ML20082R320
| ML20082R320 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 12/31/1994 |
| From: | Tremblay L VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| BVY-95-48, NUDOCS 9505020044 | |
| Download: ML20082R320 (94) | |
Text
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VERMONT YANKEE '
NUCLEAR POWER CORPORATION -
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. Ferry Road, Brattleboro, VT 05301-7002
,tEPLY TO ENGINEERING OFFICE 680 MAIN STREET
- BOLTON, MA 01740 (508) 779-6711
'I April 28,1995 BVY 95 - 48 ;
1 United States Nuclear Regulatory Commission ,
ATrN: Document ControlDesk i Washington, DC 20555
References:
- a. License No. DPR-28 (Docket No. 50-271)
Subject:
1994 Vermont Yankee Annual Radiological Environmental Surveillance Report Faclosed please find one copy of the Annual Radiological Environmental Surveillance Report for Veir:.t tankee Nuclear Power Station, submitted in accordance with Technical Specification :
6.7.C.3. 'Ihis report contains a sununary and analysis of the radiological environmental data collected for the calendar year 1994.-
Should you have any questions regarding this submittal, please contact this office. :
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Sincerely, VERMONT YANKEE NUCLEAR POWER CORPORATION
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Leonard A. Tremblay, Jr., P.E.\
SeniorLicensing Engineer 1 cx:: USNRC Region I Administrator USNRC Resident Inspector- VYNPS USNRC Project Manager- VYNPS 9505020044 9 I P - o=41231ow f6 , ,
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ANNUAL Q&x) RADIOLOGICAL
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t;j. ENVIRONMENTAL SURVEILLANCE REPORT I
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s l 1,994 Vermont Yankee Nuclear Power Corporation Vermont Yankee Nuclear Power Station Vernon, Vermont
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VERMONT YANIEE NUCLEAR POWER STATION
- NNUAL RADIOIAGICAL ENVIROlOENTAL SURVIILIANCE REPORT January - December 1994 April 1995 l
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Prepared by:
Yankee Atomic Electric Company Environmental Engineering Department 580 Main Street Bolton, Massachusetts 01740
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TABLE OF COMTENTS i
ZA&E TABLE OF CONTENTS ............................................. 11 LIST OF TABLES ................................................ iii LIST OF FIGURES ............................................... iv 4
- 1. INTRODUCTION ............................................ ..... 1 1
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- 2. NATURALLY OCCURRING AND MAN.MADE BACKGROUND RADIOACTIVITY ..... 2 I
- 3. CENERAL PIANT AND SITE INFORMATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 4
- 4. PROGRAM DESIGN ........... .................................... 6 i
- 5. RADIO 1DGICAL DATA
SUMMARY
TABLES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 26 i
- 6. ANALYSIS OF ENVIRONMENTAL RESULTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 41 t
- 7. QUALITY ASSURANCE PROGRAM ..................................... 75
- 8. LAND USE CENSUS ............................................... 83 r
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SUMMARY
....................................................... 85 j 10. REFERENCES .................................................... 86 l l
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J LIST OF TABLES 1
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. Table I1.111 fa&R l
4.1 Radiological Environmental Monitoring Program ........... 12
- 4.2 Radiological Environmental Monitoring
) Locations (Non-TLD) ................................... 14 4.3 Radiological Environmental Monitoring .
} Locations (TLD) ....................................... 16 a
4 4.4 Environmental Lower Limit of Detection (LLD) i Sensitivity Requirements .............................. 18 4.5 Reporting Levels for Radioactivity Concentrations in Environmental Samples .............................. 19 5.1 Radiological Environmental Program Summary .............. 28 5.2 Environmental TLD Data Summary .......................... 38 5.3 Environmental TLD Measurements .......................... 39 7.1 Summary of Process Control Analysis Results ............. 78 7.2 EPA Intercomparison Analysis Results .................... 79 l 7.3 Summary of EPA Intercomparison Results .................. 81 7.4 Summary of Blind Duplicate Samples Submitted . . . . . . . . . . . . 82 8.1 Land Use Census Locations ............................... 84 l
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LIST OF FIGURES l
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4.1 Radiological Environsental Sampling Incations i in Close Proximity to Plant .............................. 20 t
4.2 Radiological Environmental Sampling locations Within 5 Kilometers of Plant ............................. 21 ;
4.3 Radiological Environmental sampling Incations Creater than 5 Kilometers from Plant ..................... 22 4.4 TLD Monitoring Locations in Close Proximity to Plant ................................................. 23 4.5 TLD Monitoring Locations Within 5 Kilometers [
of Plant ............................................... 24 ,
4.6 TLD Monitoring Locations Greater than 5 Kilometers i from Plant .............................................. 25 6.1 Cross-Beta Measurements on Air Particulate Filters ...... 49 l (Quarterly Averages - Indicator vs. Control) 6.2 Cross-Beta Measurements on Air Particulate Filters ...... 50 :
(AP 11 vs. AP-21 Control) 6.3 Cross-Beta Measurements on Air Particulate Filters ...... 51 3 (AP-12 vs. AP-21 Control) 6.4 Cross-Beta Measurements on Air Particulate Filters ...... 52 I (AP-13 vs. AP-21 Control) ;
1 6.5 Cross-Beta Measurements on Air Particulate Filters ...... 53 (AP-14 vs. AP-21 Control) 6.6 Cross-Beta Measurements on Air Particulate Filters ...... 54 (AP-15 vs. AP-21 Control)
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i LIST OF FIGURES (continued)
J j Figure I1113 Zagg 6.7 Cross Beta Measurements on River Water ................... 55 N
i 6.8 Cross Beta Measurements on Ground Water ................. 56 :
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j 6.9 Cesium-137 in Milk ...................................... 57 6.10 Strontium-90 in Milk .................................... 58 i
j 6.11 Cesium-137 in Fish ...................................... 59 1,
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1 6.12 Exposure Rate at Inner Ring, Outer Ring
- and Control TLDs ....................................... 60 i
6.13 Exposure Rate at Indicator TLDs, DR 01-03 ............... 61 6.14 Exposure Rate at Indicator TLDs, DR 04, 06, 50 .......... 62 '
i i 6.15 Exposure Rate at Site Boundary TLDs, DR 07-08, 41-42 .... 63 a '
j 6.16 Exposure Rate at Site Boundary TLDs, DR 43-46 ........... 64 6.17 Exposure Rate at Site Boundary TIDs, DR 47-49, 51 ....... 65 !
6.18 Exposure Rate at Inner Ring TLDs, DR 09-15 (odd) ........ 66 i
j 6.19 Exposure Rate at Inner Ring TLDs, DR 17-23 (odd) ........ 67 i
6.20 Exposure Rate at Inner Ring TIES, DR 25-31 (odd) . . . . . . . . 68 1
- 6.21 Exposure Rate at Inner Ring TLDs, DR 33-39 (odd) ........ 69 6.22 Exposure Rate at Outer Ring TIJs, DR 10-16 (even) ....... 70 1
! 6.23 Exposure Rate at Outer Ring TLDs, DR 18-24 (even)........ 71 1
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6.24 Exposure Rate at Outer Ring TLDs, DR 26-32 (even)........ 72 i
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i LIST OF FIGURES (continued)
- - ZiE3E1 11111 Zagg i
j 6.25 Exposure Rate at Outer Ring TLDs, DR 34 40 (even)........ 73 1
6.26 Exposure Rate at Control TIS, DR-05 . . . . . . . . . . . . . . . . . . . . . 74 I
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- 1. INTRODUCTION I
! This report susmarizes the findings of the Radiological Environmental l Monitoring Program (REMP) conducted by Vermont Yankee Nuclear Power Corporation in the vicinity of the Vermont Yankee Nuclear Power Station in Vernon, Vermont during the calendar year 1994. 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 i radioactivity and radiation that is detected in the plant environs.
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4 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 Technical Specification requirements for REMP sampling, tables listing all locations sampled or monitored in 1994 with compass sectors and distances from the plant, and maps showing each j REMP location. Tables listing Iower Limit of Detection requirements and Reporting levels are also included.
l j Section 5: Consists of the summarized data as required by VYNPS Technical Specifications. The tables are in the format specified by the i NRC Radiolo8 1 cal Assessment Branch Technical Position on Environmental Monitoring (Reference 1). Also included is a summary of the environmental TLD measurements for 1994.
Section 6: Provides the results of the 1994 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. The results of the EPA j Intercomparison Program are given.
l Section 8: Summarizes the requirements and the results of the 1994 Land Use Census.
Section 9: Gives an overall summary of the results of the 1994 Radiological Environmental Monitoring Program.
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, 2. MRIErally occurrina and tran-Made mackaround n=dioactikrity k Radiation or radioactivity potentially detected in the Vermont Yankee
- environment can be grouped into three categories. The first is " naturally-l occurring" radiation and radioactivity. The second is " man-made"
! radioactivity from sources other than the Vermont Yankee plant. The third I potential source of radioactivity is due to emissions from the Vermont
- Yankee plant. For the purposes of the Vermont Yankee REMP, the first two j categories are classified as " background" radiation, and are the subject of l discussion in this section of the report. The third category is the one that the REMP is designed to detect and evaluate.
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{ 2.1 Naturally Occurrine Backaround Radioactivity i
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{ Natural radiation and radioactivity in the environment, which provide the j major source of human radiation exposure, may be subdivided into three J separate sub categories: " primordial radioactivity", "cosmogenic l radioactivity" and " cosmic radiation". " Primordial radioactivity" is made j 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
j Potassium-40 (K-40), Radium-226 (Ra-226), and Radon-222 (Rn 222).
j Uranium-238 and Thorium-232 are readily detected in soil and rock, whether j through direct field measurements or through laboratory analysis of j samples. Radium-226 in the earth can find its way from the soil into j ground water, and is often detectable there. Radon-222 is one of the
! components of natural background in air, and its daughter products are ;
I detectable on air sampling filters. Potassium-40 comprises about 0.01 l percent of all natural potassium in the earth, and is consequently l l detectable in most biological substances, including the human body. There l are many more primordial radionuclides found in the environment in addition !
, to the major ones discussed above (Reference 2).
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j The second sub-category of naturally-occurring radiation and radioactivity i is "cosmomenic radioactivity". This is produced through the nuclear )
interaction of high energy cosmic radiation with elements in the earth's
} l j atmosphere, and to a much lesser degree in the earth's crust. These j radioactive elements are then incorporated into the entire geosphere and atmosphere, including the earth's soil, surface rock, biosphere, sediments, j ocean floors, polar ice and atmosphere. The major radionuclides in this i
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J category are Carbon-14 (C-14), Hydrogen-3 (H-3 or Tritium), Sodium-22
- (Na-22), and Bery111um-7 (Be-7). Bery111um-7 is the one most rendily detected, and is found on air sampling filters and occasionally in
, biological media (Reference 2).
The third sub-category of naturally-occurring radiation and radioactivity j is " cosmic radiation". This consists of high energy atomic and sub-atomic particles of extra-terrestrial origin and the secondary particles and 3
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.
l Consequently, one can see that with increasing elevation one would be j 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 f gamma spectroscopy equipment, high pressure ion chambers and thermoluminescent dosimeters (TLDs).
5 2.2 Man-Made Backaround 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 cate5ory was the fallout from the Chernobyl accident in April of 1986, which was detected in the Vermont Yankee
! environment and other parts of the world. A much greater contributor to j this catepry, however, has been fallout from atmospheric nuclear weapons
- tests. Tests were conducted from 1945 through 1980 by the United States, the Soviet Union, the United Kingdom, China and France, with the large i majority of testing occurring during the periods 1954-1958 and 1961-1962.
l (A test ban treaty was signed in 19G3 by the United States, Soviet Union and United Kingdom, but not by France and China.) The most recent test, conducted by the People's Republic of China, occurred in October of 1980.
- Much of the fallout detected today is due to this explosion and the last j large scale one, done in November of 1976 (Reference 3),
i The radioactivity produced by these detonations was deposited worldwide.
l The amount of fallout deposited in any given area is dependent on many j factors, such as the explosive yield of the device, the latitude and 4
altitude of the detonation, the season in which it occurred, and the timing 1 of subsequent rainfall which washes fallout from the troposphere (Reference 4). Most of this fallout has decayed into stable elements, but the residue radioactivity is still readily detectable in environmental I
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l samples worldwide. The two predominant radionuclides are Cesium-137 j (Cs-137) and Strontium-90 (Sr-90). They are found in soil and in
! vegetation, and since cows and goats graze large areas of vegetation, these j radionuclides are also readily detected in milk.
I Other potential " man-made" sources of environmental " background" l l radioactivity include other nuclear power plants, coal-fired power plants, I i national defense installations, hospitals, research laboratories and
! industry. These collectively are insignificant on a global scale when
, compared to the sources discussed above (natural and fallout).
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- 3. GENERAL PLANT AND SITE INFORMATION 3 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 3 is generally rural and lightly populated, and the topography is flat or
! gently rolling.
j Construction of the single 540 megawatt BWR (Boiling Water Reactor) plant l began in 1967. The pre-operational Radiological Environmental Monitoring Program, designed to measure environmental radiation and radioactivity 2
levels in the area prior to station operation, began in 1970. Coassercial
- operation began on November 30, 1972.
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- 4. PItOGRAM DESIGN I
The Radiological Environmental Monitoring Program (REMP) for the Vermont Yankee Nuclear Power Station (VYNPS) was designed with specific objectives l in mind. These are:
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To provide an early indication of the appearance or accumulation of
, any radioactive material in the environment caused by the operation j
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To provide assurance to regulatory agencies and the public that the I l'
- station's environmental impact is known and within anticipated limits.
To verify the adequacy and proper functioning of station effluent j 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 j releases of radioactive material.
The program was initiated in 1970, approximately two years before the plant j began commercial operation in 1972. It has been in operation continuously
{ since that time, with improvements made periodically over those years.
j The current program is designed to meet the intent of NRC Regulatory Guide j 4.1, Prorrams for Monitorine Radioactivity in the Environs of Nuclear Power Plants, NRC Regulatory Guide 4.8, Environmental Technical Soecifications for Nuclear Power Plants, the NRC Branch Technical Position of November 1
1979 entitled An Accentable Radiological Environmental Monitorina Prorram, i as well as NRC NURE';-0473, Radiolorical Effluent Technical Soecifications 3 for BUR's. The environmental TLD program has been designed and tested
) around NRC Regulatory Guide 4.13, Performance. Testing and Procedural j Soecifications for Thermoluminescence Dosimetry: Environmental
- Aeolications. The quality assurance program is designed around the guidance given in NRC Regulatory Guide 4.15, Ouality Assurance for Radiolorical Monitorine Prorrs== (Normal Ooerations) - Effluent Strears and the Environment, j l
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The minimum sampling requirements of the REMP are given in Technical i Specification 3.9.C, which is summarized in Table 4.1 of this report. The l identification of the required sampling locations is given in the Offsite l
- Dose Calculation Manual (ODCM), Chapter 4 The complete list of locations '
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i l used during 1994 is given in Tables 4.2 and 4.3 of this report. These I
sampling and monitoring locations are shown graphically on the maps in
- Figures 4.1 through 4.6.
l l The Vermont Yankee Chemistry Department conducts the radiological environmental monitoring program. They collect all airborne, terrestrial i and ground water samples, and contract with Aquatec, Inc. to collect all j fish, river water and sediment samples. All TLD badges are posted and i
retrieved by the Vermont Yankee Chemistry Department, and are read out by j the Yankee Atomic Environmental Laboratory.
t 4.1 Monitorine Zones i
l The REMP is designed to allow comparison of levels of radioactivity in j samples from the area possibly influenced by the plant to levels found in
- areas not influenced by the plant. Monitoring locations within the first j zone are called " indicators." Those within the second zone are called
, " controls." The distinction between the two zones, depending on the type l of sample or sample pathway, is based on one or more of several factors, j such as site meteorological history, meteorological dispersion i
calculations, relative direction from the plant, river flow, and distance.
Analysis of survey data from the two zones aids in determining if there is j a significant difference between the two areas. It can also help in i differentiating between radioactivity or radiation due to plant releases and that due to other fluctuations in the environment, such as atmospheric j nuclear weapons test fallout or seasonal variations in the natural background.
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] 4.2 Pathways Monitored I l l l' Four pathway categories are monitored by the REMP. They are the Airborne, Waterborne, Ingestion and Direct Radiation Pathways. Each of these four i categories is monitored by the collection of one or more sample media,
) which are listed below, and are described in more detail in this section:
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l Airborne Pathway
{ Air Particulate Sampling j j Charcoal Cartridge (Radioiodine) Sampling i
j Waterborne Pathways j River Water Sampling i
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Ground Water Sampling Sediment Sampling Ingestion Pathways Milk Sampling
! Silage Sampling
} Mixed Grass Sampling Fish Sampling Direct Radiation Pathway TLD Monitoring i
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- 4.3 Descrintions of Monitorina Prorrman i
l 4.3.1 Air Samnline f Continuous air samplers are installed at six locations. (Five are required by VYNPS Technical Specifications.) The sampling pumps at these locations ,
i operate continuously at a flow rate of approximately one cubic foot per l minute. Airborne particulates are collected by passing air through a 50 mm l glass-fiber filter. A dry gas meter is incorporated into the sampling !
j stream to measure the total volume of air sampled in a given interval. The j 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 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> at the Laboratory before being analyzed for gross-beta radioactivity (indicated as GR-B in the data 4
tables). The biweekly filters are composited (by location) ar. the
- Laboratory for a quarterly gamma spectroscopy analysis.
1 If tts 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 i requires a gamma isotopic analysis on the individual sample. Whenever the j main plant stack effluent release rate of I-131 is equal to or greater than 1 0.1 uCi/sec, weekly air particulate is required, pursuant to Technical Specification 3.9.C.
1 i 4.3.2 Charcoal Cartridre (Radioiodine) Samnline Continuous air samplers are installed at six locations. (Five are required-by Technical Specifications.) The sampling pumps at these locations operate continuously at a flow rate of approximately one cubic foot per minute. A 60 cc TEDA impregnated charcoal cartridge is located downstream j :
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1 g of the air particulate filter described above. A dry gas meter is j 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 j structure. These cartridges are collected and analyzed biweekly for I-131.
j Uhenever the main plant stack effluent release rate of I-131 is equal to or i greater than 0.1 uCi/see, weekly charcoal cartridge sampling is required, I
pursuant to Technical Specification 3.9.C.
4.3.3 River Water Samnline 1
4 4 An automatic compositing sampler is maintained at the downstream sampling j location by the Vermont Yankee Chemistry Department staff, and the pump
- delivering river water to the sampler is maintained by Aquatec, Inc. The j sampler is controlled by a timer that collects an aliquot of river water
! hourly. An additional grab sample is collected monthly at the upstream control location. All river water samples are preserved with hcl and NaHS03 to prevent the plate out of radionuclides on the container walls.
! Each sample is analyzed for gamma-emitting radionuclides. Although not
} required by VYNPS Technical Specifications, a gross-beta analysis is
) performed on each sample. The monthly composite or grab samples are i composited again (by location) at the Laboratory for a quarterly H-3
) analysis, i
j 4.3.4 Cround Water Samnline i
j Grab samples are collected quarterly from two indicator and one control 4
location. (Only one indicator and one control is required by VYNPS
! Technical Specifications.) All ground water samples are preserved with hcl l and NaHS0s to prevent the plate out of radionuclides on the container walls. Each sample is analyzed for gamma-emitting radionuclides and H-3.
l Although not required by VYNPS Technical Specifications, a gross-beta j analysis is also performed on each sample.
i f 4.3.5 Sediment samnline i
j Sediment grab samples are collected semiannually from two locations by l Aquatec, Inc. At the downriver shoreline, station SE-11, one grab is j collected. At the North Storm Drain Outfall, station SE-12, multiple grab
! samples are collected. Each sample is analyzed at the Imboratory for 2
gamma-emitting radionuclides.
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- When milk animals are identified as being on pasture feed, milk samples are l j 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 j result of the annual Land Use Census, based on meteorological dispersion calculations. The fourth location is a control, which is located l sufficiently far away from the plant to be outside any potential influence from it. Other samples are typically collected from locations of interest.
i j Immediately after collection, each milk sample is refrigerated and then i typically transported by courier. Upon receipt at the laboratory, l methimazole and formaldehyde are added to the milk to prevent protc.in l binding and spoilage, respectively. Each sample is then analyzed for j gamma-emitting radionuclides. Following a chemical separation, a separate j low-level I-131 analysis is performed to meet the lower Limit of Detection j requirements in the Technical Specifications. Although not required by
] Technical Specifications, Sr-89 and Sr-90 analyses are also performed on J quarterly composited samples.
i 4.3.7 silare samnlina 3
j At each milk sampling location, a silage sample is collected at the time of ;
- harvest, if available. One sample is shipped t- the Laboratory without '
j preservative, where it is analyzed for gamma-emitting radionuclides, j Although not required by Technical Specifications, a separate silage sample
! is preserved with NaOH, and is then shipped to the Laboratory for a l 4
separate I-131 analysis. j i l l
4.3.8 Mixed crass s==nline i
l At each 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 Iower Limits of Detection. One
- sample is shipped to the Laboratory without preservative, where it is l analyzed for gamma-omitting radionuclides. Although not required by j Technical Specifications, a separate grass sample is preserved with NaOH,
! and is then shipped to the Laboratory for a separate I-131 analysis, t
4.3.9 Fish Sm=nline i
j Fish samples are collected semiannually at two locations (upstream of the 1
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l plant and in Vernon Pond) by Aquatec, Inc. The species collected in 1994 1
. were as follows: a) yellow perch and smallmouth bass at both locations for the May collection, b) yellow perch and white perch at FH-11 for the October collection, and c) yellow perch and smallmouth bass at FH-21 for j the October collection. The fish samples are frozen and delivered to the j Laboratory where the edible portions are analyzed for gamma-emitting radionuclides.
J 4.3.10 TLD Monitorine i
Direct gamma radiation exposure was continuously monitored with the use of thermoluminescent dosimeters (T1Ds). Specifically, Panasonic UD-801AS1 and
- UD-814AS1 calcium sulfate dosimeters were used, with a total of five j 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 j container. This container is attached to an object such as a fence or utility pole. A total of 40 stations are required by Technical i Specifications. Of these, 24 must be read out quarterly, while those from the remaining 16 incident response (outer ring) stations need only be de-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 (twelve more beginning in the second quarter) !
are typically posted at or near the Site Boundary. The plant staff pe=ts )
4 and retrieves all TLDs, while the Yankee Atomic Environmental Laboratory l processes them. I 4 l i
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. _ _ _ . . _ . . _ . _ _ ._._.m.__ ._._ ._____.__._..~.._.m_._.._._.__.-.._._ -- _ _ _ -.-.__ - ._ _ _.m. . _ - . . _ _ _ . _ . . . . . _
TABLE 4.1 medfoteelee( Enrframentet Itanitories program i (as respelred by Tech. Spec. febte 3.9.3)*
( Cettection Anotysle i
Exposure Pethuey d'F uwber of Routine Anotysle Analysis IPI'
- Sample sempting Cottection Type Freepsency Locatione teode Frogsency
- 1. Direct Redletlen (TLDs) 40 Continuous euerterly Gemme; Outer Ring - Each TLD de-dose enty, miees gaseous retoese LCO use encoeded
- 2. Airtisme (Perticulates 5 continuous seminenthly Porticutete semple:
and Redfolodine) Grose Sete Each temple Genus Isotopic euerterly PP ite (by location)
Radiolodine Centster 1-131 Each Sample
- 3. Unterborne
- e. Surface unter 2 Dounetress: peonthly Gamme Isotopic Each Sempte Automatic Trititsu (N-3) euerterly tospoelte compoelte.
t%stroem: greb.
- b. Greimd unter 2 Grab euerterly Gamme footopic Each Sample Tritius (N-3) Each Sample
- c. Shoreline sediment 2 Grob Upstroem: Seelemuelty. Samme Isotopic Each Sample N. Stone Drain Outfett:
As specified in 1201.
. . . ...m_._.. _ _ . . . - . _ . _ _ . . _ . - . _ . . . . . ...._.__......-.._.._...._._...--____...__...__m_._. ._.m . . _ _ . _ . _ . _ _ . . _ . _ _ . . _
TABLE 4.1 (continued)
Radletosfeet Erwironmentet IIsniterleg Program (as respired by Tech. Spec. T4te 3.9J)*
Cottection Anotyels Espesure Pethuey and/or Anotysle Anotysle Sample Medle Nominst Number of Routine Neuilnet Sample Locations Sempting Cettectlen Type Frespency Mode Frespency
- 4. Ingeetten
- e. Mitt 4 Grab Monthly Gamme Isotopic Each semple (Seetoonthly 1-131 Each sample when on posture)
- b. Fish 2 Grab Semiervusetty Gemme Isotopic on Each semple edible pertions
- c. Vegetetten
- Grace semple 1 et each air Grab ouerterly d en Gemme Isotopic Each semple sampling stetten evettehte
- Sitage semple 1 et each altk Greb At hervest Gensam Isotopic Each semple sempting station
- See Technicet specificetten Table 3.9.3 for complete footnotes.
t
4 TABLE 4.2 l 3
, Radiological Environmental Monitoring Iscations (non-TLD) in 1994 Vermont Yankee Nuclear Power Station l Distance j From Direction j Expscure Station Plant From Pathway Code Station Descrintion 7dmg* ( km ) *** Plant ***
2 1. Airborne AP/CF-11 River Sta. No. 3.3 I 1.9 SSE i
AP/CF-12 N. Hinsdale, NH I 3.6 NNW AP/CF-13 Hinsdale Substation I 3.1 E i
AP/CF-14 Northfield, MA I 11.3 SSE j AP/CF-15 Tyler Hill Road I 3.2 WNW j AP/CF-21 Spofford 14ke C 16.1 NNE 1
4
- 2. W:terborne
- c. Surface WR-11 River Sta. No. 3.3 I 1.9 Down-
! river i WR-21 Rt. 9 Bridge C 12.8 Up-river
- b. Ground WG-11 Plant Well 1 --
On-site WC-12 Vernon Nursing Well I 2.0 SSE l
WG 22 Skibniowsky Well C 14.3 N
Outfall
- 3. Ingestion i
- c. Milk TM-11 Miller Fara I 0.8 WNW l TM-12 Dominick -
I 5.2 E TM-14 Brown Farm I 2.1 S TM-16 Meadow C<est I 4.4 WNW/NW TM-18 Blodgett Fara I 3.4 SE TM-24 County Farm C 22.5 N i
i I
i l
i 4
4
)
~ _ . . .. .__ - - . _ _ _ _ -
I, -
i TABLE 4.2 (continued)
{ Radiological Environmental Monitoring Locations (non-TLD) in 1994
- Vermont Yankee Nuclear Power Station l Distance 5
From Direction l Expseure Station Plant From Pathway
- Code Station Descrintion fdtBa (km) *** Plant ***
i
! 3. Ingestion, (continued)
{
- b. Fish FH-11 Vernon Pond I -- **
FH-21 Rt. 9 Bridge C 12.8 Upriver j c. Mixed TG-11 River Sta. No. 3.3 I 1.9 SSE 1
Grass TG-12 N. Hinsdale, NH I 3.6 NNW l TG-13 Hinsdale Substation I 3.1 E j TG-14 Northfield, MA I 11.3 SSE I j'
TG-15 Tyler Hill Rd. I 3.2 WNW TG-21 Spofford Lake C 16.1 NNE
- c. Silage TC 11 Miller Fara I 0.8 WNW .
j TC-12. Dominick I 5.2 E I j TC-14 Brown Fara I 2.1 S j TC-16 Meadow Crest Fara I 4.4 WNW/NW
- TC-18 Blodgett Farm I 3.4 SE j TC-24 County Farm C 22.5 N I
i j
- I - Indicator Stations; C - Control Stations
- Fish samples are collected anywhere in Vernon Pond, which is adjacent to the
! plant (see Figure 4.1).
4
- The Distance and Direction for non-TLD sampling sites are relative to the plant stack.
1 i
i i
j i
j 1
i i TABLE 4.3 j Eadiological Environmental Nonitoring Locations (TLD) in 1994 j_ Vermont Yankee Nuclear Power Station i
j Distance Direction-Station From Plant Fron
-l code Station Descrintion 7dmg ( km) *** Plant ***
i j DR-1 River Sta. No. 3.3 I ~1.6 SSE I DR-2 N. Hinsdale, NH I 3.9 NNW l DR-3 Hinsdale Substation I 3.0 E j DR-4 Northfield, NA C 11.0 SSE j DR-5 Spofford lake C 16.3 NNE j DR-6 Vernon School I 0.46 WSW l
DR-7 Site Boundary SB 0.27 W j DR-8 Site Boundary SB 0.25 SW i DR-9 Inner Ring I 2.1 N ,
j DR-10 Outer Ring 0 4.6 N j DR-11 Inner Ring I 2.0 NNE
{ DR-12 Outer Ring 0 3.6 NNE-l DR-13 Inner Ring I 1.4 NE-j DR-14 Outer Ring o 4.3 NE i DR-15 Inner Ring I 1.4 ENE >
{ DR-16 Outer Ring 0 2.9 ENE l DR-17 Inner Ring I 1.2 E 3 DR-18 Outer Ring 0 3.0 E j DR-19 Inner Ring I 3.5 ESE
{
i- DR-20 Outer Ring o 5.3 ESE i DR-21 Inner Ring I 1.8 SE !
DR-22 Outer Ring o 3.2 SE
- DR-23 Inner Ring I 1.8 SSE
( DR-24 Outer Ring 0 3.9 SSE j DR-25 Inner Ring I 2.0 S
- DR-26 Outer Ring o 3.7 S
!. DR-27 Inner Ring I 1.0 SSW 4
DR-28 Outer Ring 0 2.2 SSW
! DR-29 Inner Ring I 0.7 WSW DR-30 Outer Ring O 2.3 SW i
i b l l
4 TABLE 4.3 l (continued) i
. Radiological Environmental Monitoring Imcations (TLD) in 1994 j Vermont Yankee Nuclear Power Station J
Distance Direction
{ Station From Plant From !
l Code Station Descrintion 7gmg* Man) *** Plant *** j l DR-31 Inner Ring I 0.8 W
) DR-32 Outer Ring 0 5.0 WSW j DR-33 Inner Ring I 0.9 ' VNW j DR-34 Outer Ring Road 0 4.9 W j DR-35 Inner Ring I 1.4 WNW j DR-36 Outer Ring 0 4.7 WNW j DR-37 Inner Ring I 3.0 NW j DR-38 Outer Ring 0 7.7' NW j DR-39 Inner Ring I 3.2 NNW
! DR-40 Outer Ring a 0 5.8 NNW 3 DR-41** Site Boundary SB 0.38 SSW i DR-42** Site Boundary SB 0.60 S l DR-43** Site Boundary SB 0.42 SSE
~
SB 0.12 NE j DR-46** Site Boundary SB 0.29 NNW i DR-47** Site Boundary SB 0.51 NNW DR-48** Site Boundary SB 0.82 NW-i DR-49** Site Boundary SB 0.27 UNW
) DR-50** Cov. Hunt House I 0.34 SSW DR-51** Site Boundary- SB 0.27 W-
{ DR-52** Site Boundary SB 0.25 SW l
i i e I - Inner Ring TLD; O - Outer Ring Incident Response TLD; C - Control TLD;
{ ** This location is not considered a requirement of Technical Specification Table i 3.9.3. '
i *** Distance and direction for TLD sites are relative to the center of the Turbine l Building.
j **** DR-8 satisfies Technical Specification Table 3.9.3 for an inner ring direct
- radiation monitoring location. However, it is averaged as a Site Boundary TIE i due to its close proximity to the plant.
I i
4 j i h
J 4 4 j
TABLE 4.4 Envizcassental Lower Limit of Detection (LLD) Sensitivity Regtirements Airborne Particulates vegetati Water or Gases Fish Milk , on Sediment Analysis (pci/1) (pci/m3) (pCi/kg) (pC1/l) (pCi/kg) (pCi/kg
-dry)
Gross-Beta 4 0.01 H-3 3000 Mn-54 15 130 Fe-59 30 260 i Co-58,60 15 130 Zn-65 30 260 Zr-Nb-95 15 I-131 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15 (Several explanatory footnotes are given in Tech. Spec. Table 4.12-1.
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)
Analysis 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 t
I-131 0.9 3 100 '
Cs-134 30 10 1000 60 1000 Cs-137 50 20 2000 70 2000 -
Ba-La-140 200 300
- 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 Eorth Storm Drain Outfall only.
9
,1 s
~
o 500 N METER 5 i
i 1 ..
a t
m, . .
i e' \.
+ N ;
s ,
. TC-81 .s )
VERNON POND
'IM-11 \
l 'g STACKF$ g
\ 'A, E-12 s
- 5 S INTAKE NG-11 5, i 's i i, i A rs-11 7 \ [I '
DISCEARGE
}l
(
VERNON EIJMENTARY SCHOOL i
,1 et 5 i
\
i ) !
s l SE-11 IINSDAI2, Nu j , "
4
~~a' i 4 l
= NoN, vT %N CONNECTICUT h I
)
i i Figure 4.1 Radiological Environmental Sampling Locations Within Close Proximity to Plant 1
1 N
A TG-12 AP/CF-12 9[ ..
d' HINSDALE, NH ,
T"-l' A T0-16 g
TG-15 A AP/CF-15 A 2o-13 AP/CF-13 1
/ ~* . I szr ENIARGEMENT IN FZGURr 4-1 vamecer nw ,
I A
AP/CF-11 Tc-14 A A ro.it
- ~14 WG-12 WR-11 m,gg TC-le 0 1 2 3 F----- 1 H H I PCMD xzzacersas Figure 4.2 Radiological Environmental Sampling Locations Within 5 Kilometers of Plant
5 4
i 1 N [
] \ l l
& 'JN-24 j Tc-24 1
I i I i sPOFFORD Z.hKE 1 TG-21 i
A wG-22 A x,/cr-21
- -21 Em WR-21 uT. A w..v n.n enEsTERrIELD 4
O \
.h BRATTLEBORO $ sar afLAJtasMENT IN FIGtstr 4-2
- ik, /
EINsDALE T l
GUILFORD 0 e A ,,c-12
! vERNONS e PIANT VERMONT ,
NEW IAMPsEIRE unssAcuusETTs p unssAcuusE:Ts
- 9 moRTEFIELD l A AP/cr-14 i TG-14 i
! l l
1 5
9 l ll a
l GREENTIELDS 0 5 10 -
l KILCHETERs i
l 1
i Figure 4.3 Radiological Environmental Sampling locations
] Creater than Five Kilometers from Plant l 4
4
}
0 50o N 3GlTERS 1
- l l
FENCELINE,,
\ ('
/%
e A DR-49'N
\
6 T
'p
's DR-47 A 'i, 1 N% ',
i VERNON POND la .
s R-33 \pR-49 ST M A cR-46 '
l
's mTAEE l og,7 sA DR-45 DR-31 A i DR 52 A A DR-44 DR-8 A #
s,
- [Dzsma DR-s A VERNONELEMENTARYSCHOOLh f
\
gg f DR-41 t
i
~
DR-29 DR-50 )
t,DR-43 A,,t' DR-42 ,#
VERNON, VT CONNECTICUT VERNON DAM RIVER DR-27 A (
\
i i
Figure 4.4 TLD Honitoring Locations in
{ Close Proximity to Plant j !
l 1
1 I
1
- l x j MNW mur 1 N i )
)
l NW A DR-40 1 DR-lo I A 'ME i l 1 DR-12 i A j DR-14 ,_
i A DR-2 A l A DR-3s HINSDALE, NH i i
$ DR-36 4
f DR-376' DR-9 R-11 l i A / A www
/
DR-16 E I
. ../ g_g
/ , 8DR-3 N g ADR-17 A DR-18 w % x i #
3 sEr ENIARGEMENT 2F FIGURE d-4 i
g i DR-32 .
% A DR-21 A DR-19 A A DR-30 A DR-23 g,g
- wsw A A DR_1 .
-8 DR-25 I VERNON, VT A !
i DR-22 i
i l i sw 1 DR-26
! A ,
A DR-24
' O 1 2 3 LILY POND umm n i ssw ss
- s k l
i i i Figure 4.5 TLD Monitoring Locations Within 5 Kilometers from Plant l 2
s
't 1
l 1
i j N l \
\ ) N l i I I
' \ :
FM M l y i
, I i A'Dm-s i
} E0 Gall 3t MT. # NI 4 1 A
! . r 1
TTLEBORD $
i i
l' N DR-3 s A _ _ _ _ mEtEN2amdENDrYZarFZeugtrdas%
1 :
I g 1
} l 7
G ,11.,e nD . SINS. DALE .
WINCIESTER g DR-34 h hERNotCe g e g j
4 8 g
's i
- lA DK-20 l I
k- .. *LG40NT, , , , , _ , , , _
NEW E M SE,I,RE l j MASSACEUSETTS /
s M SACIUSETTS '
k \
t 4* NORTEFIELD i A DR-4 4 h l 4 *4, i
i s M
/) v
\
1 i
f j
J GREENFIELD#
{
1 0 5 to j , . -
l 4 x! m = tem 8 4
I i
l Figure 4.6 TLD Monitoring locations Greater j than 5 Kilometers from Plant 1, ,
i
_ - -_ ~.
i
) 5. RADIOLOGICAL DATA
SUMMARY
TABLES i
l This section summarizes the analytical results of the environmental samples l which were collected during 1994. These results, shown in Table 5.1, are j presented in a format similar to that prescribed in the NRC's Radiological i Assessment Branch Technical Position on Environmental Monitoring (Reference j 1). The results are ordered by sample media type and then by radionaclide, j The units for each media type are also given.
{ The left most column contains the radionuclide of interest, the total j n eber of analyses for that radionuclide in 1994, and the number of 4 measurements which exceeded the Reporting Invels found in Table 3.9.4 of the VYNPS Technical Specifications. The latter are classified as "Non-l l routine" measurements. The second column lists the required Lower Limit of 7 j Detection (LLD) for those radionuclides which have detection capability j requirements as specified in the plant's Radiological Effluent Technical j Specifications (Table 4.9.3). The cbsence of a value in this column j indicates that no LLD is specified in the Technical Specifications for that i radionuclide in that media. The target LIE 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 j equipment, which results in low sample volume. Such cases, if any, are addressed in Section 6.2.
For each radionuclide and media type, the remaining three columns summarize 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 1994 for that radionuclide; and (3) the control stations, which are beyond the influence 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 a h radionuclide, the following statistical values are given:
The mean value of all concentrations, with all values that are less than the a nosteriori 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.
1 i
l i
l -
The lowest and highest concentration, with all values that are less
{ than the a nosteriori LLD hsving been converted to zero, pursuant to
. footnote (f) of Technical Specification Table 4.9.3.
i j -
The "No. Detected " or the number of positive measurements, divided j by the total number of measurements. (A concentration which is j greater than three times the standard deviation of that count, based on random uncertainty only, is considered " positive.")
l Each single radioactivity measurement datum in this report is based on a j single measurement and is reported as a concentration plus or minus a one l standard deviation uncertainty. The standard deviation on each measurement
- represents only the random uncertainty associated with the radioactive l decay process (counting statistics), and not the propagation of all j possible uncertainties in the analytical procedure.
- 1 t l
! Pursuant to VYNPS Technical Specification Table 4.9.3 (footnote f), any I f concentration below the a nosteriori LLD for its analysis is averaged as a '
1 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 l l with Laboratory reporting practices and normal data review practices used j by Vermont Yankee, a " positive measurement" is considered to be one whose concentration is greater than three times its associated standard I deviation, based on the random uncertainty as discussed above. This use of
- 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 l 1 practices.
t j The radionuclides reported in this section represent those that: 1) had an l L12 requirement in Table 4.9.3 of the Technical Specifications, or a l Reporting 1Avel listed in Table 3.9.4, or 2) had a positive measurement of j radioactivity, whether it was naturally-occurring or man-made; or 3) were j of special interest for any other reason. The radionuclides that were routinely analyzed and reported by th- Laboratory (in a gamma spectroscopy analysis) were: Th-232, Ag-110m, Ba-140, Be-7, Ce-141, Co 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, j Np-239, Ru-103, Ru-106, Sb-124, Se-75. Tel-132, 2n-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 1994.
Data from direct radiation measurements made by TIDs are provided in Table 5.2 in a format essentially the same as above. The complete listing of quarterly TIS data is provided in Table 5.3.
't j , ,
t 3
i Y
k i
-, , _ . . .- - _ ==, . , . . _ _ .
~. . . - . .. = _
b 4
1 a
1 TABLE 5.1 f
j RADitLOBICAL EuvielmeFTAL PROMAII E551 ART 1 VEmeIT VAEEE inre m 70lER STATI(NI, VERIIWI, VT
- (JAR NRT - BEE 5 W R 19 M )
1 l INDICATOR STATIcett STATION WITN NIGIIEST BEAN C011 TROL STATICIls j
j RADIONUCLIDES
- HEAN NEAN IIEAN (110. ANALYSES) REGUIRED RANGE STA. RANGE RAllGE
! (Noel ROUTINE)** LLD NO. DETECTED
- No. No. DETECTE0
- 110. DETECTED ***
e i
j 15B1851: AIR PARTIGRATES (AP) RAIITS: pCf/cehic meter OR-B (156) .01 ( 2.1 a 0.0)E 2 11 ( 2.3 a 0.1)E 2 ( 1.9 a 0.1)E 2
- ( 0) ( 1.3 3.6)E *2 ( 1.5 - 3.4)E -2 ( 1.3 - - 2.7)E 2 1 (130/130) ( 36/ N) (N/N) r 1
i
! BE 7 ( 24) ( 1.0 t 0.0)E -1 15 ( 1.2 a 0.2)E -1 ( 9.3 a 1.0)E -2 I
- ( 0) ( 8.5 - 16.0)E 2 ( 8.5 - 16.0)E -2 ( 7.5 - 12.0)E 2
( 20/ 20) ( 4/ 4) ( 4/ 4)
C0-60 ( 24) ( 0.0 s 0.0)E O ( 0.0 a 0.0)E O
.! ( 0) **
j ( 0/ 20) ( 0/ 4) l CS 134 ( 24) .05 ( 0.0 s 0.0)E O ( 0.0 a 0.0)E O
( 0) ****
i ( 0/ 20) ( 0/ 4) i CS-137 ( 24) .06 ( 0.0 a 0.0)E 0 ( 0.0 s 0.0)E O
- ( 0) **
i ( 0/ 20) ( 0/ 4) l IEDILSI: raam m a FILTERS (CF) WITS: pCf/en&fc meter i
j I 131 (156) .07 ( 0.0 a 0.0)E O ( 0.0 s 0.0)E O
- ( 0) **
j ( 0/130) ( 0/ 26)
- IEDILSI
- RIVER lETER OR) LEITS: pCf/kg j
l GR B ( 24) 4. ( 1.5 a 0.2)E O 21 ( 1.6 s 0.2)E O ( 1.6 a 0.2)E O
( 0) ( 0.0 - 2.2)E 0 ( 0.0 - 3.5)E 0 ( 0.0 - 3.5)E O l ( 11/ 12) ( 11/ 12) ( 11/ 12) j Isi 54 ( 24) 15. ( 0.0 a 0.0)E O ( 0.0 a 0.0)E O
- ( 0) ****
( 0/ 12) ( 0/ 12) i i
J
) NOTE: Footnotes any be fowid at the end of Table 5.1.
- 4 I
i
4 i
3 TABLE 5.1 i
MD10 LOGICAL ENWlEDIEWITAL PROMAft magIARY ilEMEINT YMEE mrim peer STAT 10N, WWIM, VT
, (JA M ET . set m 1994) i IWICATOR STATIONS STATION WITN NIGNEST IEMI CONTROL STATIONS j . ________________ :::::______ ::______;;;;_ ::::::::______;;
4 BADIONUCLIOES* IEAN LEAN IEAN
, (No. ANALYSES) REQUIRED RANGE STA. RAi8GE RANGE j (IION-ROUTIIIE)** LLD 110. DETECTED *** N0. NO. DETr "** 110. DETECTED"*
4 4 M I451: BI M W TER O R), contirmed IMITS: pCI/kg i
j C0-58 ( 24) 15. ( 0.0 a 0.0)E O ( 0.0 a 0.0)E O
- ( 0) ****
I ( 0/ 12) ( 0/ 12) t
- FE-59 ( 24) 30. ( 0.0 s 0.0)E O ( 0.0 a 0.0)E 0 j ( 0) ****
- ( 0/ 12) ( 0/ 12) j d
to 60 ( 24) 15. ( 0.0 a 0.0)E O ( 0.0 s 0.0)E 0
) ( 0) ****
( 0/ 12) ( 0/ 12) 1 4
i 2N-G ( 24) 30. ( 0.0 s 0.0)E O ( 0.0 a 0.0)E 0 1 ( 0) ****
j j ( 0/ 12) ( 0/ 12)
! 2R 95 ( 24) 15. ( 0.0 s 0.0)E O ( 0.0 a 0.0)E O 5 ( 0) ****
i
( 0/ 12) ( 0/ 12) f CS 134 ( 24) 15. ( 0.0 a 0.0)E O ( 0.0 a 0.0)E 0 l
- ( 0) **
4 J
( 0/ 12) ( 0/ 12) l l 1 CS 137 ( 24) 18. ( 0.0 s 0.0)E 0 ( 0.0 s 0.0)E O .
$ ( 0) ****
l ( 0/ 12) ( 0/ 12) ;
4 l
- BA-140 ( 24) 15. ( 0.0 a 0.0)E O ( 0.0 a 0.0)E O
( 0) **** {
I
- ( 0/ 12) ( 0/ 12) l i N-3 ( 8) 3000. ( 0.0 a 0.0)E O ( 0.0 a d.0)E O
- ( 0) **
l j , ( 0/ 4) ( 0/ 4) t {
I i
l
., NDTE: Footnotes any be found at the end of Table 5.1.
t 29 4
t
- 4 y
1 1
4 l
i l
1 i l i TABLE 5.1 ,
i I
i (JAEIART = WEBRER 1996) I
, IISICATOR STAfl0118 STATION WITN NIGNEST MAN CONTROL STATIONS 4
BADIONUCLIDES* LEAN IEAN IEAN
) (ND. AllALYSES) REGUIRED RANGE STA. RAIIGE BAIIGE (NDIl-ROUTINE)** LLD 110. DETECTED"* 11 0 . NO. DETECTED *** NO. DETECTEP" J
IuBItal: E mas takia (us) 13:17s: pcl/kg l E8 ( 12) 4. ( 5.6 e 1.2)E O 11 ( 7.2 s 2.1)E 0 ( 1.9 a 0.1)E 0 1 ( 0) ( 2.8 - 12.5)E O ( 3.2 - 12.5)E O ( 1.7 - 2.0)E O l ( 8/ 8) ( 4/ 4) ( 4/ 4) i i
lu 54 ( 12) 15. ( 0.0 s 0.0)E O ( ~ 0.0 s 0.0)E O I *"*
( 0) j ( 0/ 8) ( 0/ 4) i t0 58 ( 12) 15. ( 0.0 s 0.0)E O ( 0.0 s 0.0)E O
! ( 0) ****
j ( 0/ 8) ( 0/ 4)
FE 59 ( 12) 30. ( 0.0 s 0.0)E O ( 0.0 s 0.0)E 0
) ( 0) ***
- ( 0/ 8) ( 0/ 4)
- co-40 ( 12) 15. ( 0.0 s 0.0)E O ( 0.0 s 0.0)E 0 j ( 0) *"*
( 0/ 8) ( 0/ 4) 1 C 43 ( 12) 30. ( 0.0 s 0.0)E O ( 0.0 s 0.0)E 0
( 0) ****
l
( 0/ 8) ( 0/ 4) 2R 95 ( 12) 15. ( 0.0 s 0.0)E 0 ( 0.0 s 0.0)E O
, ( 0) ****
- ( 0/ 8) ( 0/ 4) 1 1
Cs 134 ( 12) 15. ( 0.0 s 0.0)E O ( 0.0 s 0.0)E O 1 ( 0) ****
( DI 8) ( 0/ 4)
- i Cs 137 ( 12) 18. ( 0.0 s 0.0)E O ( 0.0 s 0.0)E O l
! ( 0) ***
l ( 0/ 8) ( 0/ 4)
! \
I l l I
- i f' NOTE: Footnotes may be fowul at the end of Table 5.1.
30
,1 I
i i
.I
1 i
e TABLE 5.1 i RADIOLOGICAL EinflA013efTAL PR00RAll E851ARY j WEmeff YAIEEE umaa PGElt STATICII, WERuou, VT l
! (JAltanaY - merummse 1994) l i l 1
j INDICATOR STATIONS STAT!Oel WITN NIGNEST IEAN CONTROL STATIQuS f RADICIIUCLIDES* IEAll IEAN IEAN (110. ANALYSES) RE2JIRED RAltGE STA. RAIIGE RANGE f (IION ROUTillE)** LLD 100. N TECTED*** NO. 110. DETECTED *** 110. NTECTED***
.....o....... ........ ..................... ........................... .....................
d IEDIlse: MOLAS laLTR (llE), sentlensed 15ITS: pCf/kg
! BA 140 ( 12) 15. ( 0.0 s 0.0)E O ( 0.0 s 0.0)E O
( 0) ****
l ( 0/ 8) ( 0/ 4)
] N3 ( 12) 3000. ( 0.0 s 0.0)E O ( 0.0 s 0.0)E 0
! ( 0) ****
l ( 0/ 8) ( 0/ 4)
IEDILeis misENT (SE) lAIITS: pCf/kg (dry)
BE 7 ( 49) ( 6.0 a 3.7)E 1 12 ( 6.2 a 3.8)E 1 No DATA
( 3) ( 0.0 - 1.6)E 3 ( 0.0 - 1.6)E 3
! ( 3/ 49) ( 3/ 47) l K 40 ( 49) ( 1.3 s 0.0)E 4 12 ( 1.3 s 0.0)F 4 NO DATA I ( 0) ( 8.5 - 15.8)E 3 ( 9.9 - 15.8)E 3
. ( 49/ 49) ( 47/ 47) i Ind 54 ( 49) ( 0.0 a 0.0)E 0 110 DATA l C 0) ****
i ( 0/ 49) j 1 CD-58 ( 49) ( 0.0 s 0.0)E O NO DATA l C 0) ****
j ( 0/ 49) j CD-60 ( 49) ( 4.9 s 2.8)E O 12 ( 5.1 s 3.0)E 0 100 DATA
( 3) ( 0.0 - 1.0)E 2 ( 0.0 1.0)E 2
( 3/ 49) ( 3/ 47) i 4
i
! NOTE: Footnotes may be fomd at the end of Table 5.1.
i
-31 I i
I 1
1 1
i TABLE 5.1 i
RSIOLOGICAL ENVIROIBENTAL PEDeAN SagWtY 1lEWEEIT YAMEE IRELEAR MnER STATICII, ilERNOIf, VT l
(JAIRWtY - BECseER 1994)
]r ISICATOR STATI0lls STATION WITN MIGNEST IEAN 'COIITROL STATIONS )
- ===== = = = = = _ _ = = . = = = = ................
l j RADIONUCLIDES
- HEAN IIEAN IIEAN
- (110. ANALYSES) REGU! RED RANGE STA. RANGE RAIIGE 1 (Iloll-ROQIIIE)** LLD 110. DETECTED *** 11 0 . 110.' DETECTED *** 7 DETECTED
- j 4
- ImDIIst
- SEDIInff (SE), sent. 4EIITS: pcl/kg (dry)
J 2N 65 ( 49) ( 0.0 a 0.0)E 0 100 DATA
( 0) i ( 0/ 49)
- CS-134 ( 49) 150. ( 0.0 s 0.0)E O NO DATA
- ( 0) j ( 0/ 49) 1 CS 137 ( 49) 180. ( 1.8 s 0.1)E 2 12 ( 1.9 a 0.1)E 2 100 DATA
( 47) ( 0.0 - 3.4)E 2 ( 0.0 - 3.4)E 2 j ( 47/ 49) ( 45/ 47) i Tu-232 ( 49) ( 9.2 a 0.3)E 2 12 ( 9.4 a 0.3)E 2 110 DATA
} ( 0) ( 4.7 - 14.7)E 2 ( 6.1 - 14.7)E 2
, ( 49/ 49) ( 47/ 47) 1 l IEBIMII: NILE (TN) INITS: pCf/kg i
l ER-89 ( 24) ( 0.0 2 0.0)E O ( 0.0 s 0.0)E 0
( 0) ****
( 0/ 20) ( 0/ 4) 8 SR-90 ( 24) ( 1.2 s 0.3)E O 12 ( 3.0 s 0.2)E 0 ( 6.7 a 6.7)E 1 i ( 0) ( 0.0 - 3.6)E O ( 2.6 - 3.6)E 0 ( 0.0 - 2.7)E O l ( 10/ 20) ( 4/ 4) ( 1/ 4) i
- j K 40 (108) ( 1.5 0.0)E 3 12 ( 1.9 a 0.0)E 3 ( 1.3 s 0.0)E 3
( 0) ( 1.2 - 2.0)E 3 ( 1.7 - 2.0)E 3 ( 1.2 - 1.4)E 3
( 90/ 90) ( 18/ 18) ( 18/ 18)
I 131 (108) 1. ( 0.0 s 0.0)E O ( 0.0 s 0.0)E O
( 0) ,
( 0/ 90) ( 0/ 18) 1 l
. CS 134 (108) 15. ( 0.0 s 0.0)E O ( 0.0 s 0.0)E O j ( 0)
}
( 0/ 90) ( 0/ 18)
NOTE: Footnotes may be found at the end of Table 5.1.
i 1 ,
8 2
4
l l
q I
I Taalf 5.1 l RADIOLO8ICAL EuviameeffAL PeosAII spewtY VENENT YAMEE INCLEAR PGElt STATIGI, WRIIENI, VT 4
(JAEIARY . psema jgM) l
< 1 IWICATOR STAficIIS STATION WITN NIGNEST IEAN CONTROL STAT!0Its RADIONUCLIDES
- IEAll IEAll 8EAN i (NO. ANALYSES) REQUIRED ItAllGE STA. RAIIGE BANGE (II0ll RQUTINE)** LLD 110. DETECTED *** 11 0 . 110. DETECTED *** 110. M TECTED***
4
- I 3
j i IBIESI: IIILE (TII), sent. INITS: pCI/kg l l
CS-137 (108) 18. ( 1.6 s 0.5)E O 12 ( 8.1 a 1.9)E O ( 0.0 s 0.0)E 0 i ( 0) ( 0.0 - 2.7)E 1 ( 0.0 - 2.7)E 1
, ( 12/ 90) ( 11/ 18) ( 0/ 18)
BA 140 (108) 15. ( 0.0 s 0.0)E O ( 0.0 s 0.0)E O
( 0)
! ( 0/ 90) ( 0/ 18) i j ISIISI: SILA N (TC) INITS: pCf/kg SE 7 ( 6) ( 2.7 e 1.7)E 2 24 ( 8.9 a 1.3)E 2 ( 8.9 a 1.3)E 2
( 0) ( 0.0 - 7.3)E 2
( 2/ 5) ( 1/ 1) ( 1/ 1) 1 E 40 ( 6) ( 5.5 s 1.7)E 3 12 ( 1.2 a 0.1)E 4 ( 3.3 a 0.4)E 3 l ( 0) ( 3.0 - 12.1)E 3
( 5/ 5) ( 1/ 1) ( 1/ 1)
) I 131 ( 6) do. ( 0.0 a 3.0)E 0 ( 0.0 a 3.7)E O
( 0) ****
j ( 0/ 5) ( 0/ 1)
{
- CS 134 ( 6) 60. ( 0.0 s 0.0)E O ( 0.0 a 1.2)E 1
( 0) ****
( 0/ 5) ( 0/ 1)
CS 137 ( 6) 80. ( 0.0 s 0.0)E O ( 0.0 a 1.1)E 1
( 0) ****
( 0/ 5) ( 0/ 1)
SA 140 ( 6) ( 0.0 s 0.0)E O ( 0.0 a 1.0)E 1
( 0) ****
( 0/ 5) ( 0/ 1)
NOTE: Footnotes may be found at the end of Table 5.1.
i 33-
I I
I i
t j Tast2 5.1 f
EMIEMEICAL MVIAIMENTAL PROMNI EBONET
! WWENT YAMEE REl LEAR peer STATIW, ilEMEM, VT I, (JAmalRY - BECWWE 1996) 5 I MICATOR STAfl0NS STATION WITN NIGNEST IEAN CONTROL STATIONS
- _________ __ _________ __ ______ = ___ _______ .
i RADIONUCLIDES
- IEAN LEAN MAN
) (80. ANALYSES) REeulRED RANGE STA. RAIIGE BAIIGE j
- (IIDIl-ROUTIIIE)** LLD 110. DETECTED" N0. 110. DETECTED *** 110. DETECTED
- l mitat NI m M AAB (TS) 85I13 pCf/kg ,
i j BE-7 ( 18) ( 2.1 a 0.4)E 3 11 ( 2.8 a 1.2)E 3 ( 1.4 s 0.5)E 3 l ( 0) ( 0.0 - 4.2)E 3 ( 4.0 - 41.2)E 2 ( 3.2 - 21.8)E 2
. ( 14/ 15) ( 3/ 3) ( 3/ 3) 1 j E-40 ( 18) ( 5.0 s 0.5)E 3 14 ( 6.0 s 0.2)E 3 ( 4.6 s 0.9)E 3 l ( 0) ( 2.0 - 7.8)E 3 ( 5.7 - 6.4)E 3 ( 3.3 - 6.3)E . 3 1 ( 15/ 15) ( 3/ 3) ( 3/ 3) 1
! I-131 ( 18) 60. ( 0.0 a 0.0)E O ( 0.0 a 0.0)E O 4
( 0) *"
) ( 0/ 15) ( 0/ 3) j CS 134 ( 18) 60. ( 0.0 a 0.0)E O t 0.0 s 0.0)E O
- ( 0) **** ,
i ( 0/ 15) ( 0/ 3) !
CS 13/ ( 18) 80. ( 2.5 e 2.5)E O 15 ( '1.2 a 1.2)E 1 ( 0.0 s 0.0)E O l 4
( 1) ( 0.0 - 3.7)E 1 ( 0.0 - 3.7)E 1 l
( 1/ 15) ( 1/ 3) ( 0/ 3) l i l 1 IEDIREI: FI M (FR) REITS: pCl/kg l l l J
K-40 ( 4) ( 3.2 a 0.4)E 3 11 ( 3.2 a 0.4)E 3 ( 3.0 s 0.1)E 3 l a ( 0) ( 2.8 - 3.7)E 3 ( 2.8 - 3.7)E 3 ( 2.9 - 3.1)E 3 l ( 2/ 2) ( 2/ 2) ( 2/ 2) i i l
) In 54 ( 4) 130. ( 0.0 s 0.0)E O (- 0.0 s
- 0)E O
( 0) **** ]
]
i ( 0/ 2) ( 0/ 2)
! CD 58 ( 4) 130. ( 0.0 s 0.0)E O ( 0.0 s 0.9)E O l ( 0) **
~
! ( 0/ 2) ( 0/ 2) k . '
i
! PE 59 ( 4) 260. ( 0.0 s 0.0)E O ( 0.0 s 0.0)E O j ( 0) **
4
( 0/ 2) ( 0/ 2) l I
l IIDTE: Footnotes soy be foural at the end of Table 5.1.
i 34-a 4
3 i
4
i a
I TABLE 5.1 I anDIOLDEICAL EWWIRW5WITAL PEDERAfl 555tARY WENGT YAMEE RELEAR PERER STATIEN, VERNIM, VT l 3 (JAEAARY . merummes 1996)
IISICATOR STATIONS STATICII WITN NIGNEST BEAN CONTROL STATICIIS 4
j RADIGIluCLIDES* IEAN M All MAN .
(50. AllALYSES) REQUIRED RAllGE STA. RANGE RANGE l (IION-ROUTINE)** LLD Mo. DETECTED *** Wo. No. DETECTED
- NO. DETECTED
- f; ............. ........ ..................... .......................... .....................
i l 1 5 I451: FISM (FE), surst. 451T8: pCI/ks
, 00-60 ( 4) 130. ( O.0 a 0.0)E O ( 0.0 s 0.0)E O *
! ( 0) **
l ( 0/ 2) ( 0/ 2) 1 j IN-65 ( 4) 260. ( 0.0 a 0.0)E 0 ( 0.0 a 0.0)E 0
- ( 0) **
l; ( 0/ 2) ( 0/ 2)
{ CS 134 ( 4) 130. ( 0.0 a 0.0)E O ( 0.0 s 0.0)E O 4
( 0) ****
( 0/ 2) ( 0/ 2) 1
- CS 137 ( 4) 150. ( 2.1 a 2.1)E 1 11 ( 2.1 a 2.1)E 1 ( 0.0 s 0.0)E O
] ( 1) ( 0.0 - 4.2)E 1 ( 0.0 - 4.2)E 1
( 1/ 2) ( 1/ 2) ( 0/ 2)
IEDILSI: STONI BRAIN 8147 R LABITS: pCI/kg (asst)
ER-B ( 16) ( 3.3 a 0.2)E O 12 ( 3.4 s 0.3)E O 110 DATA i.
( 0) ( 2.2 - 4.5)E 0 ( 2.9 - 4.2)E O j ( 16/ 16) ( 4/ 4) 1 1e154 ( 13) ( 0.0 a 0.0)E O NO DATA i ( 0) ****
( 0/ 13)
! CD-58 ( 13) ( 0.0 s 0.0)E D 110 DATA
( 0) ****
( 0/ 13)
FE 59 ( 13) ( 0.0 s 0.0)E O NO DATA I ****
( 0)
?
( 0/ 13) i
! 00-60 ( 13) ( 0.0 s 0.0)E 0 NO DATA J
( 0) ****
1 1
( 0/ 13) l 4.
1 IIDTE: Footnotes any be found at the end of Table 5.1.
i f i
4 1
2 TAALE 5.1 RADIOLOSICAL WWIREMENTAL PEINA91 ESOIARY l WWWNT YAMEE wt m PCIER STATICII, Ummal, VT (JAINARY - '888M'88 1994) t i
IIDICATOR STATIONS STATION WITil NIGNEST IEAN 00NTROL STATIONS RADIONUCLIDES
- IEAN BEAN LEAN !
!' (No. ANALYSES) ItEQUIRED RANGE STA. RANGE RANGE l 1
(IION ROUTINE)** LLD No. DETECTED *** 10 0 . NO. DETECTED *** 110. DETECTED ***
i ............. ........ ..................... .......................... ..................... I I
] lemitBI: STenet enAIN TILTER (W), cent. IARITS: pCl/kg 2N-65 ( 13) ( O.0 a 0.0)E 0 NO DATA l ( 0) ****
.I
( 0/ 13) 1 i 2R 95 ( 13) ( 0.0 s 0.0)E 0 110 DATA
( 0) ****
4
( 0/ 13) i CS-134 ( 13) ( 0.0 s 0.0)E 0 110 DATA
! ( 0) **
1
( 0/ 13) 4 CS 137 ( 13) ( 0.0 s 0.0)E O 100 DATA l ( 0) ****
1 ( 0/ 13) i j BA-140 ( 13) ( 0.0 a 0.0)E 0 110 DATA
( 0) ****
! ( 0/ 13) i N-3 ( 14) ( 3.1 e 2.7)E 2 10 ( 4.2 s 3.5)E 2 100 DATA ,
( 1) ( 0.0 - 4.2)E 3 ( 0.0
- 4.2)E 3 l 1 ( 2/ 16) ( 2/ 12) )
1 i I i
i
! l 1
i j
4
! I d
IIOTE: Footnotes may be found at the end of Table 5.1.
-36 l
1 1
Footnotes to Table 5.1:
- The only radionuctidos reported in this table are those with LLD restrements, those for elch positive radioactivity wee detected, and those that were of some other speclet Interest. See section 5 of this report for a discuselon of other radionuclides that were anstyaed.
i
- Non Routine refers to those redlonuclides that exceeded the Reporting Levels in Technicet Specification Table 3.9.4. !
- The fraction of semple analysee yielding detectable measurements (i.e. the concentration la erseter than three times its standard devletlen) is shown in perentheses.
- Att measurements for thlt nucLtde were toss than the LLD for its analysis, and were therefore reported as sero. Conse m ently, att measurements were e g et. (Pursuant to VYWPS Technicet specification Table 4.9.3 (footnote f), any concentration below the 3 mesterfort LLD for its anstysis le averaged as a zero. Where a rence of values is reported in the tables of this section, vetwee Lees then their LLD are etso reported as sero.)
4 i
TABLE 5.2
- EuvinglBENTAL TLD SATA E85thtY 1 WEENT YMEE ElCLEAR MEER STAT!tui, WRIENI, VT q (JesumaY - mRGIGER 19M) )
i i
i 1
- \
1 j OFFSITE STATION i IllNER RING TLDs MITER RING TLDs WITH NIGilEST IEAll IXillTROL TLDs x;n u x _x_ xxx _ ;_;__n;_;_;_____;x ;. _ _ _ _ x x x _ _ _ _ _ x x ........... ........
t
- IEAN IIEAN LEAN IEAN 1 RANGE RANGE RANGE RANGE 4
j (110. DEARREIENTS)e (110. IEASURE8ENTS)e (110. IEASURE8ENTS)e (110. ps u malENTS)o j .................... .................... .................... ....................
1 l 6.4 a 0.8 6.6 a 1.0 DR 36 7.9 s 1.1 6.2 s 0.7
! 4.3 - 7.9 4.7 - 8.7 5.9 - 8.7 5.0 - 7.0 j (84) (64) (4) (8) i j
SITE SCMIDARY TLD 1 WITH NIGNEST IIEAN SITE 80UNDARY TLDs IEAll IEAN RANGE RANGE
' e (110. IEASURE8ENTS) (110. DEASUREIIENTS)e 1
DR 45 11.1 a 0.1 7.8 s 1.4 10.9 - 11.3 4.9 - 11.3 j (4) (51) i a
i 4
4 l
- Each " measurement" is based typleetly en p rterly readings from five TLD elements.
t I
i 4
l
! i i
1 1
d 9
d l
q I
- 38 :
l l
2 i
i d
i j i l I '
l TABLE 5.3
)
W WINEAS EffAL TLS meanimisumryg j 1996 potere-a per usur)
]
$ N
{ Ste. 1ST euARTER 2W GUARTER 3a0 euARTER 4TN SUARTER AVE.
j No. Description EXP. 8.D. EXP. S.D. EXP. S.D. EXP. 8.0. 8XP.
]
- se 01 Elwer Ste. No. 3.3 5.3 s 0.3 6.2 s 0.2 6.2 a 0.2 4.1 a 0.3 6.0 j DR-02 N. Ninsdste, NN 4.3 a 0.2 6.8 a 0.3 6.4 s 0.2 6.4 a 0.3 6.0 l De-05 utnedale t e station 5.6 0.2 7.9 s 0.3 7.7 s 0.4 7.7
- 0.3 7.2 j DR-06 Northfield, MA 5.0 s 0.2 6.4 s 0.3 6.2 a 0.2 6.6 s 0.2 6.1 ,
! DR-05 spefford Lake, NN 5.1 a 0.1 7.0 a 0.3 6.8 a 0.2 6.7 s 0.2 6.4 l
. ge-06 vernon schoot 4.8 s 0.1 7.1 s 0.2 6.9 a 0.3 6.7 a 0.2 6.4 08-07 Site Domdery 6.0 s 0.3 8.3 s 0.3 8.4 a 0.4 8.0 a 0.2 7.7 j De-08 site Do m dery 6.8 s 0.3 8.5 s 0.2 8.5 s 0.3 8.1 a 0.3 8.0 1 DR-09 Imer Rine 5.0 s 0.2 6.6 s 0.2 6.4 a 0.2 6.3 s 0.3 6.1 1 M 10 Outer Rins 4.7 a 0.2 5.7 a 0.3 5.5 e 0.2 5.4 a 0.3 5.3 I DR 11 Inner Alne 4.8 s 0.1 6.2 a 0.2 5.9 a 0.2 6.0 s 0.2 5.7 i DR 12 outer Rins 4.8's 0.3 6.0 s 0.3 6.0 a 0.2 5.9 s 0.2 5.7 i DR 13 Imer Ring 5.4 a 0.2 6.7 s 0.3 6.5 s 0.3 6.5 s 0.2 6.3 i M-11 Outer Rine 5.3 a 0.2 7.9 0.2 7.8 s 0.3 7.7 s 0.3 7.2 i DR 15 inner Ring 5.5 a 0.3 7.0 s 0.2 6.6 a 0.3 6.6 s 0.2 6.4 4 De-16 Outer Ring 6.1 a 0.2 7.4 s 0.2 7.0 s 0.3 7.0 s 0.2 6.9 De 17 Inner Ring 4.8 a 0.1 6.9 a 0.2 6.7 s 0.5 4.5 s 0.2 6.2 i Be-13 ' Outer Rins 5.4 s 0.2 7.3 a 0.2 6.9 a 0.2 6.7 e 0.2 6.6 i DR 19 Ircer Rins 5.1 a 0.2 7.2 a 0.2 6.9 e 0.3 6.9 s 0.2 6.5 l De 20 thster mine 5.7 s 0.3 7.9 a 0.2 7.7 s 0.3 7.5 a 0.2 7.2 j DR 21 Inner Rinii 5.5 s 0.2 7.4 s 0.2 7.3 s 0.2 7.2 a 0.2 6.9 i DR-22 Outer Ring 5.4 s 0.1 7.2 s 0.3 7.0 s 0.3 6.9 a 0.3 6.6 i DR 23 Inner Rins 5.7 s 0.2 7.0 a 0.2 7.1 s 0.2 7.0 a 0.3 6.7 i s 80 24 Outer Eins 4.9 a 0.3 6.0 a 0.1 5.7 a 0.2 5.8 s 0.2 5.6 j De 25 Inner Rine 5.1 s 0.1 6.9 : 0.2 6.5 s 0.4 6.6 a 0.3 6.3 l l 98 26 Outer Ring 4.9 s 0.1 7.1 a 0.3 6.9 s 0.4 6.8 e 0.3 4.4
- De-27 Inner Ring 5.1 a 0.2 7.2 s 0.2 6.7 a 0.3 6.6 a 0.2 6.4 l DR-28 Outer Ring 5.0 s 0.1 7.0 a 0.2 7.0 a 0.4 6.8 a 0.2 6.5 j DR 29 Imer Rins 5.2 a 0.2 7.2 a 0.1 7.0 s 0.3 6.7 a 0.3 6.5
- DR-30 Outer Ring 5.2 s 0.2 7.1 a 0.1 7.1 a 0.3 6.8 a 0.4 6.6 4 DR 31 Inner Ring 4.9 s 0.2 7.3 s 0.2 7.0 a 0.3 6.9 s 0.2 6.5
) 08 32 Outer Ring 4.8 s 0.1 6.9 a 0.3 7.1 s 0.2 6.7 a 0.2 6.4 D8-35 Imer Rins 5.0 s 0.1 7.3 s 0.2 6.9 s 0.3 6.8 a 0.2 6.5 DR-34 Outer Eine 5.2 a 0.3 7.8 s 0.3 7.4 a 0.2 7.4 a 0.4 7.0 i DR 35 Imer Ring 5.5 s 0.2 7.1 a 0.2 6.8 s 0.2 6.3 a 0.3 4.4 i DR 36 Outer Ring 5.9 0.1 8.7 s 0.4 8.6 e 0.2 8.3 a 0.2 7.9
{ pt 37 Inner Rins 4.5 s 0.2 7.0 s 0.2 7.0 s 0.5 6.5 a 0.3 6.3
! De-38 Outer Rins 5.5 a 0.1 7.6 s 0.2 7.2 a 0.2 7.2 a 0.3 6.9
! DR 39 Inner Eins 5.2 a 0.2 6.9 a 0.3 4.7 a 0.3 6.6 e 0.3 6.4 De-40 Outer Ring 5.2 a 0.1 6.9 a 0.3 6.5 s 0.2 6.4 a 0.2 6.3 1 l
3 i i l
i
}
i
TABLE 5.3, sentleesed ButleDWWITAL TLS IEASIEEBENTS 1994 Oliere t per usur's ANNUAL St2. 1ST auARTER 2 8 auARTER 3AD GUARTER 4TN SunRTER AVE.
No. Descriptfort EXP. S.D. EXP. 8.D. EMP. S.D. EXP. S.D. EMP.
M 41 Site somdery 5.4 a 0.2 7.9 a 0.3 7.8 a 0.2 7.3 a 0.3 7.1 M 42 Site somdery 5.1 a 0.3 7.3 a 0.2 7.0 a 0.3 6.9 a 0.2 6.6 M 43 Site som dery 5.5 a 0.2 7.7 a 0.2 7.6 a 0.3 7.3 a 0.3 7.0 M 44 Site tomdery 7.8 a 0.2 8.6 a 0.3 8.1 a 0.2 8.0 a 0.3 8.1 M 45 Site soundary 11.0 a 0.6 11.3 a 0.5 10.9 a 0.5 11.1 a 0.3 11.1 M 46 Site tomdery 6.6 a 0.2 8.8 a 0.3 8.6 a 0.2 8.6 a 0.3 8.2 DR 47 Site soundary 5.6 a 0.2 8.2 a 0.3 8.3 a 0.3 8.1 a 0.3 7.6 DR 48 Site Boundary 5.3 a 0.2 7.3 a 0.2 7.2 a 0.3 7.0 a 0.3 6.7 DR 49 Site somdery 4.9 a 0.2 6.9 a 0.2 6.8 a 0.2 6.4 a 0.2 4.3 DR 50 eovernor Net nouse 5.7 a 0.2 7.4 a C.2 7.3 a 0.3 7.1 a 0.2 6.9 M-51 Site Boundary 6.3 a 0.2 8.7 a 0.4 8.6 a 0.3 8.4 a 0.3 8.0 DR 52 Site Bo m dery ** 8.9 a 0.2 8.9 a 0.3 8.7 a 0.3 8.8
- Dete'not evellebte due to missing TLDs.
" DR 52 was first posted midway through the first gaerter 1994.
! 40 1
.. .- . - - - - . . - .. .. . . . . - . --. . - - -- - - - . ~. -
1 i l
} 6. AM& LYSIS OF Mf?IBOMMEMTAL RESULTS I l
6.1 * - 1tne Prorran Deviations
- Radiological Effluent Technical Specification 3.9.C allows for deviations "if cpecimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons." In 1994, coveral deviations were noted in the REMP. These deviations did not compromise the prrgram's effectiveness and in fact are considered typical with respect to what is normally anticipated for any radiological environmental monitoring program. The tpecific deviations for 1994 were
- a. Three hourly aliquots of water were missed by the automatic compositing sampler at Station WR-11 on March 23 due to maintenance work on sampling '!
building and sampling system. '
- b. The automatic compositing sampler at Station WR-11 was found out of service on April 17. Daily grab samples were collected until the pump was replaced on May 5.
- c. During the period May 24 to June 7, the air sampling pump at Station AP/CF-15 ran for only 50.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> due to a blown fuse. The fuse was replaced on June 7. l
. l l
6.2 Ca-n=rison of Achieved t.T.ns with Reauir== ants Table 4.9.3 of the VYNPS Technical Specifications (also shown in Table 4.4 of this r: port) gives the required Lower Limits of Detection (LLDs) for environmental sample !
analyses. On occasion, an LLD is not achievable due to a situation such as a low :
cample volume caused by sampling equipment malfunction. In such a case, Technical Specification 6.7.C.3 requires a discussion of the situation. At t.he Yankee Atomic- !
Environmental Laboratory, the target LIS for any analysis is typically 30-40 percent of the most restrictive required LIE. Expressed differently, the typical censitivities achieved for each analysis are at least 2.5 to 3 times great $r than l thtt required by VYNPS Technical Specifications. l l
Fsr each analysis having an LLD requirement in Technical Specification Table 4.9.3, ths a posteriori (after the fact) LLD calculated for that analysis was compared with ths required LLD. Of the over 7400 analyses performed during 1994, of which cpproximately 1300 had an LID requirement in Technical Specification Table 4.9.3, all met the requirement.
i 6.3 Connarison of Results with Reportina Lavels 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 tha cnvironmental concentrations that relate to the ALARA design dose objectives of 10 CFR 50, Appendix I. It should be noted that environmental concentrations are cvsraged over calendar quarters for the purposes of this comparison, and that Rsporting Levels apply only to measured levels of radioactivity due to plant affluents. During 1994, no Reporting Levels were exceeded.
6.4 channes in Samnline 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 chs11 be identified in the next annual Radiological Environmental Surveillance Esport." No changes were made in the required sampling locations. One TLD monitoring location was added to the site boundary (DR-52), however, near the end of tha first quarter of 1994.
6.5 Data Analysis by Media Tyne Tha 1994 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 atendard deviation. This standard deviation represents only the random uncertainty nosociated 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 thrse times the standard deviation for that analysis. With respect to data plots, all net 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 Th2 bi-weekly air particulate filters from each of the six sampling sites were cn:lyzed for gross-beta radioactivity. At the end of each quarter, the thirteen waskly filters from each sampling site were composited for a gamma analysis. The racults of the weekly air particulate sampling prog;cs are shown in Table 5.1 and Figures 6.1 and 6.2.
~ v , , , , , - - - , - - -- - r - --
r-+,-r
.-. -. . _ - . . -. -- . - . . . . _~ _ _ _ - -
As chown in Figures 6.1, there is no significant difference between the quarterly cvarege concentrations ac the indicator (near plant) stations and the control (diatcnt from plant) stations. Also notable in the Figure is a distinct annual cycle, with the minimum ccncentration in the second quarter, and the maximum cencsntration in the first. quarter. The peak seen in the second quarter of 1986 is cirborne contamination renulting from the Chernobyl accident, as detected by the Varmont Yankee monitoring program.
Figuros 6.2 throuBh 6.6 show the weekly gross beta concentration at each air p:rticulate sampling location alongside the same for the control air particulate campling location at AP-21 (Spofford Lake, NH). Small differences are evident, and oro expected, between individual sampling locations. It can also be seen that the grees-beta measurements on air particulate filters fluctuate sign'ificantly over the ccurce of a year. The measurements from control station AP-21 vary similarly, indicating that these fluctuations are due to regional changes in naturally-eccurring airborne radioactive materials, and not due to Vermont Yankee operations.
A single data point that stands out on Figure 6.6 is the gross-beta concentration at 1ccation AP-15 (Tyler Hill Road) for the sampling period May 24-June 7. The-reported concentration is suspect due to the low sample volume for that period. (See osction 6.1 above regarding the low sample volume, which was caused by a blown fuse et tha sampling station.)
Tha enly other radionuclide detected on air particulate filters was Be-7, a naturally-occurrin5 cosmogenic radionuclide.
6.5.1.2 Charcoal Cartridnes Tha bi-weekly charcoal cartridges from each of the six air sampling sites were tnalyzed 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.
i 6.5.2 Waterborne Pathways 6.5.2.1 River Water Aliquots of river water were automatically collected hourly from the Connecticut
'Riv2r downstream from the plant discharge area. Monthly grab samples were also collected at the upstream control location, also on the Connecticut River. The ccupssited samples at WR-11 were collected monthly and sent to the Yankee Atos.ic Envircnmental Laboratory, along with the WR-21 grab samples, for analysis. Table 5.1 chows that gross-beta measurements were positive in most samples, as would be cxpicted, due to naturally-occurring radionuclides in the water. The mean
I cancentrations at the indicator and control locations were not significantly different in 1994. Both mean concentrations were consistent with those detected in pr vious years, as shown in Figure 6.7. No gamma-emitting radionuclides attributable to VYNPS operations were detected in any of the samples.
Fcr ccch sampling site, the monthly samples were composited into quarterly samples fsr Tritium (H-3) analyses. None of the samples contained detectable quantities of H-3.
6.5.2.2 Ground Water l Qutrtsrly ground water samples were collected from two indicator locations (only one is required by VYNPS Technical Specifications) and one control location during 1994.
T blo 5.1 and Figure 6.8 show that gross-beta measurements were positive in all j cas.ples. This is due to naturally-occurring radionuclides in the water. The levels ct all sampling locations, including the higher levels at station WC-11, were l
j c:nsistent with that detected in previous years. The one exception to this was the I
_May 14, 1992 sample from UC-12, which had a higher gross-beta concentration than normal for that location. This was possibly explained by the incorrect addition of proosrvative 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 detseted in any of the samples.
6.5.2.3 Sediment i i
S:ciennual sediment grab samples were collected from two locations during 1994. A l cinglo sample was collected from SE-11 on May 24 and again on October 28. Twenty-l thrse (23) and twenty-four (24) grab samples were collected from a gridded area at tha Ncrth Storm Drain Outfall (SE-12) on these two respective dates. As would be l cxpscted, naturally-occurring K-40 and Th-232 were detected in all samples. l Naturally-occurring Be-7 was detected in three samples. l t
l In cddition to the above radionuclides, Cs-137 was detected in most samples, as was j cxp3cted. The levels measured at both locations were consistent with what has been mensured in the previous several years and with that detected at other New England 1ccations that are monitored as part of other Yankae-affiliated environmental monitoring programs. This Cs-137 is attributed to nuclear weapons testing fallout thst has persisted in the environment. This is further substantiated by the fact th:t there has only been one liquid release from Vermont Yankee during the period 1982 through 1994. No Cs-137 was detected in the sample of that release water.
Cs-60 was also detected in 3 of the 49 samples from station SE-12. This rcdioactivity is due to plant operations and is localized within a small area near ,
I
= -. - - . - . - - - . - - - . - - - - - - - . - - - . . -- _
l 4
3 ths west shore of Vernon Pond. Its presence has been monitored for several years.
? It should also be noted that the mean values for all radionuclides in Table 5.1 are l vsighted heavily toward station SE-12, since 47 of the 49 samples collected in 1994 ;
wars from that location. No Co-60 has been detected at station SE-11, which is !
downstream of the plant discharge structure and the North Storm Drain Outfall )
j (SE-12), i l
! 6.5.2.4 Storm Drains i >
j During 1994, grab samples of water were collected from the on-site storm drain cystem at Vermont Yankee (twelve monthly samples from the South Storm Drain W-10 j and four samples from the North Storm Drain W-12). At W-10, samples collected on Jcnuary 11 and March 2~showed detectable levels of H-3 (4230 1 250 and 780 1 210 pCi/kg, respectively). A summary of these values is given in Table 5.1. Although tha environmental Reporting Level of 30,000 pCi/kg is not used for on site samples, it can nonetheless be used to put the stora drain results into the proper i a perepective. None of the detected concentrations of H-3 approached this
! cnvironmental Reporting 14 vel.
1 ;
l 6.5.3 Innestion Pathways l 6.5.3.1 Milk I i
j Milk samples from cows or goats at several local farms were collected monthly during ,
j 1994. Semimonthly collections were made during the " pasture season" since the !
j =ilking 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. I j Quarterly composites (by location) were analyzed for Sr-89 and Sr-90. l l
! As was expected, naturally occurring K-40 was detected in all samples. Also !
I expscted were Cs-137 and Sr-90. Cs-137 was detected in 12 out of 90 indicator !
i camples. Sr-90 was detected in 10 out of 20 indicator samples. Although both l Co-137 and Sr-90 are a by-product of plant operations, the levels detected in milk 1 cra consistent with that expected from worldwide fallout from nuclear weapons tests,
{ cnd to a much lesser degree from fallout from the Chernobyl incident. These two
] radionuclides are present throughout the natural environment as a result of ,
l ctuoepheric nuclear weapons testing that started primarily in the late 1950's and i centinued through 1980. They may be found in soil and vegetation, as well as cnything that feeds upon vegetation, directly or indirectly. The Cs-137 and Sr-90
-lovals shown in Table 5.1 and Figures 6.9 and 6.10 are consistent with those j
- dstseted at other New England farms that are monitored as part of other Yankee- l t i 2
, ~ - - - - -, ,<a - , ,,n- , - - - - - ,,a- v -r,v---e.m,-
I i
l
- cffiliated environmental monitoring programs. It should be noted here that most of j tha Cs-137 concentratione and many of the Sr-90 concentrations shown on Figures 6.9 j cnd 6.10, respectively, are considered "not detectable." All values have been plotted, regardless as to whether they were considered statistically significant.
J
- As chown in these figures, the levels are also consistent with those detected in
- previous years near the VYNPS plant. There is also little difference in )
cenesntrations between farms, with one exception. The goat milk from TM-12 4
- gtnerally has had elevated levels of Cs-137 and to a lesser degree, Sr-90 relative 1 to the other locations. It has been shown in the past that fallout-related Cs-137 j ad Sr-90 in cow or goat milk can vary substantially from one farm to the next, due j primarily to the differences in feeding habits of the animals. It is also known j th-t goats have a much higher transfer coefficient from vegetation to milk for ctrentium and cesium. This means that for a given amount of Cs-137 or Sr-90 in the j vagatation, the concentration in the milk will typically be higher for a goat than j for a cow (Reference 5).
! It should be noted in Figures 6.9 and 6.10 that the plot for TM-16 includes data l from several dairy farms, all located successively on the same land. The Meedow l Crest farm has provided sampi.s only since October 1993.
l J
6.5.3.2 Silage '
}
j A silage sample was collected from each of the required milk sampling stations !
- bstwaen September 20 and October 6. Each of these was analyzed for gamma-emitting redienuclides. As expected with all biological media, naturally-occurring K-40 was f dstected in all samples. Naturally-occurring Be-7 was also detected in half of the l j eamples. No gamma-emitting radionuclides were detected in the silage samples. 1 1
6.5.3.3 Mixed Crass l l
u
! Mixsd grass samples were collected at each of the air sampling stations on three !
occasions during 1994. As expected with all biological media, naturally-occurring l
) K-40 was detected in all samples. Naturally-occurring Be-7 was also detected in '
! most samples. Cs-137 was detected in one indicator sample (37.3 8.2 pCi/kg at station TG-15 on May 25, 1994). Although Cs-137 is a by-product of plant
- eparations, the levels detected in grass are due to worldwide fallout from nuclear
] warpons tests, and to a much lesser degree from fallout from the Chernobyl incident, j This radionuclide is present throughout the natural environment as a result of ctuospheric nuclear weapons testing that started primarily in the late 1950's and i continued through 1980. It may be found'in soil and vegetation, as well as anything
- that feeds upon vegetation, directly or indirectly. The Cs-137 levels in grass chtwn in Table 5.1 are consistent with those that have been detected at other New i
4 i
---. - . -i
l i
i Eng1cnd locations that are monitored as part of other Yankee-affiliated snvirennental monitoring program.
6.5.3.4 Ilah S:ciennual samples of fish were collected from two locations during 1994, as follows: a) yellow perch and smallmouth bass at both locations (FH-11 and.FH-21) l fer the May collection, b) yellow perch and white perch at FH-11 for the October es11cetion, and c) yellow perch and smallmouth bass at FH-21 for the October collection. The edible portions of'each of these were analyzed for gamma-omitting )
redienuclides. As expected in biological matter, naturally-occurring K-40 was '
detccted in all samples.
As th:wn in Table 5.1, Cs-137 was detected in one of the two indicator samples. l This level of Cs-137 is typical of what has been detected at both the control and l indicator stations in previous years, as can be seen in Figure 6.11, and is-attributed to global nuclear weapons testing fallout. No other radionuclides were ,
detceted.
i 6.5.4 Direct Radiation Pathway Dirset radiation was continuously measured at 51 locations (52 beginning with the accend quarter of 1994) surrounding the Vermont Yankee plant with the use of tharmoluminescent dosimeters (TLDs). These are collected every calendar quarter for racd ut at the Yankee Atomic Environmental Laboratory. The complete summary of data may b found in Table.5.3.
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 1994. This indicates no significant overall increase in direct radiation exposure rates in the plent 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.
Figura 6.12 also shows an annual cycle at both indicator and control locations. 12un ,
lewaet point of the cycle occurs during the winter months. This is due primarily to ,
ths attenuating effect of the snow cover on redon emissions and on direct i irrcdiation by naturally-occurring radionuclides in the soil. Differing amounts of th2se naturally-occurring radionuclides in the underlying soil, rock or nearby ,
building materials result in different radiation leve" < between one field site and ;
enoth2r.
]
i l
i Uptn cxamining Figure 6.16, as well as Table 5.2, it is evident that in recent years ctstien DR-45 had a higher average exposure rate than any other station. This lecction is on-site, and the higher exposure rates are due to plant operations in th3 imunediate vicinity of the TLDs. There is no significant dose potential to the curraunding population or any real individual from these sources since they are loc:t;d on the back side of the plant site, between the facility and the river. The came can be said for station DR-46, which has shown higher exposure rates in pr:vicus years.
4 h
l I
l l
i l
RGURE 6.1 GROSS BETA PEASUREMNIS ON AIR PARTICULATE RLTERS l l
QUARTERLYAVERAGECONCENTRATIONS 0.16 0.16 mEFNOBYL 0.12- 9 -0.12
~
~
3 ,
I $
$ 0.08- -0.08 p -
R . -
0.04- -0.04 D 8" h 0 .
, 0 1/1/84 1/1/86 1/1/88 1/1/90 1/1/92 1/1/94 l
l J
-e- Indicator Stations
-x- Control Station 1
4 i
RGURE6.2 l
- GROSSeETAIEASUREhENTS ,
ON AIR PARTICULATE RLTERS l 0.06 0.06 l
- ~.
~
0.05f -0.05 B
0.04 '.
-0.04
~
o -
1 3 0.03 , -0.03 M -
..x. .x -
g" .x*. ,y.,x
~
Q .M '
" 0.02- .X 'x - -0.02 1
.x .
-g x'
_ .x.x.x.X.x..x x 0.01 - -0.01 1
W O' . ,
, . , 0 Jan Apr Jul Oct Jan 1994 4
-e- AP-11 River Station No. 3.3 i
x- AP-21 Spofford Lake, NH i
l I
l l
l l
l i
RGURE6.3 GROSS-BETAMEASURENENTS t
1 ON AIR PARTICULATE RLTERS 0.06 -
0.06 0.05-' _- 0.05
~
0.04 -0,04
}
$ . ~
o . ~
'.5 0.03- -0.03
.d x -.x-q O.02-
'x '
.- 0.02
- x x. x- :
0.01 i h 0.01 O' . ,
o Jan Apr Jul Oct Jan 1994
-e- AP-12 N. Hinsdale, NH x- A P-21 Spofford Lake, NH l
l l
RGURE 6.4 GROSS BETANEASUREM NTS ON AIR PARTICULATE RLTERS 0.06 , 0.06
~
0.05f -0.05 B 0.04 , -0.04
~
~
0.03- -0.03 )
.x X .X x*
3 ~
, ..X..
.g x -0.02 0.02 . .x
-R x y. . .x - y .-
, .x '
O.01 - -0.01 E
O . .
, , . . O !
Jan Apr Jul Oct Jan 1994
-e- AP-13 Hinsdale Substation x- AP-21 Spofford Lake, NH
l FIGURE 6.5 i l
GROSSaETA PEASUREMENTS l ON AIR PARTICULATE RLTERS i 0.06 0.06 0.05f -0.05 3 0.042 -0.04 fo .
-0.03 3 0 .03- -
M oa Xx -
-.x y
..x.
x 0.02 . -0.02
. .x. .g
.x . .g
-W *. .x
- x..x '*'
0.01 - - 0.01 0- . ,
, . , . O Jan Apr Jul Oct Jan 1994
-e- AP-14 Northfleid, MA I
x- AP-21 Spofford Lake, NH l
i I
RGURE6.6 GROSSOETA NEASURENENTS ON AIR PARTICUt.A'E RLTERS 0.06 , .
0.06 <
~
0.05 -0.05
~
B 0.04 - 0.04 ,
E : :
')
'~
0.03 . -0.03
..x. .x E 0.02 'x.
R -0.02
- >t x.. .x- : ,
0.01 - h 0.01 0 . . , . , , . .
. . . O Jan Apr Jul Oct Jan 1994
-e- AP-15 Tyler Hill Road x- AP-21 Spofford Lake,NH l l l
t 1
I l
1 l
i l
i
- l
. RGURE6.7 i
GROSS-BETA PEASL REMNTS ON RVER WATER
' I SEM-ANNUALAVERAGECONCENTRA'nONS 16 16 3 :
~
142 -14
- l 12i h12 i
10i h10 g .
8- -8 5
1 6c. .
~
62 -6
~
4 _~
_4 i
j .
l 2ihe e" -p;P h2 0 . , . , .
. 0 l 1/1/85 1/1/87 1/1/89 1/1/91 1/1/93 1/1/95 1
- 1 l
-e- WR 11 River Station No. 3.3 ]
l e WR-21 Rt.D Bridge i
l 4
9 i
T
1 RGURE6.8 j GROSS BETA NEASURENENTS ON GROUND WATER i SEM ANNUAL AVERAGECONCENTRATIONS 16 , _ 16 f
- 145 h.14
,' 12 . -12 i .
~
i 102 -10 m .
i ho. Bi h8 i 6- -6 J
4 -4 4
1 2- -2 4
1 0' .
i ~0 ;
4 7/1/84 7/1/86 7/1/88 7/1/90 7/1/92 7/1/94 j
i i
a WG-11 Plant Well
- ! e WG-12 Vemon Nursing Well
-x- WG-21 Brattleboro CC
! --*- WG-22 Skibniowsky Well 4
i 4
l i
RGURE6.9
~
CESIUM-137IN MLK ANNUAL AVERAGE CONCENTRATONS 20 20 15- .
-15 10- -10 cm -
5 -
oct -
4 5- -5 NM
^ ^
0 = "'
v' "' V -0 3
f .
l -
-5 .
i i . , , -5 1984 1986 1988 1990 1992 1994
-e- TM-11 Miller (cow)
--o- TM 12 Dominick (goat)
A TM-14 Brown (cow)
, e TM-16 Meadow Crest Farm (cow)
-v- TM-24 County Farm (control) 1 l
l I
j I
i l
RGURE 6.10
, STRONT1UM 90IN MLK ANNUALAVERAGECONCENTRAT10NS 10 10
~
6- -6 0 .
5 .
Q .
4- -4
- Y -
0 .
i . , .
1 0 1984 1986 1988 1990 1992 1994
-e- TM 11 Miller (cow)
-o- TM-12 Dominick (goat)
L TM-14 Brown (cow)
-o- TM-16 Meadow Crest Farm (cow)
-t- TM-24 County Farm (control) l
-ss-1 1
l l
i
i RGURE 6.11 l
4 i
CESIUM-137 IN RSH l ANNUAL AVERAGE CONCENTRATIONS j 140 140 1
l 120- -120 l .
100- -100 l
j .
i cm 80-.
-80 3
M .
!S 4
60-
-60 t .
{ . .
1 i 40- -40 l'iliiiiiiiirItlirIrl j
i O
85 86 87 88 89 Year 90 91 92 93
~
94
--O
! E FH 11 Vemon Pond O FH-21 Rt. 9 Bridge (Control) i i
i
)
RGURE 6.12 EXPOSURE RATE ATINNER RING, OUTER RING AND CONTROLT1.DS 20 20 G
m O
15- -15 1 -
u E -10 x 10-h .
$ : A= , m..i.-w .
5- x -5 G
5 0 . . .
i . . .
i 0 1990 1991 1992 1993 1994 1995 Retrieval Date
-et- Inner Ring o Outer Ring
-x- Control i
i 4
FGURE 6.13 EXPOSURE RATE AT NDCATOR TLDS, DR 01 -03 20 20 ;
15- -15 8
z -
10- -10 <
5-h %_ -
-5 0 ... ... ... .. ,...,0 1990 1991 1992 1993 1994 1995' l
Retrieval Date l l
-e- DR-01 River Stadon No. 3.3
-x-- DR-02 North Hinsdale, NH e DR-03 Hinsdale Subste6on j
l l
RGURE 6.14 i EXPOSURE RATE ATINDICATOR TLDS, DR 06, 50 20 20 15 -- -15
~
8 .
x- -
E -10 x 10- - ~
- 3 .
E -
5- -5 0 . . .
i . . . , 0 1990 1991 1992 1993 1994 1995 Retrieval Date
-e- DR-06 Vemon School j x DR-50 Gov. Hunt House I
1 FGURE 6.15 EXPOSURE RATE ATNDCATORTLDS, DR 07-06, 41 -42 20 20 15- -15 8
g . .
10- -10 4 -
8 -
5 5- -5 0 . , . . , . ,
, . . . , . . , O 1990 1991 1992 1993 1994 1995 Retrieval Date
-e- DR-07 She Boundary
-x- DR-08 Site Boundary e DR-41 Site Boundary
-o- DR-42 SRe Boundary l
i FGURE 6.16 EXPOSURE RATE Al SITE BOUNDARYTLDS, DR 43 -46 60 60 50- -50 Lowleelweste or>4lte storage .
k
- 40- -40 8
x .
30- -30 ct:
g . .
5 20- -20 10- e "e A
-10 Mi 3 NdDY Pu O , .
, 0 1990 1991 1992 1993 1994 1995 Retrieval Date
--e- DR-43 Site Boundary x DR-44 Site Boundary e DR-45 Site Boundary
-o- DR-46 Site Boundary I
RGURE 6.17 EXPOSURE RATE AT STE BOUNDARY RDS, DR 47 - 49, 51 - 52 20 20 15- -15 8
x -
10- -10
~
6 p -
lE e e x -'
5- -5 0 . . .
i 0 1990 1991 1992 1993 1994 1995 Retrieval Date
-e- DR-47 SRe Boundary
--x- DR-48 Site Boundary
--n - DR-49 Site Boundary e DR-51 She Boundary
-o- DR-52 Site Boundary l
l I
i
'1
I
\
FGURE 6.18 EXPOSURE RATE ATNNER RNG TLDS, DR 09-15 (Odd) 20 20 15- -15 5 -
0 -
I 10- -10 g :
s -
n n n n y 5- -5 0 . . .
i . . .
i 0 1990 1991 1992 1993 1994 1995 Retrieval Date
-e- DR-09 inner Ring ;
-x- DR-11 inner Ring l l
e DR-13 inner Ring j
--o- DR-15 inner Ring I
I I
l
FGURE 6.19 EXPOSURE RATE ATNNER RNG TLDS, DR 17-23 (Odd) 20 20 l I
15- -15 8
z -
10- -10
~
h _
~
5 5-M% -5 0 . . .
i 0 1990 1991 1992 1993 1994 1995 Retrieval Date
-e- DR-17 inner Ring
-x- DR-19 inner Ring a DR-21 Inner Ring !
-o- DR-23 inner Ring l
\
FGURE 6.20 EXPOSURE RATE AT NNER RNG TLDS, DR 25 -31 (Odd) 20 20 15- -15 8 -
I 10- -10 e :
3 . - - _ .
. "i^Fuyo 5- -5 t
~
. I 0 . . .
i 0 1990 1991 1992 1993 1994 1995 Retrieval Date
--e- DR-25 inner Ring x DR-27 inner Ring a DR-29 inner Ring
--o- DR-31 Inner Ring 1
I FGURE 6.21 EXPOSURE RATE ATNNER RNG T1.DS, DR 33-39 (Odd) 20 20 i 15- -15 y . -
o ~ .
I 10- -10 C . .
6 o -
y h1 -
L .
N T "'r 5- -5 0 . . .
i i . . .
i . . . , . .
.i 0 t 1990 1991 1992 1993 1994 1995 Retrieval Date
-e- DR-33 inner Rhg e DR-35 inner Rhg a DR-37 inner Rhg c DR-39 inner Rhg i
l 1
I i
I
. FGURE 6.22 l EXPOSURE RATE ATOUTER RNG T1.DS, DR 10-16 (Even) 20 20 4
i
- 15- -15 4
1 -
10- -10
, : c%, u 5- 5 -- 5 0 ...,...,...,... ...i 0 1990 1991 1992 1993 1994 1995 Retrieval Date
-e- DR-10 Outer Ring e DR-12 Outer Ring 4 DR-14 OuterRing
-o- DR-16 Outer Ring
1 FGURE 6.23 i 1
EXPOSURE RATE ATOUTER RNG TLDS, DR18-24 (Even) 20 20 15 -15 I
10- -10 5 -g N 5- -5 4 0 . . .
i . . . , 0 1990 1991 1992 1993 1994 1995 Retrieval Date
--e- DR-18 Outer Ring x DR-20 Outer Ring a DR-22 OuterRing e DR-24 OuterRing f
FGURE 6.24 EXPOSURE RATE ATOtJTER RNG TLDS, DR 26 -32 (Even) 20 20 f .
15- -15 8
x -
10 -10 tr '
h .
5 =
=& -
1 5- -5
~
I O . . ,
....i.. ,..,,O i 1990 1991 1992 1993 1994 1995 1 Retrieval Date i
A i
j --e- DR-26 Outer Ring x DR-28 OuterRing e DR-30 Outer Ring i
3 e DR-32 Outer Ring 1
4 4
1 FGURE 6.25 4
EXPOSURE RATE ATOUTER RNG TLDS, DR34-40 (Even) 20 20
~
j 15- -15 i
g I
4 10- -10
- M . .
~ '
5-
[ v- o
[W -5 0 . . . , . . , . . .
, . . . , , . . , 0 1990 1991 1992 1993 1994 1995 Retrieval Date l
-e- DR-34 Outer Ring
--x- DR-36 Outer Ring a DR-38 OuterRing
-e- DR-40 Outer Ring
)
{
l
RGURE6.26 EXPOSURE RATE ATCONTROL11.DS DR 04-05 20 20
~
e 15- -15 Ei
$m '
E 10- -10 x '
o -
^ n 5- -5 0 . . .
i . . .
i 0 1990 1991 1992 1993 1994 1995 Retrieval Date
-e- DR-04 Northfield,MA i l
x DR-05 Spofford Lake, NH l l
l l
l
_- . . -. . _ _ ~ .. - = - . . - - . .- _ . = _ . -
(
1 l
l 1
l
- 7. QUALITY ASSURhMCE PROGRAM ;
I j Tha quality assurance program at the Yankee Atomic Environmental Laboratory is l designed to serve two overall purposes: 1) Establish a measure of confidence in the j meccurement process to assure the licensee, regulatory agencies and the public that tha cualytical results are accurate and precise; and 2) Identify deficiencies in the campling and/or measurement process to those responsible for these operations so that corrective action can be taken. Quality assurance 's replied to all steps of j thz measurement process, including the collectior - reductirh , svaluation and reporting of data, as well as the record keepi g of the final results. Quality
' centrol is a part of the quality assurance program. It provides a means to control cnd measure the characteristics of measurement equipment and processes, relative to
- estchlished requirements.
l l
Tha Ysnkee Atomic Environmental laboratory employs a thorough quality assurance ,
program to ensure reliable environmental monitoring data. The program includes the 4 usa of written, approved and controlled procedures for all work activities, a j nonconformance and corrective action tracking system, systematic internal audirs, j cudits from external groups, a laboratory quality control program, and a complete
- treining and retraining system. The Intralaboratory Quality Control program at the
- Laboratory and the EPA third party interlaboratory program are discussed in more j dateil below. Also discussed is the environmental TLD quality assurance program and
- tha blind duplicate quality assurance program conducted by the Laboratory Quality j Centrol Audit Committee.
1 h
)
j 7.1 Intralaboratory Ouality control Pronram l t
} Tha Yankee Atomic Environmental Laboratory conducts an extensive intralaboratory l quality control program to assure the validity and reliability of non-TLD analytical data. Included are the internal process contr>l program and the National Institute of Stendards and Technology (NIST) Measurement Assurance Program. These together cerprise about five percent of the laboratory sample throughput. The records of the !
{ quality control program are reviewed by the responsible cognizant individaal, and i corrsctive measures are taken whenever applicable. A summary of the pragram results
] may be found in Figure 7.1 7.2 EPA Intercomoarison Pronram i
- To further verify the accuracy and precision of the Laboratory analyses via an l indspendent outside third party, the Yankee Atomic Environmental Laboratory i ptrticipates in the U.S. Environmental Protection Agency's Environmental l i i
)
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1 1
J j Redicactivity Laboratory Intercomparison Studies Program for those available species i
and r.atrices routinely analyzed by the Laboratory. Participation in this program is l required by VYNPS Technical Specification 3.9.E. Each sample supplied by the EPA is I
analyzed in triplicate, and the results are returned to the EPA within a specified tima frame. When the 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 messures 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 135 analyses for accuracy on 24 *
- cample sets. The samples consisted of water, milk and air particulate filters. The ,
l cnslyses were for gamma-emitting radionuclides, gross-beta, strontium, iodine, j tritium and radium. Tables 7.2 and 7.3 show summaries of the results for 1994 All
- of the 135 analyses met the EPA mean value control limits for accuracy. ;
3 i
j 7.3 Environmental TLD Ouality Assurance Program
] The Panasonic environmental TLD (thermoluminescent dosimeter) program at the YAEL has its own quality assurance program. In addition to instrumentation checks
) parformed 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 j Officer, and the second involves the third-party testing program by Battelle Pacific 1 Northwest Laboratories. Under these programs, dosimeters are irradiated to known ;
doses (unknown to the DSG) and given to the DSG for read-out. !
j In 1994, out of 2012 TLDs processed at the YAEL, 4.24 (84 TLDs) were processed as
- pcrt of the performance testing program. Of these 84 TLDs, 60 were from the in- i j hcuse Dosimetry QA Officer, and 24 were from the Battelle Pacific Northwest l Laboratories testing program. All of these (1004) met the acceptance criteria for
] eccuracy and precision.
i 7.4 Blind Dunlicate Ouality Assurance Program
} The Laboratory Quality control Audit Committee (14CAC) is comprised of one member I from each of the five power plants that are serviced by the Yankee Atomic 1
Environmental Laboratory. Two of the primary functions of the 14CAC are to conduct an annual audit of Laboratory operations and to coordinate the Blind Duplicate Quality Assurance Program. Under the Blind Duplicate Quality Assurance Program, e
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pairsd samples are submitted from the five plants, including VYNPS. They are prspared 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 cf the paired analyses to evaluate precision in Laboratory measurements.
A total of 50 paired samples were submitted under this program by the five participating plants during 1994. Paired measurements were evaluated for 26 gamma c=itting radionuclides, H-3, Sr-89, Sr-90, I-131 and gross beta. All measurements wara evaluated, whether the results were considered statistically positive or not, and whether the net concentration was positive or negative. Of the 1310 paired duplicate measurements evaluated in 1994, 1307 (99.8%) fell within the established ccesptance criteria. With the three paired measurements that did not meet the ccesptance criteria, none had radioactivity that was considered statistically positive. The samples submitted through this program are listed in Table 7.4.
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! TABI2 7.1 i
SUMMARY
OF PROCESS CONTROL ANALYSIS RESULTS January - December 1994
/
ACCURACY PRECISION ,
SAMPLE MEDIA NUMBER NUMBER
, ANALYSES ANALYSES NUMBER OF OUTSIDE NUMBER OF OUTSIDE
. ANALYSES ACCEPTANCE ANALYSES ACCEPTANCE CRITERIA CRITERIA AIR CHARCOAL Gamma 120 2 0 0 2
AIR FILTER l Beta 115 0 0 0 1
- Camma 9 0 3 0 j Strontium 0 0 0 0 MIIX 4 Gamma 63 2 66 0 j Iodine 24 0 24 0 Strontium 20 0 20 0 WATE l
{ Gross-Beta 3 0 3 0 Gamma 6 0 6 0 Iodine 6 0 6 0 i <
! Strontium 12 0 12 0 Tritium 0 0 0 0 SOIL / SEDIMENT Gamma 0 0 32 0 I
l TOTAL 378 4 172 0 1
- i
! l
, 1 4
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TABLE 7.2 i
EPA INTERCOMPARISON ANALYSIS RESULTS January - December 1994 EPA Ref. Sample Nuclide YAEL EPA l Date Type Mean Control (pCi/1) Limits (pci/1) 1
! 1-14-94 Water Sr-89 28.97 16.30-33.70 l Sr-90 12.17 6.30-23.70 1-28-94 Water Beta 65.31 44.70-79.30 2-4-94 Water I-131LL 121.71 98.20-139.80
- 3-4-94 Water H-3 4474.84 4078.90-5793.10 4-19-94 Water Ra-226 17.50 14.80-25.20 Ra-228 22.03 11.40-28.80 4-19-94 Water Sr-89 19.10 11.30-28.70 i Sr-90 13.13 5.30-22.70
! 4-19-94 Water Co-60 19.21 11.30-28.70
- Cs-134 32.98 25.30-42.70 i
Cs-137 29.30 20.30-37.70 6-10-94 Water Co-60 49.49 41.30-58.70 i
Zn-65 137.37 111.40-156.60 Ru-106 232.62 208.60-295.40 Cs-134 39.04 31.30-48.70 Cs-137 52.28 40.30-57.70 Ba-133 87.63 80.70-115.30
- 7-15-94 Water Sr-89 37.03 21.30-38.70 Sr-90 19.63 11.30-28.70 7-22-94 Water Beta 11.74 1.30-18.70 8-5-94 Water H-3 9868.71 8224.70-11677.3
) !
i k
TABLE 7.2, continued EPA INTERCOMPARISON ANALYSIS RESULTS January - December 1994 EPA Ref. Sample Nuclide YAEL EPA Date Type Mean Control
- (pCi/1) Limits (pci/1) -
8-26-94 Part. Filter Cs-137 15.95 6.30-23.70 8-26-94 Part. Filter Sr-90 17.17 11.30-28.70 8-26-94 Part. Filter Beta 53.56 38.70-73.30 9-30-94 Milk Cs-137 63.10 50.30-67.70 K-40 1461.72 1305.88-1554.70 9-30-94 Milk I-131LL 69.96 61.10-88.90 9-30-94 Milk I-131 76.71 61.10-88.90 9-30-94 Milk Sr-89 16.32 16.30-33.70 Sr-90 15.43 6.30-23.70 {
10-7-94 Water I-131LL 76.92 65.10-92.90 10-18-94 Water Co-60 39.60 31.30-48.70 Cs-134 18.82 11.30-28.70 Cs-137 41.46 30.30-47.70 10-18-94 Water Sr-89 18.97 16.30-33.70 Sr-90 15.53 6.30 23.70 10-18-94 Water Ra-226 8.17 7.30-12 50 Ra-228 9.87 5.80-14.40 10-28-94 Water Beta 21.95 15.58-34.53 11-4-94 Water Co-60 56.74 50.30-67.70 Zn-65 '103.72 82.70-117.30 Cs-134 23.42 15.30-32 :S Cs-137 50.19 40.30-57.70 Ba-133 71.50 60,90-85.10 e
TABLE 7.3
SUMMARY
OF EPA INTERCOMPARISON PROGRAM RESULTS January - December 1994 NO. 3F NO. OUTSIDE SAMPLE MEDIA SAMPLES NO. OF EPA CONTROL ANALYZED
- ANALYSES LIMITS **
AIR FILTER Beta 1 3 0 Camma 1 3 0 Strontium 1 3 0 MILK Gamma 2 9 0 Iodine 1 3 0 Strontium 1 6 0 WATER Gross-Beta 3 9 0 Gamma 4 51 0 Iodine 2 6 0 Radium 2 12 0 Strontium 4 24 0 Tritium 2 6 0 0 The number of EPA samples that were analyzed for the specified raolonuclide. Each of these samples was analyzed in triplicate.
00 The number of mean values (from triplicate samples) outside EPA Control Limits.
TABLE 7.4 SIDDU.RY OF BLIND DUPLICATE SAMPLES SUBMITTED January - December 1994 TYPE OF SAMPLE NUMBFJL OF PAIRED SAMPLES SUBMITTED Cow Milk 20 Cround Water 6 Surface Water 17 Irish Moss 2 Mussels 4 Food Product - 1 Cranberries TOTAL 50
- 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 reteorological sectors within a distance of five miles of the plant. It also idsntifies 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 1994 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, e 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 Method 1 screening 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 Semiannual Effluent Release Report for that period. A re-evaluation of the Critical Receptor would also be done at that time. For the 1994 Census, no such locations were identified.
Pursuant to Technical Specification 3.9.D.2, a dosimetric analysis is then performed, 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 dose (which is eliminated from the program).
For the 1994 Census, no such milk animal locations were identified.
The results of the 1994 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.
TABLE 8.1 1994 IAND USE CENSUS IDCATIONS*
SECTOR NEAREST RESIDENCE NEAREST MILK ANIMAL Km (Mi) Km (Mi)
N 1.6 (1.0) ----
NNE 1.6 (1.0)
NE 1.3 (0.7) ----
ENE 1.0 (0.6) ----
E 1.0 (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 g SSW 0.5 (0.3) ----
SW 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 **
NNW 2.1 (1.3) ----
- Sector and distance relative to plant stack.
- This location overlaps the NW and WNW sectors.
-84
- 9. SUlOULRY During 1994, 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, sediment, fish, milk, silage, mixed grass and storm drain water. In addition to these samples, the air surroundin5 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 ocmples had measurable levels of K-40, Be-7, Th-232 or radon daughter products.
These are the most common of the naturally-occurring radionuclides. 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 te 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.
l
- 10. It)BFERENCES
- 1. '.;;;'UC 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 Canada from Natural Background Radiation, National Council on Radiation Protection and Measurements, 1987.
- 3. Ionizinz Radiation: Sources and Biolorical Effects, United Nations ScientiDe Committee on the Effects of Atomic Radiation (UNSCEAR),1982 Peport F- 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 Analysis, NUREG/CR-3332, U.S. Nuclear Regulatory Commission, Washington, D.C., 1983.
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