ML20054B884

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Annual Radiological Environ Monitoring Rept,Jan-Dec 1981
ML20054B884
Person / Time
Site: Yankee Rowe
Issue date: 03/31/1982
From:
YANKEE ATOMIC ELECTRIC CO.
To:
Shared Package
ML20054B882 List:
References
NUDOCS 8204190283
Download: ML20054B884 (200)
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Text

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l YANKEE ATOMIC ELECTRIC COMPANY ANNUAL RADIOLOGICAL ENVIRON'4 ENTAL MONITORING REPORT

{

January 1, 1981 - December 31, 1981 l

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March 1981 1

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a Yankee Atomic Electric Company Engineering Office Environmental Engineering Department 1671 Worcester Road Framingham, Massachusetts 01701 m

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8204190283 820407 DR ADOCK 05000 m

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I Table of Contents I

I Page I.

Introduction......................................................

1 II.

Location of Sampling Stations.....................................

3 III.

Summa ry of Envi ronmen tal Mea suremen t s.............................

14 I

IV.

Quality Assurance Program.........................................

49 I

V.

Atmospheric Fallout 53 VI.

Analysis of Environmental Data....................................

74 I

VII.

Environmental Dosimetry...........................................

87 I

VIII.

Conclusion........................................................

89 I

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I List of Figures I

Page Figure 1.

Location of Plant 7

Figure 2.

Site Topography.............................................

8 Figure 3.

Sampling Sites Close to the Plant 9

Figure 4.

Air Monitoring and TLD Stations............................. 10 Figure 5.

Water, Soil and Vegetation Sampling Sites................... 11 Figure 6.

Aquatic Vegetation and Garden Vegetable Sampling Sites...... 12 Figure 7.

Milk and Maple Syrup Sampling Sites......................... 13 Figure 8.

1980 Gross Beta Activity in A.P. Filters.................... 54 Figure 9.

1980 Ru-103 Activity in A.P. Filters........................ 55 Figure 10.

1980 Cc-141 Activity in A.P. Filters........................ 56 Figure 11.

1980 Nb-95 Activity in A.P.

Filters......................... 57 Figure 12.

1980 Zr-95 Activity in A.P. Filters......................... 58 Figure 13.

1981 Gross Beta Activity in A.P. Filters 59 Figure 14.

1981 Ru-106 Ac t ivit y in A. P. Filt er s........................ 60 Figure 15.

1981 Ce-141 Activity in A.P.

Filters 61 l

Figure 16.

1981 Cc-144 Activity in A.P. Filters........................ 62 Figure 17.

1981 Ru-103 Activity in A.P. Filters 63 Figure 18.

1981 Cs-137 Activity in A.P. Filters 64 Figu re 19.

1981 Zr-95 Activity in A.P.

Filters 65 Figure 20.

1981 Nb-95 Activity in A.P. Filters......................... 66 Figure 21 to Fallout Radionuclides Measured in A.P.

Filter from the 27 Environmental Laboratory in Westborough, Mass.

67 to 73 I

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List of Tables Page Table 1.

EPA, Intra-laboratory and Inter-laboratory Results........... 50 l

Table 2.

Agreement of Radionuclides in Sediment Samples............... 52 Table 3.

Thyroid Doses from February I-131 Release 76 Table 4.

Average Soil Exposure Rates 80 Table 5.

Average Soil Concentrations 81 Table 6.

1981 Average TLD Exposures 85

)

Table 7.

Summary of TLD Analyses...................................... 86 Table 8.

Summary of Environmental Radiation Doses 88 l

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INTRODUCTION I

This report contains a summary and analysis of the radiological environmental data collected during 1981 by the Environmental Studies Laboratory of the Yankee Atomic Electric Company, Rowe, Massachusetts.

I Direct gamma radiation around the plant environs is measured with CaSO :Dy TLD badges. Yankee personnel prepare, distribute, measure and 4

I calibrate these dosimeters. All the environmental samples were processed by the Yankee Environmental Laboratory, located in Westborough, Massachusetts.

I Section II of this report contains a list of all sampling stations used f n 1981 as well as a tabulation of the media sampled at each station.

Figures 1 through 7 indicate the location of the plant site, its topography and the locations of the sampling stations.

I Section III summarizes the environmental data. A computer program, ERMAP, produces a digest of the 1981 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 reporred, total number of I

analysis of that radionuclide, and the number of measurements which exceeds ten times the yearly average background value. The latter are classified as "non-routine" measurements. The next column lists the nominal minimum detectable concentration (MDC) for each radionuclide.

Those sampling stations which are adjacent to the plant and which could conceivably be af fected by the operation of Yankee are called " Indicator" or

" Zone I" stations. Distant stations, which are beyond plant influence are called " Control" or " Zone II" stations.

I ERMAP calculates a set of statistical parameters for each radionuclide. This set of statistical parameters includes separate analyses for (1) the indicator stations, (2) the control stations, and (3) the station I

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I having the highest annual mean concentration. For each of these three groups I

of data, ERMAP calculates:

1) The mean value of all concentrations including negative values and values below MDC.
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 (activity which is three times greater than the standard deviation) divided by the total number of measurements.

I Section IV of this report discusses the Quality Assurance program, which includes EPA results, and Section V discusses fallout from I

weapons testing.

In the final sections, we analyze the results of our ef forts in 1981, calculate environmental radiation doses, and present our conclusions.

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I II.

LOCATIONS OF SAMPLING STATIONS The following three pages list our sampling locations. Distances are I

measured from the center of the containment building; directions are relative to true north. The media codes are:

AP Air particulate C

Charcoal air filters FD Farm crops I

FI Finfish M

Milk MS Maple syrup I

S Soil SS Sediment VA Aquatic vegetation VT Terrestrial vegetation WD Storm drain water WG Fresh water I

WR River water TG Mixed grasses I

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Direct Radiation - TLD Dosimeter Sites Sampling and Analysis Frequency - Monthly Zone I Distance (Km)

Sample Station Locations From Plant Azimuth GM 1 Furlon Ifouse 0.8 232 GM 2 Observation Stand 0.5 313 GM 3 Ford 11111 Road 2.7 152 GM 4 Harriman Station 3.2 359 GM 5 Monroe Bridge 1.1 236 GM 6 Readsboro Road Barrier 1.3 355 GM 7 Whitingham Line 3.5 32 I

GM 8 Monroe Hill Barrier 1.8 182 GM 9 Dunbar Brook 3.2 216 GM 10 Cross Road 3.5 83 GM 11 Adams liigh Line 2.1 289 GM 12 Readsboro, Vermont 5.5 344 GM 13 Restricted Area Fence 0.08 255 I

CM 14 Restricted Area Fence 0.11 300 GM 15 Res tricted Area Fence 0.08 345 GM 16 Restricted Area Fence 0.13 30 GM 17 Restricted Area Fence 0.14 70 GM 18 Restricted Area Fence 0.14 115 GM 19 Restricted Area Fence 0.16 140 GM 20 Restricted Area Fence 0.16 160 GM 21 Restricted Area Fence 0.11 205 I

Zone II GM 22 IIea rtwellville 12.6 333 GM 23 Williamstown Substation 22.2 265 I I

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SUMMARY

OF 1981 ENVIRONMENTAL DATA The following tables summarize the analytical results of all environmental samples collected during 1981. These tables were generated by the computer code: ERMAP.

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  • f 0/ a)e et n/ 7)e et o/ 2)e nu.tn3 f s) 7.or-na

( i;3 a a.1)E o

et f 1.6 i 61F T

f t.1 i 0)F 1

7.7)E 1

( l.2 to.0)r n

(

n)

(.7.1 e(

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2).

EU. toe ( 6)

.2

(

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Ot f 3.3 1 f.6)E 2

( 3.7 &

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(

n)

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a).

  • (

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!=131

(

6) n.

( 6.0 &

4.a1E P

01

( l.0 i 81E 3 f=3.2 a 3.m)E 7

Imp.n)E I

(.7.0 51F 7

(

n)

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?)*

ef 0/

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C3 134 (

h) 7.PF=0?

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07

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n

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~

f n)

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  • (

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  • (

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s2 LJ CS*l17 f 61 7.ef.n?

( 9.7 4 a.9)E t

07

( t.h A 71E P

( 1.5 1 2)F 7 27 a)E 1

( 4.2 72.m)E 1

f 1.3 1.7)F P

(

01

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BA.ta0 f 6) s.nr.n?

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01

( 3.6 1 2.1)F 7

( 2.0 g 63.01E o

f a)

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of 0/ 41 et o/

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f i7i i6.6iE o

(.. 5 4 33i 5)r i f

0)

(.p.3 -

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of 0/ e)e et n/

7)*

et n/ 21e CE taa f 6) 7

(.p.m a 1.1)F t

et f 5.6 i 1.5)F 1

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1)F t

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n) f.o.9

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.(

n/ pie of n/

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e unn.uontfor Errrog TO Twp wowere nr grPab ATF "5 a Y.or k r N TS.wirH.rpr GeFairW TwaN TFN fin) Yt=FS Twr avFuaCr R 4CM CWouDn Fou TwF PFRiom or TwF prPnof

    • TMr twar i t nm. f'r S a **t r a nes t v $r 9 VistnTen nrftrisHI5 wra90Dr*FNTS ft.F. 4%stG*al !q inn t e r trt. witwin et

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NE0 f t'u t FIS" i'%f79: otI/<G *ET gaDinNiitt f ot s f..m i r s t ne gTafinN9 winwFgi Statios Cowtorit trratto s (NO. aNat v96 9) hn*Twal

  • Ea,kant,amn

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tin

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( t.6 &

t.015 t

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(.3.5

%.11E t

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et n/

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er 0/

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N04.kpuffhF DFFFR3 TO THE NUumED (W 3EpaRaTF "Fash0FMENTS. Hick mFer GDFaTFD Twas TF h (to) 7t=FS Twr avFoaGr matrcn00Nn Fno THE Pguinn nr THE orPnot

  • e TMF FDaCTinN OF ma**LF amatvSrS VfELDING nFTErfahlF "E a st'or wF N T S (f.E. >39tGwai 79 TNoitaTF0 a f f w t *r *(

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    • N a ON ER1 1

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1 NEDIU33 #aDLE SYRUP UNITS: PCI/ LITER RADIO %UCL!nEs INDItains sfa?!ONS NIGMEsf STATION CONTROL LOCATIONS

(%0 An4 LYSES) ND"rNat "EaN.RANCE.AND "EaN,paNGF.aND MEaN, RANGE,aND (t04.;0uTINE)*

LLO NO.* DETECTFD*e STal NO. DFTECTEDee NO. OETECTEDee St=7

( 31 8.0E*01

( 6.'8 a 6a.a)E =t 01

( 6.8 1 64.'4)E.1

(.3.4 a 2.6)E O

( 0)

(=6.0

. n.01E O

  • (

0/ the e( 0/ t)e et 0/

2)*

C=48

( 31 2.0Ee02

( 1.'9 a 0)E 3 02

( 2.0 1 0)E 3

( l.9 &

1)E 3

( 0) e(

1/ 1)e et 2/ 21e

( t.9 =

2.01E 3 et 1/

t)*

CR=51

( 3)

=1.0=100

(=8$7 a 7.2iE o 03

( 1.6 i 7)E 1

( 7.7 &

8.7)E o

( 0)

(=8.7 0.0)E 0

(=1.0 16.4)E o

et 0/ 1)e

  • (

0/ 11e e( 0/ 2)e C2=54

( 33 8.'

(.l(1 a 7)E o 03

(=l.2 1 63.1)E =2

(.4.6 a a.8)E =1

( 0)

(=1.1 =, 0.8)E O

(.9.0 0.0)E =1

=

  • (

0/ 11e et 0/ 13e et 0/ 21e C0358 ( 3) 8.'

( 3.6 &

7.a)E =1 01

( 3.6 1 7.41E =1

(.5.2 &

5.a)E =t

( 0)

  • (

0/

1)*

  • (

0/ 21e

(=1.1 =

  • (

0/ t)e 0)E o FE=53 ( 3) 1.0E*01

( 2.'2 a 2.2)E O 03

( s.9 i 1.9)E o

( 2.1 &

2 R)E O

( 0)

(.6.6 40.03E *1

  • (

0/ 11e e( 0/ 1)e et 0/ 21e g

' CO=10 ( 3) 8

( 2.'7 A 8.7)E =t 03

( 1.6 i 93E o

( t.1 A 53E o

( 0)

( 5.5 =

.t6.4)E =1 et 0/ the et 0/ t)e et 0/ 2)e IN=t3

( 3)

=t.0=100

(= t '4 &

2.2)E o 03

( 1.01 1.'9 ) E O

( 2.6 &

7.9)E =t g

( 0)

(.t.a.. 0,0}E o

(.5.4 to.53E =t et 0/ 11e

  • (

0/ 1)e et 0/ 21e IR=95 (

33 1.0E*01

(-6l7 a 13.7)E =t 03

( 8.1 i 12.71E.1

(=9.3 &

90.53E 2

( 0)

(.6.7 -

0.0)E.1 (onee A.1)E *t

  • (

0/ the et 0/ 11e et 0/ 2)e e

4 h

e NON. ROUTINE RFFERS Yn THE NumRER OF sEPARATF MEisuREMENTS wHICH >ERE GREATER THaN TEN (to) TT"Es THE AVERAGE maCMGRnUND FnR THE PERIOn DF THE RFPORT ee THE FNacTinN OF SAMPLE ANALYSES VIEtnING DETECTaRLE MEASuoEMENTS (I.E. >3SIGwa) T5 INnicaTED WTTMIN *(

)*.

h t

4 4

i

M N. ctE.g or r

at ae

.46 u.6 a.

/u3 i

SUmwaRY FO9 THF PER!nD 1?}20/20 12/31/At I

i MEDIUng maple SYCUP UNITSt PCI/ LITER g

RADIONUCLICES INDItaine STATIONS HIGMEST STATION CONTRot LOCATIONS 1

(h0. ANALYSES) N0*TNAL "EaN,Rawnt.aNo WEAN,GaNGF,aNO MEaN,RaNGF, ann (CON.RouTINEle LLD NO.' 0FTECTFn*e 37al NO. DFTECTE0ee NO. DETFCTEDe*

4 N8=95

( 3)

=1.0=100

( a.'s a 9.0)E 1

01

( a.a i 9.01E =1

( 2.8 a

.t)E =t

( 0)

( 2.7 =. 3.0)E -t

  • (

0/ t)e et 0/ 21e et 0/ 1)e AG=110Mt 3)

=1.0 100

( 9.5 A 5.0)E O

02

( t.1 i

.6)E I

( 4.1 a 7.3)E o

+

~

(-3.i -

ti.a)E O

( 0) e( 0/ 1)e et 0/ 2)e

  • (

0/ 13e RU=103 ( 11 8."

( t.0 g 9)E o 01

( t.0 i

.' 9 ) E o

(.6.7 a 10.53E -t I

( 0)

(=1.7

.a)E O

  • (

0/ the

  • (

0/

1)*

e( 0/ 2)e au-306 ( 32 s.0E*01 c.6;6 a 5.5)E 0

03

(=5.a i 5.5)E o

(=7.P &

2.03E o

~

( 0)

(=6.6 =

0.0)E O

(=9.9 0.03E O

=

e( 0/ lie et 0/ 1)e et 0/ 2)e

!=t31

( 31 5

( 3.3 a 3.A)E o

01

( 3.3 1 3.'8)E o

(=1.3 A 3.8)E O

( 0)

(=5.1 2) 5)E 2

O et 0/ 1)e et 0/ 1)e et 0/

C8=134 ( 33 9.'

(=9'9 a 62.53E =2 02

( 2.3 i 6.6)E -1

( t.2 a 1.'t)E =t 7 i

( 0)

(.9.9 -, 0.01E =2

( 6.9 - 234.0)E =3 y

e( 0/ 11e et 0/

1)*

  • (

0/

2)*

a C8=137 ( 3) 9.'

( 3.3 &

6)E o 02

( 4.0 i

.1)E t

( 3.1 &

8)E t

( 0) et 1/

1)*

et 2/

2)*

( 2.3 =

et 1/ t)e

. 4.0)E 1

(=l(7=

7a 1.7)E O

02

(=e.9 i 17.5)E -1

(.t.2 a 7)E O BAsta0 ( 3) 1.5E*01

(=1 0.0)E O

(.2.0

( 0) 0.0)E 0

=

  • (

0/ t)e e( 0/ 11e et 0/ 2)e CE=tal ( 3) 2.0 Ecol

(=a 't a te.3)E.t 01

( 2.1 1 1.3)E o

(-5.0 & 2065.0)E -3

~

g

(

0)

(.a.1 0.0)E.1

(.2.1 2.1)E O

=

  • (

0/ the et 0/

1)*

et 0/

2)*

CE=t84 ( 3) 8.0Ee01

(.5(3 a 4.01E o

02

( t.3 1 4.6)E o

(=1.0 &

2.3)E o

(

0)

(=5.3 -

0.01E o

(=3.3 -

1.3)F 0

  • (

0/ the e( 0/

1)*

et 0/ 21e i

l l

l N0=. ROUTINE pFFFRS TO THE NummER OF 3FpaRaTE wEaSUREMENTS wHICH *ERE GREATER THaN TF N (to) TIMES THE AVFRaGE RaCmGRnUNO F0W TkF PENIOn OF THE REPOWT ee THE FRACTTnN OF SAMPLE AN4(YSES YTELDING DJ TECTaBLE MEeSURENENT8 (f.E. >3STGual T9 INDICATFD wiTHIN *(

)*.

I

M M

W

..s a

s.

e s

SuwwaRV fos TMF PERIOD 1?/20/80 17/31/81

E DIUM MAPLE SYRUP tlNI T 5: PCI/ LITER QADIONUCL!nES INDICATna STAT!nNS MIGHEMT STATION CONTROL LnCATInks (NO. ANALYSES) NOMINAL MEsNeesNGE,akD MEAN,eANGF,AND MEAN,pahGE AND (NON. ROUTINE)e LLD No.' nETECTFnee STAl NO. DFTECTEDee NO. DETFCTEDee TM-228 (

31 1.0E*01

( e.'9 4 2.a)E O

03

( 9.5 1 2.3)E o

( 8.7 a 8)E o

( 01

( 8.0 9.5)E o

  • (

0/ t)e

  • (

1/ t)e et 1/ 2)e e

NON. ROUTINE REFERS TO THE NUuRER OF SEPARATE *EiSURFMENTS MHICM hERE GREATER THAN TEN (30) TIMES THE AVERAGE RACNGROUND FOR TME PERIOn OF THE REPORT

    • THE FRACTION OF SAMELE ANA(VSES TIELnING OFTECTiRLE MEA 8URE"ENTS (I.E. 333!GMA) T8 INDICATED MITHIN *(

je.

/

i f

u

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M I

i

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f e

9 I

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1

yanart kn.r stFrif fF FNV f DfjNWFNT al Qan]n(nr.TCal HO4TTODTNG M7/ng/75.

FaGF tm 17/31/st 9Uwwadv rne TwF PFRinn e7ppe/an MEDIU"3 "tth HNff9 DCf/LTTre CantnNOCLtqFS inn!CafnD 97s71043 HIGHE47 StaTinN C 04 7 R01 L ttr a T ION S (NO. AwaLV9FS) Nn"fN8L "FaNeDaNCE, ann wr a N, o a NGr.. a n n

= fan,sawGF,asn (NON.80HT1NE1 Lt D N O.' DE TEC TFnee

Sfa, Hn. DFTFCTEnee NO. nFTFCTEDee 83 39 ( 16) a.

( t.3 g

. air o nt f 1.6 i 6)E e

( B.1 a P.7)F 1

75.3)F 1

5.01F o

(.1.7

(

n)

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( t.0 ef 7/ Pa)e

  • (

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.(

3/ t?)*

33.en

( 36)

.a

( Ty0 A

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( 2.0 i 7)F 0 15.2)E o

( 1.2 3.3)F e

14.7)E o

( 5.a

(

01

( l.4 of 70/ 74)e of 12/ 17)*

ef 12/ 12)*

GF.7

( 37) m.nFe01

( m4 g it. ale.1 UP

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(.7.7 & 197.7)E.7

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et n/ 13)e et 0/ 12).

Wa40

( 37) 2.0F*07

( t.I3 A

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07 f 1.s i

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( t.4 A 01E 3

( 0)

( t.2 1.51E 3

f 1.7 1.53E 1

( t.3 1.a3F 3

  • (

75/ 75)e et 13/ 13).

  • (

12/ 121e 8 C#=51

( 37)

=1.n. ton

( 3.' 4 g to.7)F 1

11

( 3.5 1 21.9)F

.t

(.9.4 &

150.6)F.?

1.5)E t

(.9.2 7.9)E n

h$

(

0)

(.1J7 1

et 0/ P5ie

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et 0/ 121e KN.5e

( 37) e,

( 3.' m a 1.0)E 1

of f 7.5 1 2.2)E

.1

( t.7 &

t.5)F.1 4.8)F.t 7.7)F 0

f.5.A

=

(

n)

( t.9 of 0/ PS)*

  • (

0/ t?)*

  • (

0/ 12)*

C0=54 f 37) 8.'

( 1.' 9 &

tt.01E.2 C7

( 9.9 1 71.3)F -7

(.2.7 A P.t)F 1

0)F 0

(

n)

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ef 0/ 13)*

  • (

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( 37) 1.nFent

(.t.m g 7.7)F 1

03

( t.t i 8.5)E.1

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f n)

(. 3.' 3 -

7.n)F n

(.5.2 -

5,4)F 0

et n/ pste

  • (

n/ t?)e et n/ 12)e C0=60

( 17) 4

(.4.' 3 A 1.8)F 1

') 7 f 3.n i 2.a)F 1

c.4.0 g 1.0)F -l 7.n1F o

(.2.n.

8)F n

f

  • )

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n/ 13)e

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0/ 12)*

e MitP.unnf it F s'F ir r o g Til TH5 p-sswnF A 0F SFPsRATF >> anes 5'rkFNTS =Mirw orpr GREATEss f H a 'a Trh (to) Tf=rs THF aW5WaGF p a t e r,pquain F#'p T95 PFWinn nF THF prPnCT et THE FpaCTfnN HF 9a*PLF aNagvqrq vf FL n1Nr. OF Tt r f shi F >' E a 918Dr M F N T 4 (1 r.

> 1 M i r," a i 79 TWhtCATFn.fTwfH et

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wvv--

v.m-_- - vvvmrw m.. mvw-w vwr.ww mn-v,mur vr

,.mvwyvp3 -- a m,c. -

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M u== M op M PF6 E M /*" @ 17 g 1 g M

E g

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  • 04 7 7s, or i f tt TF w OaDIONurLieES TNnfrafno 9vaTinwa Hinwr97 statino r nN T o ne. toratins9 (NO, ANAL 79E9) NnM I N a t,

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( 37)

=t.o. Inn

( 6.2 1 7.615 1

 ?

f 0.7 1 3.0)F

.1

(.l.2 i a.9)F 1

(

n)

(-1.5 3.C)F o

( 2.2 1.0)F a

of 0/ 7%)*

et n/ 1T)e er o/ 12)*

20=45

( 37) i.nFent

( 4;5 g s.o)F.t 01

( a.9 1 3.7)E

.1 f.3.0 g o.1)F 1

(

0)

(*1.0 7.3)F 0

(=i.T 1.0)F n

  • (

0/ PS)*

  • (

n/ i?)*

et n/ 12)e RB.45

( 37) 1.a. inn

( 9lA g 14.n)F 7

07

( 7.6 i 2.5)E

=1

( 8.4 g 15.a)F 2

(

ni

(.i.3 2.aiF n

f.a.:

9 iiE.i et o/ 75)e

  • (

0/ i3)*

et 0/ 121e AG.iiON( 37)

=1.n. Inn

(.a.'O a i?.7)E.i 01

( P.6 i i.9)E o

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t.1)F 0

(

n)

(=1.2

. 1.7)F 1

f.o.3 7.1)F o

of 0/ 75)*

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of n/ 75).

et n/ i3).

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n / 12) e i

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n/ 17)*

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t

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( 37) 5

( a;2 i 7)E.7 c1

( 3.5 i 2.i)E.2

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a i

(

n)

(.3.i ii.a)E 7

27 a)F

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  • (

n/ 17)e

  • (

0/ 12)*

cs.i3a f 37) 9

(.6;5 a i.ait i

as

(.a.5 i n.3)E.i

(.a.5 a

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(

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9)E n

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of O/ 29)e

  • (

n/

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e(

0/ v2)e c8.i37 ( 37) 9

( i.' 3 A 7)E of f 2.1 i 3)E i

( 2.7 A

.a)F n

(

3)

( 3.a.

39.A)E o

( A.R 39.61F n

( 6.5 =

56 a)F.

et 75/ 79)e

  • (

12/ 17)*

  • (

io/ i2)*

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( s.6 A 1.1)F.i et

( 6.2 A 5.1)E

( 2.5 g e.11F.i

(

0)

(. 3.' O 4.5)F q

( i.7 3.3)F o

  • (

0/ 7%)e e(

0/ 12)*

  • (

0/ i21e e

NON.RnHTINF RFFFD9 TO TMF NitM R t p nF SFPARaTF "fa9tiGFMFNTS *HICH hFDF GDEATFS THa4 TE N (in) TIFFS THF avFua r,r naCuconUHn Fou THF PEWIhn nF THE uFonwT ee Twt F u a r t i riN pr sampt F a Nag v98 9 v f Ft nf eic nF TEr t e4s F MF ASUoFwFNTS (f.F.

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g str @ r M HaF M Pr' E d.fl M P.T h ;C O /93 g

g nFF F

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)

(NO, anal y SE S) NndINag wF a,y, p a NC F,3 NQ krgN,qgNpr,g%h MFAN,gg%gy,g%h

( NON. KNIT I **E )

  • Ltn
  • ' H. nrTrrTrnee S t a,'

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NH. OrTrcirnee cE. fat ( 37)

P.nfect

(.t.2 A 7.3)F 1

  • )
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r 2.3 g 4,n)r.,

(

9)

(.7.7

. 7.8)E 9

( 2.4 4.118 n

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4/ 7%)e e(

n/ 37)e of 0/ t?)e CE-taa ( 37) a.orent

( 9.;3 A A.o)F 1

Os f t.m i 1.5)E o

( t.A A 1.gir o

f n)

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1/ PS)e

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TH.224 ( 37) 1.0F*of f. m.' O A 5.a)E

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( a.9 i 7.?)E.1

( a.9 A 7.7)F 1

(

n)

(=5.0 4.4)E O

(-2.5 e.9)r n

et 0/ 25)e e(

o/ I?)*

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IV.

QUALITY ASSURANCE PROGRAM Three separate Quality Assurance programs were performed during 1981 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 determine 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 I

samples. The records of the quality control program are reviewed by the responsible cognizant engineer, 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.

EPA, Intralaboratory and Interlaboratory The Quality Assurance program implemented at the analytical laboratory indicated good precision and accuracy in reported values. Table 1 shows the results of accuracy and precision for laboratory analyses in 1981 for EPA samples, intralaboratory analyses and interlaboratory cross-check analyses.

For accuracy, 37.1 and 61.7 percent of the results were within 5 and 10 percent of the known values, respectively, with 93.7 percent of all results falling within the laboratory criteria of 15 percent. For precision, 70.6 and 88.4 percent of the results were within 5 and 10 percent of the mean, respectively, with 99.8 percent of all results meeting the laboratory criteria of 15 percent.

M M

M M

M M

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TABLE 1 EPA, Intralaboratory and Interlaboratory Results Accuracy Precision Total Number 0 to 5%

0 to 10%

0 to 15%*

Total Number 0 to 5%

0 to 10%

0 to 15%*

of Samples of Samples 472 175 291 443 405 286 358 404 (37.1%)

(61.7%)

(93.9%)

(70.6%)

(88.4%)

(99.8%)

  • This category also contains those samples having a verified zero concentration which were analyzed and found not to contain the isotope of interest.

I Blind Duplicate-Replicate Program A total of 76 paired samples were submitted for analysis during 1981.

The data base used for the duplicate-replicate analysis consisted of pair measurements of 26 gamma emitting nuclides, tritium, Strontium-89, Strontium-90, low level 1-131, gross beta and Radium-226. A dual level criteria for agreement was established if the paired measurements fall within

+ 15 percent of their average value, then agreement between the measurements I

has been met.

If the value falls outside of the + 15 percent, then a two sigma range (95 percent confidence level) for duplicates and a three sigma range 99 percent confidence level) for replicates is established for each of the analyses.

If the ranges overlap, agreement is obtained. Two thousand three hundred and twenty-six paired duplicate and replicate measurements were analyzed for 1981. A total of 98.8 percent of all measurements fell within the established criteria discussed above. Of the 1.2 percent of the measurements which fell outside of the criteria, most of these were made up of fallout and plant-related radionuclides contained in sediment sampics. Table 2 shows the results of some radionuclides measured in sediment samples during 1981. This table indicates that only man-made radionuclides fell outside of the criteria, and that the naturally occurring radionuclides K-40 and Th-228, which are normally evenly distributed in sediment, agree well.

Since K-40 and Th-228 show good agreement in sediment samples and other media and Co-60, Cs-134 and Cs-137 show good agreement in other media, the poor agreement in sediment can be at tributed to non-uniform distribution of man-made radionuclides in these samples, rather than poor precision in laboratory analysis.

I i

I I

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M E M W.i m N> p

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TABLE 2 Agreement of Radionuclides in Sediment Samples Lab Sample Numbers C27850 G27851 G27852 G27853 G23430 G23916 G23915 C23917 G23784 Nuclides G27867 G27868 G27869 G27870 G23914 G23931 G13932 G23933 G23804 Ce-141 20-6.5%

20' 20' 12%

20' 20r 2 0~

20-Ce-144 20-20 20' 20' 12%

20' 20' 10%

20' Cs-137 14%

11%

2%

2%

Cs-134 1.6%

20' 20' 30 8%

20' Co-60 30' 10%

6.2%

10%

4%

10%

15%

Th-228 30' 5.2%

20' 6.8%

9%

2%

4%

7%

8%

K-40 2.9%

1.5%

1.6%

1.9%

3%

1%

1%

1%

3%

  • Values outside 3 sigma level.

. E V.

Anf0SPilERIC FALLOUT DURING 1981 I

On October 17, 1980, the People's Republic of China detonated a nuclear device in the atmosphere at the Lop Nor test site in northwest China. The I

explosion was estimated by the Department of Energy to be in the 200 kilotons to one megaton yield range. The clouds of radioactive debris began drifting over the western part of the United States on October 19, 1980.

During the beginning of November,1980, increased airborne beta activity was detected at both indicator and control locations (Figure S).

The g

airborne beta activity continued to increase into 1981, and a gamma analysis N

of fourth quarter composite filters showed detectable concentrations of fission products which are associated with the October Chinese test (Figures 9 to 12). As expected, a significant increase in airborne gross beta activity was detected on air particulate filter samples submitted from all sampling locations during the first three quarters of 1981. The highest airborne gross beta activity occurred during the spring and summer months when the I

intermixing of the stratosphere and troposhere causes additional radioactive debris from weapon testing to be introduced into the troposhere (Figure 13).

For the first three quarters of 1981, gamma analysis performed quarterly on m

weekly composite air particulate filter samples showed detectable concentrations of fallout fission products related to the Chinese weapons test (Figures 14 to 20).

In addition to our required Technical Specification air sampling locations, an additional control air sampler was set up at our Environmental Laboratory in Westborough, Massachusetts. Air particulate samples analyzed f rom this location showed similar levels of fission products as the filter samples submitted from the environs of the Yankee plant ( Figure s 21 to 2 7).

i Fallout was also detected in other environmental media during 1981.

Aquatic and terrestrial vegetation samples collected from indicator and control locations showed fission products related to fallout from the Chinese weapons test.

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1980 Z VALUES INDICATE ACTIVITY NUMBERS OU7 SIDE THE RANGE OF THE PLOT STATION 01

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1980 Z VALUES INDICATE ACTIVITY NUMBERS OUTSIDE THE RANGE OF THE PLOT STATION 01

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1980 Z VALUES INDICATE ACTIVITY NUMBERS OUTSIDE THE RANGE OF THE PLOT STATION 01

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ANALYSIS OF E!!VIRONME!!TAL DATA The analysis of environmental data may be divided into three sections:

airborne radioactivity, waterborne radioactivity, and direct exposure measurements. A discussion of each environmental media within these sections will follow:

1.

Airborne I

a.

Air Particulate Air monitoring stations are established at a total of seven locations.

Five of these locations are indicator while the remaining two are control stations. Airborne particulates are collected by passing air through a fiber filter; these filters are collected weekly and held for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before being analyzed for gross beta activity to allow for the decay of radon and thoron daughter I

products. Weekly composite air filters f rom each location are analyzed quarterly for gamma emitting nuclides.

A significant increase in airborne gross beta activity was measured on all weekly air particulate filter samples submitted from indicator and control locations during the first three quarters of 1981 (Figure 13).

Camma analysis performed quarterly on weekly composite filters I

showed detectable concentrations of fission products in indicator and control station samples. The highest airborne gross beta and fission product activity occurred during the spring and summer months when intermixing of the stratosphere and troposhere takes place causing radioactive debris in the stratosphere from weapons testing to be introduced in the troposhere. An additional control air sampling location was set up at our Environmental Laboratory in Westborough, Massachusetts. Air particulate samples analyzed from this location showed detectable levels of fission products with activity I

concentrations which were not significantly different from the sampling locations around the Yankee plant.

g I

I During 1981 increased airborne gross beta and fission products activity detected in indicator and control air samples was due to fallout from weapons testing (see Section V).

I b.

Radiolodine I

lodine-131 activity was detected in a charcoal filter sample collected from station 7, an indicator station located 1.1 kilometers southwest of the plant, during the week of February 16, 1981. This activity was related to an I-131 release from the Yankee plant which I

occurred on February 17, 1981. The concentration of I-131 in the charcoal sample was 1.53 E-2 pCi/ cubic meter, and this concentration was used to calculate the radiation dose to the thyroid. Using the methodology in Regulatory Guide 1.109 and conservative assumptions, the thyroid dose to dif ferent age groups is shown in Table 3.

The radiation doses are small and below the limits of 10CFR Part 20.105 (Permissible Levels of Radiation in Unrestricted Areas). No other I-131 activity was detected in charcoal filter samples during 1981.

I c.

Milk Milk samples were collected and analyzed monthly for Sr-89, Sr-90, low level I-131 and gamma emitting radionuclides. During 1981, detectable levels of Sr-89 were measured in milk samples submitted from indicator and control locations during pasture season. This radionuclide was also detected in milk samples from three additional I

milk locations used in a special study. The Sr-89 activity is related to the Chinese weapons test discussed in Section V.

Detectable concentrations of Cs-137 and Sr-90 were measured in milk samples submitted from indicator and control locations. The mean concentration of Cs-137 and Sr-90 in milk samples from the indicator locations was greater by a factor of 4.8 and 2.3, respectively, than the control location. The higher concentrations in indicator samples has been noted for several years and is not related to Yankee's I

gaseous release (see Milk section of 1979 Annual Report).

i I

1 5

1 I

i 1

I Table 3 Thyroid Doses l

1 i

Age Group Thyroid Dose (mrem)

Adult 3.51E-3 Teen 4.31E-3 Child 4.39E-3 j

Infant 6.67E-3

I

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I lI I

I An in-depth study of Cs-137 and Sr-90 levels in the environment was started in May of 1981 and continued over a four-month period to identify the cause of different levels of Cs-137 and Sr-90 in milk.

The study included present milk sampling locations plus four additional farms.

In addition to collection and analysis of milk, cattle feed and vegetation samples, in situ soil analyses were carried out at six farms during 1981. The results of the gamma in situ analysis of soil showed that naturally occurring K-40, Th-228 I

and U-238 plus man-made Cs-137 and Nb-95 were detected at all farm locations. Zr-95 was also detected at three of these locations.

Nb-95 and Zr-95 concentrations were not statistically different between indicc. tor and control locations, and these radionuclides were related to the weapons fallout during 1981. Cs-137 was the only radionuclide that could be related to the operation of the plant, but I

the lack cf any other plant-related gamma emitting nuclides and the fact that Cs-137 concentrations at all farm locations were within the expected concentrations in soil due to weapons testing, indicate that I

the Cs-137 levels in milk were not related to the operation of the Yankee plant.

The special milk study showed that Cs-137 and Sr-90 concentrations in milk and vegetation varied f rom f arm to farm. The cattle feed samples collected f rom f arm locations showed Cs-137 and Sr-90 activity which ranged from 449 pCi/kg to below detectable levels and I

547 pCi/kg to 14 pCi/kg, respectively. The primary results f rom this sp cial study indicate that f arming practices (amount of vegetation and type of vegetation that cows are allowed to feed on) were the cause for large variations of Cs-137 and Sr-90 concentrations in milk. This can be further demonstrated by the f act that during 1981, Sr-89 activity due to f allout f rom weapons testing and which is assumed to be evenly distributed, was measured in indicator station milk samples by a factor of 1.7 higher than control locations.

I d.

Food and Ca rden Crops Sampics of food crops were collected at harvest time and analyzed for gamma emitting nuclides plus low level I-131.

Potassium 40, a I I

I naturally occurring radionuclide, was the only gamma emitter detected with activity concentrations greater than minimum detectable concentrations.

I e.

K1ple Syrup I

Samples of maple syrup were collected in March f rom one indicator and two control locations. Detectable concentrations of K-40, Th-228, I

and Cs-137 were measured in these samples.

Potassium 40 and Th-228 are both naturally occurrInt; radionuclides. The average concentration of Cs-137 measured in syrup from the control locations was a factor of 10 greater than the concentration detected in the indicator station sample. The Cs-137 activity in maple syrup is the result of fallout f rom nuclear weapons testing in the atmosphere.

I f.

Mixed Vegetation Mixed vegetation samples were collectec in May, August and !1ovember from six sampling locations. These vegetation samples consisted of mixed grass and were analyzed for gamma emitting nuclides.

Detectable concentrations of fission products (Zr-95, lib-95, Ru-103, Cs-137 ar.d Cc-144) were measured in samples submitted from indicator and control locations. The concentration of these radionuclide in indicator station sampics were not statistically different from the I

concentration measured in control station samples.

Since the above radionuclides were detected in control stations, and the fact that some of these fission products were not detected in Yankee gaseous releases indicate that the activity in mixed vegetation was related to fallout from weapons testing discussed in Section V.

Soil I

Soll analysis was performed at eleven soll sampling locations during the month of September.

In situ gamma spec t romet ry was used due to its convenient and efficient method of measuring radioactivity in the I I

I soil. This technique eliminates two problems which are present in normal soil core sampling analysis; (1) the non-representative nature of a single core soil sample from a given location, (2) relatively I

long counting time due to small volume of soil. The analytical methodology was based on HASL 258 (Reference 1).

In nearly all the analyses performed, over 95 percent of the exposure rate is attributed to naturally occurring K-40, Th-232 and U-238 (Table 4). The other main component of the exposure rate is from I

Cs-137 with values ranging from 0.1 pR per hour to 0.7 pR per hour (244 pCi/kg to 130 pCi/kg). Small concentrations of Zr-95 and Nb-95 were observed in the analysis and can be attributed to recent fallout I

discussed in Section V.

Cs-137 was present at all locations and Table 5 shows that the mean concentration at indicator stations was higher than the control stations. A student t-test was performed and the results showed that the average Cs-137 values were not statistically different at the 95% confidence level. The variation of Cs-137 concentration at different locations is due to variability I

in soil (pH conditions causing different scavenging effect), and different deposition of fallout. The lack of detection of plant-related radionuclides (Cs-134, Co-60) indicates that the Cs-137 is from fallout due to weapons testing.

In conclusion, the results in situ gamma ray spectrometry indicate that there is no detectable effect on the soil at offsite stations due to she operation of the Yankee plant.

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TABLE 4 Average Soil Exposure Rates Microrem/ Hour Nuclide Indicator Locations Control Locations Mean Range Mean Range U-238 1.00 + 0.21 0.78 to 1.39 1.20 + 0.27 1.01 to 1.40 Th-232 1.83 + 0.71 0.75 to 2.93 2.69 + 0.19 2.56 to 2.83 K-40 2.44 + 0.61 1.82 to 3.48 2.32 + 0.16 2.20 to 2.43 Cs-137 0.40 + 0.20 0.19 to 0.72 0.42 + 0.15 0.24 to 0.31 I

Nb-95 0.05 + 0.01 0.04 to 0.07 0.06 + 0.01 0.05 to 0.07 l

M M

M M

M ee M

M M

M M

M M

M M

M e

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TABLE 5 Average Soil Concentrations Nuclide Indicator Locations Control Locations Mean Range Mean Range U-238 (5.50 + 1.18) E + 2) (4.28 to 7.61) E + 2 (6.60 + 0.15) E + 2 (5.54 to 7.66) E + 2 Th-232 (6.49 + 2.53) E + 2) (2.66 to 10.39) E + 2 (9.56 + 0.66) E + 2 (9.09 + 10.02) E + 2 K-40 (1.36 + 0.33) E + 4)

(1.02 to 1.94) E + 4 (1.54 + 0.26) E + 4 (1.36 to 1.73) E + 4 Cs-137 (7.31 + 3.68) E + 2 (2.64 to 13.07) E + 2 (4.99 + 1.00) E + 2 (4.20 to 5.70) E + 2 Nb-95 (6.65 + 0.92) E + 1 (5.61 to 8.77) E + 1 (7.48 + 1.10) E + 1 (6.70 to 8.25) E + 1 1

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I 2.

Waterborne Pathway a.

River Water I

River water was collected and analyzed monthly from gross beta and gamma emitting nuclides. Tritium analyses were performed quarterly on monthly composite samples.

I During 1981, the average gross beta activity was similar at indicator I

and control locations, and there were no detectable concentrations of gamma emitting nuclides in river water samples. Detectable concentrations of 11-3 were measured in indicator station samples with an average concentration of 250 pCi per liter which approximates surface water 11-3 levels in the United States.

b.

Ground Water

. 5 Ground water saa:ples wem u ll :!M fr= two indicator locations and analyzed for gamma emitting nuclides and tritium activity. Station I

01, located on the plant site, showed a detectable level of Cs-137 in the February water sample. Resampling of the water indicated no detectable concentrations of gamma emitting nuclides. Since the February water sample was collected from the secondary chemistry laboratory, there was a strong possibility that the sample was contaminated. Tygon tubing, in which the February water samples were collected through, was analyzed, and the results showed detectable

=

concentrations of I-131 indicating contamination in this lab.

For the rest of 1981 all ground water samples were collected from the I

information center to avoid the possibility of contamination.

Elevated tritium levels were measured in samples submitted from station 02 (Sherman Spring) located 0.2 km west-northwest of the plant. This tritium activity does not correlate with present plant releases and the concentration has been constant over the last few

,I years. A new liner for the spent fuel pool was replaced and the tritium activity at station 02 will be monitored to see if this installation reduces the tritium levels.

I c.

Aquatic Vegetation I

Aquatic vegetation samples were collected in May and November from three sampling locations and analyzed for gamma emitters. Detectable levels of fission products (Zr-95, Nb-95, Ru-103, Cs-137, Ce-141 and Ce-144) were measured in samples from indicator and control locations. The radioactivity in aquatic vegetation was due to I

fallout measured in air particulate samples during the spring and summer months (see Section V).

d.

Fish Fish samples were collected from three sampling locations and analyzed for gamma emitting nuclides. The only radionuclides with detectable concentrations measured in fish samples were K-40, a naturally occurring radionuclide and Cs-137.

The average Cs-137 concentration in the control station sample showed higher levels than the indicator stations, indicating that the Cs-137 activity can be attributed to residual fallout from weapons testing.

c.

Sediment I

Sediment samples showed detectable levels of K-40, Th-228, Cs-137, Nb-95 and Co-60.

K-40 and Th-228 are naturally occurring radionuclides.

Cs-1?7 was measured at station 02, Sherman Pond, at a higher level than the control location. This, plus the presence of I

detectable levels of Co-60 at this location, indicates that thcae radionuclides were plant-related. Nb-95 was detected at both indicator and control locations and can be attributed to f allout from weapons testing discussed in Section V.

I Using Regulatory Guide 1.109, the radiation dose f rom shoreline I

sediment due to plant-related radionuclides was calculated. A total body dose of 0.02 mrem /yr was calculated to the maximum individual (teen) who would spend 67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> per year in this area.

This dose is only a small fraction of the 100 mrem per year received from background. The radiation is small and below the limits of 10 CFR I

-8 3-I

I Part 20.105 (Permissible Levels of Radiation in Unrestricted Areas.)

I 3.

Direct Radiation - TLD's I

Table 6 shows the yearly average exposure from direct gamma radiation in microrem per hour from twenty-three TLD stations located on and off the Yankee site. The 1981 data exhibits similar trends as in previous years.

I Direct gamma radiation is measured with CaSO :Dy TLD badges which 4

integrate the gamma radiation exposure over a period of one month. Yankee I

Atomic personnel prepare, distribute, measure and calibrate these dosimeters. To demonstrate validity in reported measurements, Yankee participted in the Environmental Dosimeter intercomparison project, our results were in good agreement for the last intercomparison program.

I Table 7 shows that the average exposure at indicator TLD stations located of fsite were below the average exposure at control stations indicating that there were no detectable levels of direct gamma radiation due to the operation of the plant.

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I TABLE 6 1981 Average TLD Exposure Microrem per hour I

GM 1 Zone I 9.6 G1 2 Zone I 8.7 GM 3 Zone I 8.6 G! 4 Zone I 8.7 I

GM 5 Zone I 10.8 GI 6 Zone I 8.4 GM 7 Zone I 8.2 I

GM 8 Zone I 9.3 GM 9 Zone I 8.8 GM 10 Zone I 8.3 GM 11 Zone I 9.2 I

GM 12 Zone I 9.3 GM 13 Restricted Area 19.7 GM 14 Restricted Area 23.7 I

GM 15 Restricted Area 21.9 GM 16 Restricted Area 27.3 GM 17 Restricted Area 22.8 I

GM 18 Restricted Area 32.8 GM 19 Restricted area 30.7 GM 20 Restricted Area 22.1 GM 21 Restricted Area 21.8 I

G! 22 Zone II 9.0 GM 23 Zone II 9.6 I

Zone I average

= 9.0 microrem per hour (excluding restricted a rea)

Zone II average

- 9.3 microrem per hour I

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E E

E E

M E

E E

E E

E E

TABLE 7 Offsite Environmenta1-Radiological Monitoring Summary of Analyses for the Period December 31, 1980 to December 31, 1981 TLD - Direct Radiation microrem per hour Lower Limit Indicator Restricted Highest Control Analyses of Stations Areas Station Station Perf ormed Detection (mean (mean (total number)

(LLD) range) range)

TLD (276) 0.3 mean + (9.0 + 1.2)

(24.7 + 11.6) 18 (32.8 + 8.4)

(9.3 + 0.8) sigma range (6.5 to 13.5)

(13.1 to 63.1)

(23.1 to 45.6) (8.1 to 10.9) l l

l

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I VII. ENVIRONMENTAL DOSIMETRY The mean concentration of radionuclides having activity concentrations greater than the lower limit of detection values in indicator and control station samples of air particulate filters, charcoal filters, drinking water, 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 I

Regulatory Guide 1.109 (October 1977). These usage factors are:

8000 M / year of inhaled air 370 liters / year of drinking water 7.9 Kg/ year of seafood 110 liters / year of milk 190 Kg/ year of food products The product of the mean radionuclide concentration and the usage f actor yields the yearly radionuclide intake. The dose was calculated by using the dose conversion factors contained in Regulatory Guide 1.109 (Reference 2). Iodine-131 doses to the thyroid were calculated separately from data of the sample media mentioned above.

In addition, external whole body doses were measured with TLD's placed in indicator and control stations.

Table 8 summarizes the environmental doses from mean radionuclide I

concentrations greater than MDC values in indicator and control station l'

samples. The whole body dose from ingestion in indicator locations is almost entirely due to contributions of Sr-90 in milk. As mentioned in the Milk section, this activity is not related to plant releases.

I Restricted area TLD values were not used since no individuals reside at the fenceline.

Indicator TLD measurements show that nearby residents did not receive any measurable external dose f rom plant operation.

In fact, the control locations TLD's measured a higher yearly external dose.

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i TABLE 8 IW Summary of Environmental Radiation Doses (mrem /yr)

J Sou rce Plant Environs

Background

l Inhalation 4.3 E-3 4.3 E-3 1

j Seafood 8.7 E-2 8.4 E-2 l

l Food Crops I

I Milk 4.3 1.2 i

i Water 0.2 l

l I-131 3.5 E-3**

l 5 TLD 78.8 81.5 l

TOTAL P3.4 82.8 i

I No control station j

Thyroid dose for 1-131 activity

      • No concentrations greater than MDL I

I I I

VIII. CofiCLUSI0t1 During 1981, our radiological environmental monitoring program conducted in the offsite environment of the Yankee plant showed that, in general, the major radionuclides measured in environmental media were the naturally occurring radionuclidas and fallout fission products from atmospheric weapons testing. There was no significant increase in radioactivity in the environment due to the operation of the Yankee plant.

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I IX. REFERENCES 1.

HASL-258, "In-Situ (Ge(Li)) and Na(TL) Gamma-Ray Spectrometry,"

I September, 1972.

2.

U.S. NRC Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Release of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I",

1977.

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