0 2.e8 (3l2sl 1.91 - 5.01 TRM s03.8 4.0s (2113I, 2.10 - 5.01 3.08 (s/13)
L.92 - 5.31 0
Drinking Water lngestion (pci/L)
Gamma 4L lsotopic Va riou s
< LLD (01281
< LLD
< LLD
< LLD (o/13) 0 Drinking Water lngestion (pci/L)
Tritium 46 2000 so2 (11/33) 27L - 1031 TRM 473 s7r (7 lrsl 362 - 1031
< LLD (0/13) 0
APPENDIX H NOTES
- a. Natural occurring radionuclides (Pb-212, Bi-214 and others) were observed in surface water samples in 2OL7.
Table 24 - Semi-Annual Fish Radioactivity Table 23
- Monthty Well (Ground) lMater Radioactivity NOTES
- a. Natural occurring radionuclides (Pb-2L2, Bi-214 and others) were observed in surface water samples in 2Ot7,
Pathway (Measurement Unit)
Type and Number of Analysis Performed Lower Limit of Detection (LLDI All lndicator Locations Mean (Rangel Location with Highest Annual Mean Control Locations Mean (Range)
Non-routine Reported Measurements Name, Distance and Direction Mean (Range!
Ground Water lngestion (pci/L)
Gross Beta 77 4.0 2.20 (sl64l L.97 - 2.80 Well B 0.5 miles SSE 2.4o (4lr3l 2.O7 - 2.80
< LLD (o/13) 0 Ground Water Ingestion (pci/L)
Gamma 77 lsotopic Va rious (Lzl64l
< LLD
< LLD
< LLD (0/13) 0 Ground Water lngestion (pci/L)
Tritium 77 2000 4e8 (r2l54l zss - 834 Well B 0.5 miles SSE 71s (s/13) s52 - 834
< LLD (o/13) 0 Pathway (Measurement Unitl Type and Number of Analysis Performed Lower Limit of Detection (LrDl All lndicator Locations Mean (Rangel Location with Highest Annual Mean Control Locations Mean (Rangel Non-routine Reported Measurements Name, Distance and Direction Mean (Rangel Game Fish lngestion (pci/ks)
Gamma 6
lsotopic Various
< LLD (Ol4l
< LLD
< LLD
< LLD p/21 0
Cs-137 6
150 0.02 LL (214]'
0.019 - 0.023 TRM 522.8 - 527.8 0.023 (Llzl 0.023 - 0,023 0.018 (Llzl 0.018 - 0.018 0
Commercial Fish lngestion (pCi/kg)
Gamma g
lsotopic Various
< LLD (o/s)
< LLD
< LLD
< LLD (o/3) 0 Is8]
APPENDIX H Tsble 25 - Semi4nnual Shoreline Sediment Radioactivity
!{oma. Natural occurring radionuclides (Fb-ZIZ, Bi-214 and qthers) were obseryed ln curface weter samples 1n20L7.
Shoreline Sediment Direct Radiation (pci/kel
< LLD (Ol2l
< LLD l0lzl
[sel
logl SIUOd]U 9NIIVU]dO IVIN]t^INOUIAN] IVNNNV SNOIASUd OI-VIVUU] I XICN]ddV
APPENDIX I Errata to Previous AREORS There are no identified errors in previous AREORs. n "r
[51]