ML19309C291
| ML19309C291 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 03/23/1980 |
| From: | Maine Yankee |
| To: | |
| Shared Package | |
| ML19309C288 | List: |
| References | |
| NUDOCS 8004080411 | |
| Download: ML19309C291 (55) | |
Text
{{#Wiki_filter:-_ 9 1979 l Radiological Environmental Surveillance Report OPERATING LICENSE NO. DPR-36 DOCKET NO. 50-309 JANUARY 1,1979 through DECEMBER 31,1979 l s w D F =- = = - g,< j--,, ,; i,_.( c-... _A V j= MAINE YANKEE ATOMIC POWER COMPANY 8r0408040 l
MAINE YANKEE ATOMIC POWER COMPAhT ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT January 1, 1979 - December 31, 1979 March 23, 1980 Maine Yankee Atomic Power Company Engineering Office Environmental Engineering Department 20 Turnpike Road Westborough, Massachusetts 01581 4
'i 1 f 4 t 4 i TABLE OF CONTENTS t Page j 1. Introduction 4 II. Location of Sampling Stations 6 III. Summary of Environmental Measurements 18 b IV. Milk Cow Survey Results 45 1 V. Quality Assurance Program-47 4 VI. Analysis of Environmental Data 48< VII. Environmental Dosimetry. 62' j VIII. Conclusions 65 IX. References. 66 9 i I f t 4 v e -~-a-p-e c w. 4 % - ,a ~ ,-v
Lt. s LIST OF FIGURES P t P Figure 1.. Location of Plant 10 Figure 2. Site Topography 11 Figure 3 Sampling Sites Close to Plant 12 Figure 4 Marine Radiological Sampling Sites 13 Figure 5. Air Particulate and TLD Monitoring Sites 14 Figure 6. Food Crop, Vegetation, and Milk Sampling Sites 15 Figure 7 Food Crop, Vegetation, and Milk Sampling Sites 16 Figure 8. Sediment and Water Sampling Sites 17 Figure 9. Gross Beta Activity in A.P. '11ters 49 Figure 10. Ce-144 in A.P. Filters 50 Figure 11. Co-60.in Sediment 57 I Figure 12. Cs-134 in Sediment 58 T 4 t-2- g L e +y n a
e,;. ). + r LIST OF TABLES r l e i g-1 Table 1. Milk Cow Survey Results 46 Table 2. Annual Average TLD Exposures 60 i l Table 3. Offsite Environmental Radiological Monitoring-61 i l' l Table 4. Summary of Environmental Radiation Doses-64 i i i j i } i i i 1 t l l I i I 1 n a f i e I f P 1 g N 4 I I-r 4 s g ^
s I. INTRODUCTION This report contains a summary and analysis of the radiological environmental data collected during 1979 by the Environmental Studies Laboratory of the Maine Yankee Atomic Power Company. Direct gamma radiation around the plant evirons is measured with LiF TLD Chips. Maine Yankee personnel prepare, distribute, measure and calibrate these dosimeters. All the environmental samples were processed by the Yankee Environmental Laboratory, loca *d in Westborough, Massachusetts. Section II of this report contains a list of all samplir.c stations used in 1979 as well as a tabulation of the media sampled at each station.- Figures 1 through 8 indicate the location of the plant site, its topography and the locations of the sampling stations. Section III summarizes the environmental data. A computer program, ERMAP, produces a digest of the 1979 measurements. Each environmental media appears according to the alphabetical order of its media code. At the top of each page, ERMAP lists the units of measurement for each medium. The left hand column contains the radionuclide which is being reported, total number of analysis of that radionuclide, and the number of measurements which exceeds ten times the yearly average background value. The latter are called "non-routine" measurements. The next column lists the nominal lower limit of detection (LLD) for each radionuclide. The LLD used by the Yankee Environmental Laboratory for each radionuclide is based on the d
W methodology in the U.S. NRC Regulatory Guide 4.8 (Reference 1). Those sampling stations which are adjacent to the plant and which could conceivably be affected by the operation of Maine Yankee are called " indicator" or " Zone I" stations. Distant stations, which are beyond plant influence are called " Control" or " Zone II" stations. ER}UJ calculates a set of statistical parametee for each radionuclide. This set of statistical parameters includes separate analyses for (1) the indicator stations, (2) the control stations, and (3) the station having the highest annual mean concentration. For each of these three groups of data, ERMAP calculates:
- 1) The mean value of all concentrations including negative values and values below LLD.
- 2) The square root of the mean square deviation. This is an estimate of the sample variance.
- 3) The lowest and highest calculated concentration.
- 4) The number of positive measurements (measurements greater than the LLD) divided by the total number of measurements.
Section IV of this report contains the semiannual results of the milk cow survey, and Section V of this report discusses the Quality Assurance Program. In the final sections, we analyze the results of our efforts in l 1979, calculate environmental radiation doses, and present our conclusions., l
1 l II. LOCATIONS OF SAMPLING STATIONS The-following three pages list our sampling locations. Distances are measured from the center of the containment building; directions are relative to true north. The media codes are: AP Air particulate AR Arthropods C Charcoal air filters FD Farm crops FI Finfish M Milk SF Shellfish SS Sediment VA Marine algae VT Terrestrial vegetation WE Estuary water WG Fresh water i WP Precipitation i I
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f, j Direct Radiation - TLD Dosimeter Sites Sampling and Analysis Frequency - Monthly Zone I Distance (Km) Site Sample Station Locations from Plant -Quadrant TL 1 Montsweag Brook 2./ NW TL 2 Eaton Farm .5 w TL 3 Environmental Studies Lab. (Bailey Farm) .6 NE TL 4 Central Maine Power Company Mason Steam Station 4.8 NE TL 5 Edgecomb Firehouse 5.6 ENE TL 6 Westport Firehouse 1.8 S TL 7 Harrison's Trailer 6.4 SW TL 8 Restricted Boundary Site (See Figure 2) 2.2 NNE TL 9 Restricted Boundary Site (See Figure 2) .20 ENE TL 10 Restricted Boundary Site (See Figure 2) .18 ESE TL 11 Restricted Boundary Site.(See Figure 2) .32 SSE TL 12 Restricted Boundary Site (See Figure 2) .29 SSW TL 13 Restricted Boundary Site (See Figure 2) .75 WSW TL 14 Restricted Boundary Site (See Figure 2) .64 WNW TL 15 Restricted Boundary Site (See Figure 2) 1.00 NNW Zone II TL 16 Morse Farm 10.0 W TL 17 Drescan Substation 19.8 NNW '
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' s..' 1 III. SLHMARY OF 1979 ENVIR0hMENTAL DATA f_. The following.pages summarize the analytical results of all the i environmental samples which were collected during 1979. These pages were generated by the computer program, ERMAP. ~ i i 1 4 i ^ ) ) '. t. 1 l 1 1 .a e.
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SUMMARY
FOP f ill P L Il l 0D 12// 8 / f r). 1//)l/19 PE Dlues WATEa - PRECIPITAilott UNIT 5: PCI/LIItk /* PA010NUCLInf$ It4DI C A lpp 51 Al l0N5 tilGHf 51 5 ] A T If)N CUNI NUL LUC 4 Iluf45 1H0. ANAlv5f55 NOMINAL ME AM,R ANGt, AND M1AM PAMGt,AND MLAHekANGt.A1D I tsCre-> cu t ! NI 18
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- 1. TIE 2.
- t 1/- 3589
- t 1/ ttI*
- t 0/ 10l*
NEH-80UilHE DEFENS 10 flit ' MUMiiF R OF SEPANATE HE A5UdE Mt H T 5 WHI Cll' Wl R E GR E A f t R ' ite AN ftH 1100 T IME 5 THE AvtWAGF H ACE GRt1UND F OR. T eit PLkinD Ut THE REPUNI
- ~ i lif IRACTION OF S AMPLE. AN AL YSES Y it t.nlNG DE TE CI ABLt NE ASUkE Pt kT5 ll.E. >LLDI 15 IMUICAIED WITHIH
- t AND lo.
i i 4=.. 8 m (c o ) 25'e) (DEED 2,5e), m &W
i ?,. I L IV. MILK COW CENSUS DATA [ r A census of all milk cows within'an 8 Km radius of the. plant was - carried out on May 15 and October 24, 1979.~ Table 1 indicates the results of this survey; there was no change in milk sampling' locations during 1979. + l-i t + t l l i e e 4-w - - <y y-
- s. Table 1 Number of Cows Farm Location-May October Sherwood Baker Woolwich-4 4 /.2 Km, 2680 Lester Holbrook Woolwich 15 18 7.1 Km, 2690 Wayne Leeman Woolwich 1 1-7.9 Km, 2290 Bruce Dickson Wiscasset 3 'l 2.7 Km, 100 Ronald Hodgdon Wiseasset 2 1 2.1 Km, 3560 i Frank Richards Edgecomb 1 1 /./ Km, 940 Raymond Shadis Edgecomb 1 1 4.2 Km, 560 John Potter Edgecomb 1 7.9 Km, 410 I ' 46-
V. QUALITY ASSURANCE PROGRAM Three separate Quality Assurance programs were performed during-1979 to demonstrate the validity of laboratory analyses by the Yankee Environmental-Laboratory (YEL). YEL participates in the EPA Interlaboratory Comparison (cross-check) Program for those species and matrices routinely analyzed by the laboratory. This provides an independent check of accuracy and precision of the laboratory analysis. When the results of the cross-check analysis fall outside of the control limit, an investigation is made to determina the cause of the problem and corrective measures are taken. YEL maintains an intralaboratory quality control program to assure the validity and reliability of the data. This program includes quality control of laboratory equipment, use of reference standards for calibration, determination of counting efficiencies and analysis of blank and spiked samples. The records of the quality control program are reviewed by the responsible cognizant, and corrective measures are taken whenever applicable. Samples are prepared from split or homogenous media and sent to the laboratory for analysis. The results from this blind duplicate program are used to check for precision in laboratory analyses. l 3 -
VI. ANALYSIS OF ENVIRONMENTAL DATA The analysis of environmental data may be divided into'three-sections: airborne radioactivity, waterborne radioactivity and direct exposure radiation measurements. A discussion of each environmental media within tnese sections will follow: 1. Airborne a. Air Particulate Air monitoring stations are established at a total of nine locations. Seven of these locations are indicators, while the remaining two are control stations. The air pumps at these locations operate continuously at a flow rate of approximately one cubic foot per minute, resulting in a weekly air sample of approximately 300 cubic meters. Airborne particulates are collected by passing the air through a fiber filter; these filters are collected weekly and held for at least 24 hours before being analyzed for gross beta activity to allow for the decay:of radon and thoron daughter products. Weekly composite air filters from each location are analyzed quarterly for gamma emitting nuclides. Figure 9 shows the weekly concentration of gross beta activity during 1979. This figure shows that the behavior of gross beta . activity _for indicator and control stations are similar. ERMAP results show that the mean concentration of indicator and control- -4 8-v
Figure 9 I (14 [ NE GR-B GIR PARTICULRTE. 7. 5 0 f. - 0 2 -- i 6. 00 L [ t 't 1 Q It
- (
s. 4.50E.-02 ; / . ], \\ h l ~ l! l i p T )\\ .v I 'i { \\/ l j, k 8 3. 00 f. - 0 2 - ( L - J i k\\ '/ l /y ih:; i p X s p p L 1 s \\ y .i ~ hl ] ' p) l ,) 0 D 1.50E-02-. j iFR / c 9 W 1 {~ C3 %0 i, i, i. i i i i s i i s i i i rri i i ; i i i i i i i i g i i i.. i rrprrrr i i i i i s i m mrpTmTrrrp n rrr Trrrnmrprrnmulto rrn uj JAN. fEB. [14R. 6PR. [14 Y JUNE JULY (10G. S t. P. OCT. NOV-Ot I: g 1979 W Z VALUES INDICATE fiCTIVITY Nul1BERS OUTSIDE THE RGNGE Of THE PLOT g b GTATION 11
- M STATION 12
- X STAT 10N 13
- Z STATION 14
- + GT fit I ON 15
- X j
l0 S T6 T I Ort 16
- o STATIOil 17
=luSTATI0tt 20
- A STATION 23
- t
k Figure 10
- -l,.
r.. i-MRINE-CE-144 AIR PARTICULAT 15. 00 E - 0 3 --' ~ ' 4.00E-03 -. g 1 ..2 3.00E-03E. ..m m ~ 5: 0 .2.00E-033 .v 1 x 1 00t%03 _.g ~ D. . wrm. i i u m rri g.. i i... ; i... i i i i g n i n n i j Tm. i i ; a n n g i i i. ' ' " I " " ' ' TTT
- TITrrmm]m rm rrj
'JAN.
- F ED.-
NHR. -APR. 11RY JUNE JULY ..AUG. SLP.- :0C T.- NOV'.' OEC-1979 'Z:. VALUES INDICRIE-ACTIVITY NUMBERS OUTS 1DE'THE RANGE _OF li1E ~ PLOT: ' STATION 1.1- -:X STAT ION
- 1. 3
- X STATION 17J X STATION '14 z' + S T A T I O N ' 28.
=X. p
stations for gross bets activity were equal during 1979, Concentrations of Cs-137 and Ce-144 greater than LLD were detected in quarterly composite samples during 1979. This activity was primarily.due to the intermixing of the upper and lower atmosphere during the spring and summer. months. Figure 10 shows the concentration of Ce-144 activity in Zone I and Zone II stations which demonstrate this seasonal trend. b. Radioiodines Charcoal filters from nine air sampling stations were collected and analyzed weekly for 1-131 activity. Concentrations of I-131 activity in both indicator and control station samples during 1979 were below minimum detectable levels. c. Milk Milk was collected and analyzed monthly for Sr-89, Sr-90 and gamma emitting nuclides. During 1979, there was one detectable level of I-131 noted in the April milk sample from Station 16 located 7.2 Km west from.the plant. The I-131 activity was due to an abnormal release of iodine caused by a body-bonnet gasket failure on a containment spray value on March 15, 1979. Milk sampling-and analysis was increased to a weekly frequency at all milk stations for the next month. Only one concentration of I-131 in these weekly samples was above the lower-limit of. detection. Cesium 137 and Sr-90 were detected in milk samples from the-I L i
indicator and the control station. The mean concentrations of Cs-137 and Sr-90 in milk from the indicator station were greater by a factor of 2 and 4, respectively, than the control station' milk samples. This higher concentration in indicator stations has been noted for several years, and is not related to plant gaseous releases. During 1979, the total gaseous release of Sr-90 from Maine Yankee was 1.44 uC1. Using the methodology in Regulatory Guide 1.109 (Reference 2), and the annual average D/Q at station M-16, the expected Sr-90 concentration in allk is several orders of magnitude smaller than the mean concentration measured in milk. The same holds true for Cs-137 concentration in milk. Different radionuclide transfer coefficients might account for the higher concentration of Cs-137 and Sr-90 detected in the indicator station samples. The transfer coefficient for Sr-90 from diet to cows milk is dependent upon dietary calcium and can range from 0.08 to 0.16. Cesium-137 binding on clay particles associated with hay or by absorption in rumen contents can cause transfer coefficient values to range from 1 to 0.25. The cause of the higher Sr-90 and Cs-137 concentrations in milk'will be' looked ~ into during the next year. d. Terrestrial Vegetation Terrestrial vegetation samples were. collected in June.and September from six sample locations. These vegetation samples consisted l of mixed grass and were analyzed for Sr-89, Sr-90 and gamma emitting i .I /.
~_ nuclides. Positive concentrations of Sr-89, Sr-90 and Cs-137 were detected in samples from indicator and control stations. The mean concentratior,of Sr-90 were approximately equal in indicator and control stations, while Sr-89 and Cs-137 in samples from control locations had larger concentrations. Four of the six measurements from control. stations had activity concentrations of Sr-89 and Cs-137 greater than the lower limit of detection, with the highest concentration of Sr-89 seen in samples submitted from VT-24, a control station, located 19.8 Km north-northwest from the plant. The highest Cs-137 concentrations were seen in samples submitted from VT-13, a control station, located in the west sector 9.8 Km l' from the plant. Since these radionuclides are detected in both. t indicator and control station samples, this indicates that the activity in vegetation is not related to plant operation. Furthermore, the total release of Sr-89 from the plant during 1979 was below the lower limit of detection'for the effluent monitors. Using the methodology in Regulatory Guide 1.109 (Reference 2) and the annual average D/Q at Station 13, the expected Sr-89 concentration in vegetation is several orders of magnitude smaller than the mean concentration measured in'terrestrical vegetation.. it is suspected that the reason for measurements of Sr-89 were greater than the lower limit of detection value (LLD)-was due to ) the way the LLD is calculated. As recommended by a NRC Branch Technics 1 Position ~(Reference 3).the LLD is calculated'as'an a-priori ~ estimate which.is' dependent on the instruments background i L
and detection efficiency. For Sr-89 LLD calculations, the a priori estimate does not account for the interference of the Sr-90 activity and does not reflect realistic detection capabilities. e. Food and Garden Crops Apples and cabbages were collected at harvest time and analyzed for gamma emitting nuclides. Potassium 40, a naturally occuring radionuclide, was the only detectable radionuclide with activity greater than the lower limit of detection. f. Fresh Water Fresh water samples were collected from three indicator and one control station on a quarterly basis. These samples were anlayzed for tritium and gamma emitting nuclides. During 1979, no radionuclides with activity concentrations greater than minimum detectable levels were detected. g. Precipitation Precipitation samples are collected and analyzed monthly from four sampling stations for tritium activity. The results of the analysis of 43 samples showed only one analysis with an activity concentration just greater than'.the' lower limit.of detection. A P-value (probability of false positive measurements) was calculated using a binominal distribution. The P-value_was 32 percent, indicating that this' positive measurement could be due ( .to a random event. r l
'2. Waterborne Pathway a. Estuary Water Estuary water was collected and analyzed monthly for gamma emitting nuclides and quarterly for H-3 activity. Water samples from Station 15 contained detectable levels of I-131 and H-3 in March and September. This activity was due to normal plant liquid releases during the first and third quarters of 1979. Station 15 is located onsite and the samples from this station are taken from the discharge forebay located before the diffuser discharge. This undiluted discharge does not represent the environmental water concentration. When a dilution factor of 10 is applied, due to the operation of the diffuser in the Back River, the concentration of these allowable concentration are further reduced in the environment. b. Aquatic Vegetation Aquatic vegetation samples from Station 11 and 12 showed detectable concentrations of I-131 during the thits quarter of 1979. This activity is due to normal plant release mentioned in the estuary water section. Although small' amounts of I-131 are contained in algae samples, none of this activity was detected in Marine organism and therefore, there was no subsequent impact to man. I I
i. c. Mar *7e Organisms Fish, shellfish and arthropods were collected and analyzed seslannually during 1979. Potassium 40 and Thorium 228, both naturally occuring radionuclides, were the only radionuclides with activity concentrations greater than the minimal detectable level. d. Sediment Concentrations of Cobolt 60, Cesium 134 and Cesium 137 were detected in sediment samples from Station 15 located on the west side of Bailey Cove. This station is in the vicinity of the old liquid discharge point, where routine liquid releases from the plant occurred before 1975. Because of the small amount of diffusion of the liquids in this area, a discharge diffuser was installed and the liquid is now discharged into Back River. The activity noted in Station 15 sediment samples is due to the residual activity from the old releases. Figure 11 and 12 show a decrease in the mean concentration of Co-60 and Cs-134 at Station 15 over the last three years.. Concentrations of Cobolt 60 and Cesium 134 were below lower limit of detections at Station 18, which is located on the east side of Bailey Cove near the present diffuser. 3. Direct Radiation Table 2'shows the yearly average exposure.from direct gamma radiation in microrem per hour from eighteen TLD stations located on and off e --s -,,.m o-en. .-..-m .--e on o e, o - - .e,* ~.oo- -.-aoom.=== -o
- m. wm..
,o e 9 G 9 O te 6 M e M O se e h M e6 air gem M 6 m M W m e 6 e p 90 m -9 ~* Y e = NM me 6 n em M h } ee. m %e in A N t.1 1 hgm J. f* O L' w
- 8 sum k'*.
= W >= bU Ic w r.'., ~ w y* b .m c r. w 6 ( h ~ > .0 m O c.C m w %i) W he e h any B a-P. -r s. ama o p r W l a= P* m tem h -6 D's C 1 L: es. = m F = em b O sm .a - ~ 7m 4i g D6 Wihd seh
- eshme W
G he (* e tem poe sus b
- .J C
C -, c3 k me e-2 L > C ? m O g. g. g.i i,. .. i + 6 6 i i. l r: r-r ca %J w., w .m< m m w-4 + + + .ma o* m,3 m* No w s.* m, %d %e b c'eum she U"** gd b)/1"Je
- g M
e gm -[ i 1 - 3 1
.L-e..wo-... ...............-+-- -- -. J I 4 0. D emD ammy O 6 $3 no one w emSM en b
== P* em e e ti o - w [+ m ~ n 'a-- .D*- esmed g e W eme w W c C / C- ~
- a.,
~ C, w .mm ese 7,e o d 4, p C ~ g m O { **=. t*. n Q a-e O~ ~3 w e O w pium
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L:. Ls. t O C U w a .) C C, w >= I es C-w C.- + i 47 N 4. 6. = t U. L .we p
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a 4. 4.. is . i i 6. g..... g r c. ca c; N u O O C C iO O 4 4 W O C. O C O T LC C. C ~ M W 9 0'T ~ l) m w D CF/13a -f A. .a oo m
1. the Maine Yankee site. Zone I and restricted boundary stations exhibited monthly radiation exposure which range from 6.0 to 16.4-microres per hour. This compares to the 9.7 to 23.1 microres per hour range recorded at Zone II stations. The yearly average shows that the control stations had a slightly higher' exposure rate and were not significantly different-from the Zone I and restricted boundary stations. 1 4 I-I >
Table 2' 1979 Average TLD Exposures P prem/hr TL 0 Zone I /.6 TL 1 Zone I 10.9 TL 2 Zone I 11.1 TL 3 Zone I 10.5 TL 4 Zone I 10.8 TL 5 Zone I 10.5 TL 6 Zone I 11.1 TL 7 Zone I 10.1 TL 8 Restricted Boundary 10.0 TL 9 Restricted Boundary 13.8 TL 10 Restricted Boundary 12.7 TL 11 Restricted Boundary 13.4 TL 12 Restricted Boundary 14.8 TL 13 Restricted Boundary 10.2 TL 14 Restricted Boundary 12.1 TL 15 Restricted Boundary 10.7 TL 16 Zone 11 14.1 TL 17 Zone II 11.2 Average Zone I 11.3 grem/hr 1 1.7 Average Zone II g 12.7 grem/hr-12.1 i 3 s J f. ..-r .g v +
. Table 3-Offsite Environmental Radiological Monitoring Summary of Analyses for the Period 1/3/79 to 1/3/80 TLD Direct Radiation microrem per hour Analyses Lower Limit All Indicator Highest Control Perfo rmed of Stations Station Station (Total Detection (mean (mean (mean Number) (LLD) range) range) range) TLD (215) 0.3 (11.3 j; 1.7) 12(14.8 f; 1.5) (12.7 + 2.1) (6.0 to 16.4) (12.4 to 16.7) (9.7 to 23.1) 4 f f 1 I i,
VII. ENVIR)NMENTAL D0f,IMETRY The mean con:entration of radionuclides having activity concentration greater that lower limit of detection values in indicator and control station sauples of air patticulate filters, charcoal filters, drinking water, t' seafood, milk and food crops were used to calculate total body doses to adults. The average individuals' usage factors were taken from U.S. NRC Regulatory Guide 1.109 (October 1977). These usage factors are: 3 8000 M /yc of inhaled air 370 1/yr of irinking water 7.9 Kg/yr of seafood 110 1/yr of milk 190 Kg/yr of food products The product of the mean radicauclide concentra: ion and the usage factor yields the yearly radionuclide intake. The d<,se i-calculated by using the dose conversion factors contained in U.S. NRC Regulatory Guide 1.109. 1-131 doses to the thyroid were calculated raoarately from data from the sample media mentioned above. In addition, external ehole body doses were measured with TLD's placed in indicar.or and control stations. Table 4 summarizes the environments
- doses from mean radionuclide concentrations greater than LLD's in indicator and control station samples.
The whole body dose is almost entirely due to the contribution of Sr-90 in milk. As mentioned in the milk section, this activity is not related to plant gaseous releases and the cause of this higher Sr-90 activity in L
o <, =. i milk will'be looked into during 1980.. TLD measurements indicate that nearby residents did not receive .any measurable dose from plant operation. The background external doses were measured to be 12 mrem per year higher than indicator stations, showing that variation in the ns. ural environmental dose rate is greater than any contributions from the plant. 4 1 r 1 3 m,
,. p* t b Table 4 i Summary of Environmental Radiation Doses (mrem /yr) l Source Plant Environs
Background
i Inhalation 1.0 x 10-3 3.3 x 10-4 Seafood Food Crops Milk 3.6 1.0 Water i-131 1.5 x 10-2 + = TLD 99.0 111.3 Total 102.6 112.3
- All concentrations below LLD
- Thyroid dose for I-131 activity I
4 I 1 t r
~- 3 t %III. CONCLUSIONS I During 1979, a radiological environmental monitoring program conducted in.the Maine Yankee offsite environment showed, in general, that the major radionuclides measured in environmental media were the naturally [ occurring radionuclides. There was no significant. increase in the environmental radioactivity due to plant operation. 2 l I b b e f 1 l 4 e
'#+4 W 43 .e
- -E
.gC. e-4 m u e i.~ IX. REFERENCES [ 1. U.S. NRC Regulatory Guide 4.8, " Environmental Technical ~ Specificati ms for Nuclear Power Plants", 1975. l d 2. U.S. NRC Regulatory Guide 1.109, " Calculation.on Annual Doses to Ma'n from Rcutine Releases of Reactor Effluents for the Purpose of Evaluating 7 Compliance with 10CFR50", Appendix I, 1977. .i 3. U.S. NRC Branch Technical Position, "An Acceptable Radiological i l Environmental Monitoring Program", July 1979. k t .' ^ g I 8 66-- t V y y--- e ,-}}