ML20029D209
| ML20029D209 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 12/31/1993 |
| From: | Tremblay L VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| BVY-94-48, NUDOCS 9405040196 | |
| Download: ML20029D209 (99) | |
Text
{{#Wiki_filter:-. .7 w NERMONTYANKE.c E- - MNUCLEAR POWER' CORPORATION
- e. K Ferry Road, Brattleboro, VT 05301-7002 ENGINEERING OFFICE 530 MAIN STREET
, 00L10N. M A 01749 tLOS.i 7794711 April 29,1994 BVY 94 - 48 United States Nuclear Regulatory Commission
' ATTN: Document Control Desk ~
Washington, DC 20555 Refemnces: a. License No. DPR-28 (Docket No. 50-271)
Subject:
Vermont Yankee Annual Radiological Environmental Surveillance Repon Enclosed please find one copy of the Annual Radiological Environmental Surveillance Report for Vermont Yankee Nuclear Power Station, submitted in accordance with Technical Specification 6.7.C.3. This repon contains a summary and analysis of the radiological environmental data collected for the calender year 1993. Should you have any questions agarding this submittal, please contact this office. Sincerely, $ VERMONT YANKEE NUCLEAR POWER CORPORATION
,p c N'
T(COON ( ,d d X g d 0 4h 1 Leonard A. Tremblay, Jr., P.E. \ 4 Senior Licensing Engineer cc: USNRC Region I Administrator 1USNRC Resident Inspector- VYNPS USNRC Project Manager- VYNPS 03C048
-9405040196 931231
[ I I l I PDR ADOCK 05000271 1 i
.R PDR k
cl- ANNUAL
&( ) RADIOLOGICAL
;O- ENVIRONMENTAL SURVEILLANCE ,
REPORT l l c e Vermont Yankee Nuclear Power Corporation 1993 , Vermont Yankee Nuclear Power Station Vernon, Vermont
r x VERMONT YANKEE NUCLEAR POVER STATION ANNUAL RADIOLOGICAL ENVIRONMENTAL SURV",ILLANCE REPORT January - December 1993 April 1994 T B 4
.i Prepared by: q Yankee Atomic Electric Company '
Environmental Engineering Department
, 580 Main Street Bolton, Massachusetts 01740 i
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l TABLE OF CONTENTS faf4 ! TABLE OF CONTENTS ...... ...................................... ii LI S T O F TAB LES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . iii LIST OF FIGURES ..... ......................................... iv
- 1. INTRODUCTION ............................ ............... .... 1 .i l
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- 2. NATURALLY OCCURRING AND MAN-MADE BACKGROUND RADIOACTIVITY ..... 3
- 3. GENERAL PLANT AND SITE INFORMATION ............ . ............ 6
- 4. PROGRAM DESIGN ........ ....................................... 7
- 5. RADIOLOGICAL DATA
SUMMARY
TABLES ...... .. ............... .. 28 l
- 6. ANALYSIS OF ENVIRONMENTAL RESULTS .. ........................... 44
- 7. QUALITY ASSURANCE PROGRAM ......... . .... .. .. . .... . ... 79
- 8. LAND USE CENSUS ........................................... .. 88
]
- 9.
SUMMARY
........ ........................... ................. 90
- 10. REFERENCES .................... . ................... .. ..... 91 !
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LIST OF TABLES i Table Title Pane 4.1 Radiological Environmental Monitoring Program ........... it. 4.2 Radiological Environmental Monitoring Locations (Non-TLD) ................ .................. 16 4.3 Radiological Environmental Monitoring Locations (TLD) ................ ................. .... 18 4.4 Environmental Lower Limit of Detection (LLD) Sensitivity Requirements ......................... ... 20 4.5 Reporting Levels for Radioactivity Concentrations in Environmental Samples .............................. 21 5.1 Environmental Radiological Program Summary . .. .. ...... 30 5.2 Environmental TLD Data Summary ......................... 41 5.3 Environmental TLD Measurements ....... ........... ...... 42 7.1 Summary of Prbcess Control Analysis Results ............. 83 7.2 EPA Intercomparison Analysis Results .................... 84 7.3 Summary of EPA Intercomparison Results .................. 86 7.4 Summary of Blind Duplicate Samples Submitted . .......... 87 8.1 Land Use census Locations ............................... 88
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LIST OF FIGURES Firure Title Eagg 4.1 Radiological Environmental Sampling Locations in Close Proximity to Plant .............................. 22 4.2 Radiological Environmental Sampling Locations Within 5 Kilometers of Plant ............................. 23 4.3 Radiological Environmental Sampling Locations Greater than 5 Kilometers from Plant ..................... 24 4.4 TLD Monitoring Locations in Close Proximity to Plant ................................................. 25 4.5 TLD Monitoring Locations Within 5 Kilometers of Plant ............................................... 26 4.6 TLD Monitoring Locations Greater than 5 Kilometers from Plant .............................................. 27 6.1 Gross-Beta Measurements on Air Particulate Filters ...... 53 (Quarterly Averages - Indicator vs. Control) 6.2 Gross-Beta Measurements on Air Particulate Filters ....., 54 (AP-ll vs. AP-21 Control) , 6.3 Gross-Beta Measurements on Air Particulate Filters ...... 55 (AP-12 vs. AP-21 Control) 6.4 Gross-Beta Measurements on Air Particulate Filters ...... 56 (AP-13 vs. AP-21 Control) 6.5 Gross-Beta Measurements on Air Particulate Filters ...... 57 (AP-14 vs. AP-21 Control) 6.6 Gross-Beta Measurements on Air Particulate Filters ...... 58 (AP-15 vs. AP-21 Control) l l
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1 LIST OF FIGURES (continued) Firure Title Page 6.7 Gross Beta Measurements on River Water ................... 59 6.8 Gross Beta Measurements on Ground Water ................. 60 6.9 Gesium-137 in Milk ...................................... 61 4 1 6.10 Strontium-90 in Milk .................................... 62 ) l 6.11 Cesium-137 in Fish ......... ........... ...... .. ...... 63 6.12 Exposure Rate at Inner Ring, Outer Ring and Control TLDs .............................. ... ... 64 6.13 Exposure Rate at Indicator TLDs, DR 01-03 ............... 65 6.14 Exposure Rate at Indicator TLDs, DR 04, 06, 50 .......... 66 6.15 Exposure Rate at Site Boundary TLDs, DR 07-08, 41-42 .... 67 L.16 Exposure Rate at Site Boundary TLDs , DR 43-46 . . . . . . . ... 68 6.17 Exposure Rate at Site Boundary TLDs, DR 47-49, 51 ....... 69 6.18 Exposure Rate at Inner Ring TLDs, DR 09-15 (odd) ........ 70 1 6.19 Exposure Rate at Inner Ring TLDs, DR 17-23 (odd) ........ 71
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6.20 Exposure Rate at Inner Ring TLDs, DR 25-31 (odd) ........ 72 l 6.21 Exposure Rate at Inner Ring TLDs, DR 33-39 (odd) ..... .. 73 6.22 Exposure Rate at Outer Ring TLDs, DR 10-16 (even) ....... 74 6.23 'xposure Rate at Outer Ring TLDs, DR 18-24 (even)........ 75 1 6.24 Exposure Rate at Outer Ring TLDs, DR 26-32 (even)........ 76
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i I LIST OF FIGURES (continued) i Firure Title Ep_ge 6.25 Exposure Rate at Outer Ring TLDs, DR 34-40 (even)........ 77 6.26 Exposure Rate at Control TLD, DR-05 ..................... 78 i b n J i I
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- 1. 200TRODUCTION This report summarizes the findings of the Radiological Environmental Monitoring Program (REMP) conduc':ed by Vermont Yankee Nuclear Power Corporation in the vicinity of t'ae Vermont Yankee Nuclear Power Station in Vernon, Vermont during the calendar year 1993. It is submitted annually in compliance with plant Technical Specification 6.7.C.3.
The remainder of this report is organized as follows: Section 2: Provides an introductory explanation to the background radioactivity and radiation that is detected in the Vermont Yankee environs. Section 3: Provides a brief description of the Vermont Yankee Nuclear Power Station site and its environs. Section 4: Provides a description of the overall REMP program design. Included is a summary of the Radiological Effluent Technical Specification Requirements for REMP sampling, tables listing all locations sampled or monitored (by TLD) in 1993 with compass sectors and distances from the plant, and maps showing the location of each of the sampling and TLD monitoring locations. Tables listing Lower Limit of Detection requirements and Reporting Levels are also included. Section 5: Consists of the summarized data as required by VYNPS Technical Specifications. The tables are in the format specified by the NRC Radiological Assessment Branch Technical Position on Environmental Monitoring (Reference 1). Also included is a summary of the environmental TLD measurements for 1993. Section 6: Provides the results of the 1993 monitoring program The performance of the program in meeting regulatory requirements as given in the Technical Specifications is discussed, and the data acquired during the year are analyzed. Section 7: Provides an overview of the Quality Assurance programs used at the Yankee Atomic Environmental Laboratory. As required by Technical Specifications, the results of the EPA Intercomparison Program are given. Section 8: Summarizes the requirements and the results of the 1993 Land Use Census. Section 9: Gives an overall summary of.the results of the 1993 ' Radiological Environmental-Monitoring Program. ] I i 1 e 2-
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- 2. Naturally Occurrina and Man-Made Backcround Radioactivity Radiation or radioactivity potentially detected in the Vermont Yankee environment can be grouped into three categories. The first is " naturally-occurring" radiation and radioactivity. The second is " man-made" radioactivity from sources other than the Vermont Yankee plant. The third potential source of radioactivity is due to emissions from the Vermont Yankee plant. For the purposes of the Vermont Yankee REMP, the first two categories are classified as " background" radiation, and are the subject of discussion in this section of the report. The third category is the one that the REMP is designed to detect and evaluate.
2.1 Naturally Occurrine Background Radioactivity Natural radiation and radioactivity in the environment, which provide the major source of human radiation exposure, may be subdivided into three separate sub-categories: " primordial radioactivity", "cosmogenic radioactivity" and " cosmic radiation". " Primordial radioactivity" is made up of those radionuclides that were created with the universe and that have a sufficiently long half-life to be still present on the earth. Included in this category are the radionuclides that these elements have decayed into. A few of the more important radionuclides in this category are Uranium 238 (U-238), Thorium-228 (Th-228), Rubidium-87 (Rb-87),, Potassium-40 (K-40), Radium-226 (Ra-226), and Radon-222 (Rn-222). Uranium-238 and Thorium-228 are readily detected in soil and rock, whether through direct field measurements or through laboratory analysis of samples. Radium-226 in the earth can find its way from the soil into ground water, and is often detectable there. Radon-222 is one of the components of natural background in the air we breath, and its daughter products are detectable on air sampling filters. Potassium-40 comprises about 0.01 percent of all natural potassium in the earth, and is consequently detectable in most biological substances, including the human body. There are many more primordial radionuclides found in the environment in addition to the major ones discussed above (Reference 2). The second sub-category of naturally-occurring radiation and radioactivity is "cosmorenic radioactivity". This is produced through the nuclear interaction of high energy cosmic radiation with elements in the earth's atmosphere, and to a much lesser degree in the earth's crust. These radioactive elements are then incorporated into the entire geosphere and atmosphere, including the earth's soil, surface rock, biosphere, sediments, ocean floors, polar ice and atmosphere. The major radionuclides in this e category are Carbon-14 (C-14), Hydrogen-3 (H-3 or Tritium), Sodium-22 (Na-22), and Beryllium 7 (Be-7). Beryllium-7 is the one most readily detected, and is found on air sampling filters and occasionally in biological media (Reference 2). The third aub-category of naturally-occurring radiation and radioactivity is " cosmic radiation". This consists of high energy atomic and sub-atomic , particles of extra-terrestrial origin and the secondary particles and radiation that are produced through their interaction in the earth's atmosphere. The primary radiation comes mostly from outside of our solar system, and to a lesser degree from the sun. We are protected from most of this radiation by the earth's atmosphere, which absorbs the radiation. ' Consequently, one can see that with increasing elevation one would be exposed to more cosmic radiation as a direct result of a thinner layer of , air for protection. This " direct radiation" is detected in the field with gamma spectroscopy equipment, high pressure ion chambers and thermoluminescent dosimeters (TLDs). 2.2 Man-Made Backcround Radioactivity The second source of " background" radioactivity in the Vermont Yankee environment is from " man-made" sources not related to the power plant. The most recent contributor to this category was the fallout from the Chernobyl accident in April of 1986, which was detected in the Vermont Yankea environment and other parts of the world. A much greater contribut c to this category, however, has been fallout from atmospheric nuclear w spons tests. Tests were conducted from 1945 through 1980 by the United States, j the Soviet Union, the United Kingdom, China and France, with the large majority of testing occurring during the periods 1954-1958 and 1961-1962. , (A test ban treaty was signed in 1963 by the United States, Soviet Union I and United Kingdom, but not by France and China.) The most recent test, j conducted by the People's Republic of China, occurred in October of 1980. l Much of the fallout detected today is due to this explosion and the last ! large scale one, done in November of 1976 (Reference 3). l
)
The radioactivity produced by these detonations was deposited worldwide. The amount of fallout deposited in any given area is dependent on many factors, such as the explosive yield of the device, the latitude and altitude of the detonation, the season in which it occurred, and the timing of subsequent rainfall wnich vashes fallout from the troposphere ) (Reference 4). Most of this fallout has decayed into stable elements, i but the residual radioactivity is still readily detectable in environmental
samples worldwide. The two predominant radionuclides are Cesium-137 (Cs-137) and Strontium-90 (Sr-90). They are found in soil and in j vegetation, and since cows and goats graze large areas of vegetation, these I radionuclides are also readily detected in milk. j Other potential " man-made" sources of environmental " background" radioactivity include other nuclear power plants, coal-fired power plants, national defense installations, hospitals, research laboratories and industry. These collectively are insignificant on a Tobal scale when compared to the sources discussed above (natural and fallout). l j 1
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- 3. GENERAL PLANT AND SITE INFORMATION The Vermont Yankee Nuclear Power Station is located in the town of Vernon, Vermont in Windham County. The 130-acre site is on the west shore of the Connecticut River, immediately upstream of the Vernon Hydroelectric Station. The land is bounded on the north, south and west by privately-owned land, and on the east by the Connecticut River. The surrounding area is generally rural and lightly populated, and the topography is flat or gently rolling.
Construction of the single 540 megawatt BVR (Boiling Water Reactor) plant began in 1967. The pre-operational Radiological Environmental Monitorin6 Program, designed to measure environmental radiation and radioactivity levels in the area prior to station operation, began in 1970. Commercial operation began on November 30, 1972. l l 1 l I l l
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- 4. PROGF004 DESIGl[
The Radiological Environmental Monitoring Program (REMP) for the Vermont j Yankee Nuclear Power Station (VYNPS) was designed with specific objectives l i in mind. These are:
- To provide an early indication of the appearance or accumulation of any radioactive material in the environment caused by the operation of the station.
- To provide assurance to regulatory agencies and the public that the station's environmental impact is known and within anticipated limits.
- To verify the adequacy and proper functioning of station effluent controls and monitoring systems.
- To provide standby monitoring capability for rapid assessment of risk to the general public in the event of unanticipated or accidental releases of radioactive material.
The program was initiated in 1970, approximately two years before the plant began commercial operation in 1972. It has been in operation cur.tinuously since that time, with improvements made periodically over those years. The current program is designed to meet the intent of NRC Regulatory Guide 4.1, Programs for Monitorine Radioactivity in the Environs of Nuclear Power l Plants, NRC Regulatory Guide 4.8, Environmental Technical Specifications for Nuclear Power Plants, the NRC Branch Technical Position of November 1979 entitled An Acceptable Radiological Environmental Monitorine Procram, 1 as well as NRC NUREG-0473, Radiolorical Effluent Technical Specifications for BWR's. The environmental TLD program has been designed and tested l around NRC Regulatory Guide 4.13, Performance. Testing and Procedural Specifications for Thermoluminescence Dosimetry: Environmental Aeolications. The quality assurance program is designed around the guidance given in NRC Regulatory Guide 4.15, Ouality Assurance for R Radiolocical Monitorine Pronrams (Normal Operations) - Effluent Streams and the Environment. The minimal sampling requirements of the REMP are given in Technical ; Specification 3.9.C, which is summarized in Table 4.1 of this report. The identification of the required sampling locations is given in the Offsite Dose Calculation Manual (ODCM), Chapter 6 The complete list of locations 7
i i i used during 1993 is given in Tables 4.2 and 4.3 of this report. These sampling and monitoring locations are shown graphically on the maps in Figures 4.1 through 4.6. The Vermont Yankee Chemistry Department conducts the radiological l environmental monitoring program. They collect all airborne, terrestrial and ground water samples, and contract with Aquatec, Inc. to collect all fish, river water and sediment samples. All TLD badges are posted and retrieved by the Vermont Yankee Chemistry Department, and are read out by the Yankee Atomic Environmental Laboratory. 4.1 Monitorine Zones The REMP is designed to allow comparison of levels of radioactivity in samples from the area possibly influenced by the plant to levels found in areas not influenced by the plant. Monitoring locations within the first zone are called " indicators." Those within the second zone are called " controls." The distinction between the two zones, depending on the type of sample or sample pathway, is based on one or more of several factors, such as site meteorological history, meteorological dispersion calculations, relative direction from the plant, river flow, and distance. Analysis of survey data from the two zones aids in determining if there is a significant difference between the two areas. It can also help in differentiating between radioactivity or radiation due to plant releases and that due to other fluctuations in the environment, such as atmospheric nuclear weapons test fallout or seasonal variations in the natural backgrcund. a 4.2 Pathways Monitored Four pathway categories are monitored by the REMP. They are the Airborne, Waterborne, Ingestion and Di'.ect Radiation Pathways. Each of these four categories is monitored by che collection of one or more sample media, which are listed below, and are described in more detail in this section: Airborne Pathway ) Air Particulate Sampling l Charcoal Cartridge (Radioiodine) Sampling Waterborne Pathways River Water Sampling i
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s Cround 'Jater $supling Sediment Sampling Ingestion Pathways Milk Sampling Silage Sampling Mixed Grass Sampling ,, Fish Sampling Direct Radiation Pathway TLD Monitoring J 4 0 i s i h
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l i l 4.3 Descriptions of Monitorine Procrang l 4.3.1 Air Samoling Continuous air samplers are installed at six locations. (Five'are required by VYNPS Technical Specifications.) The sampling pumps at there locations operate continuously at a flow rate of approximately one cubic foot _per minute. Airborne particulates are collected by passing air through a 47 mm glass-fiber filter. A dry gas meter is incorporated into the sampling stream to measure the total volume of air sampled in a given interval. The entire system is housed in a weatherproof structure. The filters are > collected biweekly, and to allow for the decay of radon daughter products, they are held for at least 100 hours at the' Laboratory before being ) analyzed for gross-beta radioactivity (indicated as GR-B in the data tables). The biweekly filters are composited (by location) at the Laboratory for a quarterly gamma spectroscopy analysis. If the gross-beta activity on an air particulate sample is greater than ten times the yearly mean of the control samples, Technical Specification 3.9.C requires a gamma isotopic analysis on the individual sample. Whenever the main plant stack effluent release rate of I-131 is equal to or greater than 0.1 uCi/sec, weekly air particulate is required, pursuant to Technical Specification 3.9.C. 4.3.2 Charcoal Cartridte (Radioiodine) Sampline Continuous air samplers are installed at six locations. (Five are required by Technical Specifications.) The sampling pumps at these locations i operate continuously at a flow rate of approximately one cubic foot per minute. A 60 cc TEDA impregnated charcoal cartridge is located downstream of the air particulate filter described above. A dry gas meter is incorporated into the sampling stream to measure the total volume of air sampled in a given interval. The entire system is housed in a weatherproof structure. These cartridges are collected and analyzed biweekly for I-131. Whenever the main plant stack effluent release rate of I-131 is equal to'or greater than 0.1 uCi/sec, weekly charcoal cartridge sampling is required, pursuant to Technical Specification 3.9.C. 4.3.3 River Water Samuline An automatic compositing sampler is maintained at the downstream sampling location by the Vermont Yankee Chemistry Department staff, and the pump I
l I deliverir.g river water to the sampler is maintained by Aquatec, Inc. The i sampler is controlled by a timer that collects an aliquot of river water at least every two hours. An additional grab sample is collected monthly at the upstream control Location. All river water samples are preserved with R hcl and NaHSO3 to prevunt the plate out of radionuclides on the container walls. Each sample in analyzed for gamma-emitting radionuclides. Although not required by VYNPS Technical Specifications, a gross-beta analysis is performed on each san l.le. The monthly composite or grab samples are composited again (by location) at the Laboratory for a quarterly H-3 analysis. 4.3.4 Ground Water 5.ampline Grab samples are collected quarterly from two indicator and one control location. (Only one indicator and one control is required by VYNPS Technical Specifications.) All ground water samples are preserved with hcl and NadS03 to prevent the plate out of radionuclides on the container walls. Each sr.mple was analyzed for gamma-emitting radionuclides and H-3. Although not required by VYNPS Technical Specifications, a gross-beta analysis is also performed on each sample. 4.3.5 Sedimert Samplinz Sediment grab samples are collected semiannually from two locations by Aquatec, Inc. At the downriver shoreline, station SE-ll, one grab is collected. At the North Storm Drain Outfall, station SE-12, multiple grab samples are collected. Each sample is aralyzed at the Laboratory for gamma-emitting radionuclides. 4.3.6 Milk Sampling When milk animals are identified as bein6 on pasture feed, milk samples are collected twice per month from that location. Throughout the rest of the year, and for the full year where animals are not on pasture, milk samples are collected on a monthly schedule. Three locations are chosen as a result of the cnnual Land Use Census, based on meteorological dispersion calculations. The fourth location is a control, which is located sufficiently far away from the plant to be outside any potential influence from it. Other samples are typically collected from locations of interest. Immediately after collection, each milk sample is refrigerated until delivery to the Laboratory. Each sample is analyzed for gamma-emitting radionuclides. Following a chemical separation, a separate low-level I-131 p: 2 analysis.is performed to meet the Lower Limit of Detection requirements in Lthe' Technical-Specifications. Although not required by Technical Specifications, Sr-89 and Sr-90 analyses are also performed on quarterly composited samples. 4.3.7 Silane Samoline At each milk sampling location, a silage sample is collected at the time of harvest, if available. One sample is shipped to the Laboratory without preservative, where it is analyzed for gamma-emittin5 radionuclides. Although not required by Technical Specifications, a separate silage sample is preserved with NaOH, and is then shipped to the Laboratory for a separate I-131 analysis. 4.3.8 Mixed Grass Samoline At ;.ch air sampling station, a mixed grass sample is collected quarterly, when available. Enough grass is clipped to provide the minimal sample weight needed to achieve the required Lower Limits of Detection. One sample is shipped to che Laboratory without preservatise, where it is analyzed for gamma-emitting radionuclides. Although not required by Technical Specifications, a separate grass sample is preserved with NaOH, and is then shipped to the Laboratory for a separate I-131 analysis. 4.3.9 Eish Sampline Fish samples are collected semiannually at two locations (upstream of the plant and in Vernon Pond) by Aquatec, Inc. The species typically collected are yellow perch, smallmouth bass and largemouth bass. The fish samples , are frozen and delivered to the Laboratory where the edible portions are analyzed for gamma-emitting radionuclides. 4.3.10 TLD Monitorine Direct gamma radiation exposure was continuously monitored with the use of thermoluminescent dosimeters (TLDs). Specifically, Panasonic UD-801ASl and UD-814ASl calcium sulfate dosimeters were used, with a total of five elements in place at each monitoring location. Each pair of dosimeters is sealed in a plastic bag, which is in turn housed in a plastic-screened , container. This container is attached to an object such as a fence or utility pole. A total of 40 stations are required by Technical
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Specifications. Of these, 24 must be read out quarterly, while those from the remaining 16 incident response (outer ring) stations need only be de- I
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dosed (annealed) quarterly, unless a gaseous release LCO was exceeded during the period. Although not required by Technical Specifications, the TLDs from the 16 outer ring stations are read out quarterly along with the other stations's TLDs. In addition to the TLDs required by Technical Specifications, eleven more are typically posted at or near the Site Boundary. The plant staff posts and retrieves all TLDs, while the Yankee Atomic Environmental Laboratory processes them. l 4 1 i 1 l l
TABLE 4.1 Radiological Erwirmeental Monitoring Program (as reg 21rwi by Tech. Spec. Table 3.9.3)* Collection Analysis Exposure Pathway Ntrber of Routine Analysis Analysis S Mia Collection type samte Sagting Frequency Locatiens Mode Frequency I
- 1. Direct Radiation (TLDs) 40 Continuous Quarterly Gama; Outer Ring - Each TLD de-dose only, unless gaseous release LCO was exceeded
- 2. Airborne (Particulates 5 Continuous Semimonthly Particulate Sa mte: l and Radioicdine) Gross Beta Each Sagte Carrna Isotopic Quarterly Co m osite (by location)
Radiolodine Canister: 1-131 Each Sanple
- 3. Waterborne
- a. Surface Water 2 Downstream: Monthly Ganrna Isotopic Each Sanple l Automatic Tritium (H-3) Quarterly Conposite caposite.
l Upstream: greb.
- b. Ground Water 2 Grab ouarterly Game Isotopic Each Sagle .
Tritius (M-3) Each Sanple ., i l l c. Shoreline Sediment 2 Grab Upstream: Semiennually. Game Isotopic Each Sanple l l N. Storm Drain Outf all: As specified in ODCM.
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TABLE 4.1 (continued) Radiological Erwircruerstat Neitoring Program (as regstred by Tech. Spec. Table 3.9.3)* Collection Analysis Exposure Pathway p g, Nominal Ntrber of Routine Nominal Analysis Analysis
$ FreqJency Samte Locetions Sa@ ling Cottection Type Mode Frequency
- 4. Ingestion
- a. Milk 4 Grab Monthly Gamme Isotopic Each samle (Semimonthly 1-131 Each ss@te when on pasture)
- b. Fish 2 Grab Semiannually Game isotopic on Each samle edible portions
- c. Vegetation
- Grass samle 1 at each air Grab ouarterly when Gamma Isotopic Each se @te sanpling station avellebte _
- Silage samle 1 at each milk Greb At harvest Gamma Isotopic Each se @ le sampling station
- See Technical specification Table 3.9.3 for co@ tete footnotes.
1 I 1 l TABLE 4.2. Radiological Environmental Monitoring locations (non-TLD) in 1993 Vermont Yankee Nuclear Power Station Distance From Direction Exposure Station Plant From Pathway Code Station Descrintion Zone * ( km ) **
- Plant ***
- 1. Airborne AP/CF-ll River Sta No. 3.3 I 1.9 SSE AP/CF-12 N. Hinsdale, NH I 3.6 NNW AP/CF-13 Hinsdale Substation I 3.1 E AP/CF-14 Northfield, MA I 11.3 SSE -)
AP/CF-15 Tyler Hill Road I 3.2 WNW AP/CF-21 Spofford Lake C 16.1 NNE
- 2. Waterborne
- a. Surface WR-ll River Sta. No. 3.3 I 1.9 Down-river WR-21 Rt. 9 Bridge C 12.8 Up-river
- b. Ground WG-ll Plant Well I --
On-site WC-12 Vernon Nursing Well I 2.0 SSE WG-22 Skibniowsky Well C 14.3 N
- c. Sediment SE-ll Shoreline Downriver I 0.8 SSE SE-12 North Storm Drain I 0.15 E Outfall j
- 3. Ingestion ]
- a. Milk TM-ll Miller Farm I 0.8 WNW TM-12 Dominick I 5.2 E TM-14 Brown Farm I 2.1 S !
TM-15 Gayland Farm I 4.7 WNW/NW ; TM-16 Meadowerest Farm I 4.4 WNW/NW TM-18 Blodgett Farm I 3.4 SE TM-24 County Farm C 22.5 N j l l l 16-
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l I l TABLE 4.2 l (continued) l 1 Radiological Environmental Monitoring Locations (non-TLD) in 1993 Vermont Yankee Nuclear Power Station Distance From Direction Exposure Station Plant From Pathway Code Station Description Zone * ( km ) * *
- Plant ***
3, Ingestion, (continued)
- b. Fish FH-11 Vernon Pond I -- **
FH-21 Rt. 9 Bridge C 12.8 Upriver
- c. Mixed TG-11 River Sta. No. 3.3 I 1.9 SSE Grass TG-12 N. Hinsdale, NH I 3.6 NNW ,
TG 13 Hinsdale Substation I 3.1 E TG-14 Northfield, MA I 11.3 SSE TG-15 Tyler Hill Rd. I 3.2 WNW TG-21 Spofford Lake C 16.1 NNE
- c. Silage TC-11 Miller Farm I 0.8 WNW TC-12 Dominick I 5.2 E TC-14 Brown Farm I 2.1 S TC-15 Gayland Farm I 4.7 WNW/NW TC-16 Meadowerest Farm I 4,4 WNW/NW TC-18 Blodgett Farm I 3.4 SE TC-24 County Farm C 22.5 N
- d. Soil TS-10 Vernon Nursing Home I 2.0 SSE TS-12 N. Hinsdale, NH I 3.6 NNW TS-14 Northfield, MA I 11.3 SSE T3-40 Governor Hunt House I 0.60 S
- I - Indicator Stations; C - Control Stations c* Fish samples are collected anywhere in Vernon Pond, which is adjacent to the plant (see Figure 4.1).
00* The Distance and Direction for non-TLD sampling sites are relative to the plant stack.
TABLE 4.3 Radiological Environmental Monitoring Locations (TLD) in 1993 Vermont Yankee Nuclear Power Station Distance Direction Station From Plant From fode Station Descriotion Z2ng ( km ) * *
- Plant ***
DR-1 River Sta. No. 3.3 I 1.6 SSE DR-2 N. Hinsdale, NH I 3.9 NNW DR-3 Hinsdale Substation I 3.0 E DR-4 Northfield, MA 0 11.0 SSE DR-5 Spofford Lake C 16.3 NNE DR-6 Vernon School I 0.46 WSW DR-7 Site Boundary SB 0.27 W DR-8 Site Boundary SB 0.25 SW DR-9 Inner Ring I 2.1 N DR-10 Outer Ring 0 4.6 N DR-ll Inner Ring I 2.0 NNE DR-12 Outer Ring 0 3.6 NNE DR-13 Inner Ring I 1.4 NE DR-14 Outer Ring 0 4.3 NE DR-15 Inner Ring I 1.4 ENE DR-16 Outer Ring O 2.9 ENE DR-17 Inner Ring I 1.2 E DR-18 Outer Ring 0 3.0 E DR-19 Inner Ring I 3.5 ESE DR-20 Outer Ring 0 5.3 ESE DR-21 Inner Ring I 1.8 SE DR-22 Outer Ring 0 3.2 SE DR-23 Inner Ring I 1.8 SSE DR-24 Oute'r Ring 0 3.9 SSE. DR-25 Inner Ring I 2.0 S DR-26 Outer Ring 0 3.7 S DR-27 Inner Ring I 1.0 SSW DR-28 Outer Ring 0 2.2 SSW DR-29 Inner Ring I 0.7 WSW DR-30 Outer Ring 0 2.3 SW
5 TABLE 4.3 (continued) Radiological Environmental Monitoring Locations (TLD) in 1993 Vermont Yankee Nuclear Power Station Distance Direction Station From Plant From Code Station Description Zone" ( kM *** Pl ant *** DR-31 Inner Ring I 0.8 W DR-32 Outer Ring 0 5.0 USW DR-33 Inner Ring I 0.9 WNW DR-34 Outer Ring Road O 4.9 W DR-35 Inner Ring I 1.4 WNW DR-36 Outer Ring O 4.7 WNW DR-37 Inner Ring I 3.0 NW DR-38 Outer Ring 0 7.7 NW-DR-39 Inner Ring I 3.2 NNW DR-40 Outer Ring 0 5.8 NNW DR-41** Site Boundary SB 0.38 SSW DR-42** Site Boundary SB 0.60 S DR-43** Site Boundary SB 0.42 SSE DR-44** Site Boundary SB 0.21 SE DR-45** Site Boundary SB 0.12 NE DR-46** Site Boundary SB 0.29 NNW DR-47** Site Boundary SB 0.51 NNW DR-48** Site Boundary SB 0.82 NW DR-49** Site Boundary SB 0.27 WNW DR-50** Gov. Hunt House I 0.34 SSW DR-51** Site Boundary SB 0.27 .W c I - Inner Ring Tib); O - Outer Ring Incident Response TLD; C - Control TLD; SB - Site Boundary TLD.
** This location is not considered a requirement of Technical Specification Table 3.9.3.
00* Distance and direction for TLD sites are relative to the center of the Turbine Building. l
'l
TABLE 4.4 Environmental Lower Limit of Detection (LLD) Sensitivity Requirements Airborne Particulates Vegetati Water or Gases Fish Milk on Sediment Analysis (pCi/1) (pci/m3) (pci/kg) (pci/1) (pci/kg) (pci/kg
-dry)
Gross-Beta 4 0.01 i H-3 3000 I Mn-54 15 130 Fe-59 30 260 Co-58,60 15 130 Zn-65 30 260 Zr-Nb-95 15 I I-131 0.07 1 60 i Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15 (Several explenatory footnotes are given in Tech. Spec. Table 4.12-1. ll __ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - - - _ _ _ _ _ .. _ _ _ _ _ _ - - - - _ _ - _ _ _ _ _ . _ _ - _ _ . . _ _ _ _ _ _ _ _ __
TABLE 4.5 Reporting Levels for Radioactivity Concentrations In Environmental Samples Airborne Sediment Particulates Food (pci/kg-Water or Gases Fish Milk Product dry) (pci/1) (pci/m3) (pci/kg) (pci/1) (pci/kg) H-3 20,000* Mn-54 1000 30,000 Fe-59 400 10,000 Co-58 1000 30,000 co-60 300 10,000 3000** Zn-65 300 20,000 Zr-Nb-95 400 I-131 0.9 3 100 Cs-134 30 10 1000 60 1000 J l Cs-137 50 20 2000 70 2000 l Ba-La-140 200 300 l
- Reporting Level for drinking water pathways. For non-drinking water, a value of 30,000 may be used.
** Reporting Level for grab samples taken at the North Storm Drain Outfall only.
l 1 i .. . . . . . _ __. . . _ . . _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ ._.d
o 500 N HETERS o .. FENCELINE,/$,
/ %
s $
% $ h s <
TC-11 ) $ VERNON POND I TM-11 I \ g STACK s
\ s
'A SE-12
\ INTAKE e
[ e
\ s
\ \
NG-11 'g
\ \
s } l A FH-11 VERNON ELEMENTARY SCHOOL N TS-40 A, 4 k DISCHARGE eh t w ) 1 i 1 l l , SE-11 HINSDALE, NH
's~ ~ , ' s' I
VERNON, VT \ , 6
$ CONNECTICUT VERNON DAM RIVER
/
Figure 4.1 Radiological Environmental Sampling Locations Within Close Proximity to Plant 22 .
r N
)
TS-12 m-19 A TG-12 AP/CF-12 A f*g+ ~~ TC-15 A -5 HINSDALE, NH A 7"-16 TC-16 b AP/CF-15 i A To-13 AP/CF-13 [ , ser rut.Jucazur zu rzctms 4-1 l vzmon om AP/CF-11 TC-14 A 8 TG-11
*- 14 WG-12 WR-11 -
WMON, VT TS-lo A TC-18 TC-13 0 1 2 3 -A m_13 i LILY POND KILOH1TERS Figure 4.2 Radiological Environmental Sarnpling Locations Within 5 Kilometers of Plant
\
N Y [N 4 A 'IM-2 4 TC-24 I l SPCFFORD LAKE J TG-21 l A WG-22 A AP/Cr-21 FH-21 HOGBACK O WR-21 MT. A MAgL3ogo CHESTEkFIELD O , BRATTLEBORO O srr rutananeur zu rzauns 4-2
,/
i HINSDALE TC-12 GUILFORD0 ; O A m-12 l' VERNONO u O
! PLANT
[ j WINCHESTER i f VERMONT NEW HAMPSHIRE
- m-17 -A - -
-n - - -
MASSACHUSETTS ll MASSACHUSETTS O NORTHFIELD A AP/CF-14 TG-14 TS-14 l GREENFIELDO O 5 10 KILOMETERS l Figure 4,3 Radiological Environmental Sampling Locations Greater than Five Miles from Plant I 0 500 N METERS
?0 04 FENCELINE,,
\ ('
/
s' A DR-48'N s
's %
k
*P 's DR-47A$
k 's $
\ $ VERNON POND la '
R-33
\pR-49 s
STACKh' 6
'N' g
- INTAKE
'\A
- DR-45
~
DR-31 A \ s A DR-44 DR-8 h # DR-6 8 g t i VERNON ELEMENTARY SCHOOL g A e4 f DR-4,1 l DR-29 DR-50 jDR-43 A,/ DR-42,A,f' s ' B VERNON, VT $ to CONNECTICU" VERNON DAM DR-27 A i } _ Figure 4.4 TLD Monitoring Locations in Close Proximity to Plant 25-
)
i l M NNW NNE N
)
ww A DR-40 DR-10 A um DR-12 A DR-14 ,, A DR-2 A A DR-39 HINSDALE, NH '
\
DR-36 g DR-378 DR-9 DR-11 00 A A www 20 ~ DR-16
; DR-13 4 ,
k ODR-3
/
E DR-17 DR-18 w % l E j src ruuRam r zu rzauRr 4-4 i
\ A DR-19 DR-32 A'DR-21 )
b A DR-30 A DR-23 Esz wSW A A Da-1 DR-25 VERNON, VT A _ DR-22
" j sw DR-26 A A DR-24 0 1 2 3
- ILY POND KILOME N SE SSW s SSE Figure 4.5 TLD Monitoring Locations Within 5 Kilometers'from Plant
-26
h N i '
) \
p P0FTORD LAE k W f q. A'DR-s HOGnACK MT.
+ CHESTERFIELD s A MARLBOR e
RATTLEBORCie srr rurJuterxrov zu rxcv;tr 4-5 8 \ DR-38 Ai _ ___ __ , k 8 I HINSDALE cuILroRD e i * ' y,,cy,, , g DR-34 A OERNotr.. i e g A DR-20 I
- VE M NT,,,, , , , , ~ , , , ,, - , , - ,- -j ,, NEW EMSHI,E-MASSACHUSETTS '
}; MASSACHUSETTSg, N j ,
NORTHFIELD /y A DR-4.
/0
/
GREENFIELD# 0 5 10 I I I KILOMETERS ' I Figure 4.6 TLD Monitoring Locations Greater than 5 Kilometers from Plant 27-1
5, RADIOLOGICAL DATA BUMMARY TAB _LER This section summarizes the analytical results of the environmental se yles which were collected during 1993. These results, shown in Table 5.1, <;e presented in a format similar to that prescribed in the NRC's Radiological Assessment Branch Technical Position on Environmental Monitoring (Reference 1). The results are ordered by sample media type and then by radionuclide. The units for each media type are also given. The left-most column contains the radionuclide of interest, the total number of analyses for that radionuclide in 1993, and the number of measurements which exceeded the Reporting Levels found in Table 3.9.4 of the VYNPS Technical Specifications. The latter are classified as "Non-routine" measurements. The second column lists the required Lower Limit of Detection (LLD) for those radionuclides which have detection capability requirements as specified in the plant's Radiological Effluent Technical Specifications (Table 4.9.3). The absence of a value in this column indicrees that no LLD is specified in the Technical Specifications for that radionuclide in that media. The target LLD for any analysis is typically 30-40 percent of the most restrictive required LLD. On rare occasions the required LLD is not met. This is usually due to malfunctions in sampling equipment, which results in low sample volume. Such cases are addressed in < Section 6.2. For each radionuclide and media type, the remaining three columns swmmarize the data for the following categories of monitoring locations: (1) the Indicator stations, which are within the range of influence of the plant and which could conceivably be affected by its operation; (2) the station which had the highest mean concentration during 1993 for that radionuclide; and (3) the Control stations, which are beyond the ir. fluence of the plant. Direct radiation monitoring stations (using TLDs) are grouped into Inner Ring, Outer ring, Site Boundary and Control stations. In each of these columns, for each radionuclide, the following statistical values are given: r
- The mean value of all concentrations, with all values that are less than the a posteriori LLD for that analysis having been converted to zero, pursuant to footnote (f) of Technical Specification Table 4.9.3.
- The standard error of the mean.
l l
- The lowest and highest concentration, with all values that are less than the a costeriori LLD having been converted to zero, pursuant to footnote (f) of Technical Specification Table 4.9.3.
-- The "No. Detected," or the number of positive measurements, divided by the total number of measurements, (A concentration which is -
greater than three times the standard deviation of that count, based on random uncertainty only, is considered " positive,") Each single radioactivity measurement datum in this report is based on a single measurement and is reported as a concentration plus or minus a one standard deviation uncertainty. The standard deviation on each measurement-represents only the random uncertainty associated with the radioactive decay. process (counting statistics), and not the propagation of all possible uncertainties in the analytical procedure. Pursuant to VYNPS Technical Specification Table 4.9.3 (footnote f), any concentration below the a costeriori LLD for its analysis is averaged as a zero, Where a range of values is reported in the tables of this section, values less than their LLD are also reported as zero. To be consistent with Laboratory reporting practices and normal data review practices used by Vermont Yankee, a " positive measurement" is considered to be one whose concentration is greater than three times its associated standard deviation, based on the random uncertainty as discussed above. This use wt counting statistics for the determination of the presence or radioactivity, rather than the use of an LLD as a cut-off, is consistent with industry practices. The radionuclides reported in this section represent those that: 1) had an > LLD requirement in Table 4.9.3 of the Technical Specifications, or a Reporting Level listed in Table 3.9.4, or 2) had a positive measurement of radioactivity, whether it was naturally occurring or man-made; or 3) were of special interest for any other reason. The radionuclides that were. routinely analyzed and reported by the Laboratory-(in a gamma spectroscopy analysis) were: AcTh-228, Ag-110m, Ba-140, Be-7, Ce-141, Ce-144, Co-57, Co-58, Co-60, Cr-51, Cs-134, Cs-137, Fe-59, I-131, I-133, K-40, Mn 54, .Mo-99, Np-239, Ru-103, Ru 106, Sb-124, Se-75, TeI-132, Zn-65 and Zr-95. In no case did a radionuclide not shown in Table 5.1 of this report appear as a " detectable measurement" during 1993. Data from direct radiation measurements made by TLDs are provided in Table 5.2 in a format essentially the'same as above. The complete listing of 1 quarterly TLD data is provided in Table 5.3. 1
-l l
)
TABLE 5.1 RADIOLOGICAL ENVIROISENTAL PROGRAM StamART VERMONT YANKEE 10 CLEAR POKR STATION, VERNON, VT (JANUARY - DEEDBER 1993) INDICATOR STATIONS STAT.0N WITN HICHEST MEAN CONTROL STATIONS
.................e ......................... ................
RADIONUCLIDES
- MEAN MEAN MEAN (NO. ANALYSES) REQUIRED RANGE STA. RANGE RANCE (NON ROUTINE)** LLD NO. DETECTED *** No. NO. DETECTE0*** NO. DETECTED ***
BIL5t: AIR PARTIQA.ATES (AP) LaflTS: pC1/ctbic meter cross (156) .01 ( 1.9 0.0)E 2 13 ( 2.0 1 0.1)E 2 ( 1.8 2 0.1)E. 2 Beta ( 0) ( 8.5 - 32.8)E 3 ( 1.0 - 3.3)E -2 ( 9.1 - 29.2)E 3 (130/130) ( 26/ 26) ( 26/ 26) BE.7 ( 24) ( 9.1 2 0.4)E 2 21 ( 9.9 a 1.1)E -2 ( 9.9 2 1.1)E 2 ( 0) ( 6.0 - 12.0)E -2 ( 7.5 - 13.0)E -2 ( 7.5 - 13.0)E -2 ( 20/ 20) ( 4/ 4) ( ' 4/ 4) Co-60 ( 24) ( 0.0 t 0.0)E 0 11 ( 0.0 t 0.0)E 0 ( 0.0 s 0.0)E O ( 0) ( 0/ 20) -( 0/ 4) ( 0/ 4) CS-134 ( 24) .05 ( 0.0 t 0.0)E O 11 ( 0.0 2 0.0)E 0 ( 0.0 s 0.0)E D ( 0) ( 0/ 20) ( 0/ 4) ( 0/ 4) , CS 137 ( 24) .06 ( 0.0 t 0.0)E O 11 ( 0.0 2 0.0)E O ( 0.0 2 0.0)E O ( 0)
,( 0/ 20) ( 0/ 4) ( 0/ 4)
E !UN: . CHARCOAL FILTERS (CF) UNITS: pcl/cteic meter I 131 (156) .07 ( 0.0 2 0.0)E O 11 ( 0.0 2 0.0)E O ( 0.0 1 0.0)E O - ( 0) ( 0/130) ( 0/ 26) ( 0/ 26)
- EDILDt RIVER WAirt (WR) UNITS: pCl/kg cross ( 25). 4. ( 1.6 0.2)E D 21 ( 1.8 s 0.2)E O ( 1.8 2 0.2)E 0
-Bata (- 0) ( 0.0 - 2.4)E D ( 0.0 - 3.3)E O ( 0.0 - 3.3)E O ( 12/ 13) ( 11/ 12) ( 11/ 12) > L MN-54 ( 25) 15. ( 0.0 t 0.0)E O 11 ( 0.0 t 0.0)E O ( 0.0 1 0.0)E O ( 0) ( 0/ 13) ( 0/ 13) ( 0/ 12)- NOTE: Footnotes may be fourd at the end of Table 5.1. 30
.-=. - . . . ~. . .- . . _ , _. . . _ . _ . ., -
i i l TABLE 5.1 RADIOLOGICAL ENVIROWENTAL PROGRAM SLBetART VERMONT yam 1E NUCLEAR PGK.A STATION, VERNON, VT (JANUARY . DECDBER 1993) INDICATOR STAfl0NS STATION WITH NICHEST MEAN CONTROL STATIONS
.................. ......................... ................ j
. RADIONUCL! DES
- MEAN MEAN MEAN (NO. ANALYSES) REQUIRED RANCE STA. RANCE. RANCE I (NON ROUTINE)** LLD No. DETECTED *** NO. No. DETECTED *** WO. DETECTED ***
#ED! tat: RIVER WATER ( W ), continued LABITS: pCl/kg '
s Co-58 ( 25) 15. ( 0.0 0.0)E O 11 ( 0.0 a 0.0)E O ( 0.02 0.0)E O ( 0) ( 0/ 13) ( 0/ 13) ( 0/ 12) FE 59 ( 25) 30. ( 0.0 t 0.0)E O 11 ( 0.0 1 0.0)E O ( 0.0 1 0.0)E O ( 0) ' ( 0/ 13) ( 0/ 13) ( 0/ 12) Co 60 ( 25) 15. ( 0.0 t 0.0)E O 11 ( 0.0 1 0.0)E O ( 0.0 a 0.0)E O ( 0) ( 0/ 13) ( 0/ 13) ( 0/ 12) 3N 65 ( 25) 3( ( 0.0 a 0.0)E O 11 ( 0.0 t 0.0)E O ( 0.0 t 0.0)E 0 ( 0) ( 0/ 13) ( 0/ 13) ( 0/ 12) 8R 95 ( 25) 15 .- ( 0.0 a 0.0)E O 11 ( 0.0 t 0.0)E O ( 0.0 t 0.0)E 0 ' ( 0) ( 0/ 13) ( 0/ 13) ( 0/ 12) CS 134 ( 25) 15. ( 0.0 1 0.0)E 0 11 ( 0.0 t 0.0)E O ( 0.0 t 0.0)E 0 ( 0) ( 0/ 13) ( 0/ 13) ( 0/ 12) CS-137 ( 25) 18. ( 0.0 2 0.0)E O 11 ( 0.0 t 0.0)E 0 ( 0.0 t 0.0)E 0 ( 0) ( 0/ 13) ( 0/ 13) ( 0/ 12) . BA-140 ( 25) 15. ( 0.0 2 0.0)E 0 11 ( 0.0 a 0.0)E O ( 0.0 2 0.0)E 0 ( 0) ( 0/ 13) ( 0/ 13) ( 0/ 12) H3 ( . 8) 3000. ( 0.0 1 0.0)E O 11 ( 0.0 t 0.0)E-0 ( 0.0 t 0.0)E 0 ( 0) ( 0/ 4) ( 0/ 4) ( 0/ 4) 1 A l 00TE: Footnotes may be found at the end of Table 5.1. l 31 I 1
'l
a TABLE 5.1 RADIOLOGICAL ENVIRGSENTAL PROGtAM SL8sIARY WRMONT YANKEE IRJCLEAR POER STATION, VERNON, VT (JANUART . DEQ3SER 1993) INDICATOR STATIONS STATION WITH H! CHEST MEAN CONTROL STATIONS ,, RADIONUCLIDES
- MEAN MEAN MEAN l' (NO. ANALTSES) REQUIRED RANCE STA. RANCE RANCE 1 (NON ROUTINE)** LLD NO. DETECTED *** NO. NO. OETECTED***. No. DETECTED ***
l .......................... .. .................. IEDIUM: GROUND IMTER (WG) UNITS: pcl/kg , cross ( 12) 4. ( 5.6 1.0)E O 11 ( T.9 0.7)E 0 ( 1.92 0.1)E O l Bata ( 0) ( 1.3 9.1)E O ( 6.3 9.1)E O ( 1.4 - 2.1)E O ( - 4/ 4) ( 8/ 8) ( 4/ 4) RA.226 ( 3) ( 0.0 2 0.0)E D 11 ( 0.0 1.7)E O ( 0.0 t 1.6)E D ( 0) ( 0/ 2) ( 0/ 1) ( 0/ 1) RA 228 ( 3) ( 0.0 t 0.0)E O 11 ( 0.0 t 3.5)E 0. ( 0.0 t 3.4)E O ( 0) ( 0/ 2) ( 0/ 1) ( 0/ 1) 8:N 54 ( 12) 15. ( 0.0 t 0.0)E O 11 ( 0.0 t 0.0)E O ( 0.0 a 0.0)E D ( 0) ( 0/- 8) ( 0/ 4) ( 0/ 4) Co 58 ( 12) 15. ( 0.0 t 0.0)E O 11 ( 0.0
- 0.0)E 0 ( 0.0 t 0.0)E 0
( 0) ( 0/ 8) ( 0/ 4) ( 0/ 4) FE 59 ( 12) 30. ( 0.0 1 0.0)E O 11 ( 0.0 2 0.0)E O ( 0.0 t 0.0)E O ( 0) ( 0/ 8) ( 0/ 4) ( 0/ 4) Co-60 ( 12) 15. ( 0.0 2 0.0)E 0 11 ( 0.0 2 0.0)E O ( 0.0 t 0.0)E O ( 0) ( 0/ 8) ( 0/ 4) ( 0/ 4) 2N 65 ( 12) 30. ( 0.0 t 0.0)E 0 11 ( 0.0 2 0.0)E O ( 0.0 2 0.0)E O ( 0) '
' ( 0/ 8) ( 0/ 4) ( 0/ 4)
ZR 95 ( 12) 15. ( 0.0 2 0.0)E O 11 ( 0.0
- 0.0)E O ( 0.0 t 0.0)E O
( 0) ( 0/ 8) ( 0/ 4) ( 0/ 4) NOTE: Footnotes may be found at the end of Table 5.1. 32 I a
-1 l
____._______________________________________________.____.___________.___j
TABLE 5.1 RADIOLOGICAL ENVIRONKMTAL PROGRAM SLM4ARY VERf0NT YANKEE IRJCLEAR POWER STATION, VERNON, VT (JANUARY DECDBER 1993) INDICATOR STAfl0NS STATION WITH HIGHEST MEAN CONTROL STATIONS RADIONUCLIDES
- MEAN MEAN MEAN (NO. ANALYSES) REQUIRED RANCE STA. RANGE RANCE (NON ROJTINE)** LLD NO. DETECTED *** NO. NO. DETECTED *** NO. DETECTED ***
EDIL84: CREAC WATER (WC), continued IJNITS: pC1/kg CS-134 ( 12) 15. ( 0.0 2 0.0)E O 11 ( 0.0 2 0.0)E O ( 00t 0.0)E 0 ( 0) ( 0/ 8) ( 0/ 4) ( 0/ 4) CS 13F ( 12) 18. ( 0.0 t 0.0)E O 11 ( 0.0 t 0.0)E O ( 0.0 2 0.0)E O ( 0) ( 0/ 8) < 0/ 4) ( 0/ 4) SA-940 ( 12) 15. ( 0.0 2 0.0)E O 11 ( 0.0 1 0.0)E 0 ( 0.0 2 0.0)E O ( 0) ( 0/ 8) < 0/ 4) ( 0/ 4) H-3 ( 12) 3000. ( 0.0 1 0.0)E O 11 ( 0.0 2 0.0)E O ( 0.0 t 0.0)E O ( 0) ( 0/ 8) ( 0/ 4) ( 0/ 4) KVIUM: SEDIMENT (SE) UNITS: N:I/Lg (dry) BE-7 ( 82) ( 9.4 2 3.3)E 1 12 ( 9.6 2 3.4)E i NO DATA ( 0) ( 0.0 - 1.7)E 3 ( 0.0 - 1.7)E 3 ( 5/ 82) ( $/ 80) K-40 ( 82) ( 1.3 2 0.0)E 4 12 ( 1.3 1 0.0)E 4 NO DATA ( 0) ( 8.2 - 16.3)E 3 ( 8.2 - 16.3)E 3 ( B2/ 82) ( 80/ 80) MN 54 ( 82) ( 0.0 t 0.0)E O 11 ( 0.0 t 0.0)E D NO DATA ( 0) ( 0/ 82) ( 0/ 2) Co-50 ( 82) ( 0.0 2 0.0)E D 11 ( 0.0 t 0.0)E O NO DATA ( 0) ( 0/ 82) ( 0/ 2) Co 60 ( 82) ( 1.8 2 0.5)E 1 12 ( 1.9 2 0.5)E 1 NO DATA l ( 0) ( 0.0 - 2.3)E 2 ( 0.0 - 2.3)E 2 i ( 13/ 82) ( 13/ 80) i kOTE: Footnotes ray be fourd at the end of Table 5.1. l 33-
I TABLE 5.1- I
.1 RADIOLOGICAL ENVIROIsENTAL Mt0 GRAM E8 MARY VERMONT YANKEE IRJCLEAR POER STATION, VERNON, VT (JAMLIARY = DECDSER 1993)
INDICATOR STATIONS STATION WITH HIGHEST MEAN CONTROL STATIONS
- e. ...eeeeeeeeeeee eeeeeeeeeeeeeeeeeeeeeeeen e ee. **eeeeeeee RADIONUCLIDES
- MEAN MEAN MEAN (NO. ANALYSES) REQUIRED RANCE STA. RANCE RANGE (NON ROUTlWE)** LLD NO. DETECTED *" NO. NO. DETECTED *** NO. DETECTED ***
lettM: SEDIMENT (SE), cont, UNITS' pCI/kg (dry) t 20-65 ( 82) ( 0.0 t 0.0)E O 11 ( 0.02- 0.0)E 0 NO DATA ( 0) ( 0/ 82) ( 0/ 2) CS 134 ( 82) 150. ( 7.0 a 7.0)E -1 12 ( t.2 7.2)E 1 NO DATA ( 0) ( 0.0 - 5.7)E 1 ( l.0 - 5.7)E 1
'( 0/ 82) ( 0/ 80)
CS 137 ( 82) 180. ( 1.5 t 0.1)E 2 12 ( 1.8 s 0.1)E 2 NO DATA ( 0) ( 5.6 - 30.9)E 1 ( 5.6 - 30.9)E 1 ( 82/ 82) ( 80/ 30) - ACTH228 ( 82) ( 8.8 0.2)E 2 12 ( 8.8 s 0.2)E 2 NO DATA
.( 0) ( 4.6 - 13.1)E 2 ( 4.6 - 13.1)E 2
( 82/ 82) ( 80/ 80) , IEDILM: MILK (TM) UNITS: pCl/kg SR 89 ( 23) ( 0.0 t 0.0)E O 11 ( 0.0 : 0.0)E D ( 0.0 t 0.0)E ' O ( 0) ( 0/ 19) ( 0/ 4) ( 0/ 4) S3 90 ( 23) ( 9.7 2 3.1)E 1 12 ( 2.2 2 0.8)E O ( 3.6 3.6)E 1 ( 0) ( 0.0 - 3.5)E 0 ( 0.0 - 3.5)E O (. 0.0 - 1.4)E 0 ( 7/ 19) ( 3/ 4) ( 1/. 4) K-40 ( 99) ( 1.5 0.0)E 3 12 ( 1.9 s 0.0)E-3 ( 1.3 a 0.0)E 3 ( 0) ( 1.1 - 2.1)E 3 ( 1.6 - 2.1)E 3 ( 1.2 - 1.4)E 3 ( 81/ 81) ( 18/ 18) ( 18/ 18) I 131 ( 99) 1. ( 0.0 2 0.0)E O 11 ( 0.0 s 0.0)E O ( 0.0 2 0.0)E 0 ( 0) - . . ( 0/ 81) ( 0/ 18) ( 0/ 18) CS-134 ( 99) 15. ( 0.0 2 0.0)E 0 11 ( 0.0 t 0.0)E O ( 0.0 2 0.0)E O ( 0) , ( 0/ 81) ( 0/ 18) ( 0/ 18) NOTE: Footnotes may be found at the end of Table 5.1. 34 . ~
. . . - . - - - - _ ~ , - - . - - -.
.1 1
l TABLE 5.1 1 RADIOLOGICAL ENVIROMENTAL PROGtAM SlagNut? WitMONT YANKEE IRJCLEAR POKR STATION, WRNON, VT (JANUARY - DECENsCR 1993) ) INDICATOR STATIONS STAil0N WITH HIGHEST MEAN CONTROL STATIONS
.................. eeeeeeeeeeeeeeeeeeeeee**e ................
RADIONUCLID*.S* MEAN MEAN MEAN (NO. ANALYSES) REQUIRED RANGE STA. RANGE RANGE (NON ROUTINE)** LLD NO. DETECTED *** NO. NO. DETECTED *** Wo. DETECTED *** EDItst: MILK (TN), cont. UNITS: pCl/kg CS-137 ( 99) 18. ( 1.2 2 0.3)E 0. 12 ( 4.2 s 1.1)E O ( 0.0 t 0.0)E 0 ( 0) ( 0.0 - 1.6)E 1 ( 0.0 - 1.6)E 1 ( 14/ 81) ( 10/ 18) ( 0/ 18) . l BA-140 ( 99) 15. ( 0.0 a 0.0)E D 11 ( 0.0
- 0.0)E O. ( 0.0 1 0.0)E O
( 0) ( 0/ 81) ( 0/ 18) ( 0/ 18) NO)!tSt: S!LAGE (TC) tal!TS: (Cl/kg BE ? ( 6) ( 2.6 : . 1.3)E 2 14 ( 6.9 s 1.1)E 2 ( 6.4 2 0.9)E 2 ( 0) ( 0.0 - 6.9)E 2 ( 3/ 5) ( 1/ 1) ( 1/ 1) K-40 ( 6) ( 6.3
- 2.9)E 3 12 ( 1.7 2 0.1)E 4 (. 3.8 0.2)E 3
( 0) ( 1.6 - 17.4)E 3 > ( 5/ 5) ( 1/ 1) ( 1/ 1)
'l 131 ( 6) 60. ( 0.0 t 0.0)E O 11 ( 0.0 2 1.9)E O ( 0.0
- 5.5)E D
( 0) ( 0/ 5) ( 0/ 1) ( 0/ 1) CS 134 ( 6) 60. ( 0.0 t 0.0)E O 11 ( 0.0 t 4.8)E O ( 0.0 t 6.3)E D ( 0) , ( 0/ 5) ( 0/ 1) -( 0/ 1) CS 137 ( 6) 80. ( 0.0
- 0.0)E O 11 ( 0.0 t 5.3)E O ( 0.0 1 7.6)E O
( 0) ( 0/ 5) ( 0/ 1) ( 0/ 1) BA 160 ( 6) ( 0.0 2 0.0)E O 11 ( 0.0 t 1.0)E 1 ( 0.0 t 1.3)E 1 ( 0) ( 0/ 5) ( 0/ 1) ( 0/ 1) 00TE: Footnotes may be found at the end of Table 5.1. 35-1 l 1 j
, _,. . - - - . . ., .. . ~ . - - . - . .,
l TAsLI 5.1 RADIOLOGICAL ENVIRCBBENTAL PROGRAM SLBO4'AY WRMONT YANKEE IRJCLIAR POKR STATION, VERNCaf, VT (JA8RJARY - DEE3mER 1993) INDICATOR STATIONS STATION WITN HIGHEST MEAN CONTROL STATIONS
.................. eeeeeeeeeeeeeeeee*******e ................
RADIONUCLIDES * - MEAN MEAN MEAN ,
-(CO. ANALYSES) REQUIRED RANCE STA. RANCE RANCE (MON ROUTINE)** LLD NO. DETECTED *** NO. NO. DETECTED *** No. DETECTED"*
- IO!Let: MINED CRASS (TC) UNITS: pcl/kg BE ? ( 18) ( 1.72 0.5)E 3 12 ( 3.2 2 2.1)E 3 ( 9.2 t 5.0)E 2
( 0) ( 0.0 - 7.3)E 3 ( 5.7 - 73.4)E -2 ( 0.0 - 1.7)E 3 ( 14/ 15) ( 3/ 3) ( 2/ 3) , K 40 ( 18) ( 5.4 1 0.3)E 3 12 ( 5.9
- 1.1)E 3 ( 5.1
- 0.1)E 3
( 0) ( 3.5 - 7.7)E 3 ( 3.9 - 7.7)E 3 ( 4.9 - 5.4)E 3 ( 15/ 15) ( 3/ 3) ( 3/ 3) 7 t-931 ( 18) 60. ( 0.0 2 0.0)E 0 11 ( 0.0 2 0.0)E O ( 0.0 2 0.0)E 0 .; ( 0) ( 0/ 15) ( 0/ 3) ( 0/ 3) . t CS 134 ( 18) 60 ( 0.0 t 0.0)E 0 11 ( 0.0 s 0.0)E O ( 0.0 t 0.0)E O -, ( 0) ( 0/ 15) ( 0/ 3) ( 0/ 3) 'i CS 137 ( 18) 80. ( 2.6 1 2.4)E 1 12 ( 1.2 2 1.2)E 2 ( 0.0 2 0.0)E O ! ( 0) ( 0.0 - 3.6)E 2 ( 0.0 - 3.6)E '2 . ! ( 2/ 15) ( 1/ 3) ( 0/ 3) NED!LM: FISH (FM) UNITS: pCf/kg K-40 ( 4) ( 3.0 t 0.1)E 3 21 ( 3.1 0.2)E 3 ( 3.1 s 0.2)E 3 ( 0) ( 2.9 - 3.0)E 3 ( 2.9 - 3.2)E 3 ( 2.9 - 3.2)E 3 ' ( 2/ 2) ( 2/ 2) ( 2/ 2)
.NN-54 ( 4) 130. ( 0.0 t 0.0)E O 11 ( 0.0 2 0.0)E O ( 0.0 t 0.0)E O ,
( 0) ( 0/ 2) ( 0/ 2) ( 0/ 2) CO-50 ( 4) 130. ( 0.0 t 0.0)E O 11 ( 0.0 t 0.0)E O ( 0.0 2 0.0)E O ( 0) ( 0/ 2) ( 0/ 2) ( 0/' 2) FE 50 ( . 4) 260. ( 0.0 2 0.0)E O 11 ( 0.0 2 0.0)E O ( 0.0 2 0.0)E. 0 ( 0) . ( 0/ 2) ( 0/ 2) ( 0/ 2) NOTE: footnotes may be fourd at the end of Table 5.1, i
,p - , _ . , , - ,,7 _
1~ , , , , , , . - .
TABLE 5.1 ) RADIOLOGICAL ENVitatBENTAL PROGRAN SLSSIARY VERMONT YAIIKEE IslCLEAR fuER STATIUN, VERNON, VT (JAIRAARY = DECDeER 1993) l INDICATOR STATIONS- STATION WITH NICHEST MEAN CONTROL STATIONS l RADIONUCLIDES * ~ MEAN- MEAN MEAN (NO. ANALYSES) REQUIRED RANCE STA. RANCE RANCE (NON ROUTINE)** LLD No. DETECTED *** NO. No. DETECTED *** NO. DETECTED *** IEDitm: FISH (FM), cont. LIMITS: pC1/kg C0-60 ( 4) 130. ( 0.0 t 0.0)E D 11 ( 0.0 2 0.0)E O ( 0.0 1 0.0)E O
-( 0)
( 0/ 2) ( 0/ 2) ( 0/ 2) 2N-65 ( 4) 260. ( 0.0 t 0.0)E O 11 . ( 0.0 2 0.0)E 0 ( 0.0 t 0.0)E 0 ( 0) ( 0/ 2) ( 0/ 2) ( 0/ 2)
- CS 934 ( 4) 130. ( 0.0 t 0.0)E O 11 ( 0.0 t 0.0)E D ( 0.0 1 0.0)E O'
( 0) ; ( 0/ 2) ( 0/ 2) ( 0/ 2) CS-937 ( 4) 150. ( 1.1 1 1.1)E 1 21 ( 1.1 1 1.1)E 1 ( 1.1 1 1.1)E 1 ( 0) ( 0.0 - 2.2)E 1 ( 0.0 - 2.2)E 1 ( 0.0 - 2.2)E 1 ( 1/ 2) ( 1/ 2) ( 1/ 2) MEDIUM: Soll (TS) UNITS: pCi/kg (wet) BE-7 ( 20) ( 0.0 2 0.0)E O 10 ( 0.0 t 0.0)E O NO DATA' ( 0) ( 0/ 20) ( 0/ 5) i K-40 ( 20) ( 9.3 0.5)E 3 10 ( 1.2 1 0.0)E 4 NO DATA , ( 0) ( 6.9 - 13.7)E 3 ( 1.0 - 1.4)E 4 ( 20/ 20) ( 5/ 5)
~
Co 58 ( 20) ( 0.0 2 0.0)E O 10 ( 0.0 t 0.0)E 0 NO DATA ( 0) ( 0/ 20) ( 0/ 5) CO 60 ( 20) ( 0.0 2 0.0)E O 10 . ( 0.0 a 0.0)E 0 NO DATA ( 0) ( 0/ 20) ( 0/ 5) s ? CS-934 ( 20) ( 0.0 2 0.0)E O 10 ( 0.0 2 0.0)E O NO DATA ( 0) ( 0/ 20) ( 0/ 5) ,
.t i
COTE: -Footnotes may be found at the end of Table 5.1. 37
TABLE 5.1 RADIOLOGICAL EntlROBBENTAL PROGtAM StBMARY VERMONT TANKEE tuCLEAR PO ER STAT 10N, WERNON, VT (JAa0ARY - DEED sER 1993) INDICATOR STATIONS STAT!DN WITH HIGHEST MEAN CON 1ROL STAT 10NS e.......eeeeeeeeee eeeeeeeeeeeeeeeeeeeeeeeee eeeeeeeeeeeeeeen RADIONUCLIDES
- MEAN MEAN MEAN-(NO. ANALYSES) REQUIRED RANCE STA. RANCE RANCE
-(NON-ROUTINE)** LLD NO. DETECTED *** NO. No. DETECTED *** NO. DETECTED ***
MEDIUM: 50ll (TS), cont. UNITS: pcl/kg (wet) < CS-137 ( 20) ( 1.3 2 0.2)E 2 40 ( 1.6 2 0.2)E 2 NO DATA ( 0) ( 0.0 - 3.9)E 2 ( 1.1 - 2.3)E 2 ( 14/ 20) ( 5/ 5) ACTH223 ( 20) ( 6.4 2 0.3)E 2 10 ( 7.3 2 0.7)F 2 NO DATA ( 0) ( 4.5 - 9.0)E 2 ( 5.4 - 9.0)E 2 ( 20/ 20) ( 5/ 5) IED!tM: STORM DRAIN WATER (W) tailTS: FCl/kg Cross ( 14) - ( 3.2 2 0.2)E O 12 ( 3.3 1 0.4)E 0 NO DATA , Bata ( 0) ( 1.9 - 4.7)E O ( 2.7 - 4.0)E O ' ( 14/ 14) ( 3/ 3) BE 7 ( 12) ( 2.0 t 1.3)E O 10 ( 2.2 1 1.5)E O No DATA ( 0) ( 0.0 1.4)E 1 ( 0.0 - 1.4)E 1 ( 2/ 12) ( 2/ 11) r.N 54 ( 12) ( 0.0 t 0.0)E 0 10 ( 0.0 t 0.0)E O NO DATA ( 0) ( D/ 12) ( 0/ 11)
- CO-58 ( 12) ( 0.0 t 0.0)E D 10 ( 0.0 t 0.0)E O NO DATA
( 0) ( 0/ 12) ( 0/ 11) FE 59 ( 12) ( 0.0 t 0.0)E O 10 ( 0.0 t 0.0)E 0 NO DATA ( 0) ( 0/ 12) ( 0/ 11) CO-60 ( 12) ( 0.0 t 0.0)E O 10 ( 0.0 2 0.0)E O No DATA (: 0) ( 0/ 12) ( 0/ 11) I IN 65' ( 12) ( 0.0 t 0.0)E 0 10 ( 0.0 t 0.0)E 0 .No DATA l t 0) j ( 0/ 12) ( of 11) i NOTE: Footnotes may be found at the end of Table 5.1.
-38 ]
l 4
.l
.i j
TABLE 5.1 RADIOLOGICAL ENVIROISENTAL PROCRAM EpptARY VERsIDIIT YAIN2E NUCLEAR poler STATION, VERNON, VT (JARIARY - DECDSER 1993) INDICATOR STATIONS STATION WITN HICHEST MEAN CONTROL STATIONS RADIONUCLlDES* MEAN. MEAN MEAN ; (NO. ANALYSES) REQUIRED RANGE STA. RANGE RANCE (NON-Roui!NE)** LLD NO. DETECTED *** Wo. No. DETECTED *** No. DETECTED *** HEDIUM: STORM DRAIN WATER (W), cont. UNITS: PCl/kg { ZR 95 ( 12) ( 0.0 a 0.0)E O 10 ( 0.0 3 0.0)E O NO DATA ( 0) , ( 0/ 12) ( 0/ 11) CS 134 ( 12) ( 0.0 t 0.0)E O 10 ( 0.0 2 0.0)E O NO DATA ( 0) ( 0/ 12) ( 0/ 11) , CS-137 ( 12) ( 0.0 a 0.0)E D 10 ( 0.0 2 0.0)E O NO DATA ( 0) l ( 0/ 12). ( 0/ 11) SA-140 ( 12) ( 0.0 t 0.0)E O 10 ( 0.0 t 0.0)E D NO DATA ( 0) ( 0/ 12) ( 0/ 11) ; H-3 ( 14) ( 1.5 1 0.8)E 2 10 ( 1.8 1.0)E 2 N0' DATA ( 0) ( 0.0 - 7.8)E 2 ( 0.0 - 7.8)E 2 ( 3/ 14) ( 3/ 11) j l
~I
.1 COTE: - Footnotes may be found at the erd of Table 5.1.
4 l 1
I 2 i l l . Footnotes to Table 5.1:
- Th2 only radioruclides reported in this table are those with LLD requirements, those for. which positive
~ radioactivity was detected, ard those that were of some other special interest. See section 5 of this report fer e discussion of other radionuclides that were analyzed. ** Non Routine refers to those radionuclides that exceeded the Reporting Levels in Technical Specification Table 3.9.4. *** The fraction of sanple analyses yieldire detectable measurements (i.e. the concentration is greater than three times its standard deviation) is shown in parentheses.
Y
-40
..4.. . _ . . . - - - . . - -
1
-TABLE 5.2 ENVIROWENTAL TLD DATA Suewtf I
VERMONT yam 1E NUCLEAR PohER STATION, VERNON, VT (JANUARY - DECDBER 1993) OFFSITE STATION
. INNER RING TLDs OUTER RING TLDs WITN HIGHEST MEAN CONTROL TLDs j
.................... eeeeeeeeeeeeeeeeeeen seeeeeeeeeeeeeeeeeee ....................
MEAN MEAN MEAN MEAN RANGE RANCE RANGE RANCE (NO. MEASUREMENTS) (NO. MEASUREMENTS) (NO. MEASUREMENTS) (No. MEASUREMENTS) 6.7 t 0.6 6.8 0.8 DR 36 8.3 2 0.7 6.5 t 0.4 5.4 8.2 5.1 - 9.1 7.3 - 9.1 6.2 7.1 + (84) (68) (4) (4) SITE BOUNDARY TLD WITH NIGHEST MEAN SITE BOUNDARY TLDs i ................. *****........ .................e** MEAN MEAN RANGE RANGE (NO. MEASUREMENTS) (NO. MEASUREMENTS)
- DR 45 12.3 0.9 7.9 a 1.5 11.5 13.5 6.0 - 13.5 (4) (47)
- Each " measurement" is based typically on quarterly readings from five TLD elements.
s
=
r 1 4 41
TAaLE 5.3 ) ENVIRospENTAL TLD IE_ASURIXNTS 1993 l I Oticro-a per Hour) ANNUAL Ste. 1ST QUARTER 2ND QUARTER 3RD QUARTER 4TH QUARTER AVE. No. Description EXP. S.D. EXP. S.D. EXP. S.D. EXP. S.D. EXP. DR 01 River Sta. No. 3.3 6.0 2 0.2 6.2
- 0.3 6.2 e 0.3 5.8 2 0.1 6.1 DR 02 N. Ninsdale, NH 5.4 a 0.3 6.6 t 0.3 7.0 2 0.3 6.2 2 0.3 6.3 DR-03 Hinsdale substation 6.4 1 0.3 7.6
- 0.3 8.1 2 0.3 7.2 2 0.4 7.3 DR-04 Northfield, MA 5.9 0.2 6.5 0.2 6.7 0.2 5.9 2 0.2 6.2 DR 05 Spofford take, NH 6.3 1 0.2 6.5 t 0.2 7.1 a 0.3 6.2 2 0.2 6.5 DR 06 Vernon School 6.1 0.3 6.9 t 0.3 7.4
- 0.2 6.4 2 0.2 6.7 04-07 Site soundary 7.2 2 0.3 8.1 0.4 8.4 2 0.3 7.3 2 0.2 7.8 DR 08 Site somdary 8.0 t 0.2 8.3 a 0.4 9.0 t 0.3 7.5 0.3 8.2 DR 09 inner Ring 6.0 a 0.2 6.5 t 0.3 7.0 t 0.3 6.0 2 0.3 6.4 DR 10 Outer Ring 5.5 0.2 5.5 0.2 6.2 a 0.2 5.1 0.2 5.6 DR 11 Inner Ring 5.8 0.2 5.9 t 0.3 6.6 2 0.2 5,8 a 0.3 6.1 DR-12 Outer Ring 5.6 2 0.3 5.8 0.2 6.4 2 0.2 5.5 0.2 5.8 DR 13 Inner Ring 6.1 0.3 6.4 e 0.2 7.0 t 0.2 6.3 a 0.2 6.5 DR 14 Outer Ring 6.5 0.2 7.4 1 0.2 8.4 0.3 7.5 0.3 7.4 DR-15 Inner Ring 6.7 0.3 6.7 0.3 7.2 2 0.2 6.5 2 0.2 6.8 DR-16 Outer Ring 7.0 a 0.3 7.0 t 0.3 7.5 0.4 6.7 0.2 7.0 DR-17 inner Ring 5.70.3 6.6 t 0.3 7.0 2 0.3 6.1 2 0.3 6.5 DR 18 Outer Ring 6.2 t 0.4 7.0 a 0.3 7.7 0.3 6.7 0.3 6.9 DR-19 Inner Ring 6.1 0.2 6.9 0.2 7.5 t 0.3 6.6 2 0.3 6.8 DR 20 outer Ring 6.8
- 0.2 7.4 1 0.4 8.2 2 0.3 7.3 a 0.2 7.4 DR 21 Inner Ring 6.3 2 0.2 6.9 0.3 7.7 0.2 6.8 0.4 6.9 DR 22 outer Ring 6.4 a 0.3 6.8 0.2 7.5 0.3 6.5 0.2 6,8 DR 23 inner Ring 6.4 1 0.2 6.3 s 0.3 7.6 0.4 6.7 0.3 6.7 DR 24 Outer Ring 5.8 0.3 5.8 a 0.2 6.3 2 0.2 5.5 t 0.2 5.8 DR-25 Inner Ring 6.5 t 0.3 6.4 2 0.2 7.2 2 0.3 6.1 0.2 6.6 DR 26 Outer Ring 5.8 0.2 6.6 2 0.3 7.420.3 6.7 t 0.3 6.6 DR-27 inner Ring 6.1 0.2 6.6 t 0.3 7.420.3 6.5 t 0.3 6.7 DR 28 Outer Ring 6.2 2 0.3 6.6 2 0.4 7.6 2 0.2 6.6 0.3 6.7 DR-29 Inner Ring 6.1 2 0.2 6.6 2 0.2 7.4 2 0.3 6.6 2 0.2 6.7 DR-30 Outer Ring 6.2 2 0.2 6.3 a 0.2 6.6 2 0.2 7.6 2 0.3 6.7 DR-31 Inner Ring 6.1 a 0.3 7.6 0.8 7.5 t 0.3 6.6 2 0.2 6.9 DR 32 Outer Ring 5.9 0.2 6.4 1 0.3 7.7 0.2 6.5 t 0.2 6.6 DR-33 Inner Ring 6.3 2 0.3 6.9 0.2 7.6 0.4 6.6
- 0.3 6.8 DR-34 Outer Ring 6.5 2 0.2 7.2 t 0.3 8.0 2 0.3 7.0 s 0.2 7.2 DR 35 inner Ring 6.4 2 0.2 6.7 0.3 7.2 2 0.2 6.4 1 0.3 6.7 DR 36 Outer Ring 7.3 2 0.3 8.2 2 0.3 9.1 2 0.3 8.4 a 0.4 8.3 DR.37 troer Ring 6.0 t 0.2 6.9 t 0.4 8.2 2 0.3 6.5 t 0.2 6.9 DR 38 Outer Ring 6.4 2 0.3 7.4 a 0.5 7.8 s 0.3 6.9 0.2 7.1 DR-39 inner Ring 6.3
- 0.3 6.8 2 0.3 7.2 a 0.3 6.4 2 0.2 6.7 DR-40 Outer Ring 6.2 2 0.2 6.7 2 0.3 7.0 2 0.4 6.3 2 0.3 6.6 42-l 1
a
TABLE 5.3, continued ENVIRGsENTAL TLD MEASURDENTS 1993 , (Micro-R per Nour) l AhWUAL Sta. 1ST QUARTER 2ND QUARTER 3RD QUARTER 4TN QUARTER AVE. No. Description EXP. 5.D. EXP. S.D. EXP. S.D. EXP. S.D. EXP. DR 41 Site Boundary 6.6 0.4 7.7 0.4 8.2 a 0.2 7.0 t 0.2 7.1 DR 42 Site soundary 6.0 a 0.2 7.0 t 0.3 7.7 2 0.4 6.6 0.3 6.8 DR-43 Site Bomdary 6.8 0.3 7.5 t 0.3 7.8 2 0.3 6.9 0.3 7.3 DR 44 Site soundary 8.6 0.4 7.7 0.3 7.7 t 0.4 7.1 2 0.3 7.8 DR 45 Site Boundary 13.5 t 1.0 12.3 s 0.4 11.5 s 0.6 11.9 0.5 12.3 . DR 46 Site Boundary 8.0 t 0.4 8.4 a 0.2 8.9 0.2 7.8 0.2 8.3 DR-47 Site Boundary 7.1 0.2 8.1 0.3 8.8 0.2 7.7 2 0.2 7.9 DR-48 Site Boundary 6.4 2 0.3 7.2 2 0.4 7.7 s 0.3 6.7 0.2 7.0 DR-49 Site Boundary 6.0 s 0.3 6.7 0.2 7.4 t 0.3
- 7.0 DR 50 covernor Hunt House 6.6 0.2 7.5 t 0.3 7.8 2 0.2 6.7 0.3 7.1 DR 51 Site Boundary 7.3 2 0.3 8.3 0.3 8.3 t 0.3 7.6 2 0.2 7.9
- Data not available due to missing TLDs.
1 43-
- 6. ANALYSIS OF ENVJRONMENTAL RESULTS 6.1 Sampling Prnpram peviations Radiological Effluent Technical Specification 3.9.C allows for deviations "if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons." In 1993, several deviation.a were noted in the REMP.
These deviations did not compromise the program's effectiveness and in fact are considered typical with respect to what is normally anticipated for any radiological environmental monitoring program. The specific deviations for 1993 were:
- a. For the period April 13 through April 28, 1993, a blown fuse caused the air sampler at AP/CF-15 to stop sampling midway through the second sampling week,
- b. The automatic compositing sampler at Station WR-11 was out of service from approximately 0230 on April 10 through 0900 on April 13, 1993 when the monthly sample was picked up. Between April 13 and April 27, 1993, the sampler was operating sporadically.
- c. Due to the lack of growing vegetation during the winter season, only three of the quarterly mixed grass samples were collected during 1993. These were collected in May, August and October of 1993.
- d. The thermoluminescent dosimeters (TLDs) at site DR-49 were lost, due apparently to vandalism, for the fourth quarter of 1993. It should be noted that DR-49 is not one of the 40 Direct Radiation monitoring locations required by Technical Specification Table 3.9.3 and ODCM Table 4.1.
6.2 Comparison of Achieved LLDs with Reauirements Table 4.9.3 of the VYNPS Technical Specifications (also shown in-Table 4.4 of this report) giver, the required Lower Limits of Detection (L1Ds) for environmental sample analyses. On occasion, an LLD is not achievable due to a situation such as a low sample volume caused by sampling equipment malfunction. In such a case, Technical Specification 6.7.C.3 requires a discussion of the situation. At the Yankee Atomic Environmental Laboratory, the target LLD for any analysis is typically 30-40 percent of ; 1 1 i l l
i i l the most restrictive required LLD. Expressed differently, the typical sensitivities achieved for each analysis are at least 2.5 to 3 times greater than that required by VYNPS Technical Specifications. For each analysis having an LLD requirement in Technical Specification Table 4.9.3, the a nosteriori (after the fact) LLD calculated for that analysis was compared with the required LLD. Of the over 7400 analyses performed during 1993, of which approximately 1300 had an LLD requirement in Technical Specification Table 4.9.3, all met the requirement. 6.3 Comnarison of Results with Reporting Levels Technical Specification Table 3.9.4 requires written notification to the NRC (within 30 days) whenever a Reporting Level in that table is exceeded. Reporting Levels are the environmental concentrations that relate to the ALARA design dose objectives of 10 CFR 50, Appendix I. It should be noted that environmental concentrations are averaged over calendar quarters for I the purposes of this comparison, and that Reporting Levels apply only to measured levels of radioactivity due to plant effluents. During 1993, no Reporting Levels were exceeded. 6.4 Chanc.es in Samoling Locations , VYNPS Technical Specification 6.7.C.3 states that if "new environmental sampling locations are identified in accordance with Specification 3.9.D, the new locations shall be identified in the next annual Radiological Environmental Surveillance Report." Two changes were made in sampling locations during 1993, as described below (both were included in Revision 16 to the Vermont Yankee offsite Dose Calculation Manual):
- a. The Cayland Farm (TM 15 and TC-15) went out of business, with its last sample being collected on May 5, 1993. Since this location was not required by Technical Specifications, it was not immediately replaced,
- b. The Meadowerest Farm (TM-16 and TC-16) began operation in the summer of 1993, and was identified in the 1993 Land Use Census.
Following the Land Use census, it was added to the sampling program, and the first sample was collected there on October 6, 1993. l l 1 1
I l 1
.6.5 Data Analysis by Media Tyne i
Run 1993 REMP data for each media type is discussed below. Whenever a specific measurement result is presented, it is given as the concentration plus or minus one standard deviation. This standard deviation represents only the random uncertainty associated with the radioactive decay process (counting statistics), and not the propagation of all possible uncertainties in the analytical procedure. An analysis is considered to yield a " detectable measurement" when the concentration exceeds three times the standard deviation for that analysis. With respect to data plots, all not concentrations are plotted as reported, without regard to whether the value is " detectable" or "non detectable." 6.5.1 Airborne Pathways 6.5.1.1 Air Particulates The bi-weekly air particulate filters from each of the six sampling sites were analyzed for gross-beta radioactivity. At the end of each quarter, the thirteen weekly filters from each sampling site were composited for a gamma analysis. The results of the weekly air particulate sampling program are shown in Table 5.1 and Figures 6.1 and 6.2. As shown in Figures 6.1, there is no significant difference between the quarterly average concentrations at the indicator (near-plant) stations and the control (distant from plant) stations. Also notable in the Figure is a distinct annual cycle, with the minimum concentration in the second quarter, and the maximum concentration in the first quarter. The peak seen in the second quarter of 1986 is airborne contamination resulting from the Chernobyl accident, as detected by the Vermont Yankee monitoring program. Figures 6.2 through 6.6 show the weekly gross beta concentration at each air particulate sampling location alongside the same for the control air particulate sampling location at AP 21 (Spofford Lake, Nil). Small differences are evident, and are expected, between individual sampling locations. It can also be seen that the gross-beta measurements on air particulate filters fluctuate significantly over the course of a year. The measurements from control station AP-21 vary similarly, indicating that these fluctuations are due to regional changes in naturally-occurring airborne radioactive materials, and not due to Vermont Yankee operations. The only other radionuclide detected on air particulate filters was Be-7, a naturally occurring cosmogenic radionuclide. 1
'l i
6.5.1.2 Charcoal Cartride.es The bi weekly charcoal cartridges from each of the six air sampling sites were analyzed for I-131. The results of these analyses are summarized in Table 5.1. As in previous years, no I-131 was detected in any charcoal cartridge. 6.5.1.3 Soil Samples Soil core samples were collected from four off site locations as part of an in situ survey in October 1993. Each set of cores was segmented into 2-inch depth increments, with a total sampled depth of 10 inches. For each location, the 0-2 in segments were blended into a single sample, as were the 2-4 inch, 4-6 inch, 6-8 inch and 8-10 inch segments. These composite samples were then analyzed for gamma-emitting radionuclides. As Table 5.1 shows, naturally-occurring K-40 and AcTh 228 were detected in each sample, as expected. Also detected in most samples, as expected, was Cs 137, which is attributable to nuclear weapons testing fallout that is found throughout the environment. The levels detected are consistent with those detected in previous soil samples from Vermont Yankee and with those detected at other New England locations that have been monitored as part of other Yankee-affiliated environmental monitoring programs. , 6.5.2 Waterborne Pathways 6.5.2.1 River Water Aliquots of river water were automatically collected at least every two hours from the Connecticut River downstream from the plant discharge area. Monthly grab samples were also collected at the upstream control location, also on the Connecticut River. The composited samples at WR-11 were collected monthly and sent to the Yankee Atomic Environmental Laboratory, along with the WR-21 grab samples, for analysis. Table 5.1 shows that gross-beta measurements were positive in most samples, as would be expected, due to naturally-occurring radionuclides in the water. The'mean concentrations at the indicator'and control locations were not significantly different in 1993. Both mean concentrations were consistent with those detected in previous years, as shown in Figure 6.7. No gamma-emitting radionuclides attributable to VYNPS operations were detected in any of the samples. _ = _ _ ._ . _ . - - . _ _ _ _ _ . . . _ l I For each sampling site, the monthly samples were composited into quarterly l samples for Tritium (H 3) analyses. None of the samples conta!.ned j detectable quantities of H 3. i l 1 6.5.2.2 Ground Water 1 Quarterly ground water samples were collected from two indicator locations (only one is required by VYNPS Technical Specifications) and one control location during 1993. Table 5.1 and Figure 6.8 show that gross-beta measurements were positive in most samples. This is due to naturally-occurring radionuclides in the water. The levels at all sampling locations, including the higher levels at station WG 11, were consistent with that detected in previous years. The one exception to this was the May 14, 1992 sample from WG-12, which had a higher gross-beta concentration than normal for that location. This was possibly explained by the incorrect addition of preservative chemicals. A re sample on June 29 showed a gross-beta concentration typical for that location. No gamma-emitting radionuclides or Tritium (H-3) were detected in any of the samples. 6.5.2.3 Sediment Semiannual sediment grab samples were collected from two locations during 1993. A single sample was collected from SE-11 on June 2 and again on October 13. Forty (40) grab samples were collected from a gridded area at the North Storm Drain Outfall (SE 12) on the same dates. As wou.d be . expected, naturally occurring K 40 and Ac Th-228 vere detected in all samples. Naturally-occurring Be 7 was detected in five samples. In addition to the above radionuclides, Cs 137 was detected in all samples, as was expected. The levels measured at both locations were consistent with what has been measured in the previous several years and with that detected at other New England locations that are monitored as part of other Yankee-affiliated environmental monitoring programs. This Cs-137 is attributed to nuclear weapons testing fallout that has persisted in the environment. This is further substantiated by the fact that there has only been one liquid release from Vermont Yankee during the period 1982 through 1993. No Cs-137 was detected in the sample of that release water. Co-60 was also detected in 13 of the 80 samples from station SE-12. This radioactivity is due to plant operations and is localized within a small area near the west shore of Vernon Pond. Its presence has been monitored for several years.
.l.
It should also be noted that the mean values in Table 5.1 are weighted heavily toward station SE-12, since 80 of the 82 samples collected in 1993 were from that location. No Co-60 has bcLn detected at station SE-11, which is downstream of the plant discharge structure and the North Storm Drain Outfall (SE-12). l -j I f Storm Drains l- 6.5.2.4 1 [ ( During 1993, several grab samples of water collected from the on-site storm [ drain system at Vermont Yankee (specifically, from the South Storm Drain i W-10) showed detectable levels of H-3. More specifically, the monthly water samples collected in June, July and August of 1993 showed H-3 concentrations from 520 to 780 pCi/kg. A tt mary of these values is given in Table 5.1. Although Reporting Levels are used for off-site samples collected in the surrounding environs, and not for on-site samples collected inside the storm drains, they were nonetheless used to evaluate ) the concentrations detected in the storm drains. None of the detected I concentrations of H-3 exceeded the environmental Reporting Levels. An ongoing investigation is being carried out to attempt to determine the source of these low levels of H-3. l 6.5.3 Investion Pathways 6.5.3.1 Milk Milk samples from cows or goats at several local farms were collected monthly during 1993. Semimonthly collections were made during the " pasture season" since the milking cows or goats were identified as being fed pasture grass during that time. Each sample was analyzed for I-131 and other gamma-emitting radionuclides. Quarterly composites (by location) were analyzed for Sr-89 and Sr-90 As was expected, naturally-occurring K-40 was detected in all samples. Also expected were Cs-137 and Sr-90. Cs-137 was detected in 14 out of 81 indicator samples. Sr-90 was detected in 7 out of 19 indicator samples. Although both Cs-137 and Sr-90 are a by-product of plant operations, the levels detected in milk are due to worldwide fallout from nuclear weapons tests, and to a much lesser degree from fallout from the Chernobyl incident. These two radionuclides are present throughout the natural environment as a result of atmospheric nuclear weapons testing that started } primarily in the late 1950's and continued through 1980. They may be found f in soil and vegetation, as well as anything that feeds upon vegetation, i directly or indirectly. The Cs-137 and Sr-90 levels shown in Table 5 1 and Figures 6.9 and 6.10 are consistent with thosa detected at other New 1 England farms that are monitored as part of other Yankee-affiliated environmental monitoring programs. It should be noted here that most of the Cs-137 concentrations and many of the Sr-90 concentrations shown on Figures 6.9 and 6.10, respectively, are considered "not detectable." All values have been plotted, regardless as to whether they were considered statistically significant. ! As shown in these figures, the levels are also consistent with those detected in previous years near the VYNPS plant. There is also little difference in concer.trations between farms, with one exception. The goat milk from TM-12 generally has had elevated levels of Cs-137 and to a lesser degree, Sr-90 relative to the other loc,c3ons. It has been shown in the past that fallout-related Cs-137 and Sr-90 in cow or goat milk can vary substantially from one farm to the next, due primarily to the differences in feeding habits of the animals. It is also known that goats have a much higher transfer coefficient from vegetation to milk for strontium and cesium. This means that for a given amount of Cs-137 or Sr-90 in the vegetation, the concentration in the milk will typically be higher for a goat than for a cow (Reference 5). 6.5.3.2 Silare A silage sample was collected from each of the required milk sampling stations between October 19 and October 21. Each of these was analyzed for gamma-emitting radionuclides. As expected with all biological media, naturally-occurring K-40 was detected in all samples. Naturally-occurring Be-7 was also detected in many samples. No gamma-emitting radionuclides were detected in the silage samples. 6.5.3.3 Mixed Crass Mixed grass samples were collected at each of the air sampling stations on three occasions during 1993. As expected with all biological media, naturally-occurring K-40 was detected in all samples. Naturally-occurring Be-7 was also detected in most samples. Cs-137 was detected in two indicator samples: 364 i 11 pCi/kg at station TG-12 on August 25, and 23.2 i 6.7 pCi/kg at station TG-14 on the same date. Although Cs-137 is a by-product of plant operations, the levels detected in grass are due to worldwide fallout from nuclear weapons tests, and to a much lesser degree from fallout from the Chernobyl incident. These two radionuclides are present throughout the natural environment as a result of atmospheric nuclear weapons testing that started primarily in the late 1950's and continued through 1980. They may be found.in soil and vegetation, as well as anything that feeds upon vegetation, directly or indirectly. The Cs-137 levels in grass shown in Table 5.1 are consistent with those detected at other New England locations that are monitored as part of other Yankee-affiliated environmental monitoring program. The August 25 concentration at station TG-12 is somewhat higher than typically detected. It should be noted that when the August 25 collections were done, the area around the TG-12 sample site had recently been mowed, leaving no vegetation to sample. The sample was collected nearby in a small wooded picnic area. Since concentrations are expected to vary in vegetation samples, especially when taken from different soil / humus types, and since no airborne Cs-137 was detected at the continuous air sampler located at this location (nor at any of the other air monitors), this Cs-137 is deemed to originate from nuclear weapons testing fallout. The August 25 concentration at station TG-14 is consistent with levels detected in previous years in the Vermont Yankee environs. 6.5.3.4 Fish Semiannual samples of fish were collected from two locations during 1993. In May, yellow perch and smallmouth bass were collected from both Vernon Pond (FH-11) and at the upstream Rt. 9 Bridge (FH-21). In October, yellow perch and largemouth bass were collected from FH-11 and smallmouth bass and rock bass were collected from FH-21. The edible portions of each of these were analyzed for gamma-emitting radionuelldes. As expected in biological matter, naturally-occurring K-40 was detected in all samples. I As shown in Table 5.1, Cs-137 was detected in one of the two control samples. This radioactivity is attributed to global nuclear weapons testing fallout. This level of Cs-137 is typical of what has been detected at both the control and indicator stations in previous years, as can be seen in Figure 6.11. No other radionuclides were detected. 6.5.4 Direct Radiation Pathway < ' I Direct radiation was continuously measured at 51 locations surrounding the Vermont Yankee plant with the use of thermoluminescent dosimeters (TLDs). ] These are collected every calendar quarter for readout at the Yankee Atomic Environmental Laboratory. The complete summary of data may be found in I Table 5.3. H l
- - l
. .i I
l -From Tables 5.2 and 5,3 and Figure 6.12, it can be seen that the Inner and Outer Ring TLD mean exposure rates were not significantly different in 1993. This indicates no significant overall increase in direct radiation exposure rates.in the plant vicinity. It can also be seen from these ! tables that the Control TLD mean exposure rate was not significantly different than that at the Inner and Outer Rings. Figure 6.12 also shows an annual cycle at both indicator and control locations. The lowest point of the cycle occurs during the winter months. 'This is due primarily to the attenuating effect of the snow cover on radon emissions and on direct irradiation by naturally-occurring radionuclides in the soil. Differing amounts of these naturally-occurring radionuclides in the underlying soil, rock or nearby building materials result in different radiation levels between one field site and another. Upon examining Figure 6.16, as well as Table 5.2, it is evident that in 1993 station DR-45 had a higher average exposure rate than any other station. This location is on-site, and the higher exposure rates are due to plant operations in the immediate vicinity of the TLDs. There is no significant dose potential to the surrounding population or any real individual from these sources since they are located on the back side of the plant site, between the facility and the river. The same can be said for station DR-46, which has shown higher exposure rates in previous years. l 1
Figure 6.1 Gross-Beta Measurements on Air Particulate Filters Quarterly Average Concentrations 0.16 0.16 Chernobyl
\
0.12- - 0.12 M 0 0 ' E N 0.08- -0.08 ,Q - c U U 1-a. 0.04- - 0.04 I hE"N "Mf Id" [IdpRR 0 . i ,
, . 0 1984 1986 1988 1990 1992 1994
+ Indicator Stations y- Control Station I
1 1 I l l l
Figure 6.2 Gross-Beta Measurements on Air Particulate Filters 0.06 _ 0.06 0.05- '0.05 u - O v 0.04- - 0.04 c) E 0.03- -0.03 s u
~
) o 0.02-x ' [&cxx
.x\
x.
~x x
0.02 m M. & 0.01- x - 0.01 0~ , , O Dec Mar Jun Sep Dec 1993
-& AP-11 River Station No. 3.3 X- AP-21 Spofford Lake, NH L__
l 1 l l I 1 I
l Figure 6.3 Gross-Beta Measurements on Air Particulate Filters 0.06 _ 0.06 O.05- -0.05 u - e u 0.04- -0.04 o - R - O : g 0.03 7 - 0.03
- s 1
& x # - '
da 0.02 2 @ 'X
- .x . .x .
- 0.02 0.01 5 _
a - 0.01
~
0 , , i 3 0 ; Dec Mar Jun Sep Dec 1993
--g- AP-12 N. Hinsdale, NH
.x- AP-21 Spofford Lake, NH Figure 6.4 Gross-Beta Measurements on Air Particulate Filters 0.06 _
0.06 0.05- - 0.05
~
v 0.04- - 0.04 o - E - o : j 0.03- x - 0.03 o \ E u 0.02-x
- xU%
x' xO - 0.02 a j- X. bX N' Mh
~
O.01k Q - 0.01
~
0 , ,
, 0 .,
Dec Mar Jun .Sep Dec 1993 '
-D- AP-13 Hinsdale Substation
- x. AP-21 Spofford Lake, NH l
l 4 Figure 6.5 Gross-Beta Measurements on Air Particulate Filters 0.06 , 0.06 0 . 0'5 ' - 0.05 w - 0 u 0.04- - 0.04 0 - E -
~
U j 0.03- g -0.03 d *
- x. .
u 0.02- g%x 3 .X .
.X, b - 0.02 Q. -
Y]
- 0.01- x - 0 . 01 -
0~ ,
, , , O Dec Mar Jun Sep Dec 1993
-ty- AP-14 Northfield, MA
-x. AP-21 Spofford Lake, NH l
l i 1 l i
q ... Figure 6.6 Gross-Beta Measurements on Air Particulate Filters 0.06 _ 0.06
~
0.05- -- 0 . 0 5 u - 0 ~ u 0.04- -- 0 . 0 4 o - H - O . j 0.03- g - 0.03 a
.X .
0.01 g -- 0 . 01
~
0 , , i.
, O Dec Mar Jun Sep Dec 1993
--c- AP-15 Tyler Hill Road x AP-21 Spofford Lake, NH 1
m Figure 6.7 Gross-Beta Measurements on River Water Semi-Annual Average Concentrations 16 16 1 14 14 _ _ 12- -12 10- -10 3 ~
) 8- -8 U
CL : - 6- -6 4- 14 2 [gk Ow@dg -2 0~ ,
, 0 1/1/84 1/1/86 1/1/88 1/1/90 1/1/92 1/1/94
-g-- WR-11 River Station No. 3.3
+ WR-21 Rt.9 Bridge I
l
Figure 6.8 Gross-Beta Measurements on Ground Water Semi-Annual Average Cor.centrations I 16 16 14 -14
~
12- -12 i
; Deeper well ]
installed - 10- -10 E b & 6- D 6 4- ' _4 2 0~
/N -
w/ , , ,
-2 o
1/1/84 1/1/86 1/1/88 1/1/90 1/1/92 1/1/94
-g- WG-ll Plant Well
-g-- WG-12 Vernon Nursing Well x WG-21 Brattleboro CC 9- WG-22 Skibniowsky Well l
1
n. Figure 6,9 Cesium-137 in Milk Annual Average Concentrations 20 20 15- -15
, 10- -10 .x N - .a .
O _ 5 -- -5
- M "
0-
& --y N Y- =
.Y R~MA::p -0
~
-5 i , , i i -5 1983 1985 1987 1989 1991 1993
-g-- TM-11 Miller (cow)
-o-- TM-12 Dominick (goat)
-p TM-14 Brown (cow)
- c. TM-15 Gayland Farm (cow)
-y- TM-16 Tall Oaks /Meadowerest (cow) x TM-24 County Farm (control)
Figure 6.10 Strontium 90 in Milk Annual Average Concentrations l 10 10 8- -8
, 6- -6 'I a -
1 N - 4- \ -4 .
-2 2f %g _ g 9 .
W -R
~
0 ; i i i 0 1983 1985 1987 1989 1991 1993 i
--g- TM-11 Miller (cow)
-o- TM-12 Dominick (goat)
%- TM-14 Brown (cow)
-er- TM-15 Gayland Farm (cow)
--v - TM-16 Tall Oaks /Meadowcrest (cow) x TM-24 County Farm (control) -
L L-l i
I 1 Figure 6.11 Cosium-137 in Fish Annual Average Concentrations i l l 140 140 1 (
~
I i 120- - 120 I
~
l 100- -100
~
3 80- -80 ; i
.M - ) -
U - A 60- - 60 j 40 _. 4 0
~
20- - ; --
-20 0-- , , , , , , , , , 0 84 85 86 87 88 89 90 91 92 93 Year E FH-11 Vernon Pond
[ FH-21 Rt. 9 Bridge (Control) l l
Figure 6.12 Exposure Rate at Inner Ring, Outer Ring and Control TLD'S 20 20 15-u -
-15 c
o - Z _ 4 ~ 0 A 10-- -10 x o _
'y _
.x 'x, '
iM-Y ' NN 5- 'X
-5 e
0 , , , ,
, 0 1989 1990 1991 1992 1993 1994 Retrieval Date
-A- Inner Ring
- Outer Ring l -y- Control i
l l ms
Figure 6.13 Exposure Rate at Indicator TLDS, DR 01-03 20 20 15- -15 4 - o o Z "_ 4 o G 10- -10 cc
!\^
O b : ^ yP N: E 5-b g'
\/ b -
-5 .
0 , , ,
, ,,,,,,. 0 <
1989 1990 1991 1992 1993 1994 Retrieval Date
--g- DR-01 River Station No. 3.3 y DR-02 North Hinsdale, NH t DR-03 Hinsdale Substation I
-l
'l l
1
Figure 6.14 Exposure Rate at Indicator TLDS, DR 04, 06, 50 20 20 e: 15- -15
~
e ~ e u - 0) a 10- -10 t4 . 1 D 0 , , ,
, , , 0 1989 1990 1991 1992 1993 1994 Retrieval Date
-c- DR-04 Northfield, MA
-x- DR-06 Vernon School DR-50 Gov. Hunt House
A d --- # 4 1 l l 1 Figure 6.15 l Exposure Rate at Indicator TLDS, DR 07-08, 41-42 ' 20 20
~
15- -15 u - o - x ' W ~ O a 10- p. -10 cr: o _ 5- -5 ee e 0 , ,
, , , 0 i
1989 1990 1991 1992 1993 l'994 Retrieval Date 9 DR-07 Site Boundary v DR-08 Site Boundary , w- DR-41 Site Boundal.y
- c-- DR-42 Site Boundary +
l
l 1
)
-1 Figure 6.16 j Exposure Rate at Site Boundary TLDS, DR 43-46 i 60 60 50- -50 Low level waste on-site storage.
u g 40- \ -40 x 4
~
4 O R 30- -30 a: . i ~ O N A 3 20- A -20 a / x
/ b' s
~
[,e=aggevewNws gd~ e 0 , , ,
,,,,,,,,,,,,r,' 0 1989 1990 1991 1992 1993 1994 Retrieval Date
-O- DR-43 Site Boundary v DR-44 Site Boundary
--a- DR-45 Site Boundary
-r DR-46 Site Boundary i
b
I Figure 6.17 Exposure Rate at Site Boundary TLDS, DR 47-49, 51 20 20 15- -15 u - a o - 4 0 a 10- -10 a:
$! Q'W""M W4 5- -5 0 --
i i i i 0' 1989 1990 1991 1992 1993 1994 , Retrieval Date DR-47 Site Boundary x DR-48 Site Boundary
-A- DR-49 Site Boundary
-o- DR-51 Site Boundary l
I
i I l Figure 6.18 Exposure Rate at Inner Ring TLDS, DR 09-15 (Odd) 20 20 m 15- -15 4 - O - x _ W ^ Q) a 10- -10 cr; - I o - X 0 , , ,
, 0 1989 1990 1991 1992 1993 1994, ;
Retrieval Date
-e- DR-09 Inner Ring x
DR-11 Inner Ring
-4 DR-13 Inner Ring
- c. DR-15 Inner Ring 4
p l I i Figure 6.19 ! Exposure Rate at Inner Ring TLDS, DR 17-23 (Odd) 20 20 15- -15
~
e _ u o a 10- -10 cc _ N 5- -5 0 , , , i er , , , ,
, 0 1989 1990 1991 1992 1993 1994 Retrieval Date
--t3- DR-17 Inner Ring
-e DR-19 Inner Ring
-g- DR-21 Inner Ring
- c. DR-23 Inner Ring 1
l Figure 6.20 Exposure Rate at Inner Ring TLDS, DR 25-31 (Odd) 20 20 15- -15 u - a
- O u -
.0 a 10- -10 a: I NO N 5- -5 m 0 . , r' ' ' i i
, 0 1989 1990 1991 1992 1993 1994 Retrieval Date
-g- DR-25 Inner Ring
-r DR-27 Inner Ring
--g-- DR-29 Inner Ring
--e DR-31 Inner Ring l
l l Figure 6.21 Exposure Rate at Inner TLDS, DR 33-39 (Odd) 20- 20 we 15 ._ -15 u 5 -
- n W -
c) (L 10- -10 a: _ l
~
_ d h i k' - 5- -5 0 ,, , i i i i i 0 1989 1990 1991 1992 1993 1994 Retrieval Date
--c- DR-33 Inner Ring w- DR-35 Inner Ring z3 DR-37 Inner Ring c DR-39 Inner Ring 1
I Figure 6.22 Exposure Rate at Outer Ring TLDS, DR 10-16 (Even) j 20 20 15- -15 u - a O - - x _ W g . a 10- -10 m . ~ O he - q, Y _ 5- N N Y 5 0 , , r- , i
,0 1989 1990 1991 1992 1993 1994 Retrieval Date
-{y DR-10 Outer Ring
-r DR-12 Outer Ring e DR-14 Outer Ring c DR-16 Outer Ring
)
Figure 6.23 Exposure Rate at Outer Ring TLDS, DR 18-24 (Even) 20 20 15- -15
~
o - 'd a 10_ -10 m _ 5- -5 0 ,
, 0 1989 1990 1991 1992 1993 1994 Retrieval Date
-D-- DR-18 Outer Ring I
m- DR-20 Outer Ring ;
-A- DR-22 Outer Ring l
- c. DR-24 Outer Ring
l Figure 6.24 Exposure Rate at Outer Ring TLDS, DR 26-32 (Even) 20 20 ms 9 15- -15 u 5 - x . W e a 10- -10 a:
~
f MEIMEN# * - Y 5- -5 en
~
0 , ,
,0 1989 1990 1991 1992 1993 1994 Retrieval Date
-c-- DR-2 6 Outer Ring x DR-28 Outer Ring e DR-30 Outer Ring
+ DR-32 Outer Ring
-7 6 -
f Figure 6.25 Exposure Rate at Outer Ring TLDS, DR 34-40 (Even) 20 20 15- -15
~
O _ u - O A 10- -10 c: _ g # N' ' ' ' E .% g-5- -5 0 ,
, , , ,LO 1989 1990 1991 1992 1993 1994 Retrieval Date
-e- DR-34 Outer Ring x DR-36 Outer Ring
%- DR-38 Outer Ring c DR-40 Outer Ring Y - - . +
J Figure 6.26 Exposure Rate at Control TLD, DR-05 20 20 15- -15 u h . . Z _ k - 0 G 10- -10 M . t 0 ed ,
~ T4 5- -5 0 ,,, ,
, 0 .
1989 1990 1991 1992 1993 1994 Retrieval Date
-g- DR-05 Spofford Lake, NH k
I l i
l
- 7. QUALITY-ASSURANCE PROGRAM The quality assurance program at the Yankee Atomic Environmental Laboratory is designed to serve two overall purposes: 1) Establish a measure of confidence in the measurement process to assure the licensee, regulatory agencies and the public that the analytical results are accurate and precise; and 2) Identify deficiencies in the sampling and/or measurement process to those responsible for these operations so that corrective action can be taken. Quality assurance is applied to all steps of the measurement process, including the collection, reduction, evaluation and reporting of data, as well as the record keeping of the final results. Quality control is a part of the quality assurance program. It provides a means to control and measure the characteristics of measurement equipment and processes, relative to established requirements.
The Yankee Atomic Environmental Laboratory employs a thorough quality assurance program to ensure reliable environmental monitoring data. The program includes the use of written, approved and controlled procedures for all work activities, a nonconformance and corrective action tracking system, systematic internal audits, audits from external groups, a laboratory quality control program, and a complete training and retraining system. The Intralaboratory Quality Control program at the Laboratory and the EPA third party interlaboratory program are discussed in more detail below. Also discussed is the environmental TLD quality assurance program and the blind duplicate quality assurance program conducted by the Laboratory Quality Control Audit Committee. 7.1 Intralaboratory Ouality Control Pronram The Yankee Atomic Environmental Labcratory conducts an extensive intralaboratory quality control program to assure the validity and reliability of non-TLD analytical data. Included are the internal process control program and the National Institute of Standards and Technology (NIST) Measurement Assurance Program. These together comprise about five percent of the laboratory sample throughput. The records of the quality control program are reviewed by the responsible cognizant individual, and corrective measures are taken whenever applicable. For the internal process control program and the NIST Measurement Assurance Program, there were 334 analyses for accuracy and 179 for precision in 1993. Of the 334 analyses for accuracy reviewed during this period, 95.2% met the Laboratory acceptance criteria for accuracy, while 4.8% (16 out of l I l 1 1
334 analyses) were identified as cucside the Laboratory acceptance criteria. Of the 179 analyses for precision during 1993, 99.4% met the Laboratory acceptance criteria for precision, while 0.6% (1 out of 179 analyses) were identified as outside the YAEL acceptance criteria. Table ! 7.1 shows a summary of the results of this program. 7.2 EPA Intercomnarison Prorram To further verify the accuracy and precision of the Laboratory analyses via an independent outside third party, the Yankee Atomic Environmental Laboratory participates in the U.S. Environmental Protection Agency's Environmental Radioactivity Laboratory Intercomparison Studies Program for those available species and matrices routinely analyzed by the Laboratory. Participation in this program is required by VYNPS Technical Specification 3.9.E. Each sample supplied by the EPA is analyzed in triplicate, and the results are returned to the EPA within a specified time frame. When the I l know values are returned to the Laboratory, the Laboratory and EPA results are then evaluated against specific Laboratory and EPA acceptance criteria. , When the results of the cross-check analysis fall outside of the control limit, an investigation is made to determine the cause of the problem and corrective measures are taken, as appropriate. Results of this program are provided in this report in compliance with Technical Specification 4.9.E. For the EPA Intercomparison Program, there were 129 analyses for accuracy on 23 sample sets. The samples consisted of water, milk and air particulate filters. The analyses were for gamma-emitting radionuclides, gross-beta, strontium, iodine, plutonium and tritium. Tables 7.2 and 7.3 summarize the results for 1993. Of the 129 analyses for accuracy, all but two met the EPA mean value control limits, The results of the two measurements that did not meet the EPA mean value criteria are given below:
- For the set of Ba-133 measurements for the water sample with EPA Reference Date of 6/11/93, the YAEL mean value of 59.36 pCi/L fell-below of the EPA control limit of 81.7-116.3 pCi/L. This radionuclide is not in the gamma software library. Consequently, the Ba-133 results for the EPA sample set were calculated manually using the 356 kev photopeak. A review of the sample paperwork indicated that the hand.
calculated radioactivity concentrations did not incorporate the 60 percent gamma rny abundance factor required for the 356 kev photopeak. A recalculation of the Ba-133 activity concentration using this factor
}.
yielded a mean value within the EPA control limits, e For the set of Ru-106 measurements for the water sample with EPA Reference Date of 11/12/93, the YAEL mean value of 165.53 pCi/L fell below the' EPA control limit of 166.3-235.7 pCi/L. The YAEL considers the EPA known value to be suspect since the grand mean of 175.18 pCi/L is 12.8 percent below the EPA stated known value of 201 pCi/L. Assuming the grand mean is the actual activity concentration, the YAEL mean result of 165.53 pCi/L would have a bias difference of only -5.5 , percent. A subsequent internal process check analysis of an EPA Ru-106 standard supplied by the EPA to validate the process indicated a mean value within 2 percent of the known. The process is considered in compliance at this time. 7.3 Environmental TLD Ouality Assurance Prorram The Panasonic environmental TLD (thennoluminescent dosimeter) program st the Yankee Environmental Laboratory has its own quality assurance program. In addition to instrumentation checks performed by the Dosimetry Services Group (DSG), which represent approximately 10% of the TLDs processed, two independent test programs are performed for accuracy and precision. The first of these programs is performed by the in-house Dosimetry QA Officer, and the second involves the University of Michigan third-party testing program. Under these programs, dosimeters are irradiated to known doses (unknown to the DSG) and given to the DSG for read-out. In 1993, out of 1525 TLDs processed at the Yankee Environmental Laboratory, 8.3% (126 TLDs) were processed as part of the performance testing program. Of these 126 TLDs, 72 were from the in-house Dosimetry QA Officer, 18 were from the Battelle Pacific Northwest Laboratories testing program, and 36 were from Boston Edison Co. All of these (100%) met the acceptance criteria for accuracy and precision. 7.4 Elind Duplicate Ouality Assurance Program The Laboratory Quality Control Audit Committee (LQCAC) is comprised of one member from each of the five power plants that are serviced by the Yankee Atomic Environmental Laboratory. Two of the primary functions of the LQCAC are to conduct an annual audit of Laboratory operations and to coordinate the Blind Duplicate Quality Assurance Program. Under the Blind Duplicate i Quality Assurance Program, paired samples are submitted from the five ; I I
-
- _ _ , - _ _ _ _ _ _ _ . - _ _ _ _ _ _ _ _ w _-
I plants, including VYNPS. They are prepared from homogeneous environmental media at each respective plant, and are sent to the Laboratory for analysis. They are " blind" in that the identification of the matching sample is not identified to the Laboratory. The LQCAC analyzes the results of the paired analyses to evaluate precision in Laboratory measurements. l A total of 50 paired samples were submitted under this program by the five participating plants during 1993. Paired measurements were evaluated for 26 gamma emitting radionuclides, H-3, Sr 89, Sr-90, I-131 and gross-beta. All measurements were evaluated, whether the results were considered statist.ically positive or not, and whether the net concentration was positive or negative. Of the 1308 paired duplicate measurements evaluated in 1993, 1305 (99.8%) fell within the established acceptance criteria. With the three paired measurements that did not meet the acceptance criteria, none had radioactivity that was considered statistically positive. The samples submitted through this program are listed in Table 7.4. i
TABLE 7.1
SUMMARY
OF PROCESS CONTROL ANALYSIS RESULTS January - December 1993 ACCURACY PRECISION SAMPLE MEDIA NUMBER NUMBER ANALYSES ANALYSES NUMBER OF OUTSIDE NUMBER OF OUTSIDE ANALYSES ACCEPTANCE ANALYSES ACCEPTANCE CRITERIA CRITERIA AIR CHARCOAL Gamma 104 1 0 0 AIR FILTER-Beta 103 0 16 0 Gamma 0 0 0 0 Strontium 0 0 0 0 MILK Gamma 30 0 33 0 Iodine 20 3 20 0 Strontium 16 4 16 0 UATER Gross-Beta 9 1 9 0 Camma 3 0 3 0 Iodine 11 1 11 0 Strontium 16 1 16 0 Tritium 13 0 12 0 SOIL / SEDIMENT Gamma 0 0 30 0 TOTAL 325 11 166 0 l I
TABLE 7.2 EPA INTERCOMPARISON ANALYSIS RESULTS January - December 1993 EPA Ref. Sample Nuclide YAEL EPA Date Type Mean Control i (pCi/1) Limits (pci/1) 10-20-92 Water Co-60 13.54 6.30 23.70 Cs-134 5.06 0.00-13.70 Cs-137 7.56 0.00-16.70 10-20-92 Water Sr-90 13.27 1.30-18.70 1-15-93 Water Sr-89 12.11 6.30-23.70 Sr-90 9.03 1.30-18.70 1-22-93 Water Pu-239 18.77 16.50 23.50 2-5-93 Water I-131 109.43 82.70-117.30 4-20 93 Water Co-60 38.70 30.30-47.70 Cs-134 25.83 18.30-35.70 Cs-137 31.60 23.30 40.70 6-4-93 Vater H-3 10603.1 8136.80-11551.2 6-11-93 Water Cs 134 5.05 0.00-13.70 Ru-106 99.54 98,20 139.80 Cs-137 4.62 0.00-13.70 Zn-65 107.15 85.70-120.30 Co 60 13.82 6.30-23.70 Ba-133 59.36* 81.70 116.30 7-23-93 Water Beta 42.32 31.00-55.00 8-27-93 Part. Filter Beta 46.24 38.30-55.70 .l
- This mean value did not meet the EPA Control Limits. See text for explanation. )
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I I TABLE 7.2, continued ) EPA INTERCOMPARISON ANALYSIS RESULTS January - December 1993 EPA Ref. Sample Nuclide YAEL EPA Date Type Mean Control (pCi/1) Limits (PCi/1) 8-27-93 Part. Filter Sr-90 18.84 10.30-27.70 8-27-93 Part. Filter Cs-137 9.07 0.30-17.70 9-24-93 Milk 1-131 119.73 99,20-140.80 Cs-137 40.02 40.30-57.70 9-24-93 Milk I-131 125.96 99.20-140.80 9-24-93 Milk Sr-89 27.91 21.30-38.70 Sr-90 22.75 16.30-33.70 9-24-93 Milk K-40 1411.37 1278.77-1521.80 10-8 93 Water I-131 118.49 96.20-137.80 10-8-93 Water I-131 121.81 _, 96.20 137.80 10 19 93 Water Sr-89 12.59 6.30-23.70 Sr 90 8.85 1.30-18.70 10-19-93 Water Co-60 9.86 1.30-18.70 Cs-134 10.09 3.30-20.70 Cs-137 10.72 1.30-18.70 10 29-93 Water Beta 17.10 6 30 23.70 11-5-93 Water H-3 7164.08 6114.10-8681.90 11-12-93 Water Co-60 29.94 21.30-38.70 Zn 152.32 124.00-176.00 Ru-106 165.53* 166.30-235,70 Cs-134 57.10 50.30-67.70 Cs-137 41.85 31.30-48.70 Ba-133 79.97 65.10 92.90
- This mean value did not meet the EPA Control Limits. See text for explanation.
d TABLE 7.3
SUMMARY
OF EPA INTERCOMPARISON RESULTS January - December 1993 NO. OF NO. OUTSIDE SAMPLE MEDIA SAMPLES NO. OF EPA CONTROL ANALYZED
- ANALYSES LIMITS **
AIR FILTER Beta 1 3 0 0 ; Camma 1 3 Strontium 1 3 0 ; MILK Camma 1 9 0 Iodine 1 3 0 Strontium 1 6 0 VATER Cross-Beta 2 6 0 Camma 5 66 2 Iodine 2 6 0 Plutonium 1 3 0 Strontium -4 15 0 Tritium 2 6 0
- The number of EPA samples that were analyzed for the specified radionuclide. . Each of these samples was analyzed in triplicate.
** The number of mean values (from triplicate samples) outside EPA Control Limits.
TABLE 7.4
SUMMARY
OF BLIND DUPLICATE SAMPLES SUBMITTED January - December 1993 TYPE OF SAMPLE NUMBER OF PAIRED SAMPLES SUBMITTED Cow Milk 20 Cround Water 7 - River Water 4 Estuary Water- 4 Sea Water 8 Irish Moss 2 Mussels 4 Food Product - 1 Cranberries TOTAL 50 4
- 8. LAND USE CENSUS VYNPS Technical Specification 3/4.9.D requires that a Land Use Census be conducted annually between the dates of , June 1 and October 1. The Census identifies the locations of the nearest milk animal and the nearest residence in each of the 16 meteorological sectors within a distance of five miles of the plant. It also identifies the nearest milk animal (within three miles of the plant) to the point of predicted highest annual average D/Q value in each of the three major meteorological sectors due to elevated releases from the plant stack. The 1993 Land Use Census was conducted in accordance with the above Technical Specifications.
Immediately following the collection of field data, in compliance with Technical Specification 6.7.C.1.b, a dosimetric analysis is performed to compare the census locations to the " Critical Receptor" identified in the Offsite Dose Calculation Manual (ODCM). This Critical Receptor is the location that is used in the conservative Method 1 dose calculations found in the ODCM (i.e. the dose calculations done in compliance with Technical Specification 4.8.G.1). If a Census location has a 20% greater potential dose than that of the Critical Receptor, this fact must be announced in the l Semiannual Effluent Release Report for that period. A re-evaluation of the j Critical Receptor would also be done at that time. For the 1993 Census, r.o such locations were identified. Pursuant to Technical Specification 3.9.D.2, a dosimetric analysis is then perfonned, using site specific meteorological data, to determine which milk animal locations would provide the optimal sampling locations. If any location has a 20% greater potential dose commitment than at a currently. ; sampled location, the new location is added to the routine environmental ] sampling program in replacement of the location with the lowest calculated ! l dose (which is eliminated from the program). For the 1993 Census, two such milk animal locations were identified. These were the Mitchell and Meadowerest locations. Due to the small number of goats owned at the Mitchell location, the owner has not been able to provide samples of sufficient size on a regular basis. Consequently, this location was not added to the milk sampling program. The Meadowerest (TM-16) farm, however, replaced the Blodgett farm (TM-18) in the milk sampling program as defined in Table 4.1 of the ODCM. The Blodgett farm continued to be sampled, however, as a "non-Tech. Spec" station. The results of the 1993 Land Use Census are included in this report in compliance with Technical Specifications 4.9.D.1 and 6.7.C.3. The locations identified during the Census may be found in Table 8.1.
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TABLE 8.1 1993 LAND USE CENSUS LOCATIONS
- SECTOR NEAREST RESIDENCE NEAREST MILX ANIMAL Km (Mi) Km (Mi)
N 1.6 (1.0) ---- NNE 1.6 (1.0) 4.0 (2.5) Cows NE 1.3 (0.7) ---- ENE 0.97 (0.6) ---- E 0.97 (0.6) ---- ESE 2.8 (1.75) ---- SE 1.8 (1.1) 3.4 (2.1) Cows SSE 2.0 (1.3) ---- S 0.5 (0.3) 2.1 (1.3) Cows SSW 0.5 (0.3) ---- SV 0.5 (0.3) ---- WSW 0.5 (0.3) ---- W 0.5 (0.3) ---- WNW 0.6 (0.4) 0.8 (0.5) Cows , NW 1.2 (0.8) 4.4 (2.7) Cows ** tanJ 2.1 (1.3). ----
- Sector and distance relative to plant stack,
** This location overlaps the NW and WNW sectors.
I l
- 9. S0000ARY During 1993, as in all previous years of plant operation, a program was conducted to assess the levels of radiation or radioactivity in the Vermont Yankee Nuclear Power Station environment. Over 750 samples were collected (including TLDs) over the course of the year, with a total of over 7500 radionuclide or exposure rate analyses being performed on them. The samples included ground water, river water, soil, sediment, fish, milk, silage and mixed grass. In addition to these samples, the air surrounding the plant was sampled continuously and the radiation levels were measured continuously with environmental TLDs.
Low levels of radioactivity from three sources were detected in samples collected off-site as a part of the radiological environmental monitoring program. Most samples had measurable levels of K-40, Be-7, AcTh-228 or radon daughter products. These are the most common of the naturally-occurring radionuclidos. Many samples (milk, sediment, mixed vegetation and fish in particular) had fallout radioactivity from atmospheric nuclear weapons tests conducted primarily from the late 1950's through 1980. Several samples had low levels of radioactivity resulting from emissions from the Vermont Yankee plant. These were all collected in the immediate vicinity of the plant or from on-site locations. In all cases, the possible radiological impact was negligible with respect to exposure from natural background radiation. In no case did the detected levels exceed the most restrictive federal regulatory or plant license limits for radionuclides in the environment. r
- 10. REFERENCES
- 1. USNRC Radiological Assessment Branch Technical Position, "An Acceptable Radiological Environmental Monitoring Program,"
Revision 1, November 1979.
- 2. NCRP Report No. 94, Exoosure of the Pooulation in the United States and Canpda from Natural Backcround Radiation, National Council on Radiation Protection and Measurements, 1987.
- 3. Ionizine Radiation: Sources and Biological Effects, United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR), 1982 Report to the General Assembly.
- 4. Kathren, Ronald L., Radioactivity and the Environment - Sources.
Distribution. and Surveillance, Harwood Academic Publishers, New York, 1984.
- 5. Till, John E. and Robert H. Meyer, ed., Radiological Assessment -
A Textbook on Environmental Dose Analysia, NUREG/CR-3332, U.S. Nuclear Regulatory Commission, Washington, D.C., 1983. 1 i 1 1}}