Text

Annual Radiological Environ Surveillance Rept for 1979
	ML19309D484
Person / Time
Site:	Yankee Rowe
Issue date:	03/28/1980
From:	; YANKEE ATOMIC ELECTRIC CO.
To:	;
Shared Package
ML19309D468	List: ML19309D464; ML19309D484;
References
	NUDOCS 8004100374
	Download: ML19309D484 (60)
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{{#Wiki_filter:. YANKEE ATOMIC ELECTRIC COMPANT ANNUAL RADIOLOGICAL ENVIR0h?! ENTAL SURVEILLANCE i i REPORT JANUARY 1, 1979 - DECEMBER 31, 1979 t \\ MARCH 28, 1980 Yankee Atomic Electric Company Environmental Engineering Office 25 Research Drive Westborough, Massachusetts 01581 \\ \\\\ s \\ 80 0x110 0 3 7 4

TABLE OF CONTENTS Page I. Introduction 1 II. Location of Sampling Stations 3 III. Summary of Environmental Data 13 IV. Quality Assurance of Environmental Data 35 V. Analysis of Environmental Data 36 VI. Environmental Dosimetry 49 VII. Conclusion 52 VIII. References 53 i

LIST OF TABLES Page

1. 1979 Average TLD Exposures 47

2. Summary of Environmental Radiation Doses 51 11

4 LIST OF FIGURES

Page,

1. Location of Plant 6

7

2. Site Topography 8

3. Scmpling Sites Close to Plant f

9-

4. Air Monitoring and TLD Sites 10

5. Water, Soil and Vegetation Sampling Sites 11

6. Aquatic Vegetation and Garden Vegetables Sampling Sites 12

7. Milk and Maple Syrup Sampling Sites

8. Gross Beta activity in A.P. Filters Stations 37

9. Cs-137 Activity in A.P. Filters 39 40

10. Ce-144 Activity in A.P. Filters 41

11. Be-7 Activity in A.P. Filters L

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I. INTRODUCTION This repcrt contains a summary and analysis of the radiological environmental _ data collected during 1979 by the Environmental Studies Laboratory of the Yankee Atomic Electric Company, Rowe, Massachusetts. Direct gamma radiation around the plant environs is measured with CaSo4:DY TLD badges. Yankee Rowe personnel prepare, distribute, measure and calibrete these dosimeters. All the environmental samples were processed by the Yankee Environmental Laboratory, located in Westborough, Ma ssachuse tts. Section II of this report contains~a list of all sampling stations used in 1979 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. 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 4 {' 1

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 Yankee Rowe are called " Indicator" or " Zone 1" stations. Distant stations, which are beyond plant influence are called " Control" or " Zone II" stations. 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 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 discusses the Quality Assurance Program. In the final sections, we analyze the results of our. efforts in 1979, calculate environmental radiation doses, and present our conclusions. l i 2 l l l l

4 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 C Charcoal air filters FD Farm crope. FI Finfish M Milk MS Maple syrup S Soil l SS Sediment VA Aquatic vegetation VT Terrestrial vegetation WD Storm drain water WG Fresh water WR River water 3-l-

L Direct Radiation - TLD Dosimeter Sites Sampling and Analysis Frequency - Monthly Zone I Distance (Km) Sample Station Lccations From Plant Azimuth CM 1 Furlon House 0.8 2320 GM 2 Observation Stand 0.5 3130 GM 3 Ford Hill Road 2.7 1520 GM 4 Harriman Station 3.2 3590 GM 5 Monroe Bridge 1.1 2360 GM 6 Readsboro Road Barrier 1.3 3550 GM 7 Whitingham Line 3.5 320 GM 8 Monroe Hill Barrier 1.8 1820 GM 9 Dunbar Brook 3.2 2160 GM 10 Cross Road 3.5 830 GM 11 Adams High Line 2.1 2890 GM 12 Readsboro, Vermont 5.5 344o CM 13 Restricted Area Fence 0.08 2550 GM 14 Restricted Area Fence 0.11 3000 GM 15 Restricted Area Fence 0.08 3450 GM 16 Restricted Area Fence 0.13 300 GM 17 Restricted Area Fence 0.14 700 GM 18 Restricted Area Fence 0.14 1150 GM 19 Restricted Area Fence 0.16 1400 GM 20 Restricted Area Fence 0.16 1600 GM 21 Restricted Area Fence 0.11 2050 Zone II GM 22 Heartwellville 12.6 3330 CM 23 Williamstown Substation 22.2 2650 l l l I 4

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III.

SUMMARY

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e t ee + + ee r4 et Me eb e 1 1 8 8 8 I I I I $ 1 0 I $ 1 I i 0 $ E s 00e I ww ww ww ww ww ww ww ww ww e =* E o 4 m.e 44 m em ON c -e o e.e

e. e.

N. N. >eOe N P. e e e e e o e e e e e e < ow I e e u w e= 6 m ed eP fe N ee f .e f .NM O =e O .e e e ce ee N e. -e e. Ouue e am m m e am W .J g w I = o E =s I e o e e e e e e a w .J w w e A e O

O I

el 3 .g l og g ee l es t ee l +e g el l +g t D aE e U

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l M P* O e&O P em O nmo e4e 4MO 4PO e@m ONO e

e o e o e e EwO l e o e e e o e o e e e c -e eN

4 e

OEE $ e =e >= m 44

- m P= e.e e

g i me l== == g e, a

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u u l l g== l l em e o

e. e.

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==**e me== e

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w D

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e Z

.e es aw m m sie Pr e m O N me Z > >=

- m

> w p. g e e e e me e o me e e e w E "a==. mouI

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== w O 4 P N ** se Pm me P*

- sie 4

www Je 1EE $ me

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a. m Z O es me e

i ef mM em ef fe @f ee Me fe wO* D' a E 1 1 4 8 8 I $ 0 1 0 1 0 0 0 0 I I I I 3w OOe I ewOE w e.

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=

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e

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= = =. M. O. 4 rw as .w 1 4o mo ee Ne eo eO e P. O e==== >e 0L ew>e e e e e o e e e e e

e e.

O em N== 0

== aw M. ao m> eouo Ne m

== zw I .e. M.e e e. woeE e e .e e o ee e e m = w e.e p es er e me g EO O es w s O O O O O O O O O E es e Z wm t= mO l N N N N N N N N N D w > e= g E e et t +4 9 el l el l +1 g el l el l +1 0 +1 3 E.a s = a<z w> ue

0 sa a

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e oJ

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== 0 i N N M N N M N P

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"* ** > *= s N

N Pe N N N N N N EZw

9 ed eJ ** $

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=

W W e w W em 15 L

e e ) i e t t a t .t l fN en - 4 0 $ K t e QOe a ww e .e Eo $ > ad O 4N 4

w I

e e U w a= l 4N QQU e w .J K w O E as s. M .J m w O a. e uaQ el I ** D as E u > at e j MfC EwO g

e e

== 0EE

- N U

u 4 ** st O.e e.

* = = e w-M ee 4

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e & W QN 1w9 N

1OE > me > as o= lt e 3 w wt a w n el Om i E w

O-l M Q **

ce zE N o >== wi E O as e i e E er 4

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N www J .J e3 EEE I E em E as p= { es e w 4 u% u et w w

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e as as t .A N W w e o= O ** o= EOU = we O mw O W o= as >Qw er 4Ioe C er D e .4 O as O t3== as== wt 9 MN ew a 1 >M E 9-0 0 w u e= O Ew QOe I wt at O E w&

== E o I ww u.J 4 E >= 4 Q 4

a E as w Mw 4 *wj
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' OE > w s= g >e a> wt u u ( f Pm as W

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E E el B N E >.A **

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fN >E w wK

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$ Z te. M

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=

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mo e

e .o. .e. w .J z w a .*e. .e - e. a w an e= m m m m m m m m m e u .J m w i 6 O =O i +0 4 +4 9 +1 1 +4 1 +8 0 +0 1 +t 1 +1 0 +1 1 O mZ i M

=*E e

M ** O

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====e

====,m

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==e. e w e= m em q O e w *= e= mm O

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== am m en e= =e Ze i eO Ne 4 N 4 em e = w P= 4 0 4 3w O% n= as O e

e e
e e

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w 6
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e N O P Z a= >=

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as >

2 w

e eaw

+t 6 +1 1 +8 +1 +1 +0 +0 +8 +6 Om I w

O i

= eO3 O g Ez i P= m

O P= m m o O

O N O N O c o N O P O n=== e E oe e o e o e e o e e e e e z e og me w O I Ne em 4 e M me Pm N m www eJ e IEZ

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=s =e

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e me em i==

E&E en em i es== e w me e se e e

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e. m Z km Z

l l l w O== O Zw OOe en E o Z w e.

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p. ag O e..

m en am e em an an en e am an a

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3. O m>

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zw I 4e O

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e. m.%

>a

= woe = ee4 OeO NeO ceO P* N O as @ O M. P= O O. m. O w E

=

0Ezo e e o e e e e e e e e e e. I w as o eE z

= c mm me 4e e -e r= e N

me 4& >I w wE se en me 0 em 1== l es l es l ee l l ee $ $== >= w >= w3 me es e me== 0

== en e me me e to me e es es e es me

me me e es en 4 O

,J ag O e6 > e a. u w E== en e E ad O em a== en 4 O N N se N se N N w >= me m .J E O O O O O O O w w u at 5 O 8 + 8 + 1 I w = 0 to Eo0 W W W w w w w ao== w E

e.J 0

N e O W O O Pm o o se E 4 w EJ l e e e e e o e e e w== O = 0 r3 O 8 N N m N 4 e N Z

== O m a E O Z >= eJ a= at > w u.J O

3 >= m a W

e e6== 0 O a w O www g an am e an an a e= an an a= =m am m en e a2m e M Q OeE 4 P ** FO PO PO PO PO Fo PO PQ 0

w Z

O se >== 8 ZIw e =4 w eJ.J >= 0 O o= &== u at 3 3 es== ee me

= =

en en

= =

es e== me me 3 om== so 3AO I E &4m i I"e a3 u 3 I e e O c c O e

e eK 9 O

c c c 4 4 O Ouu9 I e 0 t I e I g i tee au X Z t see l Z O w O Z m 3 E. a== es g a m w w w me me a 17

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~ NCN-80UTIME REFER 5 TO THE HUM 8ER OF SEPARATE MEASUREMENTS WHICH WERE GREATER THAN TEN (109 TIMES THE AVERAGE BACKGROUND FOR THE PERIOD OF THE REPORT

- THE FRACit0N OF 5 AMPLE ANALYSES YIELDING DETECTABLE HEASUREMENTS tl.E. >LLDI 15 INDICATED WITHIM *t ANC l*.

e A

6 NN mm OO 00

* =
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== at O ee Oc me .e c .* c N& O e.

a. e ee e

e e

w e e e e e e e e e e e e e e re ee eN P= O.e e u w=

N m ee.4 .* c me m Nc es a .e N e Oou o e me e o e e i e as

== m a en a= en m w .J Z w u w g >. N N N N N N N N N

J 3s

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e
e

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w N

M N P= se Z e= e=

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== == a=

== == =

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1

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== w O e ** mM P =* N N N www .J e. ZE E l

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*

en e

wer w w u% i DIJ

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E 0 **

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E as Z O e m

M3 e O at O O a= .J Q at== e. 9 N ee mM OO O as OO O =* O =e = = = *

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m em w as w g ee at O g Kw as

w g
N N P=

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e mee m

e a e e e e =

w I ee

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O e

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u. w O O

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e e e e o e e o e

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e e e
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e O

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wE 9 4 **

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Q v*

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sm a

= = - am== en m

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w Z 9 a, a==0 m a u u e u u I 1 I 32

VAN 3EE ROVE OFF5ITE En1180xNENial RADIOLOGICAL N3 nit 0 TING 00/03/10. PACE 23 12/31/79 SuMMAar F02 iME PERIOD 12/25/18 P10turs WATER - RIVER UNII58 PCI/ LITER acoltouCL10E5 IN0!CATOR STATIONS HIGHEST STATION CONidOL LOC ATION5 IMO. ANALY5ESI NOMINAL NEAN,RANCE,AND NEAN, RANGE,AND PEAN, RANGE,AND IMON-RCuilNEl* LLO NO. OETECTED** STA. NO. OETECTE0** NO. OEitCTE0** CR-8 f 398 .9 I 2.5 1 .2tE O 02 8 2.5 1 .2tE O t 2.5 g .30E o t 09 t 1.5 - 4.90E O ( 1.6 - 4.18E O I 1.4 - 4.18E O

t 26/ 261*
t 13/ 139'
t 13/ 131*

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t 0/ 265*
t 0/ 133*
t 0/ 139*

E-40 t 199 2.CE*02 t 4.8 1 24.01E -1 02 I S.1 1 3.18E O t 3.0 1 S.llE O t of t-3.0 - 3.SIE 1 t-3.7 - 2.8tE 1

t 0/ 268*
t 0/ 13le et 0/ 1350 Pa-54 4 398 8.

t S.8 1 19.3tE -2 03 1 1.5 1

2. 7 8 E -1 t-1.6 1 2.8tE -1 f 09 t-2.1 -

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t 0/ 26t*
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t 0/ 139' CG-$8 t 199 8.

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t 0/ 261*
t 0/ 131*
t 0/ 131*

IE-59 I 399 1.CE*01 ( 8.0 1 4.71E -1 02 I 9.6 1 8.S IE -1 t 2.1 2 6.35E -1 1 08 t-2.4 - 9.91E O t-2.9 - 4.28E O ld

t 0/ 269*
t 0/ 138*
t 0/ 130*

CD-to i 398 8. 1-3.9 1 2.18E -1 01 t-1.9 1 2.llE -1 1-1.9 1 2.18E -1 1.18E O 1 01 1-2.2 - 2.4tE O (-1.4

t 0/ 261*
t 0/ 1350
t 0/ 131*

2,N-6S I 399 4. I 6.7 1 4.2SE -1 03 1 1.4 1 .4tE O t-3.8 i $0.2lE -2 I Ol t-4.4 - 4.41E o t-2.4 - 4.SIE O

I 0/ 260*
t 0/ 138*
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t 0/ 269*

01 1398

t 0/ 131*

NCH-RouilNE REFERS TO THE NUMBER OF SEPARATE NEA5UREMENTS MHICH WERE GREATER THAM TEM (108 IINES THE AVERAGE B ACKGROUNO F OR THE PERl00 0F THE REPORT

- THE FRACTION CF 5 AMPLE ANALYSE 5 YIELOING DETECTABLE HEA5uREMENT5 II.E. >LLot 15 IMOICATED WITHIM
t ANO l'.

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as as 2
n

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O m

w a e e 8" i w w wwwl em .o e em a em .m m ein am am = ma e em agg e 24 em O V. L 5 9O 90 9O OO 9O 7O 90 90 9O NO I as w EZw e K as

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m.e I l G g 3 8 m I O QUuG e 9 w me Z E l 3 3 e e e as w w I l a m-w I e a v v e w w 1 l 34

~ IV. 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 determine the cause of the problem and corrective measures are taken. YEL maintains an intralaboratory quality control program to assure a 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 engineer, and corrective measures are taken whenever applicable. Samples are prepared from split or homedenous media and sent to-the laboratory for analysis. The resulta from this blind duplicate program are used to' check for precision in laboratory analyses. l l l 35 1

V. ANALYSIS OF ENVIR0hMENTAL DATA The analysia 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 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 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 8 shows the weekly concentration of gross beta activity during 1979. The behavior of gross beta activity for indicator and control stations are similar. The annual mean gross beta activity for indicator stations were not significantly different from the mean for control stations. Concentrations of Cs-137 and Ce-144 greater than LLD were detected in quarterly composite samples of indicator and control stations 1 5 36

f hh) (ANKEL R0WE GR-B RIR PARTICULATE Figure 8 7. 5 0 E - 0 2 -- f S.00E-02 5 f1 f, 4.50E-02 _ ~ \\ \\ 1 b ,/ 1 y \\ A, t 4 } \\ \\ ll ,/f g 3 3.00E-02 ;

If il

'~\\ ,% h Q 'l p, s L' l } '\\f ,~ A /5 [

1. 50L x b

~ 0. m m i n ;i n i o s o ; o o o n i p ui o o igi n i u sii p i o n ej o o o o ig ni o o o j o o o o ig o o n i o gi n i n i o l o io o g JGN. fEB. t1 R R. APR. t14Y JUNE JULY RUG. SEP. OCT. NOV-DEC. 1979 Z VALUES IN0iCGTE ACTIVITY Nut 1BERS OUTSIDE THE RANGE OF THE PLOT ' Z STATION 05 = + STRTION 06 =X STATI0tl 02 = X STATION 03 = X STRTION 04 = SIRT10fl 07 =0 ~

during 1979. This activity was primarily due to the intermixing of the upper and lower atmosphere during the spring and summer months. Figures 9 and 10 show the concentration of Cs-137 and Ce-144 activity in Zone I and Zone II stations which demonstrate this seasonal trend. Figure 11, a plot of BE-7 activity, shows this same seasonal trend. Bery11uin 7 is produced in the ionosphere and settles out as natural fallout. b. Radioiodine Charcoal filters from seven air sampler stations were collected and analyzed for I-131 activity. DurinF 1979, all I-131 activity in the charcoal filters were below the lower limit of detection. c. Milk Milk was collected and analyzed monthly for Sr-89, Sr-90 and gamma emitting nuclides. During 1979, there were concentrations of Sr-89 reported above the LLD value from indicator stations. As H recommended by a NRC Branch Technical Position (Reference 2), the LLD was calculated as an a priori estimate which is dependent on the instruments background and detection efficiency. For Sr-89 calculations the a priori estimate does not account for the interference of Sr-90 activity and therefore does not reflect realistic detection capabilities. Since Sr-90 activity was approximately a factor of 3 greater at indicator stations, you would expect greater interference from the Sr-90 in these samples. Fur the rmore, the total gaseous release of the Sr-89 from Yankee 5 38 g

e t i' t l ,l [ g i i X i. n C = i E i D i S i i O i i. i N i V O i O I =_ i N i T g T A i O T L S = . T P . C + i.O i E : i H i T 9 i. 4 i e i P F 0 i r i g . E O u . S i N F g E O i G I N T A A .G R T .U . A S E g H Z n T E iY T iL E R nU D oJ 3 L I i 0 0 U g T C i 7 S - 9 N i E U I i 1 O T i N O i I R i U T A . J S i A P i R T g i E S R i 8 1 XB I . Y t R . 4 = u N 7 i 1 u1 3 g Y i 2 7 1 T 0 0 n. I i R V S N N C . A T O O i P I 1 I I g A T T i C i A A i i. i R E T T i R T S S i i i 1 A X0 t i C g

i D I / N . B 6 E I 1 . E 0 0 W 1 . F 0 i E N N S R j i i U O O L i. L I I E i N A T T i t i A V A A r i N i J T T H i Z S S ( . - : ~ ..___: ~

:._~

1. 3 4 4 4 0 0 0 0 ' 0 E E E E E 0 0 0 0 0 5 0 0 2 0 1 9 S 3 0 1 2s oc i w

l [ Figure 10 ( 6'J rt E f R0hE C f. - 14 4 AIR FARTICULATE 7.50f. 6% h b$.t (i. 00E -01 i ^ V g[ 'iy;.~ b hjk .t. L G E. - 0 3 - Wi vq;y, E 7 Nf k' / L ',x ~ d 1.00E-03i s I' ~# / N / '\\

1. 5G L -01 i

// f E O. E .... o.ui.o n..og.. o.o..g..o.n ogo,.n oign oin og. o.o..guin o og...n o..g.o.,o..g.......og o. . iig JAN. fE6. (1 A R. R Pii. t1R Y JUNE JULY AUG. SEP. OCT. NOV. DEC. 1979 Z V6 LUES INDICATE Af flVITY tJUMBERS OUTSIDE THE RANGE OF THE PLOT STATION 01 = X STATION 02 = X STATI0tJ 03 =Z STATION 04 = + STATION 05 =X STATION 06 =0 S7AT10tJ 07 = PJ I

Figure 11 (h'MEl. ROWE BE-7 AIR PRRTICULATE 3. 01 E -0 2 - M@> d5 i dn:) cz. 7.51E-02i "g Nm Q:f%?, @iA v., 4. S.01E-02i [p i g 23 e/ g 3 4.61E-02-{ s ~ ) -s u 3.01E-02i ~ 1.51E-02 mTrm i i n u n u i p i u n i n g i o i o n i s p o i o n i p i n i i i n p i o n i n p o i n n i g u u u i p i n i u p o u u u p u i i n i i g JAN. FEB. t14R. APR. t1 A Y JUNE JULY AUG. St.P. OCT. NOV. O E.C. 1970 Z VALUES INDICATE ACTIVITY Nul1BERC OUTSIDE THE RANGE OF THE PLOT STATION 01

X STATION 02

= X STATION 03 = Z ST ATION 04 = + STATION 05 =X STATION 06 =0 STATION 07

UJ l

Rowe during 1979 was 0.635 ACi. Using the methodology in Regulatory Cuide 1.109 (Reference 3) and the annual average D/Q at the nearest milk stations, the expected Sr-89 concentration in milk is several orders of magnitude smaller than the concentration of Sr-89 measured at this station. Strontium 90 and Cs-137 were detected in milk samples from indicator and control stations. The mean concentration of Sr-90 and Cs-137 in milk from indicator station samples were greater than the average of control station samples. This higher activity in indicator milk samples has been noted for several years, and is not related to plant gaseous releases. The total gaseous release of Sr-90 and Cs-137 during 1979 from Yankee Rowe were 0.230 A4Ci and 7.30 4C1, respectively. Using the methodology in U.S. NRC Regulatory Guide 1.109 and the annual average deposition at Station TM-01, the expected Sr-90 and Cs-137 is several orders of magnitude smaller than the concentration measured in milk. The cause of the higher Sr-90 and Cs-137 concentrations in milk will be looked into during 4 the next year. d. Food and Garden Crops -Leafy vegetation samples submitted to the Environmental Laboratory on september 20, 1979 contained concentrations of I-131. This i activity was present in both indicator and control station samples. A recount of the vegetation samples confirmed the I-131 activity in these samples. The total release of I-131 in the third quarter t l s ( 42 l

of 1979 from Yankee Rowe was 31.7s%Ci. Using the annual average D/Q from the closest vegetation station, located 2.9 km south of the plant, and the methodology in Regulatory Guide 1.109, the I-131 activity is several orders of magnitude lower than the reported I-131 concentration at this location. A plant release was unlikely due to the fact that Williamstown, located 20.9 km west-southwest of the plant, had the highest concentration of I-131, furthermore, charcoal filter for this time period had normal background readings. A replicate sample was submitted with the leafy vegetation samples, when the I-131 activity of this sample was statistically compared to its counterpart, it fell outside of our criteria used for precision. The cause can be attributed to either a lack of precision in the analysis, or can indicate that the activity in the samples was acquired after collection. Since the chemical and counting techniques, plus the counting equipment calibration and efficiencies were checked ard were found to be performing properly. The results seem to indicate that the I-131 activity in leafy vegetation samples were acquired after collection. e. Terrestrial Vegetation Vegetation samples were collected and analyzed in May, August and November from six sample locations. These vegetation samples consisted of mixed grass and were analyzed for gamma emitting i i nuclidas. Potassium 40 and Th-228, both naturally occurring l l nuclides plus EE-1 and Cs-137 were detected in both indicator and 43

e control station samples. The Ca-137 mean concentration in control station samples was slighltly higher than the concentration in indicator station samples. Cattle feed was collected in September and analyzed for Sr-89, Sr-90 and gamma emitting nuclides. As in the milk samples, Sr-89 concentrations were greater than LLD values. This was due to the underestimation of LLD values on Sr-89 calculations (see explanation in milk section). Sr-90 concentrations were detected in both indicator and control station samples. The concentration of Sr-90 in indicator stations showed a higher mean concentration and the cause of this activity will be looked into during the next year. f. Maple Syrup Three samples of maple syrup were collected from one indicator and two control locations during 1979. The concentration of radionuclides in the indicator station was not significantly different than the concentrations in the control station samples. Strontium-89 values in both indicator and control locations were greater than the LLD values. This was due to the underestimation of the LLD values as explained in the milk section. 2. Waterborne Pathway a. River Water Tritium was the only radionuclide detected in river water with l t h 4 I 44 L

concentrations greater than LLD. Two out of the four samples submitted from station 03, located 6.3 km downstream of the plant, had activity concentration greater than LLD. Samples from station WR-02, located in the area of the plant discharge, showed no concentrations of tritium greater than LLD values. b. Ground Water Ground water samples were collected monthly from two stations located on the Yankee Rowe site. A sample submitted on March 5 from station WG-01 had low concentrations of Cs-137 and Cs-134. The activity in this sample was recounted and confirmed, since no other ground water samples analyzed during 1979 showed any concentrations of gamma emitting nuclides. We feel that the activity in this sample was acquired after collection. c. _ Aquatic Vegetation Aquatic vegetation samples were collected in May and November from a one control and two indicator stations. Concentrations of radicnuclides in samples from indicator stations with values greater than LLD were not statistically different from the samples collected at the control station. d. Fish The only radionuclides detected above the lower limit of detection in fish samples during 1979 were K-40 and Cs-137. Potassium 40 is a naturally occurring radionuclide and is not plant related, 45

4 The Cs-137 mean concentration was greater in the control station. e. Sediment Concentrations of Cs-137 above the lower limit of detection were detected in all sediment samples submitted from indicator and control locations. Harriman Reservoir, a control station, located 10 km upstream from the plant, had the highest concentrations of Cs-137. Co-60 concentrations were detected in cediment samples from Sherman Pond. In 1977, this station exhibited elevated concentration of Co-60 and the activity is probably due to residual activity noted in the 1977 samples.' 3. Direct Radiation - TLD's Table 1 shows the yearly average exposure from direct gamma radiation in microrem per hour from twenty-three TLD stations located on and off the Yankee Rowe site. Zone I stations (not including TLD's posted 4 on the security fence) exhibited radiation exposures which range from 5.2 to 12.0 microrem per hour. This compares favorably to the 5.6 to 11.8 microrem per hour recorded at Zone II stations. Zone II stations had a higher average exposure rate than Zone I stations. (security fence TLD's excluded). 1 46

e Table 1 1979 Average TLD Exposure Microrem per hour GM 1 Zone I 9.5 4 GM 2 Zone I 8.2 GM 3 Zone 1 8.2 GM 4 Zone 1 8.0 GM 5 Zone I 10.6 GM 6 Zone 1 7.6 GM 7 Zone I 8.4 GM 8 Zone I 8.6 GM 9 Zone I 8.2 GM 10 Zone I 7.0 GM 11 Zone 1 8.8 GM 12 Zone I 8.8 GM 13 Restricted Area 20.3 GM 14 Restricted Area 14.7 GM 15 Restricted Area 14.4 GM 16 Restricted Area 18.5 GM 17 Restricted Area 16.4 GM 18 Restricted Area 28.9 GM 19 Restricted area 26.5 GM 20 Restricted Area 20.2 GM 21 Restricted Area 21.1 GM 22 Zone II 9.7 GM 23 Zone II 9.' ione I er? rage = 8.5 (excluding restricted area) Zone II average = 9.7 l I 47

Offsite Environmental Radiologiesl Monitoring Summary of Analyses for the Peried January 2, 1979 to December 31, 1979 TLD - Direct Radiation microrem per hour Lower Limit All Indicator Highest Cantrol Analyses of Stations Station Station Perfo rmed Dctection (mean (mean (mean (total number) (LLD) range) range) range) TLD (274) 0.3 (13.5) 18(28.9) (9.7) (5.2 to 32.0) (24.6 to 32.0) (5.6 to 11.8) 1 6 i e k l l-48 [.

e e IV. ENVIRONMENTAL DOSIMETRY The mean concentration of radionuclides having activity concentrations greater than the lower limit of detection values in indicator and cuntrol 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 Regulatory Guide 1.109 (October 1977). These usage factors are: 3 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 factor yields the yearly radionuclide intake. The dose was calculated by using the dose conversion factors contained in Regulatory Guide 1.109. 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 2 summarizes the environmental doses from mean radionuclide concentrations greater than LLD values in indicator and control station samples. The dose from environmental media is almost entirely due to the '-131 activity detected in leafy vegetation samples. As mentioned in the i i 49

e food crop section, this activity was believed to be acquired after sample collection. 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 from plant operation. In fact, the control locations TLD's measured an 11 arem per year higher external dose. s i 50 L. m

e se e Table 2 Summary of Environmental Radiation Domes (arem/yr) Source Plant Environs

Background

Inhalation 9.7 E-4 1.0 E-3 Seafood 9.0 E-2 9.5 E-2 Food Crops Milk 1.7 0.7 Water 0.2 I-131 5.6 ** 8.7 ** TLD 74 85 TOTAL 82 95 No control station Thyroid Dose for I-131 activity

- - No concentrations greater than LLD.

l I 51 u-

0 a VII. CONCLUSION During 1979, our radiological environmental monitoring program conducted in the environs of Yankee Rowe showed, in general, that the major radionuclides measured in the environments were naturally occurring and the natural external dose measured in TLD's was greater than any contribution from the plant. 52

e 4 ,*C VIII. REFERENCES 1. U.S. NRC Regulatory Guide 4.8, " Environmental Technical Specifications for Nuclear Power Plants", 1975. 2. U.S. NRC Branch Technical Position, "Ar: /.tcepta' ole Radiological Environmental Monitorirg Prograu", Juif P>/9. 3. U.S. NRC Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Release of Reactor Ef fluents for the Purpose of Evaluating Compliance with 10CPR50, Appendix 7.",1977. 9 I 53 ._}}

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