ML20035H205

Yankee Nuclear Power Station Annual Radiological Environ Operating Rept,Jan-Dec 1992

ML20035H205
Person / Time
Site:	Yankee Rowe
Issue date:	12/31/1992
From:	Jeffery Grant YANKEE ATOMIC ELECTRIC CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BYR-93-035, BYR-93-35, NUDOCS 9305030313
Download: ML20035H205 (93)

Text

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A YANKEE ATOMICELECTRIC. COMPANY

"'C"",1?gio";"l" cp 580 Main Street, Bolton, Massachusetts 01740-1398

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April 29, 1993 BYR 93-035 i

United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Reference:

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License No. DPR-3 (Docket No. 50-29) l

Subject:

ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT To Whom It May Concern:

Enclosed please find the Annual Radiological Environmental-Monitoring Report for the Yankee Nuclear Power Station.

This report contains a summary and analysis of the radiological i

environmental data collected for the year 1992 and is submitted as required by Technical Specification 6.9.5 (a).

i We trust that you will find this submittal satisfactory; however,,

if you have any questions, please contact us.

Sincerely, YANKEE ATOMIC ELECTRIC COMPANY l

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(.)M. Grant

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fnior Licensing Engineer JG/gbc l

Enclosure l

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M. Fairtile, NRC, NRR E. Kelly, IRC, Region I t'30018 11 l

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YANKEE NUCLEAR POYZR STATION ANNUAL RADIOLOGICAL ENVIRONMENTAL f

OPERATING REPORT January - December 1992 April 1993

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Prepared by:

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Yankee Atomic Electric Company Environmental Engineering Department 580 Main Street Bolton, Massachusetts 01740

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TABLE OF CONTENTS Page TABLE OF CONTENTS.............................................

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LIST OF TABLES................................................

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LIST OF FIGURES...............................................

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1.0 INTRODUCTION

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2.0 NATURALLY OCCURRING AND BACKGROUND RADIOACTIVITY..............

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3.0 GENERAL PLANT AND SITE INFORMATION............................

6 4.0 PROGRAM DESIGN................................................

7 5.0 RADI OIDGI CAL DATA

SUMMARY

TABLES..............................

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6.0 ANALYSIS OF ENVIRONMENTAL RESULTS.............................

44 7.0 QUALITY ASSURANCE PROGRAM.....................................

80 e.e tANo USE CEN US...............................................

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SUMMARY

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10.0 REFERENCES

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LIST OF TABLES Table Title Zagg 4.1 Radiological Environmental Monitoring Program...........

14 4.2 Radiological Environmental Monitoring locations (Non-T1D) 16 4.3 Radiological Environmental Monitoring Locations (TID) 18 4.4 Environmental Lower Limit of Detection (LIE)

Sensitivity Requirements.............................

20 4.5 Reporting Levels for Radioactivity Concentrations in Environmental Samples..............................

21 5.1 Environmental Radiological Program Summary..............

31 5.2 Environmental TLD Data Summary..........................

42 5.3 Environmental TLD Measurements..........................

43 7.1 Summary of Process Control Analysis Results.............

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7.2 Summary of EPA Intercomparison Analysis Results.........

85 7.3 Sumoary of Blind Duplicate Samples Submitted............

86 7.4 Summary of Blind Duplicate Results 87 8.1 1992 Land Use Census locations..........................

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LIST OF FIGURES Firure Title Eggt 4.1 Radiological Environmental Sampling locations Within 1 Mile of YNPS.........................

22 4.2 Radiological Environmental Sampling locations Within 12 Miles of YNPS.......................

23 4.3 Radiological Environmental Sampling locations Outside 12 Miles of YNPS......................

24 4.4 Environmental TLD Monitoring locations at the YNPS Restricted Area Fence.......................

25 4.5 Environmental TIE Monitoring locations Within 1 Mile of YNPS...................................

26 4.6 Environmental TLD Monitoring locations Within 12 Miles of YNPS.................................

27 4.7 Environmental TLD Monitoring locations Outside 12 Miles of YNPS................................

28 6.1 Gross-Beta Measurements on Air Particulate Filters

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(Quarterly Averages) 54 6.2 Gross-Beta Measurements on Air Particulate Filters (AP-ll vs. AP-21 Control) 55 7

6.3 Gross-Beta Measurements on Air Particulate Filters (AP-12 vs. AP-21 Control)...............................

56 6.4 Gross-Beta Measurements on Air Particulate Filters (AP-13 vs. AP-21 Control) 57 f

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LIST OF FIGURES (continued)

Firure Title Za&R 6.5 Cross-Beta Measurements on Air Particulate Filters (AP-14 vs. AP-21 Control) 58 i

6.6 Cross-Beta Measurements on Air Particulate Filters (AP-31 vs. AP-21 Control) 59

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6.7 Cross Beta Measurements of Ground Water.................

60 6.8 H-3 in Ground Water at Station WG-12....................

61 6.9 Cross-Beta Measurements of River Water..................

62 6.10 Cesium-137 in Shoreline Sediment at Station SE-11.......

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6.11 Cesium-137 in Shoreline Sediment at Station SE-21.......

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i 6.12 Cesium-137 in Shoreline Sediment at Station SE-91.......

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6.13 Cesium-137 in Fish......................................

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6.14 Cesium-137 in Milk......................................

67 6.15 Strontium-90 in Milk....................................

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l 6.16 Exposure Rate at Indicator, Outer Ring and Control TLDs.

69 6.17 Exposure Rate at Indicator TLDs, CM 01-04...............

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l 6.18 Exposure Rate at Indicator TLDs, CM 05-08...............

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I 6.19 Exposure Rate at Indicator TLDs, GM 09-12,40............

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6.20 Exposure Rate at Outer Ring TLDs, GM 24-27..............

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LIST OF FIGURES (continued)

Firure Title Zagg 6.21 Exposure Rate at Outer Ring TLDs, GM 28-31..............

74 6.22 Exposure Rate at Outer Ring T Ds, GM 32-35..............

75 6.23 Exposure Rate at Outer Ring TDs, GM 36-39..............

76 6.24 Exposure Rate at Fenceline TLDs, GM 13-16...............

77 6.25 Exposure Rate at Fenceline TLDs, GM 17-21...............

78 6.26 Exposure Rate at Control TLDs, GM 22-23.................

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l.0 INTRODUCTION This report summarizes the findings of the Radiological Environmental Monitoring Program (REMP) conducted by Yankee Atomic Electric Company in the vicinity of the Yankee Nuclear Power Station (YNPS) in Rowe, Massachusetts during the calendar year 1992.

It is submitted annually in l

compliance with plant Technical Specification 6.9.5.a.

l The remainder of this report is organized as follows:

l Section 2: Provides an introductory explanation to the background radioactivity and radiation that is routinely detected in the YNPS environs.

l Section 3:

Provides a brief description of the YNPS site and its environs.

j Section 4: Provides a description of the overall REMP program design.

Included is a summary of the Offsite Dose Calculation Manual (ODCM)

Requirements for REMP sampling, tables listing all routine sampling and thermoluminescent dosimeter (TLD) monitoring locations with compass j

sectors and distances from the plant, and maps showing the location of each of the sampling and TLD monitoring locations. Tables listing Lower Limit of Detcetion requirements and Reporting Levels are also included.

Section 5: Consists of the summarized data as required by the ODCM.

The tables are in the format specified by the NRC Radiological Assessment Branch Technical Position on Environmental Monitoring (Reference 1). Also included is a summary of the environmental TLD measurements for 1992.

Section 6:

Provides the results of the 1992 monitoring program. The performance of the program in meeting regulatory requirements as given in the Radiological Effluent Technical Specifications and ODCM 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 (YAEL). As required by l

the ODCM, the results of the EPA Intercomparison Program are given.

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Section 8:

Summarizes the requirements and the results of the 1992 Land Use Census.

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Section 9: Gives an overall summary of the results of the 1992 Radiological Environmental Monitoring Program.

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i 2.0 Naturally Occurrine and Man-Made Backcround Radioactivity Radiation or radioactivity potentially detected in the YNPS environment can

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be grouped into three categories. The first is " naturally-occurring" radiation and radioactivity. The second is " man-made" radioactivity from sources other than YNPS.

The third potential source of radioactivity is due to emissions from YNPS. For the purposes of the YNPS REMP, the first two categories are classified as " background" radiation, and are the subject of discussion in this section of the report. The third category, radioactivity from plant emissions, is the one that the REMP is primarily designed to detect and evaluate.

s 2.1 Naturally Occurrine Backcround Radioactivity i

Natural radiation and radioactivity in the environment, which provide the major source of human radiation exposure, may be subdivided into three separate sub-categories:

" primordial radioactivity", "cosmogenic radioactivity" and " cosmic radiation".

" Primordial radioactivity" is made up of those radionuclides that were created with the universe and that have a sufficiently long half-life to be still present on the earth.

Included in this category are the radionuclides that these elements have decayed into. A few of the more important radionuclides in this category are Uranium-238 (U-238), Thorium-228 (Th-228), Rubidium-87 (Rb-87), Potassium-40 (K-40), Radium-226 (Ra-226), and Radon-222 (Rn-222). Uranium-238 and Thorium-228 are readily detected in soil and rock, whether through direct field measurements or through laboratory analysis of samples. Radium-226 f

in the earth can find its way from the soil into ground water, and is often detectable there. Radon-222 is one of the components of natural background in the air we breath, and its daughter products are detectable on air sampling filters.

Potassium-40 comprises about 0.01 percent of all natural potassium in the earth, and is consequently detectable in most biological substances, including the human body. There are many more primordial radionuclides found in the environment in addition to the major ones discussed above (Reference 2).

The second sub-category of naturally-occurring rcdiation and radioactivity is "cosmorenic radioactivity". This is produced through the nuclear interaction of high energy cosmic radiation with elements in the earth's atmosphere, and to a much lesser degree in the earth's crust. These radioactive elements are then incorporated into the entire geosphere and atmosphere, including the earth's soil, surface rock, biosphere, sediments, ocean floors, polar ice and atmosphere. The major radioauclides in this _ _ _ _ _ _ _

1 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 readily detected, and is found on air sampling filters and occasionally in biological media (Reference 2).

The third sub-category of naturally-occurrirg radiation and radioactivity is " cosmic radiation". This consists of high energy atomic and sub-atomic particles of extra-terrestrial origin and the secondary particles and radiation that are produced through their interaction in the earth's I

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.

I Consequently, one can see that with increasing elevation one would be exposed to more cosmic radiation as a direct result of a thinner layer of I

air for protection. This " direct radiation" is best detected in the field with high pressure ion chambers.

l 2.2 liggi-Made Backcround Radioactivity The second source of " background" radioactivity in the YNPS environment is from " man-made" sources not related to the power plant. The most recent contributor to this category was the fallout from the Chernobyl accident in April of 1986, which was detected in the YNPS environment and much of the world. A much greater contributor to this category, however, has been fallout from atmospheric nuclear weapons tests. Tests were conducted from I

1945 through 1980 by the United States, the Soviet Union, the United Kingdom, China and France, with the large majority of testing occurring I

during the periods 1954-1958 and 1961-1962.

(A test ban treaty was signed in 1963 by the United States, Soviet Union and United Kingdom, but not by France and China.) The most recent test, conducted by the People's I

Republic of China, occurred in October of 1980. Much of the fallout detected today is due to this explosion and the last large scale one, done in November of 1976 (Reference 3).

l The radioactivity produced by these detonations was deposited worldwide.

The amount of fallout deposited in any given area is dependent on many factors, such as the explosive yield of the device, the latitude and altitude of the detonation, the ceason in which it occurred, and the timing of subsequent rainfall which washes fallout out of the tropospheric portion (Reference 4). Most of this fallout has decayed into stable elements, but I

the residual radioactivity is still readily detectable in environmental samples worldwide. The two predominant radionuclides are Cesium-137 (Cs-L

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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 radionuclides are e.lso readily detected in milk.

Other potential " man-made" sources of environmental " background" radioactivity include other nuclear power plants, coal-fired power plants, national defense installations, hospitals, research laboratories and

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industry. These collectively are insignificant on a global scale when compared to the sources discussed above (natural and fallout).

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3.0 GENERAL PLANT AND SITE INFORMATION i

The Yankee Nuclear Power Station (YNPS) is located on a 2200 acre site in a predominantly rural area of northwestern Massachusetts, three-quarters of a mile south of the Vermont border. The plant resider in the town of Rowe, Massachusetts, approximately 9 miles east-northeast of North Adams, Massachusetts. The surrounding area is heavily forested and lightly populated. Hills bounding the river valley rise 500 to 1000 feet above the site, reaching elevations of 2100 feet. The plant itself consists of several structures including a reactor containment building, turbine, auxiliary and office buildings, warehouse and storage facilities.

The Deerfield River is used extensively for hydroelectric power generation both upstream and downstream of YNPS. Sherman Dam, immediately adjacent to YNPS, operates as a hydroelectric generating station. Sherman Pond, the impoundment behind this dam, has been used as a source of cooling water for YNPS.

YNPS was voluntarily shut down on October 1, 1991 and was shut down permanently on February 27, 1992 after 32 years of reliable operation. The plant will undergo a process of decommissioning which will eventually l

entail the disassembly and removal of the plant components and structures.

This process will take place in strict conformance with USNRC regulations.

Oversight will also continue from the U.S. Environmental Protection Agency, the Massachusetts Department of Environmental Protection, Massachusetts Department of Public Health, and Massachusetts Emergency Management Administration.

l The radiological environmental monitoring program for YNPS continued to operate through 1992, and will continue throughout the decommissioning period.

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l 4.0 PROGRAM DESIGN I

The Radiological Environmental Monitoring Program for the YNPS was designed with specific objectives in mind. These were:

To provide an early indication of the appearance or accumulation of any radioactive material in the environment caused by YNPS activities.

- To provide assurance to regulatory agencies and the public that the environmental impact from YNPS is known and within anticipated limits.

- To verify the adequacy and proper functioning of station effluent

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controls and monitoring systems.

- To provide standby monitoring capability for rapid assessment of risk

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to the general public in the event of unanticipated or accidental I

releases of radioactive material.

These objectives will continue to be in force, to varying degrees, throughout decommissioning activities at the YNPS site.

Due to the shutdown status of the plant, and due to the relatively low quantities of radioactive material now on the site, some of the objectives have a different degree of importance than in the past.

The radiological environmental monitoring program was initiated in 1958, approximately two years before the plant began commercial operation in 1960.

It has been in operation continuously since that time, with improvements made periodically over those years.

The current program was designed to meet the intent of NRC Regulatory Guide 4.1, Procrams for Monitorinn Radioactivity in the Environs of Nuclear Power Plants; NRC Regulatory Guide 4.8, Environmental Technical Specifications for Nuclear Power Plants; the NRC Branch Technical Position of November 1979 entitled, An Acceptable Radiolorical Environmental Monitorine Prograrn; and NRC NUREG-0472, Radiolorical Effluent Technical Specifications for PWR's.

The environmental TLD program was designed and tested around NRC Regulatory Guide 4.13, Performenee. Testinc and Procedural Specifications for Thermoluminescence Dosimetry: Environmental ADD 11 cations. The quality assurance program was designed around the guidance given in NRC Regulatory Guide 4.15, Ouality Assurance for Radiolorical Monitorine Procrams (Normal Operations) - Effluent Streams and the Environment. l

1 Prior to August 1992, the requirements for the Radiological Environmental Monitoring Program (REMP) were given in the Radiological Effluent Technical Specifications (RETS).

In August 1992, the REKP specifications were removed from the RETS and placed in the Offsite Dose Calculation Manual (ODCM) (Reference 5) pursuant to NRC Generic Letter 89-01 (Reference 6).

Since the specific requirements of the REKP did not change at that time (they only changed documents), the current ODCM " Controls" will be cited in this report whenever discussing REMP requirements.

The minimal sampling requirements of the REHP are given in Table 4.1 of the ODCM, which is summarized in Table 4.1 of this report. The identification of the required sampling locations is given in Table 4.4 of the ODCM, as well as in Tables 4.2 and 4.3 of this report. The sampling and monitoring locations are shown graphically on the maps in Figures 4.1 through 4.7.

4.1 Monitorine Zones The REMP is designed to allow comparison of levels of radioactivity in samples from the area possibly influenced by the plant to levels found in areas not influenced by the plant. The first area is called Zone 1, and its monitoring locations are called " indicators." The second area is called Zone 2, and its monitoring locations are called " controls." The distinction between the two zones, depending on the type of sample or sample pathway, is based on one or more of several factors, such as site meteorological history, meteorological dispersion calculations, relative direction from the plant, river flow, and distance. Analysis of survey data from the two zones aids in determining if there is a significant difference between the two areas.

It can also help in differentiating between radioactivity or radiation due to plant activities and that due to other fluctuations in the environment, such as atmospheric nuclear weapons test fallout or seasonal variations in the natural background.

4.2 Pathways Monitored Four pathway categories are monitored by the REMP. They are the Direct Radiation, Airborne, Waterborne, and Ingestion Pathways.

Each of these four 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:

Airborne Pathway Air Particulate Sampling Charcoal Cartridge (Radioiodine) Sampling Waterborne Pathways River Vater Sampling Ground Water Sampling Storm Drain Water Sampling Shoreline Sediment Sampling Ingestion Pathways Milk Sampling Fish Sampling Food Product and Broad Leaf Vegetation Sampling Direct Radiation Pathway TLD Monitoring 4.3 Descriorions of Monitoring Procrams 4.3.1 Air Samoling Continuous air samplers are installed at seven locations.

(Five are required by the YNPS ODCM.) On September 22, 1992, one of the sampling stations was taken out of service, leaving six in operation for the remainder of 1992. This is discussed in more detail in section 6.1 of this report.

The sampling pumps at these locations operate continuously at a flow rate of approximately one cubic foot per minute. Airborne particulates are collected by passing air through a 47 mm glass-fiber filter. A dry gas meter is incorporated into the sampling stream to measure the total volume of air sampled in a given interval. The entire system is housed in a j

weatherproof structure. The filters are collected weekly, and to allow for I

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 YAEL before being analyzed for gross-beta radioactivity (indicated as CR-B in the data tables). The weekly filters are composited (by location) at the YAEL for a quarterly gamma spectroscopy analysis.

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4.3.2 Charcoal Cartridce (Radioiodine) Sampline Gontinuous air samplers are installed at seven locations.

(Five are required by Technical Specifications.) On September 22, 1992, one of the sampling stations was taken out of service, leaving six in operation for the remainder of 1992. This is discussed in more detail in section 6.1 of this report.

The sampling pumps at these locations operate continuously at a flow rate of approximately one cubic foot per minute. A 60cc TEDA impregnated charcoal cartridge is located downstream of the air particulate filter described above. A dry gas meter is incorporated into the sampling stream to measure the total volume of air sampled in a given interval. The entire system is housed in a weatherproof structure. These cartridges are collected and analyzed weekly for 1-131.

4.3.3 Jtiver Vater Samnline Automatic compositing samplers are located at one upstream and one downstream sampling location. The samplers are controlled by timers that collect an aliquot of river water at least every two hours. An additional

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grab sample is collected monthly at Sherman Pond. All river water samples are preserved with hcl and NaHSO, or HNO, to prevent the plate out of 3

3 potentially-available radionuclides on the container walls.

Each sample is analyzed for gross-beta and gamma-emitting radionuclides. These monthly composites or grabs are composited again (by location) at the YAEL for a H-3 analysis.

4.3.4 Ground Water Samoline Grab samples are collected monthly from two on-site locations.

(The ODCM requires a minimum of a quarterly collection.) All ground water samples are preserved with hcl and NaHS0, or HNO, to prevent the plate out of 3

3 potentially-available radionuclides on the container walls. Each sample is analyzed for gross-beta and gamma-emitting radionuclides, as well as H-3.

4.3.5 1.torm Drain Vater Samoline Grab samples are collected monthly from the West Storm Drain.

(This is not an ODCM requirement.) This water is comprised of non-radioactive secondary r

side plant effluents, as well as groundwater and precipitation (including snow melt) draining from the west side of the plant facility. All storm drain water samples are preserved with hcl and NaHS0, or HNO, to prevent 3

3 the plate out of potentially-available radionuclides on the container walls.

Each sample is analyzed for gross-beta and gamma-emitting radionuclides, as well as H-3.

4.3.6 Sediment Samuline Shoreline sediment cores are collected semiannually from two locations, one upstream and one downstream of the plant.

(The ODCM requires only a single shoreline sediment sample.) At each location, six two-inch I.D. plastic coring tubes are driven into the sediment at least six inches deep. The cores are carefully extracted and kept in an upright position and frozen prior to delivery to the YAEL. At the Laboratory, the frozen cores are cut into two-inch segments. For each location, the 0-5 cm segments are blended into a single sample, as are the 5-10 cm and 10-15 cm segments. These composite samples are then analyzed for gamma-emitting radionuclides.

An additional bottom sediment core is collected semiannually in Sherman Pond near the plant discharge. A Wildeo K. B. Core Sampler, fitted with a plastic coring tube, is dropped from a boat.

Six cores are collected here, and are processed and analyzed as described above.

4.3.7 Milk Satroline Eetween November 1 and June 1, milk samples are collected on a monthly schedule from three locations. During the " grazing season", which runs from June 1 to November 1, samples are collected once per two weeks. Two indicator locations are chosen as part of the annual Land Use Census, based on meteorological dispersion calculations. The third location is a control, which is located sufficiently far away from the plant to be outside any potential influence from it.

Immediately after collection, j

each milk sample is preserved with an appropriate amount of formaldehyde.

Methimazole is also added to prevent protein binding of any radiciodine.

Each sample is analyzed for gamma-emitting radionuclides.

Following a chemical separation, a separate low-level I-131 analysis is performed to meet the lower Limit of Detection requirements in the ODCM. Although not required by the ODCM, Sr-89 and Sr-90 analyses are also performed on j

quarterly comporited samples..

4.3.8 Fish Samoline

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Fish samples are collected semiannually at two locations (upstream of the plant and in Sherman Pond). A gill net is set overnight from a boat, and mixed species of fish are removed the following day. The species typically collected are yellow perch, smelt, pickerel, trout, bu11 heads and suckers.

The fish samples are frozen and delivered to the YAEL where the edible s

portions are analyzed for gamma-emitting radionuclides.

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4.3.9 Food Products and Broadleaf Veretation Samnline Food Products are collected annually (at harvest) at three locations. The samples are either tuberous vegetables, above-ground vegetables or fruit.

Two indicator locations are chosen as a result of the annual Land Use Census, based on meteorological dispersion calculations. The third location is a control, which is located sufficiently far away from the plant to be outside any potential influence from it.

Immediately after collection, each unwashed food product sample is preserved with an

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appropriate amount of NaOH. The edible portions of the samples are then analyzed at the YAEL for gamma-emitting radionuclides.

An additional sample of edible broadleaf vegetation is collected at a single location (as determined from the Land Use Census) and is preserved as above. A separate low-level I-131 analysis is performed on this sample to meet the Lower Limit of Detection requirements in the ODCM.

In addition to the above food products, optional maple syrup samples are collected annually, as described below.

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4.3.10 Maole Syrun Sarroline Maple syrup is an important commercial product in northern New England, including the YNPS plant environs. Because of this, samples are collected annually from three locations. These samples are collected from the syrup manufacturer as a finished product - that is, following the boiling down of the maple sap.

Since the samples have already been boiled down as part of the syrup production process, no preservatives are needed in the samples.

Following collection, the samples are analyzed at the YAEL for gamma-emitting radionuclides.

It should be noted that because of the boiling down and filtering of the sap, the resulting radionuclide measurements do not represent actual environmental concentrations.

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the resulting syrup has been concentrated by a factor of from 15 to 120 times the original sap, depending mostly on the time of the season that the sap was collected.

4.3.11 TLD Monitorine Direct gamma radiation exposurs was continuously monitored with the use'of thermoluminescent dosimeters (TLDs). Specifically, Panasonic UD-801AS1 und UD-814AS1 calcium sulfate dosimeters were used, with a total of five

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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 i

container. This container is attached to an object such as a tree, fence or utility pole. A total of 38 stations are required by the ODCK, Of l

these, 22 must be read out quarterly, while those from the remaining 16 i

incident response (outer ring) stations need only be de-dosed (annealed) quarterly, unless a gaseous release Control was exceeded during the period.

l Although not required by the ODCM, the TLDs from the 16 outer ring stations j

are read out quarterly along with the other stations's TLDs. The plant l

staff posts and retrieves all TLDs, while the YAEL processes them.

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TASLE 4.1 Redlotoelcet Emironmentet monitorine Proeren (se roupstred by cool Teide 4.1)

Cottection Analyefs Emposure Pathwey d'"

pu eer of Routine Anetyola AnetyeIo Senple Medle Samte Locetlone senplIng Coltectton Type Frequency Mode Frequmey

1. Direct Redletion (TLDs) 38 Continuous Quarterly Ceme; Outer Ring -

Eoch TLD Includes 16 Outer de-dose onty, unless Ring Incident geseous release Control Response TLDs was exceeded

2. Airborne (Perticuletes 5

Continuous Weekly Porticutete semplet end Radiolodine)

Grose Sete Eoch Senple Genne Isotopic Ouerterly Compoolte (by location)

Redfolodine Conleters

-131 Each Sample

3. Waterborne

s. Surface Weter 2

Composite Monthly Groes Dete Each Sample (eliquot every Genene f ootopic Each Semple 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />)

Trittun (N-3)

Querterly Composite

b. Ground Water 2

Grob Overterly Gensne Isotopic Each Semple Trititsu (M-3)

Each Semple

c. Shoreline Sediment 1

Grob Semiennuelty Game f ootopic toch Sample. - -

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5 Lt ey 1

mb Bn A o T c etr

(

re t r n

e g mi o

n n Eg i

i ie b

b b

b t

td o

o a

o t

c upo r

r r

r te e

o nM G

G G

G ce l

e R

i s l

S c(

o o

C to ida R

f s

o no ri

&t a

co N

3 2

3 1

L t

e ent im m e o S N

r n

e o

t t

es e

ve t

ol e

bb g

e aa e

l t

v d

s re I e t

og f

OM e

e e

s sv e

Nl c

od k

u t

e o

p r

rnt d n

n P

eui a

e o

hou o t rr r

S i

h h

d t

t s

o T gf B

s o

e i i

F M

F gn I

e b

c 4

I1l l

TABLE 4.2 Radiological Environmental Monitoring Locations (non-TLD) in 1992 Yankee Nuclear Power Station Distance From Direction Exposure Station Plant From Pathway Code Station Descriotion ZP.ng (km)

Plant

1. Airborne AP/CF-11 Observation Stand 1

0.5 NW AP/CF-12 Monroe Bridge 1

1.1 SW AP/CF-13 Rowe School 1

4.2~

SE AP/CF-14 Harriman Station 1

3.2 N

AP/CF-21 Williamstown, MA 2

22.2 W

AP/CF-31 YAEC Visitor's 1

0.8 SW Information Center AP/CF-32 Heartwellville, VT 2

12.6 NNW

2. Waterborne

a. Surface VR-11 Bear Swamp lower 1

6.3 Down-Reservoir river WR-21 Harriman Reservoir 2

10.1 Up-river WR-31 Sherman Pond 1

0.1 N

I

/

b. Ground WC-11 Plant Potable 1

On-site WG-12 Sherman Spring 1

0.2 NW 1

c. Storm W-52 West Storm Drain 1

On-site l

Drain

d. Sediment SE-11 No. 4 Station 1

36.2 Down-river SE-21 Harriman Reservoir 2

10.1 Up-river SE-91 Sherman Pond 1

0.1 N

3. Ingestion

a. Milk TM-12 Readsboro, VT 1

6.1 N

TM-13 Whitingham, VT 1

8.4 ENE TM-21 Williamstown, MA 2

21 WSW

b. Fish FH-11 Sherman Pond 1

1.5 Near Dischg.

FH-21 Harriman Reservoir 2

10.1 Up-river,

.~.

_ = -

TABLE 4.2 (continued)

Radiological Environmental Monitoring locations (non-TLD) in 1992 Yankee Nuclear Power Station Distance I

From Direction l

Exposure Station Plant From i

i Pathway Code Station Descrintion Zone *

(km)

Plant

3. Ingestion, (continued)

c. Food TF-11 Monroe Bridge, MA 1

1.3 SW

[

Products l

TF-13 Monroe, MA 1

1.9 VNW

(

TF-21

.Williamstown, MA 2

21.0 USW l

TF-32 Whitingham, Vt 1

8.4 ENE (Maple syrup)

TF-33 Rowe, MA 1

1.0 S

(Maple syrup)

TF-42 Williamstown, MA 2

28.3 WSW (Maple syrup) l

• 1 - Indicator Stations; 2 - Control Stations

\\

l k

i i

I i e

s -

TABLE 4.3 Radiological Environmental Monitoring locations (TLD) in 1992 Yankee Nuclear Power Station Distance Station From Plant Direction Code Station Descriotion Zgng*

(km)

From Plant GM-1 YAEC Visitors' Info. Center 1

0.8 SW GM-2 Observation Stand 1

0.5 NW GM-3 Rowe School 1

4.2 SE GM-4 Harriman Station 1

3.2 N

GM-5 Monroe Bridge 1

1.1 SW GM-6 Readsboro Road Barrier 1

1.3 N

)

GM-7 Whitingham Line 1

3.5 NE GM-8 Monroe Hill Barrier 1

1.8 S

GM-9 Dunbar Brook 1

3.2 SW

)

GM-10 Cross Road 1

3.5 E

GM-11 Adams High Line 1

2.1 WNW GM-12 Readsboro, VT 1

55 hw GM-13 Restricted Area Fence F

0.08 WSW GM-14 Restricted Area Fence F

0.11 kW g

CM-15 Restricted Area Fence F

0.08 NNW GM-16 Restricted Area Fence F

0.13 NNE GM-17 Restricted Area Fence F

0.14 ENE GM-18 Restricted Area Fence F

0.14 ESE GM-19 Restricted Area Fence F

0.16 SE GM-20 Restricted Area Fence F

0.16 SSE GM-21 Restricted Area Fence F

0.11 SSW GM-22 Heartwellville, VT 2

12.6 NNW GM-23 Williamstown Substation 2

22.2 W

CM-24 Harriman Dam O

7.3 N

GM-25 Whitingham, VT O

7.7 NNE CM-26 Sadoga Road O

7.6 NE GM-27 Number 9 Road O

7.6 ENE GM-28 Number 9 Road O

6.0 E

GM-29 Route BA O

8.2 ESE GM-30 Route BA O

9.4 SE - _ _ _ _ _ _ _ _ _ _ _ _

TABLE 4.3 (continued)

Radiological Environmental Monitoring Iocations (TLD) in 1992 Yankee Nuclear Power Station Distance Station From Plant Direction -

Code Station Descrintion 12Dg (km)

From Plant GM-31 legate Hill Road O

7.6 SSE GM-32 Rowe Road O

7.9 S

GM-33 Zoar Road O

6.9 SSW GM-34 Fife Brook Road O

6.4 SW GM-35 Whitcomb Summit O

8.6 USW GM-36 Tilda Road O

6.6 W

GM-37 Turner Hill Road O

6.7 WNW GM-38 West Hill Road O

6.6 NW GM-39 Route 100 0

6.8 NNW CM-40 Readsboro Road 1

0.5 W

o 1 - Indicator TLD; 2 - Control TLD; O - Outer Ring Incident Response TLD; F - Fenceline TLD. >

TABLE 4.4 Environmental Lower Limit of Detection (LLD) Sensitivity Requirements Airborne Particulates Food Water or Gases Fish Milk Product Sediment Analysis (pci/1)

(pC1/m3)

(pCL/kg)

(pci/1)

(pci/kg)

(pci/kg f

-dry)

Gross-Beta 4

0.01 H-3 2000 Mn-54 15 130 re-59 30 260 Co-58,60 15 130 En-65 30 260 Zr-Nb-95 15 I-131 1*

0.07 1

60**

Cs-134 15 0.05 130 15 60 150 co-137 18 0.06 150 18 80 180 Ba-La-140 15 15 LLD for drinking water.

• • LLD for leafy vegetation.

(several other explanatory footnotes are given in ODCM Table 4.3.

TABLE 4.5 Reporting Levels for Radioactivity Concentrations In Environmental Samples Airborne Particulates Food Water or Gases Fish Milk Product (Pci/1)

(pci/m3)

(pci/kg)

(pci/1)

(pci/kg)

Analysis H-3 3 x 10*

• Mn-54 1 x 10' 3 x 10*

Fe-59 4x 10 1x 10*

2 Co-58 1 x 10' 3 x 10' Co-60 3 x 10 1 x 10' 2

2 2 x 10' Zn-65 3 x 10 Zr-Nb-95 4x 102 I-131 2

0.9 3

1 x 102 Cs-134 30 10 1 x 10' 60 1 x 10' Cs-137 50 20 2 x 10' 70 2 x 10' Ba-La-140 2 x 102 3x 102 Reporting Level for non-drinking water pathways.

/

/5A l

~

FH-11[

Vemont

-j Massachusetts

/

N l

0 500 i

I e

e I

METERS i ShTRMN POND ;

f Y

I

//

/

AP/CF-11 A A SE-91 ~=_

W A3_3f,g f

'v '

e A WG-12 n

W PLA!U

/

k-52A

.6

/e7

+-

A WG-11 h,

• r,,

'e,

=

'AP'/CF-31 M:nroe Eric;e A AP/CF-12

• Mtyy e.,

(

Figure 4.1 Radiological Environ = ental Sampling 1.ocations Within 1 Mile of YNPS

?

l -

~

J 1

.e N

l 1

l l

i

~

j i

Hwtanut Ruervobt i

HEARTWELLVILLE A AP/CF-32 1

$5E I

~ ~ SE-21

' A FH-21

[

I

^ ' ' _

• WHITINGHAM I

TM-12 A READSBORO WR-21 A TM-13 l

l A AP/CF-14 TF-32 Sherman Portd VERMONT

[

g' ~ - ~ E 1,

1 MASSACHUSETTS l

TF-13 A l i

MONROE ERIDGE ' ~g) I

, 55g gy;;ggyzyr zy yzc;;gg

[

t PLANT 1 i

i

t. _ _ _ _ _ i i

l A TF-33 l

Ewt.Lemp Lowet Rucrvo4s A AP/CF-13 i

i

• ROWE l

A WR-11

• HEATH i

'4.gv-4 4 CHARLEMONT e

1 1

1 -

t 1

t SE-11 A KILOMETERS l

SHELBURNE FALLS,

Figure 4.2 Radiological Environmental Sampling Locations Within 12 Miles of YNPS j.. -.. -

I I

N

\\

t t

)

j i

i

{

EENNINGTON e

i t

e i

HEARTWELLVILLE l'

s

\\

l I

I

\\

l e WHITINGHAM

{

READSBORO

• l

\\

-j VT _

x i.g MONROE BRIDGE e MT E S*

y WILLIAMSTOWN e/x e

NORTH ADA".S RD'dE A AP/CF-21 i

o e

e s

A TM-21 ggg7g j

A TF-42 TF-21

/

1 4

CHARLEMONT et

'Cr4 SHELBURNE FALLS l

i l

O S

10 15 20 t

t t

t i

PITTSFIELD i

Figure 4.3 Radiological Environmental Sampling Locations Outside 12 Miles of YNPS 24-l l

)

l'.

N

. t.

i o

50 100

.y p.-

~

l kk

, 3[

fI I

e e e I

. e e i

.,c.7 I"M METERS 44' l

1 v

n.s.

.a l

f-4<

t

=..

[

,s o

i l

g?

SHEUWI NWO t

l e,

s.

,I GM-14 A

---

C l- ----- - - - - - - ~ ~' h - A GM-15 care i

House %.

I I......,

N.,

Switch 8 Offices

• li GM'.16 4

,' yardg l

g.

Turbine 8

4*.

Service i

Information Aux. Bay l Area

-.s, 0~

'"'N i

Center %

.% d f

Wse.

j 4

I t

i a

e s

y Vapor \\

"~

j Containers

.e, v ^ '.. =...

I r

p I

i L h. _ a '--

9 ;,o

_l PAB i

y 9

j i

,,,,8 g

\\

oo O t.

s' e

O a'cs.21

{

]OOl !

Waste 8

,/

i Disposal l

l e

l

/A GM-17 e

8 s

l s.

~

t i

i,

,e s

i i

I 1

s s.

s i

I s

s s,

GM - 18 A......

i

\\

I

................"A'-

GM-20 A GM-19 a

s

- _ _ _ _s l

l 1

l Fi ure 4.4 Environ:cental TLD Monitoring Locations 5

at the YNPS Restricted Area Fence 25 t

(

I t

~

\\

\\

f "y

/

Vemong

~

GM-6 A #

l

/

Massachuse t

./

i i

N 1

I o

500 g

t METERS t'

.SHERMAN PONOl

(

t i

\\

I

'\\

A

+

f~

a CM-2 4 <'

i W

a

/

\\ t l

+ 9+ ~

cf A GM-40 sv

~

sk

'g l

~$**

l l

GM-1 A i

l l

Monroe gr$gg, I

J L -5 A C

i

-~

U R,,

A cM-s l.

j Figure 4.5 E

l TLD Monitoring Locations Vi gil, of, _.

t N

j i

l l

)

i i

l l =:=

"" E" HEARTWELLVIL,LE C A CM-22 i

i M

==

f i

Q-

\\

-39 A GM-25 CM-24 A _

_.. wHi % cosAM j

CM

\\ As J

CM-12 A READSBORO

\\

GM*38 A

'gg,4 A M-26

/

f

'A he.uc Pond t

CM-37 A 5

4 CM.7 A CM-27 CM,11 A I y,.

/

VERMONT N_

') l[

MASSACHbETTS

~

f

=:

M EN W N AT IN M ar A CM-36 gj A CM-10 A CM-28 P! ANT l l

A

' 7-

/

1 7 A CM-9 Et: S~cwp LowrA tu ch, CM-3 A A CM-29 g cg.35

\\CM-34A A CM-33 HEATH A GM-30 A CM-31 A CM-32

1. '4)

)

p.

4 CHARLEMONT f

f f

f t

t KILOMETERS j

SHELBURNE FALLS,

Figure 4.6 Environmental TLD Monitoring Locations Within 12 Miles of YNPS i

l.

l 1

I N

l l

N l

t l

'NINGTON i

s I

"~

HEARTWELLY LLE e

N e

1 e

TINGHAM

. 05 BORD *

\\

VT.

f K

/

/

1. 'd.

CHARLEMONT 4%<

s BURNE FALLS

• i i

j O

5 10 15 20 i

e i

e t

OCEE PITTSFIELD e

i l

Figure 4.7 Environmental TLD Monitoring Locations l

l Outside of 12 Miles from YNPS I f 1

i

5.0 RADIOLOGICAL DATA

SUMMARY

TABLES This section summarizes the analytical results of the environmental samples which were collected during 1992. These results, shown in Table 5.1, are presented in a format similar to that prescribed in the NRC's Radiological Assessment Branch Technical Position on Environmental Monitoring (Reference 1).

The results are ordered by sample media type and then by radionuclide.

The units for each media type are also given. Table 5.2 provides the same information for direct radiation measurements made by TLDs.

The left-most column contains the radionuclide of interest, the total number of analyses for that radionuclide in 1992, and the number of measurements which exceeded the Reporting Levels found in Table 4.2 of the YNPS ODCli. The latter are classified as "Non-routine

• measurements. The second column lists the required lower Limit of Detection (LLD) for those radionuclides which have detection capability requirements as specified in the plant's ODCM (Table 4.3).

The absence of a value in this column indicates that no LLD is specified in the ODCM for that radionuclide in that media. The target LLD for any analysis is typically 30-40 percent of the most restrictive required LLD. On rare occasions the required LLD is not met.

This is usually due to malfunctions in sampling equipment, which result in low sample volume.

Such cases 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 or Zone 1 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 1992 for that radionuclide; and (3) the Control or Zone 2 stations, which are beyond the influence of the plant. Direct radiation monitoring stations (using TLDs) are grouped into Indicator, Outer Ring, Fenceline and Control stations.

In each of these columns, for each radionuclide, the following are given:

The mean value of all concentrations including negative values and values below the LLD.

The standard error of the mean.

The lowest and highest concentration.

- The number of detectable measurements divided by the total number of measurements. _ _ _ _ _

A sample is considered to yield a " detectable measurement" when the concentration exceeds three times its associated standard deviation. The standard deviation on each measurement represents only the random uncertainty associated with the radioactive decay process (counting statistics), and not the propagation of all possible uncertainties in the analytical procedure.

The radionuclides reported in this section represent those that:

1) had an LLD requirement in Table 4.3 of the ODCM, or a Reporting Imvel listed in Table 4.2 of the ODCM, or 2) had a positive measurement of radioactivity, whether it was naturally-occurring or man-made; or 3) were of specific interest for any other reason. The radionuclides that were routinely analyzed and reported by the YAEL (in a gamma spectroscopy analysis) were:

AcTh-228 Ag-110m, Ba-140 Be-7, Ce-141, Ce-144, Co-57, Co-58, Co-60, Cr-51, Cs-134 Cs-137, Fe-59, I-131, 1-133, K-40, Mn-54, Mo-99, 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 appear as a " detectable measurement" during 1992.

Data from direct radiation measurements made by TLDs are provided in Table 5.2 in a format essentially the same as above. The complete listing of quarterly TLD data is provided in Table 5.3.

i TABLE 5.1 RADIOLOGICAL EWIROIBENTAL P90 CRAM ESDERY TAIKEE mrs m Mu.R gTATICNI, RCRE, MA (JAIRMRT - DECDaER 1992)

INDICATOR STATIOks STATION WITH NIGNEST MEAN CONTROL STATIONS e...... **e.......

e e. eeeeeeeemeneeeenee eeweeweeeeeee.

RAD 1010CLIDE$*

MEAN MEAN MEAN (NO. ANALYSES) REQUIRED RANCE STA.

RANGE RANGE i

(NON-ROUTINE )"

LLD

1. 0. DETECTED *"

1. 0.

WO. DETECTED ***

NO. DETECTED ***

IEDILBt: AIR PARTIC12.ATES (AP)

LAIITS: ( I/ cubic meter l

GR-B (357)

Ai t

1.5

• 0.0)E 2 21

(

1.6 e 0.1)E -2

(

1.5 s 0.0)E 2

( 0)

(

5.1 -

37.7)E -3

(

8.6 -

31.9)E -3

(

3.8 -

31.9)E -3

• (251/251)*

• ( 53/ 53)*

• (106/106)*

BE-7

( 27)

(

7.7 1 0.4)E -2 21

(

8.7 1 0.8)E 2

(

8.1 0.5)E -2

( 0)

(

4.7 -

11.0)E -2

(

7.4 -

11.0)E 2

(

6.2 -

11.0)E -2 I

• ( 19/ 19)*

• (

4/ 4)*

• (

8/ 8)*

l CS-934 ( 27)

.05

(

-1.5 s 0.4)E -4 11

(

5.5 s 1.9)E -5

(

-2.0 s 0.7)E -4 l

C 0)

(

-4.1 -

2.2)E -4

(

-8.0 -

0.0)E -5

(

-6.1 -

0.0)E -4 l

• (

0/ 19)*

• (

C/ 4)*

• (

0/ 8)*

CS-137 ( 27)

.06

(

-2.1 6.2)E -5 31

(

1.6 s 0.7)E -4

(

-9.7 s 9.2)E -5

( 0)

(

-5.3 -

5.6)E -4

(

4.2 -

32.9)E -5

(

-4.6 -

3.8)E -4 i

• (

0/ 19)*

• (

0/ 4)*

• (

0/ 8)*

IEDILDI: CHARCDAL FILTERS (CF)

LallTS: pCI/ctbic meter l

I-131 (357)

.07

(

-7.2 s 67.4)E 5 11

(

2.4 s 1.4)E -3

(

1.4

• 74.2)E -5

( 0)

(

-3.6 -

3.8)E -2

(

-1.9 -

2.3)E -2

(

-1.8 -

2.1)E -2

• (

0/251)*

• (

0/ 53)*

• (

0/106)*

KDIL9t: RIVER IMTER (nat)

UNITS: pCl/kg CR-B

( 38) 4.

(

1.8 s 0.1)E 0 11

(

1.9 :

0.2)E O

(

1.7 0.1)E O

( 0)

(

7.0 -

29.6)E -1

(

7.0 -

29.6)E -1

(

1.0 -

2.5)E O

• ( 23/ 25)*

• ( 12/ 13)*

• ( 12/ 13)*

l MN-54 ( 38) 15.

(

2.0 t 1.4)E -1 11

(

3.5 s 2.2)E -1

(

-1.7 s 2.0)E -1 l

( 0)

(

-1.7 -

1.8)E O

(

-1.7 -

1.8)E D

(

-1.6 -

1.3)E O l

• (

0/ 25)*

• (

of 13)*

• (

0/ 13)*

COTE: Footnotes may be fotrd at the end of Table 5.1. l l

TABLE 5.1 RADIOLOGICAL ENW!ROWENTAL PROGtAM E8 MARY TAMEE IRJCLIAR PCER STATION, Robe, MA (JAIRJARY - DEMBBER 1992)

INDICATOR STATIONS STATION WITH NIGNEST MEAN CONTROL STATIONS

....e RADIOMUCLIDES*

MEAN NEAN MEAN (NO. ANALYSES) REQUIRED RANGE STA.

RANGE RANGE (WON-ROUTINE)**

LLD N0. DETECTED ***

Wo.

h0. DETECTED ***

No. DETECTED ***

IEDILDI: RIVER 18tTER OR), cant.

LallTS: pcl/kg Co-58 ( 38) 15.

(

-3.5 s 2.1)E -1 21

(

2.4 a 2.8)E -1

(

2.4 s 2.8)E -1

( 0)

(

-3.0 -

1.6)E o

(

-2.1 -

1.7)E O

(

-2.1 -

1.7)E 0

• (

0/ 25)*

• (

0/ 13)*

• (

0/ 13)*

FE-59 ( 38) 30.

(

1.2 s 0.4)E D 11

(

1.5 s 0.7)E D

(

5.9 s 6.2)E -1

( 0)

(

-1.4 -

6.7)E D

(

-1.4 6.7)E O

(

-3.1 -

4.8)E 0

• (

0/ 25)*

• (

0/ 13)*

• (

0/ 13)*

CO-60 ( 38) 15.

(

-2.7 s 2.0)E -1 31

(

1.5 s 2.6)E -1

(

-4.0 s 4.6)E -1

( 0)

(

-1.9 -

1.6)E O

(

1.6 -

1.6)E O

(

-3.0 -

2.2)E O

• (

0/ 25)*

• (

0/ 12)*

• (

0/ 13)*

2N 65 ( 38) 30.

(

-2.1 s 3.4)E -1 21

(

4.5 3.5)E -1

(

4.5 a 3.5)E -1

( 0)

(

-4.3 -

2.5)E D

(

2.0 -

2.1)E O

(

2.0 -

2.1)E 0

• (

0/ 25)*

• (

0/ 13)*

• (

0/ 13)*

ER-95 ( 38) 15.

(

-1.1 2.9)E -1 31

(

1.9 s 4.5)E -1

(

-1.2 s 5.1)E -1

( 0)

(

-2.5 -

2.6)E D

(

-1.9 -

2.6)E 0

(

-2.5 -

3.5)E O

• (

0/ 25)*

• (

0/ 12)*

• (

0/ 13)*

I 131 ( 38)

(

1.2 s 0.7)E D 11

(

1.2 s 1.0)E D

(

4.0 s 11.3)E 1

( 0)

(

-7.9 -

9.8)E O

(

-2.1 -

8.8)E D

(

-4.5 -

8.7)E O

• (

0/ 25)*

• (

0/ 13)*

• (

0/ 13)*

CS-134 ( 38) 15.

(

-8.4 s 1.6)E -1 31

(

-8.3 t 1.6)E -1

(

-8.5 a 2.8)E -1

( 0)

(

-2.8 -

0.8)E D

(

-1.8 -

0.1)E O

(

-3.1 -

1.2)E O

• (

0/ 25)*

• (

0/ 12)*

• (

0/ 13)*

CS-137 ( 38) 18.

(

-7.9 s 14.9)E -2 21

(

2.9 e 2.6)E -1

(

2.9 s 2.6)E 1

( 0)

(

-1.9 -

1.0)E O

(

-1.3 -

2.4)E O

(

-1.3 -

2.4)E D

• (

0/ 25)*

• (

0/ 13)*

• (

0/ 13)*

NOTE: Footnotes any be fowcf at the end of Table 5.1.

-32 f

TABLE 5.1 RADIOLOGICAL EWIRCEBUITAL PROGRAM RSSIAEY TANCEE wr rAR POKE STATICW, RCnE, MA (JAaRJART - DECDeER 1992)

INDICATOR STATIONS STATION WITN MIGHEST MEAN CONTROL STATIONS RADIONUCLIDES

• MEAN alEAN MEAN (NO. ANALTSES) REQUIRED RANGE STA.

RANGE RANGE (NON-ROUTINE)**

LLD No. DETECTED ***

NO.

No. DETECTED ***

No. DETECTED ***

IEDItst: RIVER HATER (WR), cant.

UNITS: pCi/kg RA-140 ( 38) 15.

(

-3.0 e 3.3)E -1 31

(

1.12 45.6)E -2

(

-1.8 0.7)E D

( 0)

(

-3.1 -

3.9)E O

(

-3.1 -

1.9)E D

(

-6.5 -

1.6)E D i

• (

0/ 25)*

• (

0/ 12)*

• (

0/ 13)*

0-3

( 12) 2000.

(

4.7 s 7.9)E 1 31

(

9.1 1 13.9)E 1

(

-5.8 6.2)E 1 i

l

( 0)

(

-1.8 -

4.0)E 2

(

-1.8 -

4.0)E 2

(

-2.3 -

0.6)E 2

• (

0/ 8)*

• (

0/ 4)*

• (

0/ 4)*

I IEDItst: GRGap WATER (WG)

LalITS: pCl/kg GR-B

( 26) 4

(

5.5 t 1.3)E D 11

(

7.4 a 2.6)E O NO DATA

( 0)

(

2.8 -

38.5)E O

(

4.0 -

38.5)E O

• ( 26/ 26)*

• ( 13/ 13)*

K-60

( 26)

(

7.9 s 28.0)E -1 12

(

2.6 2 3.3)E O Wo DATA l

( 0)

(

-3.1 -

3.6)E 1

(

-1.7 -

2.6)E 1

• (

0/ 26)*

• (

0 ' 13)*

MM-55 ( 26) 15.

(

-1.9 e 1.6)E -1 12 (

-1.1 e 24.0)E -2 No CATA I

( 0)

(

-1.4 -

1.4)E D

(

-1.1 -

1.4)E O

• (

0/ 26)*

• (

0/ 13)*

CO-58 ( 26) 15.

(

-2.1 :

1.7)E -1 12

(

-1.3 s 1.6)E -1 NO DATA

( 0)

(

-2.4 -

1.4)E O

(

-9.4 -

7.4)E -1 l

• (

0/ 26)*

• (

0/ 13)*

~

FE-59 ( 26) 30.

(

2.7

• 3.9)E -1 12 (

4.3

• 4.9)E 1 NO DATA

( 0)

(

-3.6 -

3.9)E O

(

-1.6 -

3.9)E O

• (

0/ 26)*

• (

0/ 13)*

j Co-60 ( 26) 15.

(

-8.1 2 2.2)E -1 11

(

-6.9 2 3.8)E -1 NO DATA l

( 0)

(

-3.9 -

2.3)E D

(

-3.9 -

2.3)E O l

• (

0/ 26)*

• (

0/ 13)*

j l

CCTE: Footnotes may be fourd at the erd of Table 5.1. l l

TABLE 5.1 RADIOLOGICAL Emf!BCEBENTAL Pentmaag 35m4RY YANKEE ILICLEAR PohER STATION, ache, nn

( mammy. DECDeER 1992)

INDICATOR STAi!ONS STATION WITN NIGNEST MEAN CONTROL STATIONS e........

.e

..........eeeeee RADIONUCLIDES

• MEAN MEAN MEAN (NO. ANALYSES) REQUIRED RANGE STA.

RANGE RANGE (NON-ROUTINE)**

LLD NO. DETECTED ***

No.

No. DETECTED ***

No. DETECTED ***

IEDILBE: GROLEe WATER (WG), cent.

LEIITS: pCi/ksi 2N-65 ( 26) 30.

(

5.4 s 3.5)E -1 11

(

1.4 s 0.5)E O NO DATA

( 0)

(

-2.1 -

3.9)E D

(

-1.2 -

3.9)E D

• (

0/ 26)*

• (

0/ 13)*

2R-95 ( 26) 15.

(

-1.7 a 4.0)E -1 12

(

4.8 5.2)E -1 NO DATA

( 0)

(

-4.0 -

4.7)E O

(

1.7 4.7)E O

• (

0/ 26)*

• (

0/ 13)*

I 131 ( 26) 1.

(

6.8 10.0)E.1 11

(

9.0 17.3;E -1 NO DATA

( 0)

(

-1.5 -

1.1)E 1

(

-1.5 -

1.1)E 1

• (

0/ 26)*

• (

0/ 13)*

CS-134 ( 26) 15.

(

4.3 s 19.6)E 2 11

(

3.4 s 2.9)E -1 NO DATA

( 0)

(

-1.4 -

1.7)E D

(

-1.4 -

1.4)E 0

• (

0/ 26)*

• (

0/ 13)*

CS-137 ( 26) 18.

(

-4.5 :

1.6)E -1 12

(

4.3 s 2.2)E -1 NO DATA

( 0)

(

-2.5 -

1.0)E 0

(

-2.5 0.7)E 0

• (

0/ 26)*

• (

0/ 13)*

EA-140 ( 26) 15.

(

-2.1 4.3)E -1 11

(

-3.8 s 561.5)E -3 NO DATA

( 0)

(

4.1 -

4.0)E O

(

-3.0 -

4.0)E D

• (

0/ 26)*

• (

0/ 13)*

VM-232 ( 26)

(

9.4 7.2)E -1 11

(

1.9 s 1.2)E O NO DAT A

( 0)

(

-3.8 -

9.7)E D

(

-3.8 -

9.7)E O

• (

0/ 26)*

• (

0/ 13)*

0-3

( 26) 2000.

(

3.4 s 0.8)E 2 12

(

7.1 0.3)E 2 NO DATA

( 0)

(

-1.5 -

8.6)E 2

(

4.2 8.6)E 2

• ( 13/ 26)*

• ( 13/ 13)*

1 N07E: Footnotes ney be fomd at the end of Table 5.1.

34

TABLE 5.1 RADIOLOGICAL ENVIROIBENTAL penmaat asewty YANEZI no rt r AR POER ETATION, IKnE, MA

( taan msg - DErnmars 1992)

INDICATOR STATIONS STATION WITN HIGNEST MEAN CONTROL STATIONS RADIONUCLIDES

• MEAN MEAN MEAN (NO. ANALYSES) REQUIRED RANGE STA.

RANGE RANGE (NON-ROUTINE)**

LLD NO. DETECTED ***

NO.

No. DETECTED ***

No. DETECTED ***

IEDItst: ST0ppe DRAIN lATER ( W) talITS: gCI/kg GR B

( 12)

(

2.5 s 0.5)E O 52 (

2.5 t 0.5)E D No DATA

( 0)

(

3.7 -

67.4)E -1

(

3.7 -

67.4)E *1

• ( 10/ 12)*

• ( 10/ 12)*

MN-54 ( 12)

(

5.0 a 23.5)E -2 52 (

5.0 2 23.5)E -2 NO DATA

( 0)

(

-1.5 -

1.6)E D

(

-1.5 -

1.6)E 0

• (

0/ 12)*

• (

0/ 12)*

CD-58 ( 12)

(

-5.0 2 1.9)E -1 52

(

-5.0 e 1.9)E -1 No DATA

( 0)

(

-1.9 -

0.2)E O

(

-1.9 -

0.2)E O

• (

0/ 12)*

• (

0/ 12)*

FE-59 ( 12)

(

-5.6 s 5.9)E -1 52

(

-5.6 5.9)E -1 ko DATA

( 0)

(

5.4 -

2.3)E D

(

-5.4 -

2.3)E O

• (

0/ 12)*

• (

0/ 12)*

CD-60 ( 12)

(

-3.8 s 2.8)E -1 52

(

-3.8 a 2.8)E -1 ko DATA

( 0)

(

-3.0 -

0.6)E D

(

-3.0 -

0.6)E O

• (

0/ 12)*

• (

0/ 12)*

2N-65 ( 12)

(

-1.4 a 7.7)E -1 52

(

-1.4 s 7.7)E -1 NO DATA

( 0)

(

-3.7 -

6.3)E D

(

3.7 -

6.3)E 0

• (

0/ 12)*

• (

0/ 12)*

ER-95 ( 12)

(

4.0 s 6.1)E -1 52

(

4.0 a 6.1)E 1 NO CATA

( 0)

(

-3.1 -

5.2)E D

(

-3.1 -

5.2)E O s

• (

0/ 12)*

• (

0/ 12)*

I-131 ( 12)

(

7.2 13.2)E -1 52

(

-7.2 13.2)E -1 NO DATA

( 0)

(

-1.2 -

0.6)E 1

(

-1.2 -

0.6)E 1

• (

0/ 12)*

• (

0/ 12)*

e 1

CDTE: Footnotes may te fourd at the erd of Table 5.1.

35-

i i

i TAsa 5.1 I

RADIOLOGICAL EWiaCacENTAL PROGRAM RDeMT TAMEE IUCLEAR PChu STATION, RubI, MA (JAEMY - DECDeER 1992)

INDICATOR STATIONS STATION WITH NIGNEST MEAN CONTROL STATIONS eeeeeeeeeeeeeeeeee RADIONUCLIDES

• MEAN MEAN MEAN (No. ANALYSIS) kEQUIRED RANGE STA.

RANGE RANCE (NON-ROLITINE)**

LLD NO. DETECTED ***

NO.

NO. DETECTED ***

NO. DETECTED ***

I j

IEDItal: STm M DRAIN blLTER (bEI), cent.

WITS: pCl/kg 1

CS 134 ( 12)

(

6.8 a 26.5)E -2 52

(

6.8 a 26.5)E -2 NO DATA

( 0)

(

-1.2 -

2.5)E D

(

-1.2 -

2.5)E O

• (

0/ 12)*

• (

0/ 12)*

CS-937 ( 12)

(

4.3 a 2.5)E -1 52

(

4.3 s 2.5)E 1 NO DATA

( 0)

(

-9.2 -

16.1)E -1

(

-9.2 -

16.1)E -1

• (

0/ 12)*

• (

0/ 12)*

BA-140 ( 12)

(

3.6 e 10.0)E 1 52

(

3.6 2 10.0)E -1 No DATA

( 0)

(

8.5 -

4.6)E D

(

8.5 -

4.6)E D

• (

0/ 12)*

• (

0/ 12)*

N-3

( 12)

(

9.2 2 6.7)E 1 52

(

9.2 s 6.7)E 1 NO DATA

( 0)

(

-1.5 -

6.9)E 2

(

-1.5 -

6.9)E 2

• (

1/ 12)*

• (

1/ 12)*

IEDItat: SEDIENT (SE)

UNITS: pCf/kg (dry)

BE-7

( 18)

(

4.7

• 10.4)E 1 11

(

1.6 s 1.2)E 2

(

7.2 s 11.1)E 1

( 0)

(

-7.1 -

5.0)E 2

(

-2.4 -

5.0)E 2

(

-3.0 -

4.8)E 2

• (

1/ 12)*

• (

1/ 6)*

• (

0/ 6)*

K-60

( 18)

(

1.8 0.1)E 4 91

(

2.2 s 0.1)E 4

(

1.6 0.0)E 4

( 0)

(

1.0 -

2.5)E 4

(

1.0 -

2.5)E 4

(

1.0 -

1.7)E 4

• ( 12/ 12)*

• (

6/ 6)*

• (

6/ 6)*

CO 58 ( 18)

(

-7.9 7.6)E D 21

(

1.5 a 5.3)E D

(

-1.5 a 5.3)E O

( 0)

(

-6.8 -

3.4)E 1

(

2.4 -

1.0)E 1

(

-2.4 -

1.0)E 1

• (

0/ 12)*

• (

0/ 6)*

• (

0/ 6)*

]

Co-60 ( 18)

(

4.2 1.9)E 1 91

(

9.0 2 2.4)E 1

(

-8.3 1 6.7)E O

( 0)

(

-2.1 -

17.4)E 1

(

4.0 -

17.4)E 1

(

-2.8 -

1.1)E 1

• (

2/ 12)*

• (

2/ 6)*

• (

0/ 6)*

I NOVE: Footnotes may be fomd at the end of Table 5.1.

i,

i

TABLE 3.1 RADIOLOGICAL EshrIRCBBERTAL PROGRAM RaguRT TAmKEE 1EACLIAR PGER STATION, RChE, MA

( tef. DECBGER 1992)

INDICATOR STATIONS STATION WITN MICHEST MEAN CONTROL STATIONS LADIDMUCLIDES*

MEAN MEAN MEAN (WO. ANALYSES) REau! RED RANGE STA.

LANGE RANCE (WON ROUT!KE)**

LLD 20 DETECTED ***

Wo.

h0. DETECTED ***

NO. DETECTED ***

7 IEDilst: SEDIsEJT (SE), cent.

Lat!TS: pCl/kg (dry)

CS-134 ( 18) 150.

(

8.1 a 4.7)E D 91

(

1.6 0.8)E 1

(

1.2 s 0.3)E 1

( 0)

(

-1.0 3.9)E 1

(

-3.2 -

38.6)E D

(

7.6 210.0)E -1

• (

0/ 12)*

• (

0/ 6)*

• (

0/ 6)*

CS-137 ( 18) 180.

(

1.4 0.4)E 3 91

(

2.5 s 0.4)E 3

(

2.62 0.8)E 2

( 0)

(

1.4 -

41.3)E 2

(

1.5 -

4.1)E 3

(

2.7 -

48.6)E 1

• ( 12/ 12)*

• (

6/ 6)*

• (

6/ 6)*

VN 232 ( 18)

(

1.3 a 0.2)E 3 91

(

1.8 0.1)E 3

(

3.5 0.4)E 2

( 0)

(

6.8 -

23.6)E 2

(

1.5 -

2.4)E 3

(

1.6 -

4.6)E 2

• ( 12/ 12)*

• (

6/ 6)*

• (

5/ 6)*

IED!Lat: MILE (TM)

LalTS: pC1/kg i

SR-89 ( 12)

(

-1.2 a 0.1)E D 12

(

-9.7 a 2.3)E -1

(

-1.4

• 0.3)E O

( 0)

(

-1.7 -

-0.4)E O

(

1.5 -

0.4)E O

(

-2.0 -

-0.6)E D

• (

0/ 8)*

• (

0/ 4)*

• (

0/ 4)*

l SR-90 ( 12)

(

3.0 s 0.4)E O 12

(

3.7 t 0.6)E 0

(

2.6 0.4)E D

( 0)

(

2.1 -

5.4)E D

(

2.4 -

5.4)E D

(

2.0 -

3.6)E 0

• (

8/ 8)*

• (

4/ 4)*

• (

4/ 4)*

K-40

( 60)

(

1.3 s 0.0)E 3 13

(

1.3 a 0.0)E 3

(

1.3 a 0.0)E 3

( 0)

(

1.0 -

1.5)E 3

(

1.2 -

1.5)E 3

(

1.2 -

1.4)E 3

• ( 40/ 40)*

• ( 20/ 20)*

• ( 20/ 20)*

I-131 ( 60) 1.

(

2.9 s 2.5)E 2 13

(

3.4 2 3.1)E -2

(

-7.4 s 29.5)E -3

( 0)

(

-5.6 -

4.0)E -1

(

2.6 4.0)E -1

(

-4.1 -

2.8)E 1

• (

0/ 40)*

• (

0/ 20)*

• (

0/ 20)*

CS 134 ( 60) 15.

(

-8.7

• 1.4)E -1 12

(

6.6 s 2.1)E -1

(

-9.9 e 2.2)E -1

( 0)

( - 2.7 -

1.2)E O

(

-2.1 1.2)E D

(

2.7 -

1.3)E D

• (

0/ 40)*

• (

0/ 20)*

• (

0/ 20)*

NOTE: Footnotes any be found at the end of Table 5.1.

37-

TABLE 5.1 RADIOLOGICAL EWIROWOTAL PROGRAM R3084RT YAMEEE m rt m POER STATION, ROE, MA (JAWARY - DECDGER 1992)

INDICATOR STATIONS STATION WITN NIGNEST MEAN CONTROL STATIONS

.....e.........

RADIONUCLIDES

• MEAN MEAN MEAk (NO. ANALTSES) REQUIRED RANGE STA.

RANGE RANGE (WON ROUTINE)**

LLD Wo. DETECTED ***

No.

MO. DETECTED ***

Wo. DETECTED ***

Initat: MILE (TN), cant.

LRf!TE: pCl/kg CS-137 ( 60) 18.

(

1.5 0.3)E O 12

(

2.3 0.4)E 0

(

6.7 e 2.0)E -1

( 0)

(

-1.5 -

6.3)E O

(

-1.9 - 652.0)E -2

(

-1.5 -

3.0)E O

• (

5/ 40)*

• (

5/ 20)*

• (

0/ 20)*

BA-140 ( 60) u.

(

9.5 :

44.3)E 2 21

(

9.7 5.5)E -1

(

9.7 5.5)E -1

( 0)

(

-7.3 -

6.1)E D

(

-3.3 -

6.0)E O

(

3.3 -

6.0)E 0

• (

0/ 40)*

• (

0/ 20)*

• (

0/ 20)*

I D ILDE: FISN (FN)

LRf!TS: 3Cf/kg K-60

( 4)

(

2.8 0.3)E 3 11

(

2.8 0.3)E 3

(

2.7 0.7)E 3

( 0)

(

2.6 -

3.1)E 3

(

2.6 -

3.1)E 3

(

2.0 -

3.4)E 3 j

• (

2/ 2)*

• (

2/ 2)*

• (

2/ 2)*

MN-54 ( 4) 130.

(

2.8 3.2)E O 11

(

2.8 3.2)E D

(

-5.8 0.8)E D

( 0)

(

-3.5 -

59.9)E -1

(

-3.5 -

59.9)E -1

( - 6. 6 -

5.1)E O

• (

0/ 2)*

• (

0/ 2)*

• (

0/ 2)*

Co 58 ( 4) 130.

(

-2.7 0.8)E D 11

(

2.7 0.8)E O

(

-1.2 a 0.1)E 1

( 0)

(

-3.5 -

-2.0)E D

(

-3.5 -

-2.0)E O

(

-1.3 -

-1.1)E 1

• (

0/ 2)*

• (

0/ 2)*

• (

C/ 2)*

FE-59 ( 4) 260.

(

-8.0 a 155.0)E -1 21

(

2.5 1.1)E 1

(

2.5 1.1)E 1

( 0)

(

-1.6 -

1.5)E 1

(

1.4 -

3.5)E 1

(

1.4 -

3.5)E 1

• (

0/ 2)*

• (

0/ 2)*

• (

0/ 2)*

Co-60 ( 4) 130.

(

-5.1 7.0)E -1 11

(

-5.1 7.0)E -1

(

-1.7 a 1.5)E 1 i

( 0)

(

-1.2 -

0.2)E O

(

-1.2 -

0.2)E O

(

-3.2 -

-0.3)E 1

• (

0/ 2)*

• (

0/ 2)*

• (

0/ 2)*

l ZW-65 ( 4) 260.

(

-9.6 a 11.8)E O 21

(

1.1 2.2)E 1

(

1.1 2.2)E 1

( 0)

(

-2.1 -

0.2)E 1

(

-1.1 -

3.3)E 1

(

-1.1 -

3.3)E 1

• (

0/ 2)*

• (

0/ 2)*

• (

0/ 2)*

i NOVE: Footnotes mey be fotrd at the end of Table 5.1.

l l

38 l

l l

TABLE 5.1 RADIOLOGICAL EWIROISEKTAL Pomm masqARY YANEE wrt ran pogg gTATICNf, RGE, M I

(JAlamar - DEconta 1992)

INDICATOR STATIONS ETATION WITH MIGNIST MEAN CONTROL STATIONS RADIONUCLIDES

• MEAN MEAN MEAN (NO. ANALYSES) REQUIRED RANGE STA.

RANGE ILANGE (NON ROUTINE)**

LLD No. DETECTED ***

NO.

No. DETECTED ***

No. DETECTED ***

E llst: FISN (FN), cant.

LaflTS: pCl/kg Cs-134 ( 4) 130.

(

-7.41 1.8)E 0 11

(

-7.4 1 1.8)E D

(

-1.9 a 1.5)E 1 5

( 0)

(

-9.2 -

-5.7)E 0

(

-9.2 -

-5.7)E O

(

-3.3 -

-0.4)E 1

• (

0/ 2)*

• (

0/ 2)*

• (

0/ 2)*

I CS-137 ( 4) 150.

(

3.7 1 0.1)E 1 11

(

3.71 0.1)E 1

(

1.2 1 0.7)E 1

( 0)

(

3.5 -

3.8)E 1

(

3.5 -

3.8)E 1

(

5.7 -

18.7)E 0

• (

2/ 2)*

• (

2/ 2)*

• (

0/ 2)*

m itst: FOOD CROP (TF)

UNITS: pCl/kg BE-7

( 3)

(

7.1

• 1.1)E 1 13 (

8.2 1 8.0)E 1

(

1.9 2 7.6)E 1 I

( 0)

(

6.0 -

8.2)E 1

• (

C/ 2)*

• (

0/ 1)*

• (

0/

1)*

K-40

( 3)

(

3.5 t 2.0)E 3 11

(

5.5 1 0.3)E 3

(

1.72 0.3)E 3 I

( 0)

(

1.5 -

5.5)E 3

• (

2/ 2)*

• (

1/ 1)*

• (

1/

1)*

l-131 ( 4)

(

7.8 1 7.0)E 0 13

(

1.9 1 1.1)E 1

(

-2.0 1 1.4)E 1 1

( 0)

(

5.0 -

19.1)E D

• (

0/ 3)*

• (

0/

1)*

• (

0/

1)*

Cs-134 ( 3) 60.

(

-3.4 1.7)E D 13

(

-1.7

• 9.1)E O

(

-1.8 a 1.1)E 1 I

( 0)

(

-5.1 -

-1.7)E O

• (

0/ 2)*

• (

0/ 1)*

• (

0/ 1)*

I CS-137 ( 3) 80.

(

5.9 2 5.4)E O 11

(

1.1 1 1.0)E 1

(

3.91 10.8)E D

( 0)

(

5.6 - 113.0)E -1

• (

0/ 2)*

• (

0/ 1)*

• (

0/ 1)*

I TM 232 ( 3)

(

1.5 a 1.4)E 1 11

(

Z.8

• 4.4)E 1

(

2.5 a 4.9)E 1

( 0)

(

1.1 -

28.5)E O

• (

0/ 2)*

• (

0/ 1)*

• (

0/ 1)*

1 l

1 NOTE: Footretes may be fourd at the ord of table 5.1.

39-F 1

l

TABLE 5.1 RADIOLOGICAL EWIt0IDENTAL PROGRAII mamusy TAaKEg urim PGER STATION, 30hE, MA (JAmahET - DECD SER 1992)

INDICATOR STATIONS STATIDW WITH NIGNIST MEAN CONTROL STATIONS

....................... 2 RAD 10NUCLIDES*

MEAN MEAN MEAN (810. AEALYSES) REQUIRED RANGE STA.

RANCE RANGE (Is0N-ROUTINE)**

LLD 100. DETECTED ***

Wo.

Wo. DETECTED ***

Wo. DETECTED ***

IEDItst: MAPLE SYMP (TF) talITS: pCl/Ls SE-7

( 3)

(

-9.4 a 0.8)E D 42

(

-7.7 s 10.9)E O

(

-7.7 2 10.9)E D

( 0)

(

-1.0 -

0.9)E 1

• (

0/ 2)*

• (

0/ 1)*

• (

0/ 1)*

K-40

( 3)

(

1.7 :

0.2)E 3 42

(

2.2 a b.1)E 3

(

2.2 1 0.1)E 3

( 0)

(

1.5 -

1.9)E 3

• (

2/ 2)*

• (

1/ 1)*

• (

1/ 1)*

1 131 ( 3)

(

4.6 a 2.7)E 1 32

(

7.3 s 4.8)E 1

(

2.8 s 1.4)E 1

( 0)

(

1.9 -

7.3)E 1

• (

0/ 2)*

• (

0/ 1)*

• (

0/ 1)*

CS-134 ( 3)

(

-8.6 s 1.3)E -1 33

(

7.3 a 12.8)E -1

(

-1.6 s 1.0)E D

( 0)

(

-1.0 -

-0.7)E 0

• (

0/ 2)*

• (

0/ 1)*

• (

0/ 1)*

CS-137 ( 3)

(

2.2 a 0.5)E 1 33

(

2.7 0.2)E 1

(

5.7 a 1.0)E O

( 0)

(

1.7 -

2.7)E 1

• (

2/ 2)*

• (

1/ 1)*

• (

1/

1)*

TM-232 ( 3)

(

7.1 5.1)E O 42

(

1.3 2 0.4)E 1

(

1.3 3 0.4)E 1

( 0)

(

2.0 -

12.2)E O

• (

0/ 2)*

• (

1/ 1)*

• (

1/ 1)*

WOTE: Footnotes may be fotsd at the end of Table 5.1. ?.

Footnotes to Table 5.1:

The only radionuclides reported in this table are those with LLD rowirements, those for which positive radioactivity nas detected, and those which may be of interest for some other specific reason. See Section 5 of this report for e discussion of other radiormactidos that were snelyzed.

• • Mon Routine refers to those radionuclides that exceeded the Reportine Levels in 00CM Table 4.2.

• • • The fraction of semple enetyses yielding detectable measurements (i.e. > 3 standard deviations) is shown in parentheses.

I

\\

l

.u.

i l

TABLE 5.2 ENVIRGBENTAL TLD MTA ESMARY l

TaanTr aMCLEAR PGER STATION, RGE, M l

(JAmmRT - DECEMBut 1992)

IslCATOR TLDs OUTER RING TLDs FENCELINE TLDs CONTROL TLDs x.;;;;;;

.w.....

weene.

w............

......w...

n.....

BEAN MEAN MEAN MEAN i

6 RANE RANGE RANCE RANGE (MO. wam *EMENTS)

(NO. MEASUREMENTS)

(NO. MEASUREMENTS)

(NO. MEASUREMENTS)*

6.6 s 0.7 6.8 a 1.0 14.1 a 4.4 7.2 a 0.6 5.0 - 8.8 4.5 - 8.7 9.0 - 24.3 6.0 - 7.9 (51)

(64)

(36)

(8) 0FFSITE STATION WITH NIGHEST MEAN

..w w...

w..

........ e n MEAN STA.

LANGE WO.

(ho. MEASUREMENTS) i 91-34 8.6 s 0.1 I

8.5 - 8.7 (4) s I

(

Each

• measurement" is based typicetty on cparterly readings from five TLD elements.

i 1

I f

l I

I l

1 i

f i

l l

, l f

[

TAsLE 5.3 ENVIRGIBEATAL TLD mraumwyys 1992 (Micre t per mour)

ANWuAL sta.

1si QUARTER 2e euARTER 3aD ouARTER 4TH QUARTER AVE.

no.

Gescription EKP.

s.0.

EXP.

s.0.

[KP.

s.0.

EXP.

s.0.

EXP.

GM-01 YuPs visitor's Eenter 6.7 0.3 6.6 0.3 7.1 0.4 7.3 s 0.4 6.9 QM 02 Observation stand 6.3 a 0.3 6.1 0.2 6.3 a 0.4 6.5 s 0.3 6.3 m-03 aowe school 5.0 s 0.3 5.1 s 0.2 5.5 0.2 5.4 s 0.2 5.3 m 04 marrimen station 6.3 a 0.3 6.1 0.3 6.7 0.3 6.7 s 0.3 6.5 GM 05 manroe Bridge 7.8 0.3 7.7 0.3 8.1 a 0.3 8.8 s 0.3 8.1 GM-06 Roadsboro ad. sarrier 6.5 0.3 6.9 s 0.3 7.2 s 0.2 7.1 a 0.2 6.9 eM-07 Whitingham Line 5.7 : 0.3 5.9 0.2 6.1 0.3 6.2

• 0.2 6.0 en-08 manroe mitt sarrier 6.0 s 0.2 5.9 0.3 6.3 a 0.2 6.2 a 0.3 6.1 m-09 Durter trook 6.7 0.3 6.7 0.3 7.0 a 0.3 7.0 2 0.2 6.9 eM-10 cross ad.

6.1 : 0.2 6.1 0.3 6.6 s 0.3 6.5 0.2 6.3 GM-11 Adams Nigh Line 6.8 : 0.3 7.2 a 0.4 7.5 s 0.2 7.4 a 0.2 7.2 GM-12 aeedsboro, VT 6.8 s 0.2 6.7 : 0.3 7.6 0.4 7.0 GM-13 mestr. Area fence 11.7 0.9 11.0 s 0.4 12.8 s 0.6 11.9 : 0.3 11.9 GM-14 Restr. Area Fence 9.7 s 0.4 9.0 s 0.4 10.2 s 0.5 9.6 0.3 9.6 GM-15 sestr. Area Ferce 10.2 a 0.4 9.1 s 0.4 10.6 2 0.8 10.1 0.3 10.0

[

GM-16 sestr. Area Fence 10.9 0.6 9.2 a 0.3 11.0 s 0.6 11.3 s 0.5 10.6 QM-17 Restr. Aree fence 14.3 a 0.8 12.0 s 0.6 15.1 : 0.9 14.5 s 0.6 14.0 GM-18 testr. Ares Fence 22.5 s 1.2 18.9 1.6 24.3 s 2.2 21.5 s 0.9 21.8 GM-19 Restr. Aree Ferce 20.9 s 0.8 18.1 : 0.7 22.0 s 1.1 20.5 0.6 20.4 m-20 Restr. Area Fence 16.0 s 0.8 14.2 a 0.8 17.2 a 0.6 15.8 0.7 15.8 m-21 Restr. Area Fence 13.2 a 0.6 11.5 s 0.4 14.6 0.6 13.3 s 0.6 13.2 m-22 meertweltvitte, VT 6.0 a 0.2 6.8 : 0.3 7.3 s 0.2 7.1 a 0.2 6.8 GM-23 Wittianstown subst.

7.9 0.4 7.7 : 0.5 7.5 2 0.4 7.4 s 0.3 7.6 GM-24 herriman Dam 7.3 s 0.5 7.4 s 0.3 8.1 s 0.4 8.0 s 0.3 7.7 GM-25 Whitingham, VT 5.9 : 0.3 5.9 0.3 6.5 0.3 6.4 0.2 6.2 m-26 sedoge Rd.

5.9 0.2 6.3 a 0.4 6.8 : 0.3 6.5 s 0.2 6.4 m-27 mater 9 ad.

5.4 0.3 5.6 0.3 6.2 a 0.2 6.0 s 0.3 5.8

[

GM-28 haber 9 Ed.

6.5 s 0.3 6.5 0.3 7.0 s 0.3 6.9 : 0.2 6.7 GM-29 acute SA 4.6 0.3 4.5 2 0.3 5.0 a 0.2 5.1 s 0.2 4.8 GM-30 toute &A 5.5 s 0.2 5.5 0.2 6.1 s 0.3 6.2 s 0.2 5.8 GM-31 Lesate Mill Ed.

6.1 : 0.2 6.0 a 0.3 6.7 0.3 6.4 s 0.2 6.3 m-32 aowe Rd.

6.2 s 0.4 6.0 s 0.2 6.5 s 0.3 6.2 s 0.2 6.2 GM-33 2 oar Rd.

6.2 s 0.3 5.9 0.3 6.5 s 0.3 6.3 a 0.2 6.2 GM 34 Fife Brook Rd.

8.6 s 0.5 8.5 : 0.3 8.6 0.4 8.7 0.3 8.6 GM-35 Whitcomb swenit 6.2 s 0.3 6.5 0.3 7.6 2 0.3 7.3 s 0.3 6.9 GM-36 filda Ed.

6.3 a 0.3 6.8 0.3 7.3 s 0.3 7.3 a 0.3 6.9 CM 37 Turner mitt Rd.

7.2 a 0.4 7.4 s 0.3 8.0 s 0.3 8.0 s 0.3 7.7 m-38 West allt Rd.

7.2 s 0.4 7.8 : 0.3 8.4 a 0.3 8.2 s 0.4 7.9 GM 39 Route 100 7.1 s 0.3 7.9 : 0.4 8.5 s 0.3 8.6 0.3 8.0

+

en-40 keedsboro Rd.

6.1 0.3 6.6 s 0.3 7.1 a 0.3 7.0 a 0.3 6.7

• TLD sissing, amarently dee to vandattaa.

43

1 l

l 6.0 ANALYSIS OF ENVIRONMENTAL RESULTS 6.1 Samnline Prorram Deviations ODCM Control 4.1 allows for deviations "if specimens are unobtainable due to hazardous conditions, seasonal unavailability or to malfunction of automatic sampling equipment." In 1992, eleven deviations were noted in the REMP. These deviations did not compromise the program's effectiveness and in fact are considered insignificant with respect to what is normally anticipated for any radiological environmental monitoring program.

The specific deviations for 1992 were:

1.

A loose coupling on the air volume integrator intake may have led to an erroneously low volume reading for the week March 3-10.

2.

Approximately 35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br /> of sampling were missed at station AP/CF-11 during the week of June 16-23 dee to a transformer insulator change at the Sherman hydro station.

3.

Approximately 5.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> of sampling were missed at station AP/CF-11 during the week of July 14-21 due to work being done on the transformer and power line at Sherman Station.

4.

Approximately 5.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> of sampling were missed at station AP/CF-14 during the week of July 14-21 due to wiring replacement for a new power supply to the gas pump at the Harriman Station warehouse building.

5.

Approximately 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> of sampling were missed at station AP/CF-12 during the week of August 4-11 due most likely to a power I

interruption caused by dam construction at Monroe Bridge.

6.

Approximately 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> of sampling were missed at station AP/CF-12 during the week of August 25 to September 1 due most likely to a power interruption caused by dam construction at Monroe Bridge.

7.

Several hours of sampling were missed at station AP/CF-14 on August 29 due to a power outage caused by a thunderstorm.

8.

Two-and-a-half hours of sampling were missed at station AP/CF-11 on September 11 due to maintenance work at Sherman Station.

9.

The air sampler at station AP/CF-12 was taken out of service at i l

0800 hrs on September 22 due to das construction in Monroe Bridge.

It remained out of service for the remainder of 1992.

This sampler was effectively replaced by the nearby sampler at the Yankee Visitor's Information Center (AP/CF-31).

10. Approximately 35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br /> of sampling were missed at station AP/CF-13 during the week of December 22-29 due to unexplained reasons.

11.

The automatic composite water sampler at station VR-11 was temporarily moved from No. 5 Hydro Station to Fife Brook Hydro Station. This was due to a loss of water supply from.

construction projects associated with No. 5 Hydro Station and the dam at Monroe Bridge.

(Fife Brook Hydro Station is just downstream from No. 5 Station.) The sampler remained at this location for the remainder of 1992.

6.2 Coroarison of Achieved LLDs with Recuirements Table 4.3 of the ODCM (reproduced as Table 4.4 in this report) gives the j

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 sample volume caused by sampling equipment malfunction.

In such a case, Control 7.1 of the ODCM requires a discussion of the situation in the Annual Radiological Environmental Operating Report. At the YAEL, the target LLD for any analysis is typically 30-40 percent of the most restrictive required LLD.

Expressed differently, the typical sensitivities achieved for each analysis are at least 2.5 to 3 times greater than that required by the YNPS ODCM.

For each analysis having an LLD requirement in ODCM Table 4.3, the a costeriori (after the fact) LLD calculated for that analysis was compared j

with the required ilD. Of the approximate 6000 analyses performed during 1992, of which approximately 1800 had an LlD requirement in ODCM Table 4.3, I

all met the requirement.

l 6.3 1992 Results Cornared Arainst Reportine Levels ODCM Control 4.1.a requires the written notification of the NRC (within 30 1

j days) whenever a Reporting Level in ODCM Table 4.2 is exceeded. Reporting Levels are the environmental concentrations that relate to the ALARA design dose objectives of 10 CFR 50, Appendix I.

It should be noted that l

[

environmental concentrations are averaged over calendar quarters for the purposes of this comparison, and that Reporting levels apply only to

{

measured levels of radioactivity due to plant effluents.

During 1992, no Reporting levels were exceeded.

(

6.4 Data Analysis by Media Tyne

(

The 1992 REKP data for each media type are discussed below. These are arranged in the same order as in Table 5.1, and are further categorized by pathway. Graphical plots of monitoring data are shown at the end of the

(

chapter in Figures 6.1 to 6.20.

With respect to data plots, all values are plotted, whether they are " detectable" or "non-detectable."

6.4.1 Airborne Pathways 6.4.1.1 Air Particulates

{

The weekly air particulate filters from each of the seven sampling sites were analyzed for gross-beta radioactivity. At the end of each quarter, the thirteen weekly filters from each sampling site were composited for a gamma analysis. The results of the weekly air particulate sampling program are shown in Table 5.1 and Figures 6.1, 6.2 and 6.3.

The air sampler at station AP/CF-12 was taken out of service at 0800 hrs on September 22 due to dam construction in Monroe Bridge. It remained out of service for the remainder of 1992. This sampler was effectively replaced by the nearby sampler at the Yankee Visitor's Information Center (AP/CF-31).

As shown in Figure 6.1, there has been no significant difference between the quarterly average concentration at the indicator (near-plant) stations and the control (distant from plant) stations. Also notable is a distinct annual cycle, with the minimum concentration in the second quarter, and the maximum concentration in the first quarter. The peak seen in the second

[

quarter of 1986 is airborne contamination resulting from the Chernobyl accident, as detected by the YNPS monitoring program.

{

Figures 6.2 through 6.6 show the weekly gross beta concentration at each air particulate sampling location alongside the same for the control air particulate sampling location at AP-21 (Williamstown, MA).

It can be

(

readily seen that the gross-beta measurements on air particulate filters E

l fluctuate significantly over the course of a year. The measurements from control station AP-21 vary similarly, indicating that these fluctuations

{

are due to regional changes in naturally-occurring airborne radioactive materials, and not due to YNPS operations. Table 5.1 shows that the mean concentrations from indicator stations are equal to those from control locations, further supporting this conclusion. The only other radionuclide

^

detected on air particulate filters was Be-7, a naturally-occurring cosmogenic radionuclide.

As shown in Figures 6.1, 6.2 and 6.3, gross-beta measurements on air g

particulate filters fluctuated significantly over the course of.the year.

[

The measurements from control stations AP-21 and AP-32 vary similarly, indicating that these fluctuations are due to regional changes in

[

naturally-occurring airborne radioactive materials, and not due to YNPS l

operations. Table 5.1 shows that the mean concentrations from indicator stations are not significantly different than those from control locations, further supporting this conclusion. One gross-bete reasurement shown on Figure 6.6 that bears explanation is the concentration at station AP-31 for the week of March 3-10, 1992. At the time of particulate filter collection

{

on March 10, it was discovered that the coupling on the air volume integrator intake was loose. This apparently led to an erroneously low volume reading, and consequently an erroneously high gross-beta

(

concentration. The only other radionuclide detected on air particulate filters was Be-7, a naturally-occurring cosmogenic radionuclide.

6.4.1.2 Charcoal Carrridces The weekly charcoal cartridges from each of the seven air sampling sites were analyzed for I-131.

The results of these analyses are summarized in Table 5.1.

As in previous years, no I-131 was detected in any charcoal cartridge during 1992.

The air sampler at station AP/CF-12 was taken out of service at 0800 hrs on September 22 due to dam construction in Monroe Bridge.

It remained out of service for the remainder of 1992. This sampler was effectively replaced

{

by the nearby sampler at the Yankee Visitor's Information Center (AP/CF-31).

(

{ [

[

r I

I 6.4.2 Vaterborne Pathways 6.4.2.1 Ground Vater Monthly ground water samples were collected from two on-site locations during 1992.

(Only quarterly samples are required by ODCM Table 4.1.)

Table 5.1 and Figure 6.7 show that gross-beta measurements were positive in most samples. This is due to naturally-occurring radionuclides in the water. The levels were consistent with that detected in previous years, with one exception, described below.

The gross-beta measurement for the VG-11 (plant potable) sample collected on January 27, 1992 stands out in Figure 6.7.

(This data point is averaged with the other week's data and plotted as a semiannual average.) An investigation revealed that the high gross-beta measurement was related to a temporary water supply problem at the plant. Due to brownish water in the plant taps on January 24, the well water system was isolated. The water storage tank was soon emptied, and water was trucked in from an outside source and pumped into the plant storage tank. The high gross-beta measurements were possibly caused by sediment stirred up from the bottom of the storage tank as new water was pumped in.

In any case, the water sampled was not from the plant well but from the outside source after it had been pumped into the storage tank. No plant-related radionuclides were detected in the water sample, and the subsequent monthly samples in 1992 had typical gross-beta concentrations.

H-3 was detected in all of the VG-12 (Sherman Spring) samples, as shown in Table 5.1 and Figure 6.8.

The water from Sherman Spring leaves the ground on YNPS property and flows into the Deerfield River.

(Neither the Deerfield River nor Sherman Spring are used for drinking water.) The maximum monthly concentration was 860 pCi/kg, and the mean value for 1992 was 710 pCi/kg. This is due to early plant operations and has been detected in all previous samples from this location.

The concentration of H-3 at this location has decreased steadily for many years. The above maximum concentration of 860 pCi/kg may be compared against the NRC Reporting Level of 30,000 pCi/kg (for drinking water) in ODCM Table 4.2.

f At this Reporting Level, which is based on 10CFR50 Appendix 1 Design Dose Obj ectives, the YNPS ODCM would require notification to the NRC in writing within 30 days. This maximum concentration at station WG-12 is only 2.9 percent of the above Reporting Level.

No gamma-emitting radionuclides were detected in any of the ground water samples. -

6.4.2.2 River Vater Aliquots of river water were automatically collected every two hours from the Deerfield River downstream from the plant, as well as at the Harriman Reservoir control location. These composited samples were collected monthly and sent to the YAEL for analysis. Monthly grab samples were also collected at Sherman Pond near the discharge area.

Taile 5.1 shows that gross-beta measurements were positive in most samples, as would be expected, due to naturally-occurring radionuclides in the water. The historical concentrations at the indicator and control locations have not been significantly different, as shown in Figure 6.9.

During the last half of 1992, however, the levels at VR-11 were slightly elevated relative to the control. Since there were no discharges from YNPS during this period, it is believed that this was due indirectly to the dam construction upstream from the sampler at Monroe Bridge.

Prior to this period, most of the Deerfield River water was diverted from the natural river channel to a canal leading to the No. 5 Hydro Station (where the water was sampled and subsequently returned to the river). In August of f

1992, due to dam construction and modifications to the No. 5 Hydro Station, the water was allowed to flow through the natural river bed as opposed to the canals.

It is believed that the higher gross beta measurements during this period were due to the increased sediment in the water from the river bed.

No gamma-emitting radionuclides attributable to YNPS operations were detected in any of the samples.

For each sampling site, the monthly j

samples were composited into quarterly samples for Tritium (H-3) analyses.

l No Tritium was detected in river water samples during 1992.

6.4.2.3 Storm Drain Vater Monthly grab samples were collected from the Vest Storm Drain (W 52) during 1992. Each sample was analyzed for gross-beta and gamma-emitting radionuclides and H-3.

Cross-beta measurements were positive in ten of the

(

twelve samples, as would be expected. The levels are consistent with or less than those from previous years. No gamma-emitting radionuclides were detected in any of the samples.

H-3 was detected in one of the twelve monthly samples (January 27, 1992 collection) at a concentration of 690 1 210 pCi/kg. This concentration may f

be compared against the NRC Reporting Level of 30,000 pCi/kg in ODCM Table,

e I'.

i 4.2.

(This is a conservative comparison for two reasons:

1) the actual number to compare against a Reporting Level is a quarterly average, which would be lower than this maximum value; and 2) the Reporting Level is also intended to be used for drinking water, and the storm drain water is not used for drinking.) At this Reporting Level, which is based on 10CFR50 Appendix I Design Dose Objectives, the YNPS ODCM would requiro notification to the NRC in writin5 within 30 days. This maximum concentration at station WW-52 is only 2.3 percent of the above Reporting Level.

6.4.2.4 Sediment Semiannual sediment core samples were collected from two locations during 1992.

Each set of samples was segmented by depth (0-5, 5-10,10-15 cm) and analyzed for gamma-emitting radionuclides. As would be expected, naturally-occurring K-40 cnd Ac-Th-228 were detected in all samples. Not surprisingly, naturally-occurring Be-7 was also detected in one sample.

In addition to the above radionuclides, Cs-137 was detected in most segments. The lavels measured at downstream location SE-11 were consistent with what has been measured in the previous several years (see Figure 6.10) and are attributed to nuclear weapons testing fallout that has persisted in the environment. The lower amount of Cs-137 in the control location SE-21 (see Figure 6.11) samples may be explained by the very low organic matter content there relative to the downstream location at SE-11.

Cs-137 tends to bind to the sandy and rocky sediment at the control location to a lesser degree than at the indicator.

In both cases, the lack of any recent Cs-137 contribution, from any source, to the sediment is demonstrated by the lower concentration in the upper layers of sediment (see Figures 6.10 and 6.11).

Table 5.1 and Figure 6.12 show higher levels of Cs-137 at station SE-91.

These samples were collected from a deep water location near the plant discharge in Sherman Pond. Although some of the Cs-137 in these samples is likely due to plant effluents, much of it is believed to be due to global nuclear weapons testing fallout, due to the rich organic content of the mud that is collected from the bottom of Sherman Pond. Two of the six core segments collected in 1992 contained detectable levels of co-60 (maximum concentration of 174 pCi/kg (dry)), which is due to plant effluents. It should be noted that all of the SE-91 samples were collected in deep water, well away from the shoreline. None of this radioactivity is involved in any significant pathway of exposure to man. _ _ _ _ _ _ _ _ _

6.4.3 Inrestion Pathways 6.4.3.1 gilk Milk samples from cows at three local farms were collected twice-per-month during the 1992 pasture season, and monthly during the remainder of the year. Each sample was analyzed for I-131 and other gamma-emitting radionuclides. Quarterly composites (by location) were analyzed for Sr-89 and Sr-90.

As was expected, naturally-occurring K-40 was detected in all samples.

Also expected was Cs-137 and Sr-90.

Cs-137 was detected in 5 out of 40 indicator samples.

Sr-90 was detected in all 8 indicator samples, and all 4 control samples. Although no Cs-137 was detected in the 1992 control samples, it has been in previous years, as shown in Figure 6.13.

Although both Cs-137 and Sr-90 are a by-product of plant operations, the levels detected in milk are due to worldwide fallout from nuclear weapons tests, and to a much lesser degree from fallout from the Chernobyl incident. These two radionuclides are present throughout the natural environment as a result of atmospheric nuclear weapons testing that started primarily in the late 1950's and continued through 1980. They may be found in soil and vegetation, as well as anything that feeds upon vegetation, directly or indirectly. The Cs-137 and Sr-90 levels shown in Table 5.1 and Figures 6.13 and 6.14 are consistent with those detected at other New England farms that are monitored as part of other Yankee-affiliated environmental monitoring program. As shown in these figures, the levels are also consistent with those detected in previous years near YNPS.

6.4.3.2 Eish Semiannual samples of fish were collected from two locations during 1992.

The edible portions of each of these were analyzed for gamma-emitting radionuclides. As expected in biological matter, naturally-occurring K-40 was detected in all samples. As shown in Table 5.1 and Figure 6.15, Cs-137 was detected in the two indicator samples, but not in the two control samples.

(In 1991, Cs-137 was detected in both control samples, but neither indicator.) This radioactivity is attributed to global nuclear weapons testing fallout. No other radionuclides were detected.

i 6.4.3.3 Food Products / Broad Leaf Vecetation The food crops collected in 1992 consisted of samples of kale, peas and j

cucumbers.

Each was analyzed for gamma-emitting radionuclides.

K-40 was detected in all samples. No other radionuclides were detected.

A sample of kale was collected in 1992 at Station TV-11 to satisfy the i

broad leaf vegetation sampling requirement. A low-level 1-131 analysis was done on this sample. No I-131 was detected.

6.4.3.4 Maple Syruo Processed maple syrup samples were collected from three locations in April of 1992. These samples had been concentrated, relative to the original tree sap, by boiling. Naturally occurring K-40 was detected in all three samples, and Ac-Th-228, also naturally-occurring, was detected in one sample.

Cs-137 was detected in all samples. The concentrations of Cs-137 in 1992 samples are consistent with that detected in both indicator and control samples in previous years, and is attributed to global nuclear weapons testing fallout. This radioactivity has been detected in most samples since collection was started in 1972.

6.4.4 Direct Radiation Pathway Direct radiation is continuously measured at 40 locations surrounding YNPS with the use of thermoluminescent dosimeters (TLDs). These are collected every calendar quarter for readout at the YAEL.

As can be seen in Figures 6.16 to 6.26, there is a distinct annual cycle at both indicator and control locations. The lowest point of the cycle occurs during the winter months. This is due primarily to the attenuating effect of the snow cover on radon emissions and on direct irradiation by naturally-occurring radionuclides in the soil. Differing amounts of these naturally-occurring radionuclides in the underlying soil, rock or nearby building materials result in different radiation levels between one field i

site and another. This explains why the control TLD station at the Fife l

Brook Road station (GM-34, 6.4 km from the plant) had the highest mean j

exposure for 1992, as can be seen in Tables 5.2 and 5.3, as well as Figure 6.22.

From Table 5.2 and 5.3, it can be seen that the mean exposure rates for the i I

l l

J

~ Indicator, Outer Ring and Control categories were not statistically different in 1992. This indicates no significant overall increase in-direct radiation exposure rates in the plant vicinity. As shown in Figures 6.16 to 6.26, the levels in 1992 are consistent with those in previous C

years.

)

]

f i

(

(

( [

<l.

l P

FIGURE 6.1 GROSS-BETA MEASUREMENTS ON AIR PARTICUIATE FILTERS QUARTERLY AVERAGES 0.16 0.12-4 1

k i

i es E

M 0.08 l

.o s

U N

l

-et O

0.04 -

R8 h

BD g

b f

g D gg l

g 0

l Jan-1982 Jan-1984 Jan-1986 Jan-1988 Jan-1990 Jan-1992 l

?

1 i

-e-AP - Indicator Stations l

l

-x-AP - Control Stations

I L

1 FIGURE 6.2 GROSS-BETA MEASUREMENTS ON AIR PARTICUIATE FILTERS -

J l

l 0.06 0.052 l

u o

0.04:

uo E

U

~.

x y

0. 0 3 --

D

~

X 4

U

~

D 9

Exx o

0.02-a xx.;.

.x

\\-

x.,.x [

n.

s x

n ',x R.

\\/ x l

Q\\

e 0.01-X b

Q

g a

a.

t i

0 Dec Mar Jun Sep Dec j

I 1992 i

i l

-e-AP-11 Observation Stand

-x-AP-21 Williamstown, MA (control) l l

t

~, l i

(

= _.

. _ - = -

i I

l i

i FIGURE 6.3 GROSS-BETA MEASSUREMENTS ON AIR PARTICUIATE FILTERS 0.06 I

0.05-u o

0.04:

ao E

U i

j 0.03-j x

p

~

g U

N

' xxx d

0.02 2 x

. 1 };

x Y '. x l

x x

c.

x :.

0.01.

0' l

i Dec Mar Jun Sep Dec l

1992 i

l t

-e-AP-12 Monroe Bridge

-y-AP-21 Williamstown, MA (control) i I

i. - -

FIGURE 6.4 GROSS-BETA MEASUREMENTS ON AIR PARTICUIATE FILTERS 0.06 0.05-'

u o

0.04 ao E

U x

-d 0.03-x u

h 0.02 -

xx..

x B

x P

x.. y : x -

a.

0.01{

k

.. x,.g.

!.xx i o

3 X

Ubu D

xg g

6 0'

Dec Mar Jun Sep Dec 1992 9 AP-13 Rowe School

-y-AP-21 Williamstown, MA (control)

[

I u r

i.

i FIGURE 6.5 GROSS-BETA MEASUREMENTS ON AIR PARTICUIATE FILTERS l

0.06 r

0.05{

t u

E oa 0.04 2 o

E o

i x

0.03-

.o X

c Q

o

)

G

(

l '.

xxx x.. x.x

~'.

i o

0.02-p y.

5 x.

xx..

x a

alg S

/, *

• 95 x j'. p.M x

l O

l x

x x

4 i

i

0. 01 --

Q fg6 O

a I

?

l 0

Dec Mar Jun Sep Dec 1992

-e--

AP-14 Harriman Station

-x-AP-21 Williamstown, MA (control) l 1

t t

h l

l,

FIGURE 6.6 GROSS-BETA MEASUREMENTS Ot4 AIR PARTICUIATE FILTERS 0.06 l

~

0. 0 5 --

u o

0.04:

uo E

o i

X y

0.03.

x 2

^

Q

,g i

U j

x..

i N

xx,

x u

0.022 A

.s x.-

X p.

21 x x 7\\

x

, ' '?..':

• • k l6 x

,?

0.01 eo 0

i i

-i Dec Mar Jun SeP Dec l

l i

1992 8

{

c AP-31 YAEC Visitor's Info. Center i

r i

.x.

AP-21 Williamstown, MA (control) t' l

i 1

l 9 ;

i--

FIGURE 6.7 GROSS-BETA MEASUREMENTS OF GROUND WATER i

SEMI-ANNUAL AVERAGES 16 14 2 12-

~

l 10-l x

8:

~

Ua 6-i 4

YC C u s

2.

O ~

i Jan-1982 Jan-1984 Jan-1986 Jan-1988 Jan-1990 Jan-1992

--c-WG-11 Plant Potable e

WG-12 Sherman Spring I

, l l

l

FIGURE 6.8 H-3 IN GROUND WATER STATION WG-12, SHERMAN SPRING 2000 e

a.

'lll dfyDE 1{&q G

i f

Jan-1988 Jan-1989 Jan-1990 Jan-1991 Jan-1992 Jan-1993 1

t t I

FIGURE 6.9 GROSS-BETA MEASUREMENTS OF RIVER WATER SEMI-ANNUAL AVERAGES 6

5._

4-'

3 3-u c.

1_

0' Jan-1982 Jan-1984 Jan-1986 Jan-1988 Jan-1990 Jan-1992 g

WR-11 Bear Swammp Lower Reservoir

-x-WR-21 Harriman Reservoir

{

- u

l l

FIGURE 6.10 CESIUM-137 IN SHORELINE SEDIMENT STATION SE-11, NO.4 STATION 600 500-I 400' g

s l

300-3 0

5/89 10/89 5/90 10/90 5/91 10/91 5/92 10/92 E O - 5 cm E 5 - 10 cm O 10 - 15 cm - -

I l

FIGURE 6.11 l

CESIUM-137 IN SHORELINE SEDIMENT l

STATION SE-21, HARRIMAN RESERVOIR 600 i,

500 ~

4 i

i J

i 400-E i

u j

t 300-i j

tr xs 200-~

'i

-~

1 o

a l

100-~

l 4

l 0

1 i

a c-,__, 3 j

-100 i

5/89 10/89 5/90 10/90 5/91 10/91 5/92 10/92 j

0 - 5 cm 1

E 5 - 10 cm O 10 - 15 cm

FIGURE 6.12

{

CESIUM-137 IN BOTTOM SEDIMENT l

STATION SE-91, SHERMAN POND 6000 5000-1 j

{

g 4000k j

3000-j 3

I E 2000 1000-1 0

i i

i i

i 5/89 10/89 5/90 10/90 5/91 10/91 5/92 10/92 l

3 0 - 5 cm l

E 5 - 10 cm O 10 - 15 cm i

i 4 :

i i

FIGURE 6.13 CESIUM-137 IN MILK ANNUAL AVERAGES 15 10-tn

~

x N

~

A

~

Oa N

5-X f.

X

'X

~~ k

' 'X x

y._.y.

n a

0, 1977 1979 1981 1983 1985 1987 1989 1991 1993

-e-TM-12 Readsboro, VT e

TM-13 Whitingham, VT

-y-TM-21 Williamstown, MA (control) i l

l l I

i l

l

[

FIGURE 6.14 STRONTIUM-90 IN MILK ANNUAL AVERAGES 15 e

10-tn

~

x N

~

w

~

U C.

X 5-

/

}

x.,

X.;

f p.__a

.y_ )-

x x

x-X X.

0, 1977 1979 1981 1983 1985 1987 1989 1991 1993 C

TM-12 Readsboro, VT e

TM-13 Whitingham, VT

-x-TM-21 Williamstown, MA (control) _ _ _ _ _ _ _ _ _ _ - _.

FIGURE 6.15 CESIUM-137 IN FISH ANNUAL AVERAGE CONCENTPATIONS 200 180 1 160 2 140 1

120 1

?

3 100-80-60 2 0

80 81 82 83 84 85 86 87 88 89 90 91 92 Year g TH-11 sb man Pond O ra-21 aarriman aeservoir < control) (

FIGURE 6.16 EXPOSURE RATE AT INDICATOR, OUTER RING AND CONTROL TLD 'S i

15 1

uo 10-2 4

K' 0

O.

.K

.xs..

- \\..

..x g

X a

O 5

4 0

5-l w

E i

i f

f l

i 0

1988 1989 1990 1991 1992 1993

-e-Indicators I

e Outer Ring l

l

-x-Control 1 I i

1 i

i t

l i

FIGURE 6.17 l

EXPOSURE RATE AT INDICATOR TLDS, GM 01-04 l

f i

i 1

l t

25 i

~

l l

i f

20-

[

u

s

,o 15-i u

f c)

C.

c:

h e

0 10-u

+

U

~A 2:

p[b f

/

o 5-i 0

1988 1989 1990 1991 1992 1993 l

t Retrieval Date i

l

--t3-GM-Ol Visitors' Info. Center

]

i i

I A

GM-02 Observation Stand i

x GM-03 Rowe School y GM-04 Harriman Station i <

4 l

i

FIGURE 6.18 EXPOSURE RATE AT INDICATOR TLDS, GM 05-08 25 20-u a

15-4 C.

~

y o

10-y @eh 1

l A

5-0 1988 1989 1990 1991 1992 1993 Retrieval Date

--e-GM-05 Monroe Bridge e

GM-06 Readsboro Road Barrier x

GM-07 Whitingham Line v GM-08 Monroe Hill Barrier

) L

1 FIGURE 6.19 i

EXPOSURE RATE AT INDICATOR TLDS, G4 09-12, 40 l

i 25 i

20-u l

s t

O*

15-i u

e i

n.

M

~

e 0

10-7 w

u o

t E

5-i i

0 1988 1989 1990 1991 1992 1993 f

I Retrieval Date i

c GM-09 Dunbar Brook e

GM-10 Cross Road v GM-11 Adams High Line c,

GM-12 Readsboro, VT i

t GM-40 Readsboro Road

! I l

1

l FIGURE 6.20 EXPOSURE RATE AT OUTER RING TLDS, Gti 24-27 25

~

=

l 20-u

~

2 o*

15-i u

Oc.

I a,:

I o

10-u U

4 b

a

\\

/

1 5-i 0

1988 1989 1990 1991 1992 1993 Retrieval Date

-e-GM-24 Harriman Dam e

GM-25 Whitingham, VT GM-26 Sadoga Road c.

GM-27 Number 9 Road I

FIGURE 6.21 EXPOSURE RATE AT OUTER RING TLDS, Q4 28-31 25 20-4 D

O*

15-u oIL

~

E I

0 10-U

- -a 5-M

/

_m u

a M

0 1988 1989 1990 1991 1992 1993 Retrieval Date

-t3--

GM-28 Nurt.ber 9 Road e

GM-29 Route BA x

GM-30 Route BA O

GM-31 Legate Hill Road l

I r

I i

l I

j t 1

i l

t FIGURE 6.22 EXPOSURE RATE AT OUTER RING TLDS, Gt4 32-35 l

25 r

I I

1 20-i i

e u

s 9

i 15-u CJ n.

cd l

o 10-x x x x >

/

x 5-i 1

t 0

j 1988 1989 1990 1991 1992 1993 i

i Retrieval Date s

j

--e-GM-32 Rowe Road i

A GM-33 Zoar Road x

GM-34 Fife Brook Road e

GM-35 Whitcomb Sunnit r I

FIGURE 6.23 l

EXPOSURE RATE AT OUTER RING TLDS, GM 36-39

[

[

25

[.

~

20-(

.9 15-

~

y

{

/

0 10-U k

y N /

[

/

5-

[

0

{

1968 1989 1990 1991 1992 1993 Retrieval Date

[

-t=)-

GM-36 Tilda Road e

GM-37 Turner Hill Road x

GM-38 West Hill Road v GM-39 Route 100

[

[

[

->e.

E E

1 s

i I FIGURE 6.24 4

EXPOSURE RATE AT FENCELINE TLDS, GM 13-16 50 i

i 40 1 a

u c

i O

30]

i l

u o

C.

~

a:

I 4

0 20-l 3

~

d 10-i e

0 i

i 1988 1989 1990 1991 1992 1993 I

Retrieval Date t GM-13 Restricted Area Fence 3

GM-14 Restricted Area Fence v GM-15 Restricted Area Fence o

GM-16 Restricted Area Fence

. I I

FIGURE 6.25 l

EXPOSURE RATE AT FENCELINE, Q417-21 i

i 50

)

~

40-j 4

o t

1 l

0 30~-

l u

o gg b

I 20-wo g

D j

E 10-i 0

i I

i J

g g

r l

1988 1989 1990 1991 1992 1993 1

Retrieval Date l

-e-GM-17 Restricted Area Fence A

GM-18 Restricted Area Fence j.

y GM-19 Restricted Area rence l

l v GM-20 Restricted Area Fence C;

GM-21 Restricted Area Fence i

1 l i

L

FIGURE 6,26 EXPOSURE RATE AT CONTROL TLDS, GM 22-23 25 l

20-l

~

u p

.9

{

15-u On.

i

~

l o

10-u O

-,4 d

[

\\

5-i I

1 l

1 l

0; 1988 1989 1990 1991 1992 1993 i

Retrieval Date O

GM-22 Heartwellville, VT e

GM-23 Williamstown Substation i

I 1

I 7.0 OUALITY ASSURANCE PROGRAM The quality assurance program at the Yankee Atomic Environmental Laboratory (YAEL) is designed to serve two overall purposes:

1) Establish a measure of confidence in the measurement process to assure the licensee, regulatory agencies and the public that the analytical results are accurate and precise; and 2) identify deficiencies in the sampling and/or measurement process to those responsible for these operations so that corrective action can be taken. Quality assurance is applied to all steps of the measurement process, including the collection, reduction, evaluation and reporting of data, as well as the record keeping of the final results. Quality control is a part of the quality assurance program.

It provides a means to control and measure the characteristics of measurement equipment and processes, relative to established requirements.

The YAEL employs a thorough quality assurance program to ensure reliable

[

environmental monitoring data.

The program includes the use of written, l

approved and controlled procedures for all work activities, a nonconformance and corrective action tracking system, systematic internal audits, audits from external groups, a laboratory quality control program, and a complete training and retraining system.

The Intralaboratory Quality Control program at the YAEL and the EPA third party interlaboratory program are discussed in more detail below. Also discussed is the environmental TLD quality assurance program and the blind duplicate quality assurance program conducted by the Laboratory Quality Control Audit Committee.

7.1 Intralaboratory Ouality control Program The YAEL conducts an extensive intralaboratory quality control program to assure the validity and reliability of non-TLD analytical data.

Included are the internal process control program and the National Institute of Standards and Technology (NIST) Measurement Assurance Program. These together comprise about ten to fifteen percent of the laboratory sample throughput. The records of the quality control program are reviewed by the responsible cognizant individual, and corrective measures are taken

{

whenever applicable.

For the internal process control program and the NIST Measurement Assurance

{

Program, there were 566 analyses for accuracy and 615 for precision in 1992. Of the 566 analyses for accuracy reviewed during this period, 98.6%

met the YAEL acceptance criteria for accuracy, while 1.4% (8 out of 566 analyses) were identified as outside the YAEL acceptance criteria. Of the r l

L r

i 615 analyses for precision during 1992, 100% met the YAEL acceptance criteria for precision. Table 7.1 shows a summary of the results of this program.

7.2 EPA Intercomparison Program l

To further verify the accuracy and precision of the YAEL analyses via an independent outside third party, the YAEL participates in the U.S.

l Environmental Protection Agency's Environmental Radioactivity Laboratory Intercomparison Studies Program for those available species and. matrices l

routinely analyzed by the YAEL. Participation in this program is required by YNPS Technical Specification 6.8.5.b.

Each sample supplied by the EPA l

is analyzed in triplicate, and the results are returned to the EPA within a specified time frame. When the known values are returned to the YAEL, the

~

j YAEL and EPA results are then evaluated against specific YAEL and EPA acceptance criteria. When the results of the cross-check analysis fall outside of the control limit, an investigation is made to determine the cause of the problem and corrective measures are taken, as appropriate.

l Results of this program are provided in this report in compliance with ODCM l

Control 7.1.

l For the EPA Intercomparison Program, there were 171 analyses for accuracy l

on 96 samples.

The samples consisted of water, milk and air particulate l

filters. The analyses were for gamma-emitting radionuclides, gross-beta, strontium, iodine, plutonium and tritium. Table 7.2 shows a summary of the l

results for 1992. Of the 171 analyses for accuracy, all met the EPA mean j

value control limits.

In addition to the above, six water samples and six air particulate filter samples were analyzed for gross-alpha. Since gross-alpha analyses are not routinely performed as part of the YNPS radiological environmental monitoring program, these results are not reported here.

l In 1991, as reported in the 1991 Annual Radiological Environmental Operating Report, a set of Strontium analyses on three water samples (Laboratory Sac;ae Nos. S97981, S97982 and S97983) did not meet the EPA mean value control limits. The mean value was 38.6 pCi/1 and the EPA Control Limits were from 40.3 - 57.7 pCi/1. The YAEL investigated this set of results under Yankee Laboratory Corrective Action Request YLCAR ASG 92.

The sample set was reprocessed, but the Sr-89 results did not indicate the presence of statistically positive radioactivity since the achieved Minimum Detectable concentrations (MDCs) were either at or above the Sr-89 "known" value of 49 pCi/1. The reprocessed analyses were thus inconclusive f

since the Sr-89 had decayed through four half-lives.

i t l

While no explanation was found for the low mean bias for the Sr-89 sample set, the YLCAR was closed out with the issuance of Memorandum EL $20/92, which describes the results of six EPA interlaboratory sample sets containing mixtures of both Sr-89 and Sr-90 analyzed subsequent to the original outlier EPA sample set S97981-S97983. All six EPA sample sets met both YAEL add EPA acceptance criteria at similar Sr-89,90 ratios and activity levels.

7.3 Environmental TLD Ouality Assurance Procram j

The Panasonic environmental TLD (dacrmoluminescent dosimeter) program at l

the YAEL has its own quality assurance program.

In addition to instrumentation checks performed by the Dosimetry Services Group (DSG),

which represent approximately 10% of the TLDs processed, two independent test programs are performed for accuracy and precision. The first of these programs is performed by the in-house Dosimetry QA Officer, and the second involves the University of Michigan third-party testing program. Under these programs, dosimeters are irradiated to known doses (unknown to the DSG) and given to the DSG for read-out.

In 1992, out of 1428 TLDs processed at the YAEL, 6.7% (96 TLDs) were processed as part of the performance testing program, Of these 96 TLDs, 72 were from the in-house Dosimetry QA Officer, and 24 were from the University of Michigan testing program. All of these (100%) met the acceptance criteria for accuracy and precision.

1 l

i 7.4 Blind Duplicate Ouality Assurance Program The Laboratory Quality Control Audit Committee (LQCAC) is comprised of one member from each of the five power plants that are serviced by the YAEL.

i Two of the primary functions of the LQCAC are to conduct an annual audit of YAEL operations and to coordinate the Blind Duplicate Quality Assurance Program. Under the Blind Duplicate Quality Assurance Program, paired samples are submitted from the five plants, including YNPS. They are I

prepared from homogeneous environmental media at each respective plant, and are sent to the YAEL for analysis. They are " blind" in that the identification of the matching sample is not identified to the YAEL.

The LQCAC analyzes the results of the paired analyses to evaluate precision in YAEL measurements.

i t

A total of 51 paired samples were submitted under this program by the five !

l l

participating plants during 1992.

Faired measurements were evaluated for 26 gamma emitting radionuclides, H-3, Sr-89, Sr-90, I-131 and gross-beta.

All measurements were evaluated, whether the results were considered statistically positive or not, and whether the net concentration was positive or negative. Of the 1273 paired duplicate measurements evaluated in 1992, 1271 (99.8%) fell within the established acceptance criteria.

With the two paired measurements that did not meet the acceptance criteria, none had radioactivity that was considered statistically positive. The results of this program are summarized in Table 7.3 and 7.4.

[

[

[ F L

F

?

TABLE 7.1

SUMMARY

OF PROCESS CONTROL ANALYSIS RESULTS January - December 1992 l

l l

ACCURACY PRECISION SAMPLE MEDIA NUMBER NUMBER ANALYSES ANALYSES NUMBER OF OUTSIDE NUMBER OF OUTSIDE ANALYSES ACCEPTANCE ANALYSES ACCEPTANCE CRITERIA CRITERIA AIR CHARCOAL I

Camma 116 3

82 0

I AIR FILTER Beta 221 0

221 0

Gamma 7

0 6

0 Strontium 6

0 6

0 l

MI1K Camma 72 3

103 0

Iodine 46 0

46 0

Strontium 31 0

31 0

WATER Gross-Beta 8

1 8

0 t

Camma 12 0

12 0

Iodine 11 0

11 0

l Strontium 16 1

16 0

Tritium 20 0

17 0

SOIL / SEDIMENT i

Gamma 0

0 56 0

1 TOTAL 566 8

615 0

l

! l i

TABLE 7.2

SUMMARY

OF EPA INTERCOMPARISON ANALYSIS RESULTS January - December 1992 NO. OF NO. OUTSIDE SAMPLE MEDIA SAMPLES NO. OF EPA CONTROL ANALYZED

• ANALYSES LIMITS **

AIR FILTER l

Beta 2

6 0

Gamma 2

6 0

l Strontium 2

6 0

l I

MI1X t

Gamma 2

15 0

Iodine 2

6 0

(

Strontium 2

12 0

WATE l

l Gross-Beta 3

9 0

Gamma 5

66 0

t Iodine 2

6 0

Plutonium 2

6 0

Strontium 4

24 0

Tritium 3

9 0

The number of EPA samples that were analyzed for the specified radionuclide. Each of these samples was analyzed in triplicate.

Ihe number of mean values (from triplicate samples) outside EPA Control Limits..

TABLE 7.3

SUMMARY

OF BLIND DUPLICATE SAMPLES SUBMITTED January - December 1992 TYPE OF SAMPLE NUMBER OF PAIRED SAMPLES SUBMITTED Cow Milk 20 Ground Water 8

River Water 4

Surface (Fresh) Water 1

Estuary Water 5

Sea Water 6

Irish Moss 2

Mussels 4

Food Product -

1 Cranberries TOTAL 51

) r i

TABLE 7.4

SUMMARY

OF BLIND DUPLICATE RESULTS January - December 1992 TOTAL ANALYSES

• ANALYSIS TYPE FDOD MARINE MIII WATER PRODUCT AILAE MUSSEL TOTAL Camma 479 (0) 561 (2) 25 (0) 49 (0) 96 (0) 1210 (2)

Sr-89/90 8 (0) 8 (0)

H-3 12-(0) 12 (0)

Cross Beta 11 (0) 11 (0)

I-131 20 (0) 4 (0) 24 (0)

The number of paired measurements that did not meet the acceptance criteria are given in parentheses.

See text for details.

i l

{ L I

I 8.0 IAND USE CENSUS I

A Land Use Census is conducted annually between the dates of June 1 and October 1 to identify the locations of the nearest milk animal, the nearest I

residence and the nearest garden of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a lE distance of five miles f the p ant.

At the time f the 1992 Land Use 3

Census, the requirements were in the Radiological Effluent Technical Specification 3/4.12.2.

On November 1992, the detailed requirements of the II Land Use Census were moved to the Offsite Dose Calculation Manual, with the overall requirement for conducting the Census being kept in the Technical l

Specifications under 6.8.5.b.2.

In this report, for the sake of convenience to the reader and because the text of the detailed census 1

requirements in the two documents is the same, the ODCM controls are cited.

Immediately following the collection of field data, in compliance with ODCM Control 4.2, a dosimetric analysis is performed to compare the census locations to the " Critical Receptor" identified in the Offsite Dose Calculation Manual (ODCM). This Critical Receptor is the location that is used in the conservative Method 1 dose calculations found in the ODCM (i.e.

the dose calculations done in compliance with ODCM Surveillance Requirement I

3.4.

If a census location has a 20% greater potential dose than that of the Critical Receptor, this fact must be announced in the Semiannual i E Effluent Release Report for that period. A re-evaluation of which location

g to use as a Critical Receptor would also be done at that time.

For the 1992 Census, no such locations were identified.

!g E

Pursuant to ODCM Control 4.2, a dosimetric analysis is then performed, using site specific meteorological data, to determine which milk and food I

product census 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 later eliminated from the program). For the 1992 Census, no such garden locations were identified, and consequently i

no changes were mandated for the food product or broadleaf vegetation sampling programs. One such milk animal location was identified during 1992. This was in Rowe, MA in the Southeast sector at 3.2 km.

The owner was not able at that time, however, to supply milk to YNPS due to the small number of goats owned. Consequently, no changes were made in the milk sampling program.

The Land Use Census was carried out and completed between the dates of June I I

i i

l l

1 and October 1, as required. The results of the 1992 Land Use Census are included in this report in compliance with ODCM Surveillance Requirement 4.2.

The locations identified during the Census may be found in Table 8.1.

i I

l i

l l

l L

i I

l l

I i

I

\\

i i

I l

{

L

l TABLE 8.1 1992 IAND USE CENSUS LOCATIONS NEAREST NEAREST SECTOR RESIDENCE CARDEN NEAREST MILK ANIMAL Km (Mi)

Km (Mi)

Km (Mi)

N 4.8 (3.0) 3.5 (2.2) 6.1 (3.8) (Cow) hTE 4.4 (2.75) 4.4 (2.75)

NE 3.1 (1.9) 3.1 (1.9)

ENE 3.1 (1.9) 5.8 (3.6) 8.4 (5.2) (Cow)

E 3.0 (1.9) 3.1 (1.9)

ESE 3.2 (2.0) 3.5 (2.2) 7.9 (4.9) (Cow)

SE 2.3 (1.4) 2.3 (1.4) 3.2 (2.0) (Coat, Cow)

SSE 2.1 (1.3) 2.9 (1.8)

S 2.3 (1.4) 2.9 (1.8)

SSV SW 1.3 (0.8) 7.7 (4.8)

WSW 1.3 (0.8) 1.3 (0.8)

V 1.9 (1.2) 2.7 (1.7) 6.9 (4.3) (Coat)

WNV 1.9 (1.2) 1.9 (1.2) 6.8 (4.2) (Cow)

NW 0.45 (0.3) 4.6 (2.8) l NNW 2.9 (1.8) 3.9 (2.4)

No location was identified within 5 miles of the plant.

6 - _ - - - _ _ - _ _ _ - _ _ _ _ _ _ -

9.0

SUMMARY

During 1992, as in all previous years since 1958, a program was conducted to assess the levels of radiation or radioactivity in the Yankee Nuclear Power Station environment. Over 1,000 samples were collected (including TLDs) over the course of the year, with a total of over 5,000 radionuclide or exposure rate analyses being performed on them. The samples included ground water, river water, sediment, fish, locally grown food products, maple syrup and milk.

In addition to these samples, the air surrounding the plant was sampled continuously and the radiation levels were measured continuously with environmental TLDs.

Iow levels of radioactivity from three sources were detected. Most samples had measurable levels of K-40, Be-7, AcTh-228 or radon daughter products.

These are the most common of the naturally-occurring radionuclides. Many samples (milk and sediment 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 I

from emissions from YNPS. These were all collected in the immediate vicinity of the plant or from on-site locations.

In all cases, the possible radiological impact was negligible with respect to exposure from I

natural background radiation.

In no case did the detected levels approach or exceed the most restrictive federal regulatory or plant license limits for radionuclides in the environment.

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10.0 REFERENCES

1.

USNRC Radiological Assessment Branch Technical Position, "An Acceptable Radiological Environmental Monitoring Program,"

Revision 1, November 1979.

2.

NCRP Report No. 94, Exposure of the Pooulation in the United States and Canada from Natural Backcround Radiation, National Council on Radiation Protection and Measurements, 1987.

3.

Ionizine Radiation-Sources and Biolorical Effects, United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR), 1982 Report to the General Assembly.

4.

Kathren, Ronald L., Radioactivity and the Environment - Sources.

Distribution. and Surveillance, Harwood Academic Publishers, New York, 1984.

5.

Letter, " Issuance of Amendment No. 146 to Facility Possession Only License No. DPR-3-Yankee Nuclear Power Station," M.

Fairtile, NRC to J. Grant Yankee Atomic Electric Company, dated November 5, 1992.

6.

NRC Generic Letter 89-01,

Subject:

Implementation of Programmatic Controls for Radiological Effluent Technical Specifications in the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of RETS to the Offsite Dose Calculation Manual or to the Process Control Program. Dated January 31, 1989. r t

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