Text

Annual Radiological Environ Operating Rept,Jan-Dec 1992
	ML20036A214
Person / Time
Site:	Maine Yankee
Issue date:	12/31/1992
From:	Herbert J; Maine Yankee
To:	Martin T; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
	JRH-93-88, MN-93-45, NUDOCS 9305100222
	Download: ML20036A214 (86)
	v • d • e

{{#Wiki_filter:MaineYankee AEllABLE ELECTRICITY SINC _[ 1972 EDISON DRIVE

AUGUSTA, MAINE 04330 + (207) 6224868 April 29, 1993 MN-93-45 JRH-93-88 UNITED STATES NUCLEAR REGULATORY COMMISSION Region I 475 Allendale Road King of Prussia, PA 19406 Attention:

Mr. Thomas T. Martin, Regional. Administrator

Reference:

(a) License No. DPR-36 (Docket No. 50-309)

Subject:

Annual Radiological Environmental Operating Report Gentlemen: Pursuant to the requirements of T.S.5.9.1.5, enclosed is the Annual Radiological Environmental Operating Report for the Maine Yankee. Atomic Power Station. This report contains a summary and analysis of the radiological environmental data collected for calendar year 1992. The results of the program for 1992 are summarized in the Executive Summary at the beginning of the report. Please contact John Arnold should you have questions or comments on this report. Very truly yours, 0James R. Hebert, Manager Licensing & Engineering Support Department-JRH/ jag Enclosure DoEUMAEC$ntYSl$DdsE -i'M6 Charles' S. Marschall c: Mr. E. H. Trottier. Mr. Patrick J..'Dostie American Nuclear Insurers. Mr. Donald Hoxie, Maine Division of Health Engineering La\\93mn\\9345 93051'06222 921231- [ .PDR ADOCK 05000309. y R .PDR J

s' M A ' mW'* = *.

a V i., %g, 4 Tr.

,,s. T "w, t- ' e' I, 't " if

s*.,,*W *..k.

e ,y e ' ' ~ uswi g -u-w i e eus A f 4 =s- .w. =6 8 J q. .g'g 1,.. '1 <..c g g 1.. k f, . u. yk' iNOh,@SLi[k.MdMADNNN[bM" 'd. ' J. ~ ~ . m,. '+ ~ 4 @yM.,brsgr%y@.s& Mmgm%l2': ~'. / J L&wm. .. %.,.;'f 4.J f k wb ~+ - ( e .-.s+, .g ( i V T' pu - t -e. it. +,. .g .,3 sJ * * '. t. 5# ' b .t.. 3 q..- '9-*:4 e y3.g g &. < M W - W

n.:. & &

7: o e h[o

aa v x =

x ? 's ,~ -. .4,3 - _ a._,i *,. .,eq; - w y z

p".

I - _p2 %'a'43, " J.> _ r e-fhf4 W~..- n .m ~ ++.s m v. : a,,n,n,, z.x n. i.,

r '

sW4 ( _R.y. Y'.' O- &f '5y'h% a. 'E ~

m. ;u s

sj w' a. m,. e e-. 5 "' . j.M h e w.,,.-- a w.,.. J L'. .<.-*L' g. i, 'T 4 ' -- f+ 9 .p, .,.~ m.. - - u. a.6 . s.w,.f. 4 _ z _ _ 2

w. 9

..c Ar.. a

l,h : i t i I i -f ) . j s t MAINE YANKEE NUCLEAR POWER STATION f ANNUAL RADIOIDGICAL ENVIRONMENTAL OPERATING REPORT l -i January - December 1992 l r + .i .i April 1993 -i; s; l t

l t

1 .i ~ -? > Prepared-by: j Yankee Atomic Electric Company j Environmental Engineering Department 580 Main Street Bolton, Massachusetts 01740 l .r; i 'l 't 'l 1 g ' W

-4 EXECUTIVE

SUMMARY

i During 1992, as in all previous years of plant operation, a program was conducted to assess the levels of radiation or radioactivity in the Maine Yankee environment. Over 700 samples were collected (including TIES) over -l the course of the year, with approximately 4000 radionuclide or exposure rate analyses being performed on them. The samples included ground water, i estuary water, sediment, marine algae, fish, mussels, crabs, lobsters, Brass, soil 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. i Low levels of radioactivity from naturally-occurring, fallout and plant emission sources were detected. Most samples had measurable concentrations-of K-40, Be-7, AcTh-228'or Radon daughter products. These are the most common of the naturally-occurring radionuclides. Many samples (milk, soil [ and sediment in particular) had fallout radioactivity from atmospheric nuclear weapons tests conducted primarily from the late 1950's through 7 1980. Several samples had low levels of radioactivity resulting from emissions from Maine Yankee. These were all collected in the immediate t vicinity of the plant or from on-site locations. In all cases, the possible radiological impact was negligible with respect to exposure from-natural background radiation. In no case did the detected levels approach or exceed the most restrictive federal regulatory or plant license limits for radionuclides in the environment. Consequently, there was judged to be no environmental or health impact. l q t I L t I i i -i [ t __ _ r?

3 TABLE OF CONTENTS i! i a LI g i EXECUTIVE

SUMMARY

11 l.! P TABIE O F CONTENTS............................................. iii LIST OF TABLES'................................................ iv r LIST OF FIGURES.............................................. v 1. INTRODUCTION.................................................. l' ,q 2. NATURALLY OCCURRING AND MAN-MADE BACKCROUND RADIOACTIVITY..... 2 l 3. CENERAL PIANT AND SITE INFORMATION............................ 5

s A

4 PROGRAM DESIGN................................................ 6 5. RADIO 1DGICAL DATA

SUMMARY

TABLES.............................. -26 l 6. ANALYSIS OF ENVIRONMENTAL RESULTS............................. 42 i 7.' QUALITY ASSURANCE PROGRAM..................................... 69 i 8. LAND US E C EN S U S............................................... .76 9. REFERENCES.................................................... -78 'a s

3

' l f O s ? + W -1 f ,l ..iii-1 i 1 g ,g

~, ~ .~ LIST OF TABLES I q t i4 I IAhlt D ZA&R r I 4.1 Radiological Environmental Monitoring Program........... 12 t 4.2 Radiological Environmental Monitoring Locations (Non.TLD) in 1992........................... 14 l i 4.3 Radiological Environmental Monitoring Loc ations (TID) in 19 9 2............................... 16' 4.4 Environmental Lower Limit of Detection (LID) ' Sensitivity Requirements.............................. 18 l 4.5 Reporting Levels for Radioactivity Concentrations in Environmental Samples.............................. 19-t 5.1 Environmental Radiological Program Sumeury.............. 28 5.2 Environmental TLD Data Summary.......................... 40-r 5.3 Environmental TLD Measurements........................... 41-7.1 Summary of Process Control Analysis Results............. -72 ?

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

73 d 7.3 Summary of Blind Duplicate Samples Submitted........... .74 t 7.4 Summary of Blind Duplicate Results...................... 75 i 8.1 1992 Land Use Census Locations.......................... 77 l I -i = -f -t \\ ..iv. -I -i 1-b _._;'-____i__-_.i_-------------------------

t 4 JJST OF FIGURES Firure 11111 gggg 4.1 Radiological Environmental Sampling Locations Within 1 Kilometer of Maine Yankee...................... 20 4.2 Radiological Environmental Sampling Locations Within 12 Kilometers of Maine Yankee..................... 21 4.3 Radiological Environmental Sampling Locations Outside 12 Kilometers of Maine Yankee................... 22 4.4 Direct Radiation Monitoring Locations Within i Kilometer of Maine Yankee -...................... -23 4.5 Direct Radiation Monitoring Locations Within 12 Kilometers of Maine Yankee 24 4.6 Direct Radiation Monitoring Locations Outside'12 Kilometers of Maine Yankee...................

25 6.1 Cross-Beta Measurements on Air Particulate Filters......

49 (Quarterly Average Concentrations) 6.2 Gross-Beta Measurements on Air Particulate Filters-...... 50 (AP-11 vs. AP-29 Control) ~ 6.3 Cross-Beta Measurements on Air Particulate Filters......- 51' (AP-13 vs. AP-29 Control) 6.4 Gross-Beta Measurements on Air Particulate. Filters...... 52 (AP-14'vs. AP-29 Control) Cross-Beta Measurements on Air Particulate Filters...... '53 6.5 (AP-16 vs. AP-29 Control) 6.6 Cesium-137 in Shoreline Sediment Station SE-16, Old_Outfall Area.......-................. 54 .y. A

1,. LIST OF... FIGURES (continued) Fi rure Title gagg 6.7 Cesium-137 in Shoreline Sediment Station SE-18, Foxbird Island........................... 55 6.8 Cesium-137 in Milk (Annual Average Concentrations) 56 6.9 Strontium-90 in Milk (Annual Average Concentrations) 57 6.10 Exposure Rate at inner Ring, Outer Ring and Control TLDs. 58 6.11 Exposure Rate at Inner Ring TLDs, TL 01-04.............. 59 6.12 Exposure Rate at Inner Ring TLDs, TL 05-08.............. 60 6.13 Exposure Rate at Inner Ring TLDs, TL 09-10, 12-13....... 61 6.14 Exposure Rate at Inner Ring TLDs, TL 14-16.............. 62 6.15 Exposure Rate at Inner Ring TLDs, TL 17-19.............. 63 6.16 Exposure Rate at Outer Ring TLDs, TL 11, 20-22.......... 64 6.17 Exposure Rate at Outer Ring TLDs, TL 23-26.............. 65 6.18 Exposure Rate at Outer Ring TLDs. TL 27-30.............. 66 6.19 Exposure Rate at Outer Ring TLDs, TL 31-35.............. 67 6.20 Exposure Rate at Control TLDs TL 36-38................. 68 -vi-z-

1. INTRODUCTION This report summarizes the findings of the Radiological Environmental Monitoring Program (REMP) conducted by Maine Yankee Atomic Power Company in the vicinity of the Maine Yankee Nuclear Power Station in Wiseasset, Maine during the calendar year 1992.

It is submitted annually in compliance w',th Appendix C, item no. 1 of the Offsite Dose Calculation Manual (ODCM) and Technical Specification 5.9.1.5. This remainder of this report is organized as follows: Section 2: Provides an introduction to the background radioactivity and radiation that is detected in the Maine Yankee environs. Section 3: Provides a brief description of the Maine Yankee Nuclear Power Station site and its environs. Section 4: Provides a description of the overall REMP program design. Included is a summary of the ODCM requirements for REMP sampling, tables listing all routine sampling and TLD monitoring locations with compass sectors and distances from the plant, and maps showing the location of each of the sampling and TLD monitoring locations. Tables listing Lower Limit of Detection requirements and Reporting Levels are also includad. 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 are complete environmental TLD data. Section 6: Provides the results of the 1992 monitoring program. The performance of the program in meeting ODCM requirements is discussed, and the data acquired during the year are analyzed. Section 7: Provides an overview of the Quality Assurance programs used at the Yankee Atomic Environmental Laboratory. The results of the EPA Intercomparison Program required by Technical Specification 5.8.1.b.3 are also given. Section 8: Summarizes the requirements and the results of the 1992 Land Use Census. Section 9: Gives an overall summary of the results of the 1992 Radiological Environmental Monitoring Program. rr

~ 2. Naturally occurrina and Man-Made Backcround Radioactivity Radiation or radioactivity potentially detected in the Maine Yankee environment can be grouped into three categories. The first is

naturally-occurring" radiation and radioactivity.

The second is " man-made" radioactivity from sources other than the Maine Yankee plant. The third potential source of radioactivity is due to emissions from the Maine Yankee plant. For the purposes of the Maine Yankee REMP, the first two categories are classified as " background" radiation, and are the subject of discussion in this section of the report. The third category is the one that the REMP is designed to detect and evaluate. 2.1 Naturally Occurrine Baektround Radioactivity Natural radiation and radioactivity in the environment, which provide the major source of human radiation exposure, may be subdivided into three separate sub-categories: " primordial radioactivity", "cosmogenic radioactivity" and " cosmic radiation", " Primordial radioactivity" is made up of those r nonuclides that were created with the universe and that have a sufficiently 1cag 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 (En-222). Uranium-238 and Thorium-228 are readily detected in soil and rock, whether through direct field measurements or through laboratory analysis of samples. Radium-226 in the earth can find its way from the soil into ground water, and is often detectable there. Radon-222 is one of the components of natural background in the air we breath, and its daughter products are detectable on air sampling filters. Potassium-40 comprises about 0.01 percent of all natural potassium in the earth, and is consequently detectable in most biological substances, including the human body. There are many more primordial radionuclides found in the environment in addition to the major ones discussed above (Reference 2). The second sub-category of naturally-occurring radiation and radioactivity is "cosmorenic radioactivity". This is produced through the nuclear interaction of high energy cosmic radiation with elements in the earth's atmosphere, and to a much lesser degree in the earth's crust. These radioactive elements are then incorporated into the entire geosphere and atmosphere, including the earth's soil, surface rock, biosphere, sediments, ocean floors, polar ice and atmosphere. The major radionuclides in this. - f

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-occurring radiation and radioactivity is " cosmic radiation". This consists of high energy atomic or sub-atomic particles of extra-terrestrial origin and the secondary particles and radiation that are produced through their interaction in the earth's atmosphere. The primary radiation comes mostly from outside of our solar system, and to a lesser degree from the sun. We are protected from most of this radiation by the earth's atmosphere, which absorbs the radiation. Consequently, one can see that with increasing elevation one would be exposed to more cosmic radiation as a direct result of a thinner layer of air for protection. This " direct radiation" is detected in the field with gamma spectroscopy equipment, high pressure ion chambers and thermoluminescent dosimeters (TLDs). 2.2 Man-Made Background Radioactivity The second source of " background" radioactivity in the Maine iankee 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 Maine Yankee 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 1945 through 1980 by the United States, the Soviet Union, the United Kingdom, China and France, with the large majority of testing occurring during the periods 1954-1958 and 1961-1962. (A test ban treaty was signed in 1963 by the United States, Soviet Union and United Kingdom, but not by France and China.) The most recent test, conducted by the People's Republic of China, occurred in October of 1980. Much of the-fallout detected today is due to this explosion and the last large scale one, done in November of 1976 (Reference 3). The radioactivity produced by these datonations was deposited worldwide. The amount of fallout deposited in any given area is dependent on many factors, such as the explosive yield of the device, the latitude and altitude of the detonation, the season in which it occurred, and the timing of subsequent rainfall which washes fallout out of the tropospheric portion (Reference 4). Most ofLthis fallout has decayed into stable elements, but the residual radioactivity is still detectable at low levels in 3 I E l

') 1 I envirormental samples worldwide. The two predominant radionuclides are l Cesium-137 (Cs 137) and Strontium-90 (Sr-90). They are found in soil and s ' in vegetation, and since cows and goats graze large areas of vegetation, these radionuclides are also readily detected in milk. i 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 'I industry. These collectively are insignificant on a global scale when compared to the sources discussed above'(natural and fallout). r I l ~! 1 . l o l 1 r' E

l 1 x. t

3. GENERAL PLANT AND SITE INFORMATION The Maine Yankee Nuclear Power Station is located in the town of Wiscasset.

Lincoln County, Maine, approximately six miles northeast of Bath, Maine. i The site vicinity is rural'and lightly populated. The plant site is located on Bailey Point, a peninsula bounded to the east 4 ~ I by the Back River and to the west by a shallow inlet known as Bailey Cove. Both of these estuaries flow south into Montsweag Bay, which is a tidal' estuary of the Sheepscot River. (See the maps in Figures 4.1 to 4.6.) Bailey point is an elongated bedrock ridge with flat or gently rolling topography rising to an average elevation of about 25 feet above sea level (Reference 5). The single 900 megawatt PWR (Pressurized Water Reactor) unit at Maine Yankee began commercial operation in 1972. The Radiological Environmental Monitoring Program (REMP) began preoperational measurements in 1970, two years prior to commercial operation. The REMP has been in continuous operation since that date. L i [ i t 7 h 5-i 4 t sf

4

4. PROGRAM DESIGN The Radiological Environmental Monitoring Program (REMP) for the Maine Yankee Nuclear Power Station was designed with specific objectives in mind. These are:

To provide an early indication of the appearance or accumulation of any radioactive material in the environment caused by the operation of the station. To provide assurance to regulatory agencies and the public that the station's environmental impact is known and within anticipated limits. - To verify the adequacy and proper functioning of station effluent controls and monitoring systems. - To provide standby monitoring capability for rapid assessment of risk to the general public in the event of unanticipated or accidental releases of radioactive material. The program was initiated in 1970, approximately two years before the plant began commercial operation in 1972. It has been in operation continuously since that time, with improvements made periodically over those years. Prior to January 1992, the requirements for the Radiological Environmental Monitoring Program (REMP) were given in the Radiological Effluent Technical Specifications (RETS). In January 1992, the REMP specifications were removed from the RETS and placed in the Offsite Dose Calculation Manual (ODCM) pursuant to NRC Generic Letter 89-01 (Reference 6). The REMP is a requirement of Technical Specification 5.8.1.b. The detailed sampling requirements of the REMP are given in Table 2.3 of ODCM Section 2.4 This table is summarized in this report as Table 4.1. The required samplin5 locations are identified in Chapter 5 of the ODCM. The locations actually monitored in 1992 are shown on Tables 4.2 and 4.3, as well as Figures 4.1 through 4.6 of this report. The locations in these tables and figures consist of the required locations specified in the ODCM, as well as any additional optional sampling locations used in 1992. - 2 __ _

u.n s w. , =. .1.aa + ^%- a 2 1 t 4.1 Monitorine Zones The REMP is designed to allow comparison of levels of radioactivity in l samples from the area possibly influenced by the plant to levels found in f 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 j 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 l -meteorological history, meteorological dispersion calculations, relative direction from the plant, river flow, and distance. Analysis of survey data from the two zones aids in determining if there is a significant difference between the two areas. It can also help in differentiating between radioactivity or radiation due to plant releases and that due to other fluctuations in the environment, such as atmospheric nuclear weapons test fallout or seasonal variations in the natural background. 1 4.2 Pathways Monitored Four pathway categories are monitored by the REMP. They are the Direct l 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. p Airborne Pathway i Air Particulate Sempling -{ Charcoal Cartridge (Radioiodine) Sampling i Mixed Grass Sampling (for airborne deposition) l .l Waterborne Pathways Estuary Water Sampling Ground Vater Sampling .I Shoreline Sediment Sampling Marine Algae Sampling l Ingestion Pathways -Milk Sampling l .Fisn and Invertebrate Sampling i i Direct Radiation Pathway TIE Monitoring ) .i 1 ^. 7 1 ~ f

_- - ~ ~. - JI ^ i 4.3 Descrintions of Monitorine Prorr=== l !i 4.3.1 Air Sa=nline l l Continuous air' samplers are installed at five locations. h sampling pumps at these locations operate continuously at a flow rate of ? approximately one to two cubic feet per minute.- Airborne particulates are collected by passing air through a 47 ass glass-fiber filter.. A dry-gas. meter is incorporated in the sampling stream to measure the total amount of.- air sampled in a given interval. The entire air. sampling system'is housed l in a weatherproof structure. The filters are collected weekly and are initially screened at the Maine Yankee Environmental Services Laboratory. with a gas flow proportional counter. To allow for the decay of radon j daughter products, they are then held for at least.100 hours at the Yankee Atomic Environmental Laboratory before being analyzed for gross-beta radioactivity (indicated as CR-B in the data tables)' The weekly filters j are composited (by location) at the Laboratory for a quarterly gasma i spectroscopy analysis. [ i j 4.3.2 Charcoal Cartridre (Radiciodine) Samnline-j [ 1 Continuous air samplers are installed at five locations. The sampling pumps at these locations operate continuously at a flow rate of .l approximately one to two cubic feet per minute. A 60 cc TEDA-impregnated l . charcoal cartridge is located downstream of the air particulate filter l described above. These cartridges are collected and analyzed weekly for I- { 131. A dry-gas meter is incorporated in the sampling stream to measure the 'l total amount of air sampled in a given interval. The entire air.samp1'ng- .j i system is housed in a weatherproof structure. The filters are collected i weekly and are initially. screened at the Maine Yankee Environmental Services Laboratory with an Eberline Model RM-14 monitor with an HP-210-j pancake probe. lj 'l 4.3.3 Mixed Crass Samnline i Although there~is no Technical' Specification-requirement for mixed grass'or vegetation sampling, a sample is collected from an on-site location twice --during the growing season. -To collect this sample,'all-grass is cut to.a-j height of-one. inch above' ground level from a 4 ' square meter plot. h= l grass is shipped to the. Laboratory in a plastic bag, where.it is analyzed j for gamma-emitting radionuclides. l} . -l 1 l 4 m.

i 4.3.4 Estuary Unter Sampling An automatic compositing sampler is located at the discharge forebay to monitor water discharged to the Back River. (In-plant systems monitor water prior to release to the discharge forebay.) The sampler is controlled by a timer that collects an aliquot of this water at least every two hours. Every week a one-liter sample is gathered from this composited sample. These one-liter samples are again composited at the Environmental i Services laboratory before shipping to the Yankee Atomic Environmental Labcratory at the end of the month. A weekly grab sample is collected at l the control location in the Kennebec River. These are composited for a l monthly sample at the Environmental Services Laboratory. All estuary water ( samples are preserved with hcl and NaHSO3 to prevent the plate out of radionuclides on the container walls. Each monthly composite or grab sample is analyzed for gamma-emitting radionuclides. These are composited again (by location) at the Laboratory for a quarterly H-3 analysis. 4.3.5 Cround Vater Samoline Due to the hydraulic gradient at the Maine Yankee site, whereby the ground water flow is southward down the peninsula and toward the water on the east and west sides, ground water sampling is not required at the Maine Yankee site, pursuant to ODCM Table 2.3. Nevertheless, grab samples are collected quarterly from the one on-site location and one control location. All [ ground water samples are preserved with hcl and NaHS0 3 to prevent the plate out of radionuclides on the container walls. Each sample is analyzed for gamma-emitting radionuclides and H-3. During 1992, additional ground water samples were collected from on-site monitoring wells. These special samples are discussed in Section 6.4.2.2. t I i ( 4.3.6 Sediment Samoline Shoreline sediment cores are collected semiannually from two locations on Bailey Point. At each location, six two-inch 1.D. plastic coring tubes are driven into the sediment to a depth of at least six inches. The cores are ~ then kept in an upright position and frozen prior to delivery to the Laboratory. At the Laboratory, the frozen cores are cut into two-inch se gments. 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 [

f f

1 e F

are then analyzed for gamma-emitting radionuclides. 4.3.7. Marine Airae Samoline Mixed samples of Pucus and Asconhv11um marine algae are collected semiannually frca two locations, one near the plant diffuser discharge and one at a control location. (Neither of these samples is required by ODCM Table 2.3.) Each sample is frozen for shipment to the Laboratory. At the Laboratory, they are analyzed for gamma-emitting radionuclides. 4.3.8 Milk Samoline Milk samples are collected on a monthly schedule from at least three locations. Two locations are chosen as a result of the annual Land Use Census, based on a hypothetical potential dose commitment. The third location is a control, which is located sufficiently far away from the plant to be outside any potential influence from it. At the time of sampling, each milk sample is preserved with an appropriate amount of formaldehyde. Methimazole is also added to prevent protein binding of any radioiodine. 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 quarterly composited samples. Beginning in late 1991 and into early 1992, the milk animal location at TM-17 was not able to reliably provide milk samples to Maine Yankee. At about the same time, in early 1992, the presence of milking cows at the Chevonki Foundation became known. A meteorological dispersion / dose analysis was performed, and it was determined that the Chewonki location would be acceptable as a replacement for the TM-17 location. ODCM Table 5.1 was revised appropriately in May of 1992. 4.3.9 Fish and Invertebrate Samoline Samples of commercially important fish and invertebrates are collected semiannually at two locations (near the plant discharge and at a control location on the Sheepscot River). A commercial lobsterman was contracted in 1992 for the collection of fish (using gill nets), crabs and lobsters. Mo11use (blue mussel) samples are collected at both sampling locations by l ' i

~ IJ Maine Yankee Environmental Services s'taff. All samples'are separated by species type and are then frozen and delivered to the Laboratory, where the edible portions are analyzed for gamma-amitting radionuclides. l 4.3.10 TLD Monitorine Direct gamma radiation exposure was continuously measured with the use of thermoluminescent dosimeters (TLDs). Specifically, Panasonic UD-814 calcium sulfate dosimeters were used, with a total of six elements.in place at each monitoring location. Each pair of dosimeters is sealed in a plastic bag, which is in turn housed in a plastic-screened container. This container is attached to an object such as a tree, fence or utility pole. A total of 38 stations, with a quarterly readout schedule, are required by [ ODCM Table 2.3. The plant staff posts and retrieves all TLDs, as well as processing them on their Panasonic UD-702E TLD reader. 1 i F 1 i i a 3 !.r -11 h ? .r-

s. 6 y; TAALE 4.1 Radletogical Efwirersentet MaritterIns Program (en rosystred dartre 1992 by t001 Tatde 2.3) Cottoction. Analyele Esposure Pethway d'" ' Wusber of Routine Anotysle Anotysle-sample Medle semple Locatione semptins Cottection Type Fresysency Mode Fregnney

1. Of rect Radletion (TLDs) '

Totet Locatione: 38 Continuous cuarterly Gasme dose Each TLD

2. Airborne (Particulates Total Locationes 5 Continuous Weekly Porticutete semple:

and Radiolodine) Grose Sete Each sample Gamum footople Guerterly Compoelte (by location) Radiolodine Centster: 1 131 Each sample

3. Waterborne

e. Estuary Weter Total Locottones 2 Cospoelte Monthly Gamme Isotopic Each semple (ellquot every Trittum (M-3)

Ouerterly Ceepoelte 2 hours)

b. Gremd Water Total Locations: 2 Grob ouarterly Gasen footopic Each temple Tritium (M-3)

Each sample

c. Shoreline Sedlasnt Total Locetione 2 Grab soolonnuelty Gemme Isotopte Each sample Groundmeter semples shett be taken ideen thle source le tapped for drtr*Ing or irrigetlen purposee in erees idwre hydroutte gradient or recherge properttee are suitable for contamination.

1. -

L ' I: [; i TASLE 4.1 (cont f rused) l' medloteeleet Emirernmentet stanitertg Program -(en togstred darig 1992 by esos Tadde 2.3) ( . Exposure Pathuey Collection Analyste d Nominst Ntaber of Routine Nominst Anotysle Analysts 8*'PI' M I' Sample Lccettone Sempting Cottection Type Frecpsency Mode Frequency

4. Ingeotton

e. Mitk Total Locations: 3 Grab Monthly Gesume lootopic Each semple I 131 Each sample b.

Floh and Irwertebrates Total Locations: 2 Grab Seelannuelty Gesume Isotopic on Eoch sample (coussereietty or (or seesonet if-edtbte port 1one recreationetty appropriate) leportant spectee)

c. Food Products (3 types Total Locatione 3 Grab nonthly when Gemme footopic Each sagte of breed teef evellebte I-131 Each semple vegetetlan)**-

Food Pro &ct sempting performed only If milk sempting to not done. t . ~-

4

~ o 3 TABLE 4.2 l i Radiological Environmental Monitoring locations (non-TLD) in 1992 Maine Yankee Nuclear Power station 1 Distance. From Direction i Exposure Station Plant From-Pathway Code Station Descriotion Z2ng Tkm) Plant

1. Airborne

a. Air Part.

AP/CF-11 Montsweag Brook 1 2.7 NW & Charcoal AP/CF-13 Bailey Farm (ESL) 1 0.6 NE Filters AP/CF-14 Mason Steam Station 1 4.8 NNE i AP/CF-16 Westport Firehouse 1 1.8 S AP/CF-29 Dresden Substation 2 19.8 N-

b. Mixed Crasses TG-11 Bailey Farm (ESL) 1 0.6

.NE } TG-02 Tracks & Ferry Road 1 1.2 N i '[

2. Waterborne

a. Surface WE-12 Plant Outfall 1

0.3 SV Water (Composite Sample) t VE-20 Kennebec River 2 9.8 SW (Grab Sample) i

b. Ground WG-13 Bailey Farm (ESL) 1 0.6 NE i

Water WG-24 Morse Well 2 9.8 W

c. Sediment SE-16 Old Outfall Area 1

0.4 SW SE-18 Foxbird Island 1 0.7 s

d. Marine Algae AL-11 Long Ledge Area 1

1.1 S AL-24 Sheepscot River 2 11.2 s-

3. Ingestion

a. Milk TM-15 Mitman Farm 1

5.8' s TM-16 Baker Fars 1 7.2 W TM-17 14eman Farm .1-7.9 SW TM-18 Chewonki Foundation 1 1.2 Wsv TM-25 Hanson Farm. 2 16.0 W B ? 1 t i i M1 .o

,m- ? . J r TABLE 4.2 i (continued) 'j Radiological Environmental Monitoring 14 cations (non-TLD) in 1992 Maine Yankee Nuclear Power Station - j Distance. From-Direction Exposure Station Plant Froa l Pathway Code Station Descrintion Z2Di (km) ~ Plant

3. Ingestion,.(continued) f

b. Fish &

FH-11 Long Ledge Area 1 1.1 .S l' . Invertebrates MU-11 CA-11 i HA-11 l FH-24 Sheepscot River 2 11.2 S MU-24 CA-24 ~' HA-24 i i

1 - Indicator Stations; 2 - Control Stations.

9' j M l I TABLE 4.3 Radiological Environmental Monitoring Locations (TLD) in 1992 Maine Yankee Nuclear Power Station-i r Distance Station From Plant Direction Code Station Descrintion Z2Dg (km) From Plant [ TL-1 Old Ferry Rd. I-1.0 N TL-2 Old Ferry Rd. I -0.8 NNE TL-3 Bailey House (ESL) I 0.6 NE TL-4 Westport Island, Rt. 144 1 1.2-ENE TL-5 MY Information Center 1 0.2 E TL-6 Rt. 144 & Greenleaf Rd. 1 0.9 E i TL-7 Westport Island, Rt. 144 1 0.8 ESE TL-8 MY Screenhouse 1 0.2 SE TL-9 Westport Island, Rt. 144 I 0.9 SE TL-10 Bailey Point I 0.4 SSE TL-11 Mason Station 0 4.8 NNE TL-12 Vestport Firehouse I 1.8 S 1 TL-13 Foxbird Island I 0.4 SSW TL-14 Eaton Farm I 0.8 SW TL-15 Eaton Farm I 0.8 WSW e TL-16 Eaton Farm 1 0.7 W TL-17 Eaton Farm Rd. I 0.6 UNW TL-18 Eaton Fara Rd. I 0.8 NW TL-19 Eaton Farm Rd. I 1.0 NNW TL-20 Bradford Rd.. Viscasset 0 6.5 N TL-21 Federal St., Wiscasset 0 7.2 NNE TL-22 Cochran Rd., Edgecomb 0 8.3 NE TL-23 Middle Rd., Edgecomb 0 7.0 ENE TL-24 River Rd., Edgecomb 0 .7.8 E-TL-25 River Rd. & Rt. 27 0 -7.5 ESE TL-26 Rt. 27 & Boothbay RR Museum 0 7.8 SE l TL-27 Barters Island O 7.0 SSE TL-28 Westport Island, Rt. 144 & O 7.7 S ? East Shore Rd. TL Harrison's Trailer 0 6.3 SSW .TL-30 14eman Farm, Woolwich 0 7.6-SW-i N 7 4 .e

m 1 "d-TABLE 4.3 (continued) , Radiological Environmental Monitoring Locations (TLD)~in 1992 Maine Yankee Nuclear Power. Station i i i Distance Station From Plant' Direction Code Station Descriotion Zgng* (km) From Plant ?; TL-31 Barley Neck Rd.. 0 6.7 WSW TL-32 Baker Farm, Woolwich 0 7.2 W TL-33 Rt. 127, Woolwich 0 7.3 WNW> TL-34 Rt. 127, Woolwich o 7.9 NW ' TL-35 Rt. 127, Dresden O 9.1 NNW TL-36 Boothbay Harbor Fire Station 2 11.4 SSE TL-37 Bath Fire Station 2 10.4 WSW l TL-38 Dresden Substation 2 19.8 N ?

I - Inner Ring TLD; O - Outer Ring TLD; 2 - Control TLD.

i '3 6 f i 2 -

q L-M r TABLE 4.4 Environmental'Iower Limit of Detection (LLD) Sensitivity Requiremente Airborne' Fleh &

Particulates Inverte-Food-Sediment Analysis Water or Games brates Milk Product. (pci/kg (PCl/1) (Pci/m3) (pci/kg) (pci/1) (pci/kg) ~ -dry) Grose-Beta 4 0.01 H-3 2000

Mn-54 15 130 Fe-59 30 260 co-58,60 15 130 En-65 30 260 Er-Nb-95 15 I-131 1 **

0.07 1 60 'co-134 15 0.05 130 15 60 150 co-137 -18 0.06 150 18 80 180 Ba-La-140 15 15 If no drinking water pathway exists, a value of 3000 pci/1 may be used.

- If no'. drinking water existe, a value of 15 pci/1 may be used.

(Several other-explanatory. footnotes are given in Tech. Spec.. Table 4.8-2. 4 k _ O l., 1 TABLE'4.5 Reporting Levels for Radioactivity Concentrations In Environeontal Samsples. Airborne Fish & Particulates Inverte-Food Analysis-Water or Cases brates Milk . Product (PC1/1) (pC1/m3) (pci/kg) (pci/1) (pci/kg) H-3 20,000

Mn-54 1000 30,000 Fe-59 400 10,000

.co-58 1000 30,000 Co-60. 300 10,000 E n 300 20,000 Er-Nb-95 400 ** I-131 ~2 *** 0.9 3 100 Co-134 .30 10 1000-60 1000 Co-137 50 20 2000 70 2000 Ba-La-140 -200 ** 300 .If no drinking water pathway exists,-a value of 30,000 pCi/i may be used.

- Parent only. _

If no drinking. water exists,:a value of 20 pCL/1 may be used. b' . n

N To-11 / WG-13 I I 4 $ AP/CF-13 i ,Il k. 1117tE oar.!stA1.'r IhTAKE DISCHARGE FORESAY "WE.12 5 BAltEY PT. s O f f SE-16 @. @ SE 18 p .':) 3 ih WESPocr istA w g Mu-11 AL 11 ~ DISCHARGE AREA U 100 200 300 (DIFFUSER) RA-11 TH-il@ CA-11 Figure 4.1 Environmental Radiological Sampling Locations k'ithin 1 Kilometer of Maine Yankee - 3 ~

f . A. : o 5 I 1 ./. i,,.. 5 <stM nns i W15CA55tT'e, .n-AP/CF-Is J @ AP/CF-Il 1 set in.Aactnen a r:ccat *.1 f .. TG-02 WEQUASSET LAKE 0 (

f g ;;

- y' * .'s w-24 run g TM.13 ~ '. - '- . f[ . toctcons P .g a

['

t ' Uf-16 h. -(j~~. l-f

p

~ ' & AP/CF-16 l ..~ ^ EATH e 4 WOOLWICH ... [$.p,* wE 20 i l} .s .-[., TM-17.* 2? **: ~ ~ f ', y ~' n TH 15 6 l j Y .1 A i i c d$ 194 4: FW24) g t q.. g,'.

)

At. 24 Q ~ (: i . l i MU 24 ,j j g .g HA-24 4 BOOTH 8AY HARBOR 'Y ~ ff' .CA 24 g , e,,~~ ,1 t' y 1. .s .~~ l lc: ' ' - 'f ):. crotcti s u istA W *. .f f j. Figure 4.2 Environmental Radiological Sampling' Locations Within 12 Kilometers of Maine Yankee, a

^ j y.oi,4. 9.... l 0 ,'.3 .u l l .4 ). RICHMOND..

[ ORE $ DEN

,lg *. j. SEE ENtARGE.9ENT ZW TZGGJtE 4.2

NEWCASTL.E,

, p. 3

l. l E$ f.

h' c'. DAMAR 15 COTTA .j 3 '- BOWD0!NHAM 9 . I' W15CASSET *- 'l-l I ?, ~+- 1 e p. EDGECOMB. ....,six. y i

4.. l Md BRUNSWICK 4 -

.f ' l '( ~

Q g. (i.

\\

k

~ - [- ~ l <_ _p

[.;. r;,

w ..y o g N )j ll t h ATLAur!C OCEAw .j t o to

o i

KILOMCTERS

'l l

Figure 4.3 Environmental Radiological Sampling Locations j Outside 12 Kilometers of Maine Yankee j 1 ] .r

TL-19 ) I@ TL-3 TL-la @ q to TL-17 @f [TL-S LITTLE CAR IS13D 9 c is. TAKE nGE FOREBAY d.- @ TL-16 TL-13 .g -30 h $ TL-15 LEY 57. &p TL-1 @ g @ f. TL-14 @ TL-9 s+ 4' y a s

-i WE5 U 1SlwD y

6 0 100 200 20 r DISCKARGE AREA (DirruSER) SSr S h Figure 4.4 Direct Radiation Monitoring Locations Within 1 Kilometer of Maine Yankee r

~ '. b N g g,. 5 o 2 I E I LI4tETERS L @ TL-35 ,h . i. @[ [. TL-21 ,/ rL-10 @ISCA SET n.22 - l W e: @ TL-34 y e e TL-Il @ TL-23 I: g j

n. 33 @ ser exwcrxin zu riant * +

- 5. - \\ "Y [ l n. TL-2 s WEQUASSET LAKE ,., [ # g., W .~,- 'r' TL $f g e EDGECOMB tl_ _ ; ! n-24 ~ ~/ ~ [ ~ jl-n.32 @ b; y J' p ~ e i @ TL-31. g l'

f

, 4 ^ TL-3.. _ f.. ~ (; n 25 g EATH,! 4 WOOL CH p p' [ l 9 m.;

f g

5 k [ - 'g I ' L-26 @ TL 30 ~ I' ~~ e n.29 ' E yj E:h.

a R.

n-27 g I :

c q

.*.h, [ -28 '\\' '. { ~ c v; ~ f 8 BOOTHBAT HAABOR - l^ ~, r-5 "{ . eg n-36 4 5 j.: GEORCETOWM 1SL wo *

cfc,

S ;y S. '.

\\ S Figure 4.5 Direct Radiation Monitoring Locations Within 12 Kilometers of Maine Yankee g,e 'N[- c.annantR e . ut.mxit en g g$TL-38 ] M. [b-R1CHMOND g\\ .

DRE50 N

^ y k f SEE ENLARGEMENT IN TZGURE 4.5 1 _ g: 3 o: .o AMARISCOTTA : .c ,52 n.. s \\ y-y, B0VD0thHAM * ,b I s /EDGECO N.E'

g..

o BR STOL. W 't .3 .,4,: ,/ n. p. [f, 3 ~

f I' -

BRU ' ' s. ll.}jl.'lxR ...h. / [ h. :' 'Y!' _ 8 m tt

'L.

Y L. ~ .. G' Nl I '

10 Mues -

N Af.: fc b ATLAWTIC CEAu SStr l 0 to 2e KILOMETERS N S s Figure 4.6 Direct Radiation Monitoring Locations Outside 12 Kilometers of Maine Yankee -25 i 1 -- ~ C- ---

-t ~5. 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 ~ 1 presented in a format similar to that prescribed in the NRC's Radiolo8 cal Assessment Branch Technical Position on Environmental Monitoring (Reference 1). The results are ordered by sample media type and then by_radionuclide. The units for each media type are also given. The left-most column contains the radionuclide of interest, the total number of analyses for that radionuclide in 1992, and the number of t measurements which exceeded the Reporting Levels found in Table '2.5 of the ODCM. 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 ODCM Table 2.4. 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 L1D. On rare occasions the required LLD is not met. This is usually due to malfunctions in sampling equipment, which results in low sample volume. Such cases are addressed in Section 6.2. For each radionuclide and media type, the remaining three columns 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 an Inner Ring and an Outer Ring (for emergency response), as well as into a Control or. Zone 2 category. In each of these columns, for each radionuclide, the following statistical values 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: -26 r r

~ n measurements. For. example,-(4/20).would indicate.that four of the twenty samples _ collected in 1992, for:that sample type and that; a radionuclide,' contained' detectable radioactivity. 1 A sample is considered to yield a=" detectable measurement"Lwhen the l concentration exceeds three times its associated-standard deviation. The standard deviation on each measurement represents only the random a uncertainty associated with the radioactive decay process-(counting-i statistics), and not the propagation'of all possible uncertainties in'the analytical procedure. l 1 The radionuclides reported in this section represent'those that: ;l) had an I LLD requirement in Table 2.4 of the ODCM, or a Reporting Level listed in; Table 2.5, or 2) had a positive measurement of radioactivity', whetherLit was naturally-occurring or man-made; or 3) were of specific interest for l any other reason. The radionuclides that were routinely analyzed and j reported by the imboratory (in a gamma spectroscopy analysis) were: AcTh - j 228, Ag-110m, Ba-140, Be-7,;Ce-141, Ce-144, Co-57,' Co-58,.Co-60,LCr-51, Cs-j 134, Cs-137, Fe-59, I-131,.I-133, K-40, Mn-54, Mo-99, Np-239 Ru-103 Ru-106, Sb-124, Se-75, TeI-132, Zn-65 and Zr-95. In no case did a o radionuclide not shown in Table 5.1 appear as a " detectable measurement" - during 1992. i ~ Data.from direct radiation measurements made by TLDs are provided.in Table 5.2'in.a format essentia11y'the same as above. The' complete. listing.of: l quarterly TLD data is provided in Table 5.3. P 'n .j 'f i i i 1 N

TAELE 5.1 ENv!ROWNENTAL RAD 10 LOGICAL PROGRAM supewtf MAINE YANKEE NUCLEAR POWER STATION, WISCASSET, ME (JANUARY - DECEMBER 1992) INDICATOR STATIONS ETATION WITN NIGNEsf IEAN CONTROL STATIONS e......... eeeeee eeeeeeeeeeeeeeeeeeeeeeeee RAD 10NUCLIDES* 8EAN 8EAll IEAN (NO. ANALYSES) REQUITED RANGE STA. RANGE RANGE (NON-ROUTINE)** LLD No. DETECTED *** No. No. DETECTED *** No. DETECTED ** 'i IEDItat: AIR PARTIQJLATES (AP) tallTS: pCl/cahic meter Gross (265) .01 ( 1.8 0.0)E 2 16 ( 1.8 0.1)E -2 ( 1.8 s 0.1)E 2-Beta ( 0) ( 6.3 - 39.1)E -3 ( 7.7 - 29.8)E -3 ( 9.4 - 34.1)E 3 (212/212) ( 53/ 53) ( 53/ 53) BE 7 ( 20) ( 7.6 s 0.5)E 2 16 ( 8.2 1.2)E -2 ( 7.8 0.7)E -2 ( 0) ( 4.3 - 10.0)E -2 ( 4.7 - 10.0)E -2 ( 6.1 - 8.9)E'-2 ( 16/ 16) ( 4/ 4) ( 4/ 4) CS-134 ( 20) .05 ( -1.7 0.4)E 4 29 ( -7.3 a 10.7)E -5 ( -7.3 s 10.7)E -5 ( 0) ( -4.7 - 1.5)E 4 ( -2.5 - 2.2)E 4 ( 2.5 - 2.2)E 4 ( 0/ 16) ( 0/ 4) ( 0/ 4) CS 137 ( 20) .06 ( -1.9 : 4.4)E 5 14 ( 8.9 6.8)E -5 ( 6.0 8.8)E -5 ( 0) ( -3.2 - 2.2)E -4 ( 7.7 - 22.1)E -5 ( -2.5 - 1.8)E -4 ( 0/ 16) ( 0/ 4) ( 0/ 4) 8EDILDt: CNARC04L CARTRIDES (CF) talITS: pCl/cahic meter I-131 (265) .07 ( -5.5 s 5.8)E -4 16 ( 1.6 s 0.9)E 3 ( 1.4 s 0.9)E -3 ( 0) ( -2.6 - 2.9)E -2 ( -1.4 - 1.4)E 2-( -1.0 - 1.9)E 2 ( 0/212) ( 0/ 53) ( 0/ 53) SEDIL8I: MIXED GRASSES (TG) latITS: pCf/kg BE 7 ( 4) ( 2.5 0.4)E 3 02 ( 3.1 a 0.0)E 3 NO DATA ( 0) ( 1.8 - 3.4)E 3 ( 4/ 4) ( 1/ 1) E 40 ( 4) ( 5.8 s 0.7)E 3 11 ( 6.0 1.0)E 3 NO DATA ( 0) ( 4.2 - 7.6)E 3 ( 4.2 - 7.6)E 3 ( 4/ 4) ( 3/ 3) I-131 ( 4) ( 2.1 2.4)E 2 11 ( 3.1 s 3.1)E 2 NO DATA ( 0) ( 8.7 - 92.4)E 1 ( 2.5 - 92.4)E 1 ( 0/ 4) ( C/ 3) r NOTE: Footnotes may be found at the end of Table 5.1. P h

TAALE 5,1 ENVIRONMENTAL RADIOLOGICAL PROGRAN SupeuRT MAlkE TANKEE NUCLEAR POER STATION, WISCASSET, ME (JANUART - DECEMBER 1992) INDICATOR STATIONS STAfl0N WITN MIGNE$T BEAN CONTROL STATIONS eeeeeeeeee=*ee**ee

- - - - eeee**ee m m ee m ee m eeeeee m ee RADIC3EACLIDES*

MEAN 8EAN SEAN l (No. AEALTSEE) REQUIRED RANGE STA. RANGE RANGE (NON ROUTINE)** LLD No. DETECTED *** No. No. DETECTED

No. DETECTED **

SEDIL9t: NIXED ERASSEE (TC), cant. LWITS: pCf/kg i CS-134 ( 4) ( 8.8 6.3)E O 11 ( -8.2 8.9)E 0 No DATA ( 0) ( 2.3 - 0.7)E 1 ( 2.3 - 0.7)E 1 ( 0/ 4) ( 0/ 3) I C5 137 ( 4) ( 1.4 a 0.9)E 1 11 ( 1.9 a 1.0)E 1 No DATA ( 0) ( -3.8 - 355.0)E -1 ( 8.7 - 355.0)E -1 ( 0/ 4) ( 0/ 3) IEDilst: ESTUART WLTER (if) LaflTS: pCl/kg K-40 ( 24) ( 2.3 a 0.1)E 2 12 ( 2.3 s 0.1)E 2 ( 2.8 0.6)E 1 ( 0) ( 1.7 - 2.6)E 2 ( 1.7 - 2.6)E 2 ( -9.8 - 66.9)E 0 ( 12/ 12) ( 12/ 12) ( 4/ 12) INi-54 ( 24) 15. ( 9.1 a 12.2)E -2 12 ( 9.1 a 12.2)E 2 ( -1.8

2.5)E -1 t

( 0) ( -6.9 - 6.3)E -1 (. -6.9 - 6.3)E -1 ( -1.5 - 1.5)E D ( 0/ 12) ( 0/ 12) ( 0/ 12) Co-58 ( 24) 15. ( 2.7 a 2.8)E -1 12 ( 2.7 s 2.8)E -1 ( -1.8 a 27.4)E -2 ( 0) ( -1.0 - 2.3)E O ( -1.0 - 2.3)E O ( -2.2 - 1.6)E O ( 0/ 12) ( 0/ 12) ( 0/ 12) i FE-59 ( 24) 30. ( -3.4 a 3.1)E -1 20 ( 9.1 a 3.8)E -1 ( 9.1 2 3.8)E -1 ( 0) ( -1.7 - 1.9)E 0 ( 7.0 - 26.7)E 1 ( 7.0 - 26.7)E -1 ( 0/ 12) ( 0/ 12) ( 0/ 12) i Co-60 ( 24) 15. ( -4.3 a 1.T)E -1 12 ( -4.3 4 1.7)E -1 ( -1.2 0.3)E O ( 0) ( -1.3 - 0.8)E 0 ( 1.3 - 0.8)E D ( -4.5 - -0.2)E D ( 0/ 12) ( 0/ 12) ( C/ 12) r ZN-65 ( 24) 30. ( 7.9 7.5)E -1 12 ( 7.9 a 7.5)E -1 ( 1.9 4.5)E -1 ( 0) ( -4.4 - 4.9)E 0 ( -4.4 - 4.9)E O ( -3.3 - 2.3)E D ( C/ 12) ( 0/ 12) ( 0/ 12) ZR 95 ( 24) 15. ( 1.4 s 4.9)E -1 12 ( 1.4 a 4.9)E -1 ( -1.9 a 2.8)E -1 ( 0) ( -1.5 - 4.6)E O ( -1.5 - 4.6)E O ( -1.4 - 1.4)E O ( 0/ 12) ( 0/ 12) ( 0/ 12) i t NOTE: Footnotes any be found at the end of Table 5.1., e

-~ TABLE 501 ENVIRONMENTAL RADIOLOGICAL PROGRAN

SUMMARY

[ MAINE TANKEE NUCLEAR POWER STATION, WISCASSET,stE (JANUART - DECE8SER 1992) IISICAfok STATIONS STATION WITN NIGNEST M AN CONTROL STATIONS i eeeeeeee. I RADIGIRJCLIDES* EAN BEAN EAN (NO. ANALYSES) REQUIRED RANGE STA. RANGE RANGE (a0N-talTIME)** LLO NO. DETECTED *** ho. No. DETECTED

NO. DETECTED **

6 I f e ltst: ESTUARY WTElt OE), cent. talITS: pCf/kg I-131 ( 24) 15. ( 9.2 a 5.2)E -1 12 ( 9.2 a 5.2)E -1 ( 1.3 a 1.3)E 0 ( 0) ( -3.1 - 3.4)E O ( 3.1 - 3.4)E O ( 9.7 - 4.7)E O 1 ( 0/ 12) ( 0/ 12) ( 0/ 12) CS-134 ( 24) 15. -( -7.5 s 2.7)E -1 20 ( -5.8 a 2.4)E -1 ( -5.8 s 2.4)E -1 ( 0) ( 1.8 - 1.3)E D ( -1.7 - 0.9)E 0 ( -1.7 - 0.9)E D ( 0/ 12) ( 0/ 12) ( 0/ 12) CS-137 ( 24) 18. ( -3,0 s 2.6)E -1 20 ( 3.1 1.7)E 1 ( 3.1 : 1.7)E -1 ( 0) ( -1.5 - 2.1)E D ( 9.6 - 11.1)E 1 ( -9.6 - 11.1)E -1 ( 0/ 12) ( 0/ 12) ( 0/ 12) SA-140 ( 24) 15. ( -1.0 a 5.3)E -1 12 ( -1.0 a 5.3)E -1 ( -2.0 a 5.7)E -1 ( 0) ( -2.4 - 3.5)E 0 ( -2.4 - 3.5)E O ( -3.3 - 4.4)E O ( 0/ 12) ( 0/ 12) ( 0/ 12) N.3 ( 8) 3000. ( 4.6 a 1.0)E 2 12 ( 4.6 a 1.0)E 2 ( -4.1 a 4.3)E 1 ( 0) ( 2.8 - 7.2)E 2 ( 2.8 - 7.2)E 2 ( 1.2 - 0.7)E 2 ( 1/ 4) ( 1/ 4) ( 0/ 4) 8 EDIT 9t: Gtame MTER (WC) INIITS: pCf/kg Gross ( 6) ( 4.4 a 2.0)E ) 56 ( 1.4 a 0.1)E 2 ho DATA Beta ( 0) ( 5.5 - 136.0)E D ( 6/ 6) ( 1/ 1) K-40 ( 24) ( 4.4 s 1.7)E 1 99 ( 2.6 s 0.2)E 2 ( 3.1 a 6.7)E O ( 0) ( -8.8 - 264.0)E o ( 1.5 - 1.6)E 1 ( 3/ 20) ( 1/ 1) ( 0/ 4) pen-54 ( 24) ( 5.6 a 1.9)E -1 62 ( 2.1 a 1.2)E 0 ( -6.6 s 3.6)E -1 ( 0) ( -5.8 - 21.1)E -1 ( 1.5 - 0.0)E ' O ( 0/ 20) ( 0/ 1) ( 0/ 4) CD-58 ( 24) ( -1.5 a 2.1)E -1 54 ( 8.5 a 3.9)E -1 ( -8.6 a 4.5)E -1 ( 0) ( -2.1 - 1.3)E D ( (.6 - 12.4)E -1 ( -2.1 - 0.0)E D ( 0/ 20) ( 0/ 2) ( 0/ 4) NOTE: Footnotes any be found at the end of Table 5.1. - f?

if TABLE 5.1 ENVIRONENTAL RADIOLOGICAL PROGRAM SLSSIART EINE TANKEE BEJCLEAR POKR STATION, WISCASSET, NE (JANUART - DECEMBER 1992)- INDICATOR STATIONS STATION WITN NIGNE$T E AN CONTROL STATIONS .e RAD 10NUCLIDES* EAN EAN BEAN (No. ANALYSES) REQUI8ED RANGE STA. RANGE RANGE (NON RtNTIE}** LLD No. DE1ECTED*** No. 110. DETECTED *** No. DETECTED ** Eplust: ea0Las nsLTER (WG), cent. IsilTS: pCI/kg FE 59 ( 24) ( 6.9 5.4)E 1 57 ( 4.3 s 2.5)E O ( -6.7 s 7.2)E -1 ( 0) ( 3.6 - 5.4)E D ( -2.4 - 1.1)E O' ( 0/ 20) ( 0/ 1) ( 0/ 4) Co-60 ( 24) ( +4.0 s 2.3)E -1 58 ( 1.4 a 1.5)E o ( 6.5 : ~ 7.9)E 1 ( 0) ( -2.2 - 1.4)E D ( -2.5 - 1.4)E O ( C/ 20) ( 0/ 1) ( 0/ 4) ZN-65 ( 24) ( 6.5 5.4)E 1 61 ( 7.3

3.6)E O

( 1.6 a 1.1)E 0 ( 0) ( 3.2 - 7.3)E O ( -8.5 - 43.8)E 1 ( 0/ 20) ( 0/ 1) ( 0/ 4) 2R-95 ( 24) ( 6.9 s 41.3)E -2 56 ( 2.7 a 2.2)E O ( -1.0 s 1.0)E O ( 0) ( -3.0 - 3.7)E O ( -3.1 - 0.9)E O ( 0/ 20) ( 0/ 1) ( 0/ 4) 1-131 ( 24) ( -7.6 2 4.7)E -1 56 ( 2.2 a 3.0)E O ( -1.3 a 1.3)E O ( 0) ( -4.4 - 4.6)E D ( -4.7 - 1.6)E 0 ( 0/ 20) ( 0/ 1) ( 0/ 4) Cs.134 ( 24) ( 1.2 s 3.5)E 1 57 ( 2.3 a 1.4)E O ( 6.3 s 36.2)E -2 ( 0) ( -2.2 - 4.4)E O ( -1.0 - 0.7)E O ( 0/ 20) ( 0/ 1) ( 0/ 4) Cs 137 ( 24) ( -6.5 s 3.1)E -1 55 ( 1.3 a 0.5)E 0 ( 2.0 s 5.4)E -1 ( 0) ( -2.9 - 1.8)E D ( 8.5 - 17.8)E -1 ( -1.7 - 0.8)E O ( 0/ 20) ( 0/ 2) ( 0/ 4) SA 140 ( 24) ( 9.8 a 3.8)E -1 99 ( 1.6 a 2.4)E O ( 1.1 a 11.0)E -1 ( 0) ( -3.5 -' 2.2)E O ( 2.1 - 2.7)E O ( 0/ 20) ( 0/ 1) ( 0/ 4) N-3 ( 24) ( 2.9 a 1.6)E 2 59 ( 2.6 s 0.2)E 3 ( -9.7 s 7.8)E 1 ( 0) ( 3.8 - 25.6)E 2 ( -3.3 - -0.1)E. 2 ( 5/ 20) ( 1/ 1) ( 0/ 4)- NOTE: Footretes may be found at the end of Table $.1. 31-cr

TABLE 501 ENyleCapIENTAL RADIOLOGICAL P90GRAN SU M ARY MA!NE TANKEE NUCLEAR POWER STATION, WI$CAS$ET, ME (JANUARY. DECEMBER 1992) INDICATot STATION 5 STATION WITN WIGNEST 8EAN CONTROL STATIONS n eeeeeeeeeeeeeeee oeeeeeeeeeeeeeeeeeeeeeeee

= :::::eeeeee RADIGILICLIDES*

LEAN LEAN BEAN (No. ANALYSES) REQUIRED RANGE STA. RANGE . RANGE (NON-ROUTINE)** LtD No. DETECTED *" No. No. DETECTED *** NO. DETECTED" IEDItst: SEDINENT (SE) WITS: pCf/kg ( & y) BE-7 ( 12) ( 4.2 s 7.3)E 1 16 ( 8.4 a 10.3)E 1 110 DATA ( 0) ( 3.3 4.5)E 2 ( -3.3 3.3)E 2 ( 0/ 12) ( 0/ 6) K-40 ( 12) ( 1.9 s 0 0)E 4 18 ( 1.9 s 0.1)E 4 NO DATA ( 0) ( 1.0 - 2.2)E 4 ( 1.0 2.2)E 4 ( 12/ 12) ( 6/ 6) 00-58 ( 12) ( 1.1 a 6.6)E O 18 ( 1.2 a 0.3)E 1 NO DATA ( 0) ( 4.3 2.2)E 1 ( 3.7 22.5)E O ( 0/ 12) ( C/ 6) CD-60 ( 12) ( 2.6 s 0.8)E 1 18 ( 4.0 a 0.8)E 1 NO DATA -( 0) ( -3.9 - 6.6)E 1 ( 1.2 6.6)E 1 ( 0/ 12) ( 0/ 6) t C$.134 ( 12) 150. ( 1.2 2 5.3)E D 18 ( 3.9 s 6.5)E O NO DATA ( 0) ( 3.0 2.1)E 1 ( 1.8 2.1)E 1 ( 0/ 12) ( 0/ 6) [ CS 137 ( 12) 180. ( 1.9 s 0.3)E 2 18 ( 2.5 s 0.3)E 2 No DATA ( 0) ( 2.7 32.4)E 1 ( 1.2 - 3.2)E 2 ( 10/ 12) ( 6/ 6) ACTN228 ( 12) ( 8.2 s 0.3)E 2 18 ( 8.3 s 0.5)E 2 No DATA ( 0) ( 6.9 10.2)E 2 (. 6.9 10.2)E 2 ( 12/ 12) ( 6/ 6) I n itst: MARINE ALGAE CAL) WITS: pcl/kg BE-7 ( 6) ( 3.0 a 4.3)E 1 24 ( 1.4 a 1.5)E 2 ( 1.4 : ~ 1.5)E 2 ( 0) ( -8.5 - 12.0)E 1 ( 1.9 - 29.0)E 1 ( 1.9 29.0)E 1 ( 0/ 4) ( 1/ 2)' ( 1/ 2) K 40 ( 6) ( 5.2 a 0.4)E 3 24 ( 5.7 s 0.0)E 3 ( 5.7 a 0.0)E 3 ( 0) ( 4.0 6.0)E 3 ( 5.7 5.7)E 3 ( 5.7 5.7)E~3-( 4/ 4) (. 2/ 2) ( 2/ 2) NOTE: Footnotes may be found at the ord of Table 5.1. 32-1

l TABLE 5.1 l i ENVIROMENTAL RADIOLOGICAL PROGRAM SlagtARY MAINE YANKEE NUCLEAR P0hER STATION, W!SCASSET, NE (JANuntT DECDSER 1992) ItCICATOR STATIONS STATION WITN NIGNEST MEAN CONTROL STATIONS j e....... eeeeeeee eeeeeeeeeeeeeeeeeeeeeeeee RADIGIRACLIDES* MEAN 8EAN aEAN i (No. ANALYSES) REQUIRED R.ANCE STA. RANGE RANGE (NON-RQUTINE)" LLD No. DETECTED *** No. No. DETECTED"* No. DETECTED ** 1 s e !Last MARINE ALCAE (AL), cent. talITS: pCl/kg [ mu-54 ( 6) ( 3.9 a 1.0)E O 11 ( 3.9 s 1.0)E O ( 3.5 s 2.4)E 0 ( 0) ( 2.4 - 6.9)E D ( 2.4 - 6.9)E O ( 1.1 - 5.9)E. O ( 0/ 4) ( 0/ 4) ( 0/ 2) co-58 ( 6) ( 2.0 s 1.5)E D 11 ( 2.0 e ' 1.5)E O ( 5.3 s 84.8)E -1 ( 0) ( -9.4 - 62.6)E -1 ( 9.4 - 62.6)E -1 ( -7.9 - 9.0)E O' I ( 0/ 4) ( 0/ 4) ( 0/ 2) FE 59 ( 6) ( 6.1 a 24.6)E -1 11 ( 6.1 s 24.6)E -1 ( -1.8 s 0.3)E 1 ( 0) ( 2.6 - 7.9)E 0 ( -2.6 - 7.9)E O ( -2.1 - 1.5)E 1 ( 0/ 4) ( 0/ 4) ( 0/ 2) Co-60 ( 6) ( 4.2 a 1.5)E O 24 ( 8.1 e 2.1)E O ( 8.1 s - 2.1)E O ( 0) ( 3.2 - 73.9)E -1 ( 5.9 - 10.2)E O (- 5.9 - 10.2)E O ( 0/ 4) ( 0/ 2) ( 0/ 2) i ZN-65 ( 6) ( -7.2 a 68.5)E -1 24 ( 7.3 s 13.7)E O ( 7.3 s 13.7)E O ( 0) ( 1.9 - 1.3)E 1 ( -6.4 - 21.0)E O ( -6.4 - 21.0)E 0 ( 0/ 4) ( 0/ 2) ( 0/ 2) AC 110nt 6) ( 1.6 s 0.5)E 1 11 ( 1.6 s 0.5)E 1' ( 8.3 a 9.3)E O ( 0) ( 5.2 - 28.1)E O ( 5.2 - ~ 28.1)E 0 ( 1.0 - 17.6)E D ( 3/ 4) ( 3/ 4) ( 0/ 2) ss 124 ( 6) ( -1.7 s 3.2)E O 11 ( -1.7 a 3.2)E o ( -9.0 a 8.3)E 0 ( 0) ( -7.3 - 5.7)E D ( -7.3 - 5.7)E O ( -1.7 - -0.1)E 1 ( ' 0/ 4) ( 0/ 4) ( 0/ 2) - Cs-134 ( 6) ( -3.0 a 1.7)E O 11 ( -3.0 s 1.7)E 0 (, -4.1 a 1.8)E 0 ( 0) ( -7.3 - 0.0)E D C -7.3 - 0.0)E 0 ( -5.9 - -2.3)E D ( 0/ 4) ( 0/ 4) ( 0/ 2) Cs 137 ( 6) ( -1.4 s 4.1)E O 24 ( 1.9 0.7)E D ( 1.9 0.7)E O ( 0) ( 1.4 - 0.4)E 1 ( 1.2 - 2.6)E O ( 1.2 - 2.6)E D ( 0/ 4) ( 0/ 2) ( 0/ 2) f TM 232 ( 6) ( 4.6 s 0.6)E 1 11 ( 4.6 s 0.6)E 1 ( 3.0 s 0.5)E 1 ( 0) ( 3.8 - 6.2)E 1 ( 3.8 - 6.2)E 1 ( 2.5 - 3.5)E -1 ( 3/ 4) ( 3/ 4) ( 0/ 2) NOTE: Footnotes may be fotrid at the end of Table 5.1. l ' I ra

~. ) TAsti 5.1 ENVIRONENTAL RADIOLOGICAL PROGRAN R30 NARY NAlhE TANGE NUCLEAR POER STATION, WISCAssET, E (JAILIART DECEMER 1992) INDICATOR STATIONS STATIDW WITN NIGNEIT MEAN CONTROL STAfl0NS ......w.......... ..w........w......w. RADIONUCLIDES

EAN -

MAN 8EAN (NO. ANALYSES) REQUIRED - RANGE STA. RANGE RANGE (NON ROUTINE)** LLD No. DETECTED *" NO. NO. DETECTED"' No. DETECTED" IEDILSI: NILK (TM) ImITS: ~ pct /kg l st.89 ( 14) ( 1.1 s 0.4)E O 18 ( -9.1 a 3.3)E -1 ( -1.2 a 0.3)E O ( 0) ( -3.4 - 0.5)E O ( -1.9 - -0.5)E D ( -2.0 - -0.4)E O r' ( 0/ 10) ( 0/ 4) ( 0/ 4) SR-90 ( 14) ( 5.7 a 0.8)E O 16 ( 8.2 a 0.7)E O ( 4.6 s 0.6)E O I ( 0) ( 1.8 - 9.6)E O ( 6.6 - 9.6)E O ( 3.0 - 5.7)E 0 ( 10/ 10) ( 4/ 4) ( 4/ 4) K 40 ( 42) ( 1.2 a 0.1)E 3 15 ( 1.5 s 0.0)E 3 ( 1.3 s 0.0)E 3 ( 0) ( 7.5 - 16.1)E 2 ( 1.5 - 1.6)E 3 ( 1.1 - 1.4)E 3 ( 30/ 30) ( 6/ 6) ( 12/ 12) 1-131 ( 42) 1.0 ( 6.2 a 3.4)E 2 15 ( 1.3 a 1.4)E -1 (' 10.0 a 6.5)E 2 ( 0) ( -1.5 - 8.5)E 1 ( -5.5 - 85.0)E -2 ( 1.4 - 5.7)E -1 ( 0/ 30) ( 0/ 6) ( 0/ 12) e Cs 134 ( 42) 15. ( -1.0 s 0.1)E D 25 ( -5.1 s 3.0)E -1 ( -5.1 a 3.0)E -1 ( 0) ( 2.4 - 0.6)E O ( 1.9 - 1.1)E 0 ( -1.9 - 1.1)E O-( 0/ 30) ( 0/ 12) ( 0/ 12) CE 137 ( 42) 18. ( 7.2 a 0.7)E D 17 ( 1.2 a 0.2)E 1 ( 4.6 s 0.7)E 0 ( 0) ( 1.2 - 14.7)E O ( 1.5 - 9.0)E O ( 25/ 30) ( 1/ 1) (. 7/ 12) SA-140 ( 42) 15. ( -9.1 s 4.5)E -1 16 '( -4.4 7.0)E -1 ( -7.1 a 4.6)E ( 0) ( 5.7 - 4.7)E O ( -5.7 - 2.7)E O ( -4.1 - 1.7)E O ( 0/ 30) ( 0/ 12) ( 0/ 12) IEDltst: S0lt (TS) LalITS: pcl/kg (aset) E 40 ( 4) ( 1.5 s 0.7)E 4 02 ( 1.8 s 0.1)E 4 NO DATA l ( 0) ( 1.0 - 1.9)E 4 ( 1.0 - 1.9)E 4 ( 4/ 4) ( 2/ 2) Co-58. ( 4) ( -1.6 a 9.4)E O 02 -( 3.9 a 10.6)E O ND DATA. ( 0) ( 2.6 - 1.5)E 1 ( -6.7 - 14.5)E 0 ~ ( 0/ 4) ( 0/ 23 -t NOTE: Footnotes may be found at the end of Table 5.1. l f P . 2 r

l r TABLE 5.1 ENVIRONIENTAL RADIOLOGICAL PROGRAM RaguRT stAINE TANKEE NUCLEAR POWER STATION, WISCASSET, IE - l (JANUART. DECD SER 1992) IISICATOR STATIONS ETATION WITN WIGNEST 8EAN CONTt0L BTATIONS .eeeeeeeeeeeeeeeeee eeee m eeeeeeeeeeeeeeeeee

. ::__:::::e RADIONUCLIDES' IEAN IEAN EAN (No. ANALYSTS) REQUIRED RANGE STA.

RANGE RANGE' (NON-ROUTINE)** LLD No. DETECTED *** Wo. No. DETECTED *** 110. DETECTED ** IEDItst: SDIL (TS), cent, tal!TS: pCl/kg (met) Co-60 ( 4) ( 1.7 s 0.4)E 1 02 ( 1.1 a 0.2)E 1 No DATA ( 0) ( -2.7 -0.8)E 1 ( 1.3 -0.8)E 1 ( 0/ 4) ( 0/ 2) ,i Cs-134 ( 4) ( 8.5

4.6)E O 02

( 1.6 s 0.1)E 1 No DATA ( 0) ( 4.0 175.0)E -1 ( 1.5 - 1.7)E 1 ( 0/ 4) ( 0/ 2) Cs 137 ( 4) ( 2.8 a 1.1)E 2 01 ( 4.4 1.4)E 2 No DATA ( 0) ( 9.6 57.6)E 1 ( 3.0 5.8)E 2 ( 4/ 4) ( 2/ 2) ACTN228 ( 4) ( 6.6 s 0.1)E 2 02 ( 6.6 s 0.3)E 2 No DATA i ( 0) ( 6.3 7.0)E 2 ( 6.3 7.0)E 2 ( 4/ 4) ( 2/ 2) IEDILBt: FISE (FN) LABITS: pCl/kg i K-40 ( 4) ( 3.4 0.1)E 3 11 ( 3.4 a 0.1)E 3 ( 3.4 s 0.1)E ' 3 I ( 0) ( 3.3 3.5)E 3 ( 3.3 - 3.5)E 3 ( 3.3 3.5)E 3 ( 2/ 2) ( 2/ 2) ( 2/ 2). i seu-54 ( 4) 130. ( 1.9 s 0.8)E D 24 (- 1.1 2 1.2)E 1 ( 1.1 a 1.2)E 1 ( 0) ( 2.6 1.1)E D ( 4.4 228.0)E.1 ( 4.4 228.0)E.1 ( 0/ 2) ( 0/ 2) .( 0/ 2)* Co-58 ( 4) 130. ( 4.8 a 1.5)E O 11 ( 4.8 a 1.5)E D ( -2.5 a 172.5)E.2-f ( 0) ( 3.3 6.2)E D ( 3.3 6.2)E 0 '( 1.7 - 1.7)E C ( 0/ 2) ( 0/ 2) ( 0/ 2) FE-59 ( 4) 260. ( 3.5 s 17.7)E 0 24 ( 1.5 0.1)E 1 ( 1.5 0.1)E 1 ( 0) ( -1.4 - 2.1)E 1 ( 1.4 1.5)E 1 ( '1.4 1.5)E 1 ( 0/ 2) ( 0/ 2) ( 0/ 2). CD 60 ( 4) 130. ( -5.0 s 6.9)E D 11 ( .$.0 a 6.9)E O' ( 6.3 :, 2.1)E D ( 0) ( 1.2 - 0.~2)E 1 ( 1.2 0.2)E 1 ( -8.4 4.2)E O ( 0/ 2) ( 0/ 2) ( 0/ 2) e r b r NOTES. Footnotes may be fotrd at the end of Table 5.1. 1 35 j .f

i taste 5.1 ENVIRONMENTAL RADIOLOGICAL PROGRAM SLNetARY - MAINE TANKEE NUCLEAR POWER STATION, WISCA55ET, NE (JANUARY - DECEMBER 1992) i INDICATOR STATIONS STATION WITN NIGNEET EAN-CONTROL STAtl0NC . = = =. RADIONUCLIDEB* NEAN 8EAN EAN (No. ANALYSES) REQUIRED RANGE STA. RANGE RANGE (NON-RalTihE)" LLD No. DETECTED *** NO. No. DETECTED *** Wo. DETECTED" IEDILpt: FISE (FN), cant. LEITS: pCl/kg ZN-65 ( 4) 260. ( 2.3 s 1.3)E 1 11 ( 2.3 s 1.3)E 1 ( 8.0 a 247.0)E -1 ( 0) ( 9.7 - 35.9)E D ( 9.7 - 35.9)E D ( -2.4 - 2.5)E 1 ( 0/ 2) ( 0/ 2) ( 0/ 2) AG 110N( 4) ( 2.0 a 6.9)E O 24 ( 3.4 s 3.4)E D C 3.4 s 3.4)E O ( 0) ( -4.9 - 8.9)E O ( 0.0 - 6.8)E O ( 0.0 - 6.8)E O-( 0/ 2) ( 0/ 2) ( 0/ 2) sa-124 ( 4) ( 8.9 s 8.9)E o 24 ( 2.3 s 2.4)E 1 ( 2.3 s 2.4)E 1 ( 0) ( 0.0 - 1.8)E 1 ( 0.0 - 4.7)E 1 ( 0.0 - 4.7)E 1 ( 0/ 2) ( 0/ 2) ( 0/ 2) Cs.134 ( 4) 130. ( -1.0 s 0.1)E 1 11 ( -1.0 s 0.1)E 1 ( -1.5 0.5)E 1 ( 0) ( -1.2 - -0.9)E 1 ( 1.2 - -0.9)E 1 ( 2.1 - =1.1)E 1 ( 0/ 2) ( 0/ 2) ( 0/ 2) Cs-137 ( 4) 150. ( 1.4 a 0.5)E 1 11 ( 1.4 s 0.5)E 1 ( 4.0 a 123.0)E'-1 ~ ( 0) ( 8.8 - 18.5)E O ( 8.8 - 18.5)E 0 ( -1.2 - 1.3)E 1 ( 0/ 2) ( 0/ 2) ( 0/ 2) f e ltst: CNUSTACEANS (CR) tallTS: pCl/kg K-40 ( 10) ( 1.9 : 0.2)E 3 24 ( 2.2 a 0.4)E 3 ( 2.2 s 0.4)E 3 ( 0) ( 1.3 - - 2.6)E 3 ( 1.3 - 3.1)E 3 ( 1.3 - 3.1)E 3 ( 6/ 6) ( 4/ 4) ( 4/ 4) MW-54 ( 10) 130. ( 7.6 s 3.8)E D 11 ( 7.6 a 3.8)E D ( -1.9 : 4.9)E 0 ( 0) ( 1.1 - 23.7)E D ( 1.1 - 23.7)E O ( 1.2 - 0.7)E 1 e ( 0/ 6) ( 0/ 6) ( 0/ 4) CO-58 ( 10) 130. ( -5.4 s 51.2)E -1 24 ( 1.6 s 4.4)E O ( 1.6 s 4.4)E O ( 0) ( -1.3 - 2.4)E 1 ( -1.0 - 0.9)E 1 ( -1.0 - 0.9)E 1 ( 0/ 6) ( 0/ 4) ( 0/ 4) FE-59 ( 10) 260. ( 3.0 e 12.7)E O 24 ( 1.2 s 0.6)E 1 ( 1.2 s 0.6)E 1 ( 0) ( 4.4 - 3.8)E 1 ( 5.3 - 28.9)E D (- 5.3 - 28.9)E O ( 0/ 6) ( 0/ 4) ( 0/ 4) i ) i NOTE: Footnotes may be fourd at the end of Table 5.1. -36 - = R

TAst2 5.1 ENVIROMENTAL BAD 10 LOGICAL PROGRAM ELpetARY IIAINE TANGE NUCLEAR POWER STATION, WISCASSET, NE (JAsuutt. DECDSER 1992) l 't ISICATOR STATIONS STAT 10N WITN BIGNEST 8EAN CONTROL STATIONS eeeeeeeeeeeeeeeeee =..... = = : : : = = ; we ee _ = = = =.ee RADIONUCLIDEt* 8EAN 8EAN 8EAN (No. ANALYSTS) REQUIRED RANGE STA. RANGE RANCE (NON-ROUTINE)** LLD No. DETECTED"* No. No. DETECTED *** No. DETECTED" t 3EDItst: CausTAEANs (CR), cent. 151173 : pCf/kg Co-60 ( 10) 130. ( 6.6

38.2)E.1 24 (

4.0 s 5.3)E O ( 4.0 s 5.3)E O ( 0) ( -1.2 1.2)E 1 ( -3.3 - 19.6)E -0 ( -3.3 19.6)E O ( 0/ 6) ( C/ 4) ( 0/ 4) ZN-65 ( 10) 260. ( 4.2 a 75.9)E -1 24 ( 1.5 a 4.2)E O ( 1.5 a 4.2)E O; ( 0) ( 3.5 1.3)E 1 ( -4.9 - 12.8)E O ( -4.9 12.8)E O ( 0/ 6) ( 0/ 4) ( 0/ 4) .e l Ac.110M( 10) ( 2.3

0.7)E 1 11

( 2.3 a 0.7)E 1 ( 6.3 a 5.2)E O ( 0) ( -5.9 - 43.1)E O ( -5.9 - 43.1)E O ( 3.2 - 20.2)E D ( 1/ 6) ( 1/ 6) ( 0/ 4) ss-124 ( 10) ( -7.5 s 20.4)E D 24 ( 5.4 a 15.8)E 0 ( 5.4 s 15.8)E O ( 0) ( -7.1 - 7.3)E 1 ( -2.8 - 4.0)E 1 ( 2.8 4.0)E 1 ( 0/ 6) ( 0/ 4) -( 0/ 4) CS 134 ( 10) 130. ( 8.7 s 4.3)E O 11 ( 8.7 s 4.3)E 0 ( -9.7 a 3.6)E 0 ( 0) ( -2.0 - 0.5)E 1 ( 2.0 0.5)E 1 ( 1.6 - 0.1)E 1 ( 0/ 6) ( 0/ 6) ( 0/ 4) Cs-137 ( 10) 150. ( -5.9 a 4.4)E O 11 ( ' 5.9 a - 4.4)E O ( -7.1 a 1.8)E O ( 0) ( -2.5 0.6)E 1 ( 2.5 - 0.6)E 1 ( +9.9 -1.8)E O ( 0/ 6) ( 0/ 6) ( 0/ ' 4) IEDILBt: 8Us5ELS (881) (51178 pCf/k3 r.40 ( 4) ( 1.1 s 0.1)E 3 24 ( 1.3 a 0.5)E 3 ( 1.3 a 0.5)E 3 ( 0) ( 1.0 - 1.2)E 3 ( 7.5 18.4)E 2 ( 7.5 18.4)E 2 ( 2/ 2) ( 2/ 2) ( 2/ 2) 8eN-54 ( 4) 130. ( 6.9 s 3.4)E O 24 ( '1.7 s 0.2)E 1 ( 1.7 a 0.2)E 1 ( 0) ( 3.6 10.3)E D ( 1.6 - 1.9)E 1 ( 1.6 1.9)E 1 ( 0/ 2) ( 0/ 2) ( S/ 2) CD-58 ( 4) 130. ( 2.3 a 5.1)E 0 11 ( 2.3 a 5.1)E O ( 7.1 a ' 1.5)E O ( 0) ( -2.8 7.4)E D ( -2.8 7.4)E O ( -8.6 - 5.6)E C ( 0/ 2) ( 0/ 2) ( 0/ ' 2) I NOTE: Footnotes may be found at the end of Tabte 5.1. j 37 i i =.

.l TABLE 501 ENVIRouMENTAL RADIOLOGICAL PROGRAM R30WtY NAlhE TANKEE NUCLEAR P0bER STATION, WISCASSET, NE (JANUARY - DECDSER 1992) INDICATOR STAftout STATION WITN NIGNEST 8EAN CONTROL STATIONS eseerneeeeeeeeeee seeeer. : = = = : = :ee z _ _ _ uuue RADIGINCLIDE9' NEAN 8EAN IEAN (ND. AAALYSEE) REQUttED RANGE STA. RANGE RANGE (mon-ROUTINE)" LLD me. DETECTED *** m0. No. DETECTED"* so. DETECTED ** IEDILat: IUEEELE (IEJ), cent. 85175: 3Cf/kg FE 59 ( 4) 260. ( 2.7 e 1.1)E 1 11 ( 2.7 a 1.1)E 1 ( -1.5 a 0.5)E 1 ( 0) ( 1.6 - 3.2)E 1 ( 1.6 - 3.8)E 1 ( 2.0 - -1.0)E 1 ( 0/ 2) ( 0/ 2). ( 0/ 2) Co-60 ( 4) 130. ( 5.1 s 2.2)E D 24 ( -1.0 a 119.0)E -1 ( -1.0 a 119.0)E -1 ( 0) ( -7.3 - -2.9)E D ( -1.2 - 1.2)E 1 ( -1.2 - 1.2)E 1 ( 0/ 2) ( 0/ 2) ( 0/ 2) IN-65 ( 4) 260. ( 3.1 0.3)E 1 11 ( 3.1 a 0.3)E 1 ( 2.1 ~ 9.3)E 0 ( 0) ( 2.8 - 3.5)E 1 ( 2.8 - 3.5)E 1 ( -7.2 - 11.4)E D ( 0/ 2) ( 0/ 2) ( 0/ 2) AG-11(ast 4) ( 1.1 's 0.3)E ' 1 11 ( 1.1 a 0.3)E 1-( -1.5 s 0.7)E 0 ( 0) ( 8.8 - 13.9)E D ( 8.8 - 13.9)E D ( -2,2 - -0.8)E O ( 0/ 2). ( 0/ ' 2) ( 0/ 2) $8-124 ( 4) ( -4.1 s 6.2)E D 24 ( 3.8 a 17.2)E O ( -3.8 a 17.2)E O ( 0) ( -1.0 - 0.2)E 1 ( -2.1 - 1.3)E 1 ( -2.1 - 1.3)E 1 ( 0/ 2) ( 0/ 2) ( 0/ 2) Cs 134 ( 4) 130. ( -3.1 t 11.5)E O 11 ( -3.1 e 11.5)E O ( -1.9 s 0.1)E 1 ( 0) ( 1.5 - 0.8)E 1 ( -1.5 - 0.8)E 1 ( -2.0 - -1.8)E 1 ( 0/ 2) (. 0/ 2) ( C/ 2) Cs 137 ( 4) 150. ( 4.2 s 10.8)E 0 24 ( 4.3 s 4.5)E O ( 4.3 4.5)E O ( 0) ( 6.6 - 15.1)E D ( -2.6 - 88.2)E -1 ( 2.6 - 88.2)E -1 ( 0/ 2) ( 0/ 2) ( 0/ 2) NOTE: Footnotes may be fcmd at the end of Table 5.1. -38 .n_

i Footnotes t) Tebts 5.1: The only radienuclides' reported in this table are these with LLD rewirements and these for dich positive reeleectivity was detected. See section 5 of this report for e discussion of other redlersactidos that were anstyzed. son-Routine refers to those radionuclides that exceeded the Reportire Levels in Technicet speelfleetion Table 4.8-3.

The fractlen of soepte anstyses yielding detectobte sensureaants (l.a. > 3 standard devlettens) le shown in parentheses.

I i ? I i t 4 a . i s l M O ~

TABLE 502' ENVIRONIENTAL TLD DATA ESMARY MAINE TANGE NUCLEAR POWER STATION, WISCASSET, ME (JANUART. DECEMBER 1992) INNER RINS TLDs CUTER RING TLDs STATION WITN NIGNEST IEAN (XINTROL TLDs

u.n........ u ;

eeeeeeeeeeeee

- - - - ==e**e

n...... eeeeee***

IEAN BEAN BEAN 8EAN RANGE RANGE STA. RANGE RANGE (NO. 8EARREMENTS) (No. DEASUREMENTS) No. (NO. NEASUREMENTS) (NO. NEASUREMENTS) 7.8 s 0.8 7.9 0.7 37 10.8 s 0.6 8.6 a 1.7 5.8 - 9.8 5.5 10.3 10.0 - 11.5 6.9 - 11.5 (6B) -(67) (4) (12) I 4 D I e

Each ameasuremente is based typically en cparterly readings from sin TLD elements.

L i i o 1 I i i ) i 1 ?' 40 f

TABLE 5.3 ENVit0MMENTAL TLD MEASUREMENTS 1992 (Micro-t per Nour) ANMUAL Sta. 157 QUARTER 2ND QUARTER 3RD QUARTER 4TN QUARTER AVE. 50. Description EXP. S.D. EXP. S.D. EXP. S.D. EXP. S.D. EXP. TL-01 Old Ferry Rd. 7.5 0.3 8.0 s 0.2 7.8 s 0.3 8.6 s 0.4 8.0 TL-02 Old Ferry Rd. 6.3 a 0.3 7.1 a 0.2 7.5 s 0.3 8.2 a 0.2 7.3 TL 03 Salley house (ESL) 6.4 0.4 7.4 0.2 7.8 s 0.5 7.9 s 0.1 7.4 TL-04 Westport Ist./tt.144 5.8 s 0.3 6.6 s 0.2 7.3 a 0.4 6.6 TL 05 NT Inforastion cent. 7.6 s 0.4 9.0 e 1.2 8.3 0.2 9.1 s 0.1 8.5 TL 06 tt.144/creenleaf ad. 8.0 a 0.3 8.1 : 0.2 7.8 : 0.3 8.7 a 0.5 8.2 8.1 : 0.2 7.8 0.1 8.5 0.2 8.1 TL-07 Westport Isl./tt.144 TL 06 NT se eerhouse 6.8 0.4 7.3 s 0.2 7.5 0.2 8.0 s 0.3 7.4 9.2 s 0.3 9.8 : 0.4 9.5 TL 09 Westport Ist./tt.144 TL-10 Balley Pt. 6.8 0.3 7.4 s 0.4 7.4 s 0.2 7.8 s 0.2 7.4 TL-11 Mason station 7.9 : 0.3 8.4 a 0.4 8.4 a 0.2 8.6 s 0.4 8.3 TL-12 Westport Firehouse 7.3 0.3 7.8 s 0.2 7.8

0.1 8.4 a 0.6 7.8 TL-13 Foxbtrd Istard 8.1 s 0.3 8.5 s 0.5 8.1 a 0.3 8.8 : 0.3 8.4 TL-14 Eston Fors 6.4 s 0.1 7.0 s 0.1 7.3 a 0.2 7.5 0.2 7.1 TL-15 Eaton Feria 5.9 0.2 6.7 : 0.3 6.9 0.1 6.9 s 0.2 6.6 TL-16 Eston Farm 7.1 s 0.1 8.2 s 0.2 7.6 s 0.4 7.6 s 0.1 7.6 TL-17 Eaton Farm ad.

8.5 s 0.2 9.3 s 0.5 9.3 s 0.2 9.2 s 0.3 9.1 TL 18 Estcn Farm ad. 7.2 s 0.3 7.9 0.2 8.0 s 0.2 8.3 a 0.3 7.9 TL-19 Eston Farm ad. 6.4 s 0.2 7.3 a 0.2 7.7 a 0.2 7.7 a 0.2 7.3 TL-20 Bradford Rd. 6.2 s 0.1 7.5 0.3 7.3 a 0.2 7.4 a 0.2 7.1 TL-21 Federat st. 6.5 0.2 7.9 0.5 7.3 a 0.2 7.6 s 0.3 7.3 TL-22 Cochran Rd. 6.8 s 0.2 7.9 s 0.2 8.2 a 0.2 8.2 s 0.2 7.8 ft 23 Middle Rd. 8.7 s 0.2 10.0 s 0.4 10.0 a 0.4 10.3 a 0.2 9.8 TL-24 River Rd. 7.4 s 0.5 8.5 0.4 7.8 0.1 8.4 s 0.2 8.0 TL 25 tiver Rd./tt.27 7.1 : 0.2 8.4 a 0.4 8.1 a 0.1 8.1 : 0.2 7.9 TL 26 Scothbey at Museum 7.4 a 0.2 8.1 0.4 8.1 a 0.1 8.5 s 0.3 8.0 TL 27 Barters Island 7.5 0.3 7.8 a 0.2 7.8 s 0.2 7.7 TL 28 Rt.144/E. shore Rd. 6.8 s 0.2 7.5 0.2 7.5 0.1 7.7 s 0.4 7.4 TL-29 karrison's Trailer 6.3 0.2 7.3 a 0.1 7.5 0.2 7.6 0.3 7.2 TL 30 Leeman Fars 7.7 0.2 9.0 s 0.4 8.7 : 0.2 9.2 a 0.4 8.7 TL 31 Barley neck Rd. 8.3 s 0.4 9.2 s 0.3 9.0 s 0.2 9.6 : 0.5 9.0 TL-32 Baker Fars 7.2 a 0.1 8.4 a 0.1 8.8 0.3 8.6 s 0.5 8.3 TL-33 Rt.127 6.5 s 0.1 7.5 0.3 8.0 s 0.4 7.8 s 0.2 7.5 TL-34 Rt.127 6.3 0.2 8.0 s 0.4 7.6 s 0.1 8.2 a 0.7 7.5 TL 35 at.127 5.5 t 0.3 6.7 0.3 7.7 0.2 7.6 s 0.2 6.9 TL-36 Soothb.ube.Ftre sts. 6.9 s 0.2 7.4 0.3 6.9 s 0.2 7.9 s 0.3 7.3 TL 37 seth Fire sta. 10.0 s 0.2 10.8 : 0.3 10.7 s 0.4 11.5 0.2 10.8 TL 38 Dresden testation 7.5 0.4 8.2 s 0.3 8.8 s 0.3 7.2 s 0.2 7.9

TLD tost, apparently &e to verdelism.

41 f

t 6. ANALYSIS OF ENVIRONMENTAL RESULTS 6.1 s==nline Prorram Deviations Table 2.3 of the Offsite Dose Calculation Manual (ODCM) allows for deviations in the REMP schedule "if specimens are unobtainable due to hazardous conditions, to seasonal unavailability or to malfunction of sampling equipment." Such deviations do not compromise the program's effectiveness and in fact are considered insi nificant with respect to what 5 is normally anticipated for any radiological environmental monitoring program. The specific deviations for 1992 were limited to missing TLD badges, which were assumed to have been stolen in the field. The missing TLD badges were: TL-07, TL-09 and TL-27 in the first quarter;.TL-09 in the second quarter; and TL-04 in the third quarter. 6.2 Comoarison of Achieved LLDs with Recuirements Table 2.4 of the ODCM gives the required Lower Limits of Detection (LLDs) for environmental sample analyses. (This table is duplicated in Table 4.4 of this report.) 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, ODCM Appendix C, Section 1 requires a discussion of the situation. At the Yankee Atomic Environmental Laboratory, 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 Maine Yankee ODCM. For each analysis having an LLD requirement in ODCM Table 2.4, the a posteriori (after the fact) LLD calculated for that analysis was compared with the required LLD. Of the over 3700 analyses performed during 1992, of which approximately 1200 had an associated LLD in Table 2.4, all met the required LLD. ? 6.3 Comnarison of Results Arsinst Reportine Levels { Section 2.4.3.3 of the ODCM requires the notification of the NRC (via the Semiannual Effluent Release Report) whenever a Reporting Level in ODCM Table 2.5 is exceeded. Reporting Lavels are the environmental concentrations that relate to the ALARA design dose objectives of 10 CFR 50, Appendix I. It should be noted that environmental concentrations are [ 42 1

i ) ' averaged'over calendar _ quarters _for the purposes of this comparison, and. j that Reporting Levels apply only to measured levels of radioactivity due to plant effluents.t.During 1992, no Reporting Lavels were exceeded.' i i i 6.4 Data As=1vais by Media Tyne j The 1992 REMP data for each media type is discussed below. Whenever a l specific measurement result is. presented, it is given as the concentration .] plus or minus'one standard deviation. This standard deviation. represents only the random uncertainty associated with the radioactive decay process j (counting statistics), and not the_ propagation of all possible uncertainties in the analytical procedure. A sample is considered to yield l a " detectable measurement" when the concentration exceeds three times its 1 associated standard deviation. With respect to data plots,-it should be noted that all values for a given graph are plotted, whether or not they ~ are considered statistically significant. 6.4.1 Airborne Pathways i 6.4.1.1 Air Particulates The weekly air particulate filters from each of the five sampling' sites were analyzed for gross-beta radioactivity. At tho'end of each quarter, j 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 through 6.5. i 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 l annual cycle, with the minimum concentration in the second quarter, and the i maximum concentration in the first quarter. The peak seen in the second quarter of 1986 is airborne contamination resulting from the Chernobyl j accident, as detected by the Maine Yankee monitoring program. i Figures 6.2 through 6.5 show the weekly gross' beta concentration at each' j air particulate sampling location alongside the same for the control air particulate sampling location at AP-29' (Dresden Substation). It can be Jreadily seen that.the gross-beta' measurements on air particulate filters fluctuate significantly over the course of a year. The measurements from, i control station AP-29 vary similarly, indicating that these fluctuations 1 T P P .y i

are due to regional changes in naturally-occurring airborne radioactive materials, and not due to Mairr Yankee 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 radionuclida detected on air particulate filters was Be-7, a naturally-occurring cosmogenic radionuclide. 6.4.1.2 Charcoal Cartridres The weekly charcoal cartridges from each of the five 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. 6.4.1.3 Mixed crasses Although not required by the Maine Yankee ODCM, mixed Erass samp1ss were collected twice at the Environmental Services facility during 1992, and once at a nearby location. No radionuclides attributable to Maine Yankee operations were detected in either sample. Naturally-occurring K-40 and Be-7 were detected in all three samples, as expected. 6.4.1.4 1211 Although not required by the Maine Yankee ODCM, soil samples were collected on June 29, 1992 at two locations - the Bailey House (Environmental Services laboratory) and the intersection of the railroad tracks and Ferry Road adjacent to the Maine Yankee site. Two samples were collected at each location - one from 0-4 inches deep, and the other from 4-8 inches deep. As expected, naturally occurring K-40 and AcTh-228 were detected in all - samples. Also detected was Cs-137. The levels'of this radionuclide were consistent with that detected in other soil samples in the northeastern United States and is attributed to fallout from nuclear weapons tests. 6.4.2 Waterborne Pathways 6.4.2.1 E.etuarv Vater Aliquots of estuary water were automatically collected in the discharge s h-

canal outfall every two hours during 1992. These composited samples were l collected monthly and sent to the Yankee Atomic Environmental Laboratory for analysis. Monthly grab samples at the control location were also collected. Table 5.1 shows that naturally-occurring K-40 was detected in l each sample, as is typical with sea water. No gamma-emitting radionuclides I attributable to Maine Yankee operations were detected in any of the samples. L For each sampling site, the monthly samples were composited into quarterly I samples for Tritium (H-3) analyses. One of the four samples at station WE-I 12 (Discharge Canal Outfall) showed detectable levels of H-3 due to plant l operations. The concentration for this sample, which was collected over i the third quarter of 1992, was 720 1 210 pCi/kg. In accordance with Table 5.1 of the ODCM, a dilution factor of 10 is applied to this concentration r since the samples were taken from the discharge forabay, prior to release to the Back River via the underwater diffusers. The resulting maximum concentrations of 72 pCi/kg may be compared against the NRC Reporting Level of 30,000 pCi/kg. (If this Reporting Level was reached, the Maine Yankee ODCM would require notification to the NRC in the Semiannual Effluent Release Report.) 6.4.2.2 Ground Vater Although not required by the Maine Yankee ODCM, quarterly ground water samples were collected from the well at the Environmental Services building and at a control site. The results of the gamma and H-3 analyses are shown in Table 5.1. No H-3 or gamma-emitting radionuclides were detected in any of these samples. In 1989 several ground water monitoring wells were installed on the Maine Yankee site to monitor the effects of a sodium chromate spill in 1988. An additional monitoring well was installed in 1992 for the closure of the ferrous sulfate tank. To characterize the ground water in the vicinity of the Maine Yankee facility, a series of ground water samples was collected in March and again in August of 1992 at these wells. In addition to a series of non-radiological water quality analyses that were performed on the samples, radiological analyses were done at the Yankee Environmental [' Laboratory. These results are summarized in Table 5.1, along with the routine quarterly ground water samples collected from WG-13 and WG-24. As expected, naturally-occurring K-40 was detected in many samples, and gross-beta measurements were positive, due to naturally-occurring radionuclides. No gamma-emitting radionuclides, other than K-40, were detected. H-3 was 6, m Y

1 detected, however, in five of the fourteen on-site samples (duplicates and ' l ~ blanksLexcluded). LThe maximum concentration'of 2560 1 230 pCi/kg from on-site well no. BK-1 did not exceed the-Reporting 14 vel for H-3 of 20,000 j pCi/kg as given in Table 2.5 of the ODCK.

j i

6.4.2.3 Shoreline sediment I Semiannual sediment core samples were collected from two on-site. 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 and'Ac-Th-228 were detected in all samples. -i In addition to the above radionuclidas, Cs-137 was' detected in ten of.the H ~! twelve segments. Although some Cs-137-is expected to be present from worldwide weapons testing fallout, much of it is due to early plant. j operations. In the early, years cf plant operation, routine liquid effluents were discharged in.the sediment-collection area. Due to poor diffusion with this method, an underwater diffuser was installed, and now' d the liquid effluents are discharged into the Back River. The Cs-137 lev'els in sediment are plotted in Figures 6.6 and 6.7. These graphs show that the j ~ levels have not changed significantly over the past several' years. ] 4 Although there is no Reporting Level for Cs-137-in sediment samples, one-ij might appreciate the negligible dosimetric consequence when the measured l concentrations are compared against.the reporting levels for fish (which, j unlike sediment, are assumed to be eaten by the public). The mean'and' ~! maximum Cs-137 seasurements were 190 and 320 pCi/kg.(dry). well under the. Cs-137 Reporting evel in fish of 2000 pCi/kg (wet). l -i R d 6.4.2.4. Marine Alrae ~I e Although not required by the Maine Yankee ODCM,. mixed samples of Bgag and Asconhv11um marine algae (" seaweed") were collected at-Long Imdge and'a-control'1ocation during 1992. All samples were analyzed for gamma-emitting radionuclides..As expected, naturally-occurring K-40'was detected on all. samples. Naturally-occurring Be-7 and Ac-Th-228 were detected on one. sample and three samples, respectively. .f j - Three out of four samples collected from long 14dge (AL-11) showed. 1 measurable concentrations of Ag-110s,;all due to controlled plant discharges. The mean and maximum concentrations there 16 and 28 pCi/kg,. 46-1 1 i ~ .a J

respectively. These are well within anticipated levels, and will have no impact on man via the direct consumption pathway since the algae from this location is not consumed. 6.4.3 Inrestion Pathways 6.4.3.1 gilk Milk samples (consisting of either cow or goat milk) from several farms were collected monthly during 1992. Although samples are only required from three locations by the Maine Yankee ODCM, they were collected from up to five locations during 1992. 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 25 out of 30 indicator samples and 7 out of 12 controls. Sr-90 was detected in all samples, both indicator and control. Although both 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. Considerable variation is found to occur in milk samples from one farm to another, depending on the soil, vegetation and farming practices at each location. The Cs-137 and Sr-90 levels shown in Table 5.1 and Figures 6.8 and 6.9 are consistent with those detected at other New England farms that are monitored as part of other Yankee-affiliated environmental monitoring programs. 6.4.3.2 Fish & Invertebrates Semiannual samples of fish and invertebrates were collected from two locations during 1992. On June 30, striped bass were collected at both locations, and on September 15, striped bass were collected from FH-11 and menhaden from FH-24. Invertebrate samples consisted of lobsters, rock crabs and blue mussels. 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., o

One crab sample from Long Ledge, collected on September 15, 1992, contained 43 1 11 pCi/kg Ag-110m. This is consistent with the low-levels of Ag-110m detected in marine algae at this location during 1992. To put this level in perspective, the dose was calculated for a hypothetical individual who consumes a large but credible amount of these crabs (5 kilograms per year), using USNRC Regulatory Guide 1.109 (Reference 7) methodology. The resulting dose was 0.013 mram per year. This may be compared to an estimated 200 mrem per year received by the average individual from natural background radiation each year (Reference 4). A follow-up crab sample collected from Long Ledge on October 17, 1992 did not show any detectable Ag-110m. None of the three lobster samples collected from this location in 1992 showed detectable levels of Ag-110m, including that collected on September 15, 1992. 6.4.4 Direct Radiation Pathway Direct radiation is continuously measured at 38 locations surrounding the Maine Yankee plant with the use of thermoluminescent dosimeters (T1Ds). These are collected every calendar quarter for readout at the Maine Yankee Environmental Services Laboratory. As can be seen in Figures 6.10 to 6.20, 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 site and another. This explains why the control TLD station at the Bath Fire Station (TL-37, 7.0 km from the plant) had the highest mean exposure for 1992 (see also Figure 6.20). From Tables 5.2 and 5.3, as well as from Figure 6.10, it can be seen that i the Inner and Outer Ring TLD mean exposure rates were not significantly different in 1992. This indicates no'significant overall increase in direct radiation exposure rates in the plant vicinity. It can also be seen I from these tables that the Control TLD mean exposure rate was not significantly different than that at the Inner and Outer Rings. . 4 v

er 8 i FIGURE 6.1-GROSS-BETA MEASUREMENTS ON AIR PARTICUIATE FILTERS ' QUARTERLY AVERAGE CONCENTRATIONS .f 0.16 0.12 u J o D e5 U w 0.08 e 1 6 N t u ~t c. 0.04 - - f k k O -u 1983 1985-1987 1989 1991 1993 i s n n. t i t Indicator Stations' -y. Control Stations . er

s.,- FIGURE 6.2 GROSS-BETA MEASUREMENTS ON AIR PARTICUIATE' FILTERS 0.06 1 0.05{ 4 0 ~ + 0.04. a c Ei '.f f ~ j 0.03-i i 6 x ~ n . i. D 0.02- \\ D0 x p ~ i ~ k. ? 6 0.01-0' i Jbn Dec Feb Apr Aug Oct Dec 1992 i -e-AP-11 Montsweag Brook - w - AP-29 Dresden Substation (Control): LI

N

. f ={ --50-- . M'

6 FIGURE 6.3 .l GROSS-RETA MEASUREMENTS ON AIR PARTICUIATE FILTERS r 0.06 L l 0.05f i t o 1 u 0.04-o 5 U j 0. 0 3 -- I8 ^ x. c ~ " x U &j d 0.02-~ C\\ y 8 .x a. x. fx l [ .X c b 8 -l 0.01-I O j Dec Feb Apr Jun Aug Oct Dec 1992 r \\ -e-AP-13 Bailey 'n rm (ESL) + .i -x-AP-29 Dresden Substation (Control) ?.i

l i

.j ? ? i -i r 5 I -l .i

4 t FIGURE 6.4 GROSS-BETA MEASUREMENTS ON AIR PARTICUIATE ' FILTERS 0.06 e . j. 0.05f u oa 0.04 2 o E o i y 0.03 7 g x x a x ~ o x ~

. g y a

x 'N* ,X a d ',

x. g x

-u 0.02-7\\ x x 0.01 6 0 0. [ Dec Feb Apr Jun Aug Oct Dec' . i 1992 t ~ --t3-- AP.-14 Mason. Steam Station -y-AP-29 Dresden F"" station.(Control) 'S =, P f e '? ii ~$ 3 I I

-I. j s i FIGURE 6.5 'l . GROSS-BETA MEASUREMENTS ON AIR PARTICUIATE FILTERS 0.06 i 0.05k l u .[ y .. e 0.04. .uos-o Y 'I y 0.03-x 5 .k i s 4 C 0.02. V. f* x 4 g, XX g ~ { ka x 0.01-t 0 3 Dec Feb Apr Jun Aug Oct Dec 1992 I i + -e-AP-16 Westport Firehouse -y-AP-29 Dresden Substation (Control) i i ~l i i r V - i ? I f. t 3 = N$

FIGURE 6.6 l CESIUM-137 IN SHORELINE SEDIMENT STATION SE-16, OLD OUTFALL AREA 600 500 i 3 300-i en ( I O i i i i i 5/89 10/89 5/90 10/90 5/91 10/91 5/92 10/92 Month / Year 3 0 - 5 cm i j g 5 - 10 cm O 2 0 - 2 5 c= 1 ! l^ l' r.

= i FIGURE 6.7 CESIUM-137 IN SHORELINE SEDIME:NT STATION SE-18, FOXBIRD ISIAND 600 t 500 400f 3 u 0-i i i j i i i 5/89 10/89 5/90 10/90 5/91 10/91 5/92 10/92 Month / Year 3 0 - 5 cm 3 5 -- 10 cm O lo - 15 c= l- [ l l \\ l-r

'F h r FIGURE 6.8 f CESIUM-137 IN MILK .) ANNUAL AVERAGE CONCENTRATIONS 60 j ~

t, 50.

40. en x' 30- .6 -s ~ U ~ C. 20. 0 X., v 10- ,x, i 'X.. "W 0 1977 1979 1981 1983 1985 1987-1989 '1991 1993 i + .. k + TM-15 Mitman ram -e-TM-16 Baker Farm l e TM-17 Leeman~rarm-({ e TM-18 Chewonki Foundation- . x '. TM-25 Hanson Farm

}

6 i b I 1

!.l I

o '- 'l 3 l r 5 i .[,.'

[2 I a FIGURE 6.9 STRONTILE-90 IN MILK l t ANNUAL AVERACE CONCENTRATIONS- <j 25 t i j 20- ~i t y v G s .A ^! U -i 10-i S-0 I 1977 1979 -1981 1983 1985 1987 1989 1991 1993 r- --e-TM-15 Mitman Farm --o-TM-16 Baker Farm e TM-17 Leeman Farm } [ g -TM-1B Chewonki-Foundation x TM-25 Hanson-Farm .] i ~ i ~$: ) - ; l ~ .i i I 1 L I w A 1.- A- ' l ---.-...N.

n J '4 FIGURE 6.10 EXPOSURE RATE AT INNER RING, OUTER RING-AND CONTROL TLDS 25 1 20-o" r O* 15-u + O Q. ~ j c: 1 o 10-w ~ 'x'*#' ' ' x.. x' * ' ' * ~ 'M ' r -. - .3 x' ~ x.- s x y. 5-c t = 0 4, i . i 1988 1989 1990 1991 1992 .1993-Retrieval Date .J -e-Inner Ring e outer Ring-t -x-Control' t ,1 7 ' I h i : I 3 4 /

_,r

I h FIGURE 6.11 EXPOSURE RATE AT INNER RING TLDS, TL 01-04 25 l i 20-i h g .. t O* i 15-u e CL .i a: .i b 10-a j uu

e4 o

5-o 0 1988 1989 1990 1991. 1992 1993 i Retrieval Date --t3-- TL-Ol' old Ferry Road v TL-02 Old Ferry Road-I e TL-03' Bailey House (ESL)' c. TL-04 Westport Island, Rt. 144 i I i r" + i

I' l FIGURE 6.12 EXPOSURE RATE AT INNER RING TLDS, TL 05-08 25 20-u ~ a O* 15-u CJa e, P o 10- /. u U w E y e 5-0 1988 1989 1990 1991 1992 1993-Retrieval Date -e-TL-05 MY Information Center TL-06 Rt.'144 and Greenleaf Road --g-. TL-07 Westport Island, Rt. 144 g TL-08 MY Screenhouse

a [ f FIGURE 6.13 EXPOSURE RATE AT INNER RING TLDS,.TL 09-10, 12-13 -l 25 i i 20-u 3 O* 15- .u Oa. To 10-3 A -N / Mo x v 5-0 1988 1989 1990 1991 -1992 .1993 -Retrieval Date- --e-TL-09 Westport Island, Rt. 144 x TL-10 Bailey Point --n-- - TL-12..Westport Firehouse e TL-13 Foxbird Island ( ~61-

.i i FIGURE 6.14 ' I EXPOSURE RATE AT INNER RING TLDS, TL 14 l 25 r 20-u n 1 O 15-u W + c. M I0 10-u + o + Z [ - i 5-0 1988 1989 1990 -1991 1992 1993. i Retrieval Date -e-TL-14 Eaton Farm x TL-15 Eaton Farm' ' e-TL-16 Eaton ' Farm . I ,i . i ~ i '. j i b I =

f v

h '.'t a i I FIGURE 6.15 i EXPOSURE RATE AT INNER. RING TLDS, TL 17-l'9 j a 25 1 7 20-l t u ~

s t

O' 15- ~ u to Q. a: ~ \\ 0 10-u 'DO-f X ["h [ f 5- { -3 0 1988 1989 1990 1991 1992 1993

b Retrieval'Date

[.'f -g3- ~ TL-l'1 Eaton Farm Road }} .6:r x 'TL-18 Eaton Farm Road

(

1 5 TL-19.Eaton Farm Road a -j i .I i .' i t h r I ? e ! l 5 '.} i u.. .t = =

i FIGURE 6.16 l EXPOSURE RATE AT OUTER RING TLDS, TL 11, 20-22 25 - j 20-u n O* 15-u C c, [ c: o 10- [ 4 o A Z l N 5-t i 0 1988 1989 1990 1991-1992 1993-Retrieval Date --gy- 'TL-11 Mason Station r x TL-20 Bradford Road,'Wiscasset e TL-21 Federal Street, Wiscasset. e, TL-22 Cochran Road,.Edgecomb. -t (- }. . ;.i i. i Y i 1 .u . 1

o i ~ i: [ h FIGURE 6.17 EXPOSURE RATE AT OUTER RING.TLDS, TL 23-26 l 25 ~ ri t 20-u o o 15-u On, a a: / - r= s g a -r 5-e t 0 1988 1989 1990 1991 1992 1993 in Retrieval Date. -e-TL-23 Middle _ Road', Edgecomb i y TL-24 River Road, Edgecomb ~ -) e TL-25;. River Road and Route _27- 'i c, TL-26 Rt. 27 and Boothbay RR Museum l 'i i h .1 L n e

r: 1,, p r-FIGURE 6.18-EXPOSURE RATE AT OUTER RING TLDS, TL 27-30 25 20-un O* 15-u C) Q. CC ~ s 8 10-i 0 -*4 5-0 1988 1989 1990 1991 1992 1993~ Retrieval Date' -t3-- TL-27 Barters Island v.TL-28 Westport Island, Rt 144 & East Shore Rd e TL-29 Harrison's Trailer t... -e-TL-30 Leeman Farm, Woolwich . 1l. ~. = -

i ? FIGURE 6.19 EXPOSURE RATE AT OUTER RING TLDS, TL 31-35 25-I 20-l 9 t

s O

15-u C. i O g e o 10-l u U 6 w p 5-l .0 1988 1989 '1990 1991 -1992 1993 Retrieval Date t --e-TL-31 Barley Neck Road, Woolwich i TL-32 Baker Farm, Woolwich e TL-33 R'oute'127, Woolwich f g TL-34 Route-127, Woolwich --y - TL-35 Route'127, Woolwich ? , i l 1 -L

h h FIGURE 6.20 EXPOSURE RATE'AT CONTROL TLDS, TL 36-38 i i '25 1 Li -e 20-k

s S

i 15-1.1 u c Q.. g I e 0 10-u - u w u 5- .t i 0 .{ i. 1988 1989 1990 1991 1992-1993- 'i; e Retrieval Date -e-TL-36 Boothbay Harbor Fire Station II 'TL-37 Bath Fire Station e TL-38 Dresden Substation- ] I r e y . -j j,. 1. l !i l - = f-: --- --

7. QUALITY ASSURANCE PROGRAM The quality assurance program at the Yankee Atomic Environmental Laboratory is designed to serve two overall purposes:

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

It provides a means to control and measure the characteristics of measurement equipment and processes, relative to established requirements. The Yankee Atomic Environmental Laboratory employs a thorough quality assurance program to ensure reliable environmental monitoring data. The program includes the use of written, approved and controlled procedures for all work activities, a nonconformance and corrective action tracking system, systematic internal audits, audits from external groups, a laboratory quality control program, and a complete training and retraining system. The Intralaboratory Quality Control program at the Laboratory and the EPA third party interlaboratory program are discussed in more detail below. Also discussed is the blind duplicate quality assurance program conducted by the Laboratory Quality Control Audit Committee. 7.1 Intralaboratory Ouality control Procram The Yankee Atomic Environmental Laboratory 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 approximately 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 Laboratory acceptance criteria for accuracy, while 1.4% (8 out of r-

566 analyses) were identified as outside the hboratory acceptance criteria =. Of the 615 analyses for precision during 1992, 1004 met the. Laboratory acceptance criteria for precision. Table.7.1.shows a summary of the results of this program. 7.2 EPA InterconDarison Prorran To further verify the accuracy and precision of the hboratory analyses via an independent outside third party, the Yankee Atomic Environmental Laboratory participates in the U.S. Environmental Protection Agency's Environmental Radioactivity Laboratory Intercomparison Studies Program-for those available species and matrices routinely analyzed by the hboratory. Participation in this program is required by Maine Yankee Technical Specification 5.8.1.b.3. and ODCM Section 2.4.5. Each sample supplied by the EPA is analyzed in triplicate,.and the re'sults are returned to the EPA within a specified time frame. When the know values are returned to the: Laboratory, the hboratory and EPA results are then evaluated against specific Laboratory and EPA acceptance criteria. When the results of 'he t cross-check analysis fall outside of the control. limit, an investigation is made to determine the cause of the problem and corrective measures are taken, as appropriate. Results of this program are provided in this report in compliance with ODCM Section 2.4.5. For the EPA Intercomparison Program, there were 171~ analyses for accuracy on 96 samples. The samples consisted of-water, milk and air particulate filters. The analyses were for gamma-emitting radionuclides, gross-beta,- strontium, iodine, plutonium and tritium. Table 7.2 shows~ a summary of the - results for 1992. Of the 171 analyses for accuracy, all' met the EPA mean 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. Maine Yankee radiological environmental monitoring program, these results are not, reported here. In 1991,-as reported in the 1991 Annual Radiological Environmental Operating Report, a set of Strontium analyses on three water samples, (hboratory Sample Nos; S97981, S97982-and 897983) did not meet the EPA mean value control limits. The mean_value was 38.6.pci/1Tand.the EPA Control Limits were from 40.3 - 57.7 pCi/1. The Laboratory investigated-this set of results under Yankee laboratory Corrective Action Request Y14AR - ASG-01-92. The sample set'vas: reprocessed, but the Sr-89 results did not - indicate the presence'of statistically positive radioactivityLsince the; b-Aev m- -e ww-ww' mew e a4 d- -e-g

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 since the Sr-89 had decayed through four half-lives. 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 520/92, 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 Laboratory and EPA acceptance criteria at similar Sr-89.90 ratios and activity levels. 7.4 Blind Dueliente Ouality Assurance Prorram The Laboratory Quality Control Audit Committee (LQCAC) is comprised of one member from each of the five power plants that are serviced by the Yankee Atomic Environmental Laboratory. Two of the primary functions of the MCAC are to conduct an annual audit of Laboratory operations and to coordinate the Blind Duplicate Quality Assurance Program. Under the Blind Duplicate Quality Assurance Program, paired samples are submitted from the five plants, including the Maine Yankee Nuclear Power Station. They are prepared from homogeneous environmental media at each respective plant, and are sent to the Laboratory for analysis. They are " blind" in that the identification of the matching sample is not identified to the Laboratory. The LQCAC analyzes the results of the paired analyses to evaluate precision in Laboratory measurements. A total of 51 paired samples were submitted under this pro 5 ram by the five participating plants during 1992. Paired measurements were evaluated for 26 gamma emitting radionuclides, H-3, Sr-89, Sr-90, I-131 and gross-beta. All measurements were evaluated, whether the results were considered statistically positive or not, and whether the not concentration was positive or negative. Of the 1273 paired duplicate measurements evaluated ir_ 1992, 1271 (99.8%) fell within the established acceptance criteria. Of -l the two paired measurements that did not meet the acceptance criteria, neither had radioactivity that was considered statistically positive. The results of this program are summarized in Table 7.3 and 7.4. . e

TABLE 7.1

SUMMARY

OF PROCESS CONTROL ANALYSIS RESULTS January - December 1992 ACCURACY PRECISION SAMPLE MEDIA NUMBER NUMBER ANALYSES ANALYSES NUMBER OF OUTSIDE NUMBER OF OUTSIDE ANALYSES ACCEPTANCE ANALYSES ACCEPTANCE CRITERIA CRITERIA AIR CHARCOAL Camma 116 3 82 0 AIR FILTER Beta 221 0 221 0 Cama 7 0 i 6 0 Strontium 6 0 6 0 MI1X Cama 72 3 103 0 Iodine 46 0 46 0 Strontium 31 0 31 0 VATER Cross-Beta 8 1 8 0 Camma 12 0 12 0 Iodine 11 0 11 0 Strontium 16 1 16 0 Tritium 20 0 17 0 SOIL / SEDIMENT Camma 0 0 56 0 TOTAL 566 8 615 0 . a

r TABLE 7.2

SUMMARY

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

ANALYSES LIMITS **

AIR FILTER Beta 2 6 0 Camma 2 6 0 Strontium 2 6 0 MIlX Gamma 2 15 0 Iodine 2 6 0 Strontium 2 12 0 WATER Cross-Beta 3 9 0 Camma 5 66 0 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.

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

g

i TABLE 7.3

SUMMARY

OF BLIND DUPLICATE SAMPLES SUBMITTED January - December 1992 TYPE OF SAMPLE NUMBER OF PAIRED SAMPLES SUBMITTED Cow Milk 20 Cround Water 8 River Water 4 Surface (Fresh) Water 1 Estuary Water 5 Sea Water 6 Irish Moss 2 Mussels 4 Food Product - Cranberries 1 TOTAL 51 , r~

1 TABLE 7.4 i SUMMART OF BLIND DUPLICATE RESULTS January - December 1992 TOTAL ANALYSES

i ANALYSIS TYPE FOOD MARINE MILK WATER PRODUCT AISAE MUSSEL TOTAL Gamma 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) 11 (0) Gross Beta 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 , W

f 8. LRED_USE_CENERA Maine Yankee Technical Specification 5.8.1.b.2 requires that e Land Use Census be conducted annually, pursuant to the details given in Section 2.4.4 of the Offsite Dose calculation Manual (ODCM). The Census identifies the locations of the nearest milk animal, the nearest residence and the nearest garden of greater than 500 square feet producing fresh leafy i vegetables in each of the 16 meteorological sectors within a distance of five miles of the plant. The 1992 Land Use census was conducted between the required dates of June 1 and October 1. Pursuant to Section 2.4.4 of the ODCM, a dosimetric analysis is performed, using site specific meteorological data, to determine which milk aninal locations would provide the optimal sampling locations. If any location has twice the potential dose commitment of 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 eltninated from the progras). For the 1992 Census, one such milk animal location was identified. This location was not added to the milk sampling program, however, since it had been shown in the past to be unreliable with regard to supplying milk samples (see Section 4.3.8 of this report). Consequently no changes were made in the milk sampling program. The results of the 1992 Land Use census are included ic this report in compliance with ODCM Section 2.4.4.3 and ODCM Appendix 0 Part 1. The locations identified during the census may be found in Table 8.1. F t 1 i

. f

._= 1 i TABLE 8.1 l 1992 LAND USE CENSUS LOCATIONS f I i SECTOR NEAREST NEAREST RESIDENCE CARDEN NEAREST MIIX ANIMAL Ka (Mi) Km (Mi) Ka (Mi) l I N 1.3 (0.8) 1.3 (0.8) l NNE 2.3 (1.45) 2.5 (1.6) NE 1.3 (0.8) 1.3 (0.8) 5.5 (3.4) (Coats) i ENE 0.9 (0.6) 1.2 (0.7) 1.2 (0.7) E 0.9 (0.6) 0.9 (0.6) [ ESE 1.4 (0.9) 1.4 (0.9) l SE 0.7 (0.4)

3.2 (2.0)

SSE 0.9 (0.6) 0.9 (0.6)

S 1.7 (1.1) 2.7 (1.7) 5.6 (3.5) (Coats)

SSW 3.0 (1.9) 5.1 (3.2) f SW 1.4 (0.9) 1.4 (0.9) 7.9 (4.9) (Cows) WSW 1.0 (0.65) 1.1 (0.7) 1.9 (1.2) (Cows)

V 2.6 (1.6) 2.6 (1.6) 7.2 (4.5) (Cows)

~ WNW 0.8 (0,5) 2.8 (1.7) i s NW 2.0 (1.3) 2.0 (1.3) w* hTJ 1.1 (0.7) 1.1 (0.7) The nearest residence, garden or milk animal to Maine Yankee. No location was identified within 5 miles of the plant. i I )

~ .i 9. REFERENCES r 1. USNRC Radiological Assessment Branch Technical Position, "An r ' Acceptable Radiological Environmental Monitoring Program," Revision l 1, November 1979. 2. NCRP Report No. 94 Ernosure of the Pooulation in the United States and Canada from Natural Backrround Radiation, National Cotcacil on l Radiation Protection and Measurements, 1987. 3. Ionirina Radiation: Sources and Biolonical Effects United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR), 1982 Report to the General Assembly. l b 4. Kathren, Ronald L., Radioactivity'and the Environment ' Sources. [ Distribution. and Surveillance, Harwood Academic Publishers, New York, 1984. 5. Maine Yankee Final Safety Analysis Reoort. 6. NRC Ceneric Letter 89-01,

Subject:

Implementation of Programmatic! Controls for Radiological Effluent Technical Specifications in the Administrative Controls Section of the Technical' Specifications and t the Relocation of Procedural-Details of RETS to the Offsite Dose Calculation Manual or to the Process Control Program.. Dated January 31, 1989. 7. USNRC Regulatory Guide 1.109,'" Calculation of Annual Doses to Nan-from Routine Releases of Reactor Effluents for the Purpose of r Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977.. L ? -) .h i 9, ff1 .}}

ML20036A214

Contents

Text

Reference:

Subject:

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

Subject:

Navigation menu

ML20036A214

Text

Reference:

Subject:

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

Subject:

Navigation menu

Search