Text

Annual Radiological Environ Monitoring Rept 1989
	ML20034C791
Person / Time
Site:	Maine Yankee
Issue date:	12/31/1989
From:	; YANKEE ATOMIC ELECTRIC CO.
To:	;
Shared Package
ML20034C661	List: ML20034C660; ML20034C791;
References
	NUDOCS 9005140230
	Download: ML20034C791 (73)
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MAINE YANKEE ATOMIC POWER' STATION

. ANNUAL' RADIOLOGICAL' ENVIRONMENTAL MONITORING REPORT

?t

. January - December 1989-4 I s

I April 1990:

I I

Prepared By:

Yankee Atomic Electric Company Environmental Engineering' Department I

580 Main Street Bolton, Massachusetts 01740 I

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4 9005140230 900427 I

DR ADOCM 050 3 9.

s.

(T

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EXECUTIVE

SUMMARY

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During 1989, as in all previous years of plant operation, a program was

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conducted to assess the levels of radiation or radioactivity in the Maine L

Yankee environment. Over 700 samples were collected (including TLDs) over the i

I course of the year, with a total of over 2,600 radionuclide or exposure rate analyses being performed on them. The samples included ground water, estuary watcr, sediment, marine algae, fish, mussels, crabs, lobsters, grass, and j

milk.

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

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. Low levels of radioactivity from three sources were detected. Most samples had measureable levels of K-40, Be-7, Th-232,..or Radon daughter products.

These'are the most common of the naturally-occurring radionuclides..Many samples (milk and sediment in particular) had fallout radioactivity from atmospheric nuclear weapons tests conducted primarily from the late 1950's through 1980, or from fallout originating at'the Chernobyl plant in 1986.

Several samples had low levels of radioactivity resulting from emissions from I

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

In all cases, the possible radiological impact was negligible with respect to exposure from natural background radiation..In no case did the detected levels approach or exceed the most restrictive federal' regulatory or plant license limits for radionuclides in the environment.

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TABLE OF CONTENTS

~

IAEA

-b EXECUT IV E S U!91ARY.................................................

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

iv i

~ LIST OF_ FIGURES...................................................

V 1;0 INTRODUCTION......................................................

1-2.0-RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE PROGRAM...................

2

'l 3.0

SUMMARY

OF RADIOLOGICAL ENVIRONMENTAL DATA'...................~......

12.

I e

3.1 -Air Particulate.............................................

~14 3.2 Charcoal Filter........'........'.............................

.18

-3.3 Mi1k............................

20 3.4' Mixed Vegetation............................................

25 3.5 Food Crop...................................................-

28 i

I 3.6 Groundwater............

-29L j

3.7 Estuary Water..............................................'.

32 3.8 Marine A1gae................................................

3.9 Sediment....................................................

_35 l

-38 1

3.10 Fish........................................................

42-3.11 Mussels.....................................................-

-45 3.12. Crustaceans.....................................'.............

48-i 3.13 Direct Radiation............................................

51 t

4.0 QUALITY ASSURANCE PR0 GRAM.........................

61 5.0 LAND USE CENSUS...................................................-

64 6.0

SUMMARY

AND CONCLUSIONS...........................................

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7.0 REFERENCES

67 i

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i n

1 43.

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m LIST OF TARLES E-Number Title

.EASA 2.1-

. Radiological Environmental Surveillance Program.............

3 2.2 Radiological-Environmental Surveillance Locations.~..........

4 3.1 Environmental Direct Radiation Measurements....s.............

54

~ 4.1 EPA Interlaboratory and Intralaboratory Results..............

63

-5.1' 1989 Land Use Census Results................................

65

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LIST _.0F FIGURES F-Number T1 tie Ea&R L

2.1 Environmental Radiological Sampling Locations Within One Kilometer of Maine Yankee.......'........................

6 2.2 Environmental Radiological Sampling Locations Within 1

12 Kilometers of Maine Yankee...............................

7 2.3

~ Environmental Radiological Sampling Locations Outside 1<

12 Kilometers of Maine Yankee...............................

8 i

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2.4 Direct Radiation _ Monitoring Locations Within 1 Kilometer i

of Maine Yankee.............................................-

9 2.5 Direct Radiation Monitoring Locations Within 12~ Kilometers of Maine Yankee.............................................,

10 1

2.6 Direct Radiation Monitoring Locations outside 12 Kilometers-i Of Maine Yankee.............................................

11

~i 3.1 Gross-Beta Measurements of Air Particulate Filters..........

_15-3.2 Cesium-137 in M11k....................................,.....

21 3.3 Strontium-90 in M11k........................................

22 1

1 3.4 Cesium-137 in Sediment......................................

39 i

3.5 Exposure Rate at Inner Ring TLDs, TL 01-06..................

54 I

3.6 Exposure Rate at Inner Ring TLDs, TL 07-10, 12-13...........

55 j

3.7 Exposure Rate at Inner Ring TLDs, TL 14-19..................

56-l 1'

i 3.8 Exposure Rate at Guter Ring TLDs, TL 11, 20-24..............

57

]

3.9 Exposure Rate at Outer Ring TLDs, TL 25-30...............e...

58 3.10 Exposure Rate at Outer Ring TLDs, TL 31-35..................

59 3.11 Exposure Rate at Control TLDs, TL 36-38.....................

60 i

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1.0 INTRODUCTION

The Radiological Environmental Surveillance Program at'the Maine Yankee

~

4 Atomic Power Station has been designed and' carried out with-specific objectives in mind.-- They are-as followst g.

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To provide an early indication of the appearance or' accumulation of'any radioactive material in the environment caused by the operation'of the nuclear power station.-

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To provide assurance to regulatory agencies and the public that?

the station's environmental-' impact is known and within' anticipated limits.

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i To verify the adequacy and proper functioning of station effluent j

controle and monitoring systems.

To provide standby monitoring capability for rapid assessment of risk to the general public in the event-of unanticipated or accidental releases.of radioactive material.

'l During 1989, as in the past, the Environmental Services Laboratory I

(ESL) staff collected all environmental samples and processed all l

environmental thermoluminescent dosimeters'(TLDs)'for direct radiation I

measurements. After the initial processing, all non-TLD.sairples were sent to the Yankee Atomic Environmental Laboratory for further processing and

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radionuclide analysis.

This report is a summary of the-findings of the Radiological i

Environmental Surveillance Program for 1989.

It is being provided in

~ compliance with plant Technical Specification 5.9.1.5.

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2.0 RADIOLOGICAL ENVIRONMENTAL SURVEfLLANCE PROGRAM

.)

7 In this section, Table 2.1 outlines the surveillance program as k

required by plant Technical Specification 4.8.

Table 2.2 lists the sampling stations and their specific locations (distances are measured from the center i

of the Containment Building).

The sampling locations are shown on the maps in' Figures-2.1 through 2.6.

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4, Table 2 d s-Radiolonical Environmental Survalliance Program-g Maine Yankee Atomic Power Station.,

y Media

.Sampline-Frequency

' Required Analyses Air Particulate (AP)

Weekly Gross-beta l

Quarterly Composite Gamma spectroscopy Charcoal Filter (CF)

Weekly I-131 l

,.I Milk (TM)-

sMonthly Gamma spectroscopy, I-131

~

Annually (Harvest)

Gamma spectroscopy, Food Crop (TF)*

I-131-Groundwater (WG)**

Quarterly H-3, gamma spectroscopy l

Estuary Water-(WE)-

Monthly Composite Gamma spectroscopy.

Quarterly Composite H-3 1

Sediment (SE)

Semiannually Gamma spectroscopy Fish and Invertebrates Semiannually or in Gamma spectroscopy-(FH, MU, CA, HA)

Season' Direct Radiation (TL)

- Quarterly Integrated gamma dose 1

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~* Performed only if milk sampling is not done.

Groundwater samples shall be taken when this source is tapped for drinking-or irrigation purposes in areas where hydraulic gradient or recharge properties are suitable for contamination.

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I Table 2.2 Radiological Environmental Surveillance Locations i

Maine Yankee Atomic Power Station I

Distance Station. Code Zone ** or From Plant Direction (Media - Sta. N d Station Description ILD_ Ring ***

(km)

From Plant

AP/CF-11 Montsweag Brook

~ 1

'O.6 NE 1.

2.7 NW

AP/CF-13

' Bailey Farm I

Mason Steam Station 1

4.8 NNE

AP/CF-14 j

AP/CF-16 Westport Firehouse 1

1.8 S

AP/CF-29 Dresden Substation 2

19.8 N

IN-16 Baker Farm 1

7.2 W

IN-17 Leeman Farm 1

7.9 SW

IN-25 Hanson Farm 2

16.0 W

TG-11 Bailey Farm 1

0.6 NE

WG-13 Bailey Farm 1

0.6 NE

WG-24 Morse Well 2

9.8 W

I

WE-12 Plant Outfall 1

0.3 SW

WE-20 Kennebec River 2

9.8 SW j

i AL-11 Long Ledge 1

0.8 S

AL-19 Long Ledge 1

0.8 S

AL-24 Sheepscot River.

2 11;2 S

1 AL-29 Maine Yankee Dock 1

On-Site

SE-16 Old Outfall Area

'l 0.4 SW

SE-18 Foxbird Island 1

0.7 S

i

Fh/MU/CA/HA-11 Long Ledge Area 1

1.1 S

FH/MU/CA/HA-24 Sheepscot River 2

11.2 S

I

TL-1 Old Ferry Rd.

I 1.0 N

TL-2 Old Ferry Rd.

I 0.8-NNE

TL-3 Bailey House I

0.6 NE-

TL-4 Westport Island, Rt. 144 I

1.2 ENE-

-j

TL-5 MY Information Center I

0.2 E

TL-6 Rt. 144 and Greenleaf 1'.

I 0.9 E

TL-7 Westport: Island, Rt. 14;.

I 0.8 ESE-

TL-8 MY Screenhouse.

I 0.2 SE

TL-9 Westport Island, Rt. 144 I-0.9 SE

TL-10 Bailey Point I

0.4

.SSE-

TL-11 Mason Steam S6ation 0

4.8

'NNE

TL-12 Westport Firehouse I

1.8 S

i WPP12/27 i

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Table 2.2 (Continued)

Radiological Environmental Surveillance Locations Maine Yankee Atomic Power Station Distance Station Code..

Zone ** or From Plant Direction i

(Media - Sta. End Station Description, TLD Rine***

(km)

'from Plant-

TL-13 Foxbird Island-I 0.4 SSW I

TL-14 Eaton Farm I

0.8 SW-

TL-15 Eaton Farm I

0.8

. WSW

TL-16 Eaton Farm-I 0.7 W

I

TL-17 Eaton Farm Rd.-

_I 0.6 WNW

TL-18 Eaton' Farm Rd.

I 0.8 NW1

TL-19 Eaton Farm Rd.

I 0.9

NNW

TL-20 Bradford-Rd., Wiscasset 0

6.5 N

I

TL-21 Federal St., Wiscasset O'

7.2 NNE

TL-22 Cochran ha.,-Edgecomb 0

8.3 NE

TL-23 Middle Rd., Edgecomb' 0

7.0

.ENE I

TL-24

_ River Rd., Edgecomb-0 7.8 E

TL River Rd., and Rt. 27 0

7.5 ESE I

TL-26 Rt. 27 and Boothbay RR 0

7.8 SE-1 Museum

TL-27 Barters. Island 0-7.0 SSE

-j

TL-28 Westport Island, Rt.1144, 0_

7.7 S

i and East Shore Rd.

I

TL-29 Harrison's Trailer 0

.6.3 SSW

TL-30=

Leeman Farm, Woolwich-0 7.6-SW

- i

TL-31 Barley Neck.Rd., Woolwich 0

'6.7 WSW i

I

TL-32 Baker Farm, Woolwich 0

7.2 W

l

TL-33 Rt. 127, Woolwich 0

7.3' WNW'

TL-34

.Rt. 127. Woolwich 0

,7.9' NW

TL-35 Rt. 127, Dresden 0

9.1 NNW I

TL-36 Boothbay Harbor Fire 2

11.4-SSE j

Station 1

TL-37 Bath Fire Station 2

10.4 WSW

TL-38 Dresden Substation 2

19.8 N

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Listed in the Off-Site Dose Calculation Manual, Table 4.1.

- Zone 1 = Indicator Stations; Zone 2 = Control Stations.

- - I'= Inner Ring Stations; O = Outer Ring Stations; 2 = Control Stations.

i 1 WPP12/27

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V -13 AP/CF 13 I

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AL 29 l

(11TLE OAK ISLAM' l

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thTAKE'

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015 CHARGE FOREBAY

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AL-11/19

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U 100 200 300 O!5 CHARGE AREA (DIFFUSER) l L

llA-ll g.yg g FHll@

CA-11 Q,

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Figure.2.1 Environmental Radiological Sampling Locations Within 1 Kilometer of Haine Yankee,

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A I LOMr.Ti.ne.

f' WlSCA55(1 o :

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' Sit istARctHENT IN TIGURE: t.1

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'M 1 trW Figure 2.2 Environmental Radiological Sampling Locations Within 12 Kilometers of Maine Yankee ^

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Figure 2.3 Environmental Radiological Sampling Locations Outside 12 Kilometers from Maine Yankee i,

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TL-19 @

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I@ TL 3 TL 18 $

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.. :X -

I TL 17. @!

,I-TL-S t!TTLE OAA: ISLAND l

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TL 8 TL k3 f

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@ TL 15 g

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100, 200 300 (DIFrUSER)

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Figure 2.4 Direct Radiation Honitoring Locations

-l Within 1 kilometer of Maine Yankee l I

1

ps4 N

ggg, 4

4 n-5

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EILnHETERS I

L'

@ TL 35 k

. h :

l TL 21 @'

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TL 22,h I

TL 20 @ISCA SET ' e :

W

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@ TL 34

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TL-ll

@ TL 23

=\\

l TL-33 $ SEC ENL.ARCCMENT IN

'URE t.4 f

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..1 TL 2 s j

NEQUASSET LAKE

.s t

p p

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TLdf e [DGCCOMB-g

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TL 24 h,,1,

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c, TL 32 @

h I

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' { $ TL-31.

p

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TL 37 4

TL 2s @

WOOL CH g.

BATH t-e.:j:

L 28 r.'. ?.

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Figure 2.5 Direct Radiation Monitoring Locations j

Within 12 Kilometers of Maine Yankee _

C.ARDINTR e e ktdatHRf'H.

b h

pm a R1 CHM &OND a

g

$tt CNLARCCMENT Ik flGV

5

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35Wl(M-9.

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f, h... -

A ATL AVTIC CEAW.

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0 10 20

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EILOMETERS 5".

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I Figure 2.6 Direct Radiation Monitoring Locations Outside 12 Kilometers from Maine Yankee j..l

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300

SUMMARY

OF'RADIOLQQICAL ENVIRONMENTAL DATA I

The following pages summarize the analytical results of the environmental samples which were collected during 1989.. Each environmental

,~

media category is presented as a separate subsection. A discussion of the sampling program and results is followed by a table which summarizes the year's data for each category.. At the top of each table are listed the units of measurement for each medium.

The~1 eft hand column contains the radionuclide which is being reported, total ~ number of analyses of that radionuclide, and the number of measurements which exceeds ten times the yearly average background value. The latter are classified as "nonroutine" i

measurements..The next column lists the Lower Limit of Detection (LLD) for 1

those radionuclides which have detection capability requirements as specified in the plant Radiological Effluent Technical Specifications (Table 4.8-2).

(Guidance is not given for many of the radionuclides routinely measured and reported herein.)

Those sampling stations which are adjacent t'o 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.

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influence are called " control" or " Zone. II" stations.

Direct radiation monitoring locations are broken down into inner ring, outer ring, and control (Zone II) stations.

A set of statistical parameters is calculated 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, g

the following is calculated:

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

o The standard error of the mean.

I

~ ' - " ' - ' " ' ' " " ' " - " - * " "

- WPP12/27 i

o Th2 number of positive m nsuram2nts-(sctivity which is thres,timas greater than the standard deviation) divided by the total number e

of measurements.

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Each single radioactivity measurement datum in this report is-based on a single measurement and is reported as a concentration plus or minus a one standard deviation uncertainty. The qucted uncertainty term represents only the random uncertainty associated with the radioactive decay process (counting statistics), and not the propagation of all possible uncertainties in the analytical procedure. Radioactivity is considered to be present in a sample when the concentration exceeds three times its associated standard deviation.

With respect to the plots, all values less than three standard deviations.

(i.e., those where no activity was detected) were plotted as zero.

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.3.1 Air Particulate 4

Air monitoring stations are established at a total of five 4

locations. Four of these locations are indicators, while the remaining ~one is a control station.. The air pumps at these

(

-locations operate continuously at a flow rate of approximately 1.5 cubic feet per minute. Airborne particulates are collected by passing the air through a' fiber f11ter. These f11ters are-collected weekly and,.following a radiological field' check at the-Maine Yankee Environmental Services 1.aboratory, are held for at I

least 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months before being analyzed for gross-beta act.ivity (indicated as GR-B in tables)-to allow for the decay of radon and j

. eekly composite air filters from each thoron daughter products.

W location are analyzed quarterly for gamma emitting radionuclides.

l Gross-beta measurements (Figure 3.1) show similar-environmentally-induced fluctuations throughout much rf the year.

at all sampling locations including controls, thereby indicating that any plant contribution is. negligible. Naturally occurring Be-7-was also detected in all samples.

[

l The following air particulate and charcoal filter sampling intervals were interrupted in 1989:

a.

Between March 10 and 17, the sampling pun.p broke down at AP/CF-14.

It was replaced on March 17.-

j b.

Between November 24 and December 1, 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months were lost at

. 1 AP/CF-11 due to a power outage.

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-15 I

' ENVIRONMENTAL' RADIOLOGICAL PROGRAM

SUMMARY

MAINE TAWKEE ATOMIC POWER STATION, WISCA$$ET, NE (JANUART DECEMBER 1969)

MEDIUMt AIR PARTICULATE UNITS PCl/CU. M INDICATOR STAtl0N5 STAfl0N WITH HIGNEST MEAN CONTROL STATIONS l

RADIONUCLIDES MEAN MEAN MEAN I

(NO. ANALT$[S) REQUIRED RANGE' STA.

RANGE RANGE (NDN ROUTlWE)*

LLD NO DETECTED" N0.

No. DETECTED **-

No. DETECTED **

GR B (265)

.01

(

2.0 s 0.1)E 2 13 (

2.1 :

0.1)E 2

(

2.1 0.1)E 2

( 0)

(

4.0 - 57.5)E 3

(

6.6 - 53.4)E 3

(

6.4 - 53.6)E 3

(212/212)*

( 53/ 53)*

( 53/ $3)*

BE 7 ( 20)

(-

4.6 s 0.1)E 2 13 (

4.9 s 0.4)E*2

(

4.6 :~

~0.2)E 2

( 0)

(

4.0

6.1)E 2

(

4.2

6.1)E 2

(

4.2 5.0)E *2 1

( 16/ 16)*

(

4/- 4)*.

(

4/ 4)*

MN 54 ( 20)

(

3.5 s 5.5)E +5 14 (

2.2 s 1.1)E 4

(

7.0 4.3)E 5

( 0)

(

2.5 -

5.3)E 4

(

6.9 - 52.7)E 5

(

4.1 -

16.8)E 5

(

0/ 16)*

(

0/ 4)*

(

0/ 4)*

W CO 58 ( 20)

(

3.5 a 4.9)E 5 -

14 (

6.8 s 10.5)E ~5

(

8.9 a 17.3)E 5

( 0)

(

3.3

3.8)E 4

(

8.6 -

37.9)E '5

(

2.8 -

2.7)E 4

(

0/ 16)*

(

0/ 4)* -

(

0/ 4)*

FE 59 ( 20)

(

4.4 s - 15.1)E 5 14

(

4.7 s 1.5)E 4

(

1.3 1.9)E 4

( 0)

(

1.2 -

0.8)E 3

(.

4.5 -

71.9)E 5

(

3.9 -

5,0)E 4 i

~

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0/ 16)*

(.

0/ 4)*

(

0/ 4)'

Co 60 ( 20)

(

4.9 :

5.1)E 5 13' (

5.2 15.4)E 5

(

6.3 17.4)E 5 -

( 0)

(

3.9

4.9)E 4

(

1.9 -

4.9)E 4

(

3.7 -

2.6)E 4

(

0/ 16)*

(

0/ 4)*

(

0/ 4)*

ZN 65 ( 20)

(

1.4 s 1.4)E 4 29 (

4.7 s 0.5)E 4

(

4.7

-0.5)E 4

( 0)

(

7.2 -

15.0)E 4

(

3.5 -

5.5)E 4

(

3.5 -

5.5)E 4

(

0/ 16)*-

(

0/ 4)*

(

0/ 4)*

SE 75 ( 20)

(

3.9 6.9)E' 5 13 (

6.6 :

14.8)E 5

(

4.1 8.5)E 5 I

.(

0)

(

5.6 -

3.5)E 4

(

-3.0 -

3.5)E 4

(

2.0 -

1.6)E 4

.('- 0/ 16)*

(

0/

4)*'

(

0/ 4)*

2R 95 ( 20) -

(

9.1 11.6)E 5 11

(

4.0 s 2.0)E 4

(

1.9

31.5)E 5 I

( 0)

(

6.6 -

8.5)V 4

(

8.2 -

84.9)E 5

(

8.1 -

7.3)E 4

(

0/ 16)*

(

0/ 4)*

(

0/ 4)*

NON ROUTINE REFERS TO THE NUMBER OF SEPARATE MEASUREMENTS WHICH WERE GREATER p

THAN TEN (10) TIMES THE AVERAGE BACKGROUND FOR THE PERIOD OF THE REPORT.

]

THE FRACTION OF SAMPLE ANALYSES Y!ELDING DETECTABLE MEASU P ENTS (1.E. >3 STD DEVIATIONS) !S INDICATED WITH *(

)*.

\\ I

ENVIRONMENTAL RADIDLOGICAL PROGRAM SUMNARY MAINE YANKEE ATOM!C POWER STAfl0N, WISCASSET, NE (JANUARY DECEMBER 1989)

/

j-MEDIUM: AIR PARTICULATE UNITS: PCl/CU. M INDICATOR STATIONS STAfl0N WITH HIGNEST MEAN CONTROL STAfl0NS RADIONUCLIDES MAN MEAN MEAN (NO. ANALYSES) REQUIRED RANGE STA..

RANGE RANGE (NON ROUTlWE)*

LLD No. DETECTED **

NO.

No. DETECTED" No. DETECTED"

{

AG 110Mt 20)'

(

2.6 e 79.8)E 6 29 (

6.7

3.1)E 5-(. 6.7 a 3.1)E 5

( 0)

(

5.9 -

5.4)E 4

(

2.4 -

12.0)E 5

(

2.4 - -12.0)E 5

(

0/ 16)*

(

0/ 4)*

(

0/ 4)*

RU 103 ( 20)

(

3.8 5.4)E 5 13 (

1.8 a 1.3)E 4

(

9.0 a 86.3)E 6

( 0) -

(

4.6

5.2)E 4

( + 8.5. - 52.5)E 5 - (

2.0 -

2.2)E 4

(

0/ 16)*

( = 0/ 4)*

(

0/ 4)*

RU 106 ( 20)

(

3.5 s 5.3)E 4 13 (

1.1 :

0.4)E +3

(

7.7 a 3.7)E.4

( 0)

(

3.6 -

4.2)E. 3-(

2.0 - 21.1)E 4

(

0.0 -

1.6)E 3

(

0/ 16)*

(

0/ 4)*

(

0/ 4)*

$8 124 ( 20)

(

9.2 :

17.7)E 5 13 - (

1.4 s 4.3)E 4

(-

1.4 s ~

1.7)E 4

( 0)

(

9.7 -

13.6)E 4

(

5.1 -

13.1)E 4-(

2.4-5.5)E 4 1

(

0/ 16)*

(

0/ 4)*

(

0/ 4)*

CS 134 ( 20)

.05

(

9.7 6.9)E 5 it

(

8.5 s 14.7)E 5

(

2.0 s -

0.5)E -4

( 0)

(

6.5

4.1)E 4

(

2.8 -

3.7)E 4

(

2.8 -

0.4)E 4 q

(

0/ 16)*

(

0/ 4)*

(

0/' 4)*

CS 137 ( 20)

.06

(

7.4 s 6.0)E 5 11

(-

2.0 s 1.1)E 4

(

-1.7 a 1.5)E 4

( 0)

(

4.7 -

4.8)E -4

(

1.9

48.4)E 5

(

1.1 -

5.1)E 4

(

0/ 16)*

(~

0/ 4)*

(

0/. 4)*

BA 140 ( 20)

.(

1.5 s 1.7)E 4 13 ( '3.7 3.6)E 4

(

4.0 s 1.6)E 4

( 0)

(

1.7 -

1.3)E 3

(

3.8 -

13.3)E 4

(

7.9 -

'O.0)E 4

(

0/ 16)*

(

0/ 4)*

(

0/ 4)*

CE 141 ( 20)

(

4.1

6.6)E 5 13

(

1.0 s 1.0)E -4

(

3.8 s 8.4)E 5

( 0)

(

6.0 -

3.7)E 4

(

1.0 -

3.1)E P4

(

2.1 -

'1.7)E 4

(

0/ 16)*

(

0/ 4)*

(.0/ 4)*

CE 144 ( 20)

(

2.2 a 1.4)E 4 14

(

1.6 s 38.0)E 5

(

2.6 e 70.6)E 5

~ !

( 0)

(

1.1 -

0.8)E 3

(

1.0 -

0.8)E 3

(

-1.9 -. 1.2)E 3

(

0/ 16)*

(

0/ 4)*

(

0/ 4)*

NON ROUTINE REFERS To THE NUMBER OF SEPARATE MEASUREMENTS WHICH WERE GREATER THAN TEN (10) TIMES THE AVERAGE BACKGROUND FOR THE PERIOD OF THE REPORT.

i

- - THE FRACTION OF SAMPLE ANALYSES YIELDING DETECTABLE MEASUREMENTS (1.E. >3 STD DEVIATIONS) l$ INDICATED WITH *(

)*..l

3.2-Charcoal Filters-r Charcoal. filter. cartridges are situated in series with-the air particulate fiber filters. Monitoring stations are located at a J

total of five stations, four of which are indicators and one of which is a control. The mir pumps at-these locations operate l

continuously at a flow rate of approximately one cubic foot per minute.

I Charcoal filters from the five air sampling stations were-l g

collected and. analyzed weekly for I-131 activity. No I-131 was=

W

. detected.

i

-Two sample intervals were interrupted.during 1989 and are discussed in Section 3.1, Air Particulate'.

I a

i I

~

i I

1 t

l 1

)

WPP12/27 l

ENVIRONMENTAL RADIOLOGICAL PROGRAM SUPMARY -

MAlWE YANKEE ATOMIC POWER STATION, WISCASSET, ME (JANUARY

DECEMBER 1999)~

MEDIUM: CHARCOAL FILTER UNITS: PCl/CU. M INDICATOR STAtl0NS STAfl0N WITN WlGNEST MEAN CONTROL STAfl0NS j

eeeeeeeeeeeeeeeeee e eeeeeeeeeeeseeeeeeeeee.

. eeeeeeeeeeeeee RADIONUCLIDES MEAN MEAN MEAN (NO. ANALYSES) REQUIRED RANGE' STA.

RANGE RANGE (NON* ROUTINE)*

LLD No. DETECTED **

NO.

No. DETECTED **

NO. DETECTED **

_4 I

1*131~(265)

.07

-(

2.9 s 5.2)E +4 11

(

6.1 A 10.1)E +4

(

1.7 a 1.1)E +3 i

( 0)

(

+2.9.-

1.9)E 2

(

1.6 -

1.7)E +2-(

2.0

1.5)E +2

(

0/212)*

(

0/ 53)*

(

0/ 53)*

{

'I NON* ROUTINE REFERS TO THE NUMBER OF SEPARATE MEARUREMENTS WHICH WERE GREATER TNAN TEN (10) TIMES THE AVERAGE SACKGROUND FOR THE PERIOD OF THE REPORT.

- THE FRACTION OF SAMPLE ANALYSES YlELDING DETECTABLE MEASUREMENTS (1.E. >3 STD DEVIATIONS) IS INDICATED WITH *(

)*.

I i

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-3. 3 till k 8

Milk samples were collected and analyzed monthly for. low level' I-131 and gamma-emitting radionuclidea. Sr-89 and Sr-90 analyses, I

not. required by Technical Specifications, were done on quarterly.

composites.

As.in previous' years,' detectable concentrations of Cs-137 and Sr-90 were measured in milk samples submitted from the indicator j

and control locations.

(See Figures 3.2 and-3.3.) These levels were similar to those in past' years and, as discussed in previous 1 reports, may be attributed to fallout from nuclear weapons tests conducted primarily by the Peoples' Republic of China (the last

_]

I a

test was in 1980). The relatively high levels of Os 137 and Sr-90' at the Leeman Farm were noted in 1980 and 1981 during a special study, and in later years when sampling was resumed'there. These are also attributed-to fallout <from nuclear weapons. tests.

It'has l

also been shown in previous reports that' farming practices (amount j

of vegetation and type of vegetation-that the cows-are allowed to

- l feed on) were the cause for the large variations ~of Os-137 and-Sr-90 concentrations in milk from farm to farm particularly during j

the pasture season. The input of additional Cs-137 into'the-milki I

pathway due to the Chernobyl accident in May of 1986 raised levels j

somewhat in milk.

I i

Naturally-occurring K-40 was'also detected in all milk samples.-

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(NVIRONMEOTAL kAD10 LOGICAL #ff) JAM SLDWRY MAINE YANKEt ATONIC PNFR $1Atl0N, WISCAt$tt, ME (JANUARY

DECEMDER 1989) 1 NEDIUM: NILK UNifSt PCl/KO 3

I n

INDICATOR 81Atl0NS

$1Afl0N W!!N MlWNttf MEAN CONTROL $1All0NS

- - - - eeeeeee,*eeee

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(ND. ANALYttS) ht0UlktD kAWot RfA.

AMGE kAN0t (NON.R0utlNt)*

LLD No. DtittilD**

No.

NO. DtitCitD**

NO. DtittitD**

1.......................

St.89 ( 12)

(

1.5 e 2.1)E.1 25 (

4.8 e 2.4)t 1

(

4.8 s 2.4)(.1

( 0)

(

+6.6 9.3)E.1

(

1.T +

9.3)t.1 -

(

1.7 +

9.3)t.1

( 0/ 8)*

(

0/ 4)*

(

0/ 4)*

St.90 ( 12)

(

9.7 a 0.8)E O 16 (

1.0 a 0.1)E 1

(

4.8 e 0.2)E O g 0)

(

5.6 11.6)E 0

(

9.3 +

11.6)t 0

(

4.5 5.3)t 10

( 4/ 8)*

(

4/ 4)*

(

4/ 4)*

l l

K 40 ( 36)

(

1.1 s 0.0)E 3 25 (

1.3 a 0.0)t 3

(

1.3 a 0.0)t 3 l

( 0)

(

7.7 13.7)E 2

(

1.0 -

1.4)t 3

(

1.0 -

1.4)E 3 jI

( 24/ 24)*

( 12/ 12)*

( 12/ 12)*

NN.54. V. J

(

7.6 a 206.5)E.3 16 (

4.4 s 2.3)E.1

(

1.7 a 3.2)E.1

( 0)

(

2.0 -

1.9)E O

(

4.6 18.5)E 1

(

1.9 1.7)E O

(

0/ 24)*

(

0/ 12)*

(

0/ 12)*

CD 58 ( 36)

(

3.1 2.4)t 1 17 (

3.3 s 3.6)t.1

(

7,0 a 3.1)E.1

( 0)

(

1.8 2.5)E D

(

.i.6 2.3)E D

(

2.9 -

0.7)E O

(

0/ 24)*

(

0/ 12)*

(

0/ 12)*-

7E.59 ( 36)

(

1.4 a 0.6)E O 16 (

i.7 0.9)E 0

(

2.0 s 6.13t 1 l

( 0)

(

3.8 6.4)E O

(

+3.8 7.3)E O

(

3.3 6.6)E O

(

0/ 24)*

(

0/ 12)*

(

0/ 12)*

Co 60 ( 36)

(

5.0 e 2.2)E.1 16 (

2.5 a 3.1)E 1

(

5.6 4.1)E.1

( 0)

(

2.8 -

2.6)E D

(

1.5 -

2.6)E D

(

3.1 1.7)E O

(

0/ 24)*

(

0/ 12)*

(. 0/ 12)*

2W.65 ( 36)

(

2.5 a 6.1)E.1 16 (

7.9 t 7.9)E.1

('.5.6 e 7.5)t.1

( 0)

(

6.9 -

5.5)E O

(

4.0 5.5)E O

(

5.2 -

3.1)E O

(

0/ 24)*

(

0/ 12)*

(

0/ 12)*

2R 95= ( 36)

(

4.8 s 3.9)E 1 17 (

9.1 a 6.4)t.1

(

T8:

7.3)E.1

( 0)

( 4.6 -

5.5)E 0

(

2.4 -

5.5)E 0'

(

4.7 4.8)E O

(

0/ 24)*

(

0/ 12)*

(

0/ 12).

NON.ROuilNE REFER $ TO THE MUMBER OF SEPARATE MEA 80ntMEWit WAICN WEtt CREATER INM TEN (10) f!Mtt THE AVERAGE BACKGROUND FOR THE PERIOD OF THE REPORT.

THE FRACil0N OF $ AMPLE ANALYSES YlELDING DtitCTABLE MEA'UREMEN18 S

(1.E. e3 STD DEVIATIONS) l$ INDICAftD WifH *(

)*. = i

,J l

4 fNVIRONMENTAL R210 LOGICAL PROGRAM SIAguRT MAINE TANKit ATONIC POWER $fAfl0N, WISCA$$ti, NE (JANUART

DECEMttR 1999)

MEDIUN MILE UNITS: PCl/KG INDICATOR STAfl0NS STAfl0N WITH MlbNilf MEAN CONTROL STAfl0NS ee***ee.ooe**eeeee eeeeeeeeeeeeeeeeeeee eeeee eeeeeeeeeeeeeee.

RADIONUCLlDE$

MtAN MtAN MtAN (NO. ANALYttl) RfeUIRED RANet STA.

kANGE RANGE (NON ROUTINE)*

LLD NO. DtitCitD**

N0.

No. DtTECitD**

'NO. DtittitD'*

RU*iO3 ( 36)

(

2.5 a 2.5)t 1 16 (

5.9 41.1)t 2

(

6.2 a 3.0)E +1

( 0)

(

2.7

2.3)t 0

(

2.F -

2.3 )E 0

(

2.0

2.1)t 0

(

0/ 24)*

(

0/ 12)*

(

0/ 12)*

RU 106 ( 36)

(

1,4 s 2.2)t 0 25 (

4.3 3.2)E O

(

4.3 3.2)t 0

( 0)

(

2.5 -

1.7)t 1

(

2.4

1.9)t 1

(

2.4 -

1.9)E 1

(

0/ 24)*

(

0/ 12)*

st 0/ 12)*

$8 124 ( 36)

(

1.7 :

0,4)E O 25 (

4.1 :

7.3)E *1

(

4.1 s 7.3)E 1 l

( 0)

(

5.6 -

2.1)E O

(

3.7 4.7)E O

(

3.7

4.7)E 0

(

0/ 24)*

(

0/ 12)*

(

0/ 12)*

3+131 ( 36) 1.0

(

9.1 s 15.1)t +3 16 (

1.7 s 2.8)t *2

(

1.7 s 1.8)E 2

( 0)

(

i.8

1.2)t +1

( + 1. 8 +

1.2)E +1

(

1.2 -

1.4)E *1

(

0/ 24)*

(

0/ 12)*

(

0/ 12)*

CS 134 ( 36) 15.

(

+9.4 1.8)E *1 25 (

+6.1 4.0)E 1

(

+6.1 4.0)E at t 0)

(

2.5 +

0.9)E O

(

3.5 -

1.4)E 0

(

3.5 -

1.4)E O

(

0/ 24)*

(

0/ 12)*

(

0/ 12)*

C$*137 ( 36) 18.

i 7.8 0.8)t 0 16 (

9.3 1.0)E 0

(

5.9 1.2)E 0

( 0)

(

2.2 -

15.3)E O

(

5.4 -

15.3)E D

(

1.7 - 155.0)E *1

( 20/ 24)*

( 12/ 12)*

(

8/ 12)*

SA 140 ( 36) 15.

(

2.7 5.5)E *1 17 (

7.7 :

4.7)E *1

(

6.3 :

6.4)E..)

i

( 0)

(

3.5

2.8)E 0

(

1.4

2.8)E 0

(

+3.1 +

4.0)E 0

(

0/ 24)*

(

0/ 12)*

(

0/ 12)*

CE 141 ( 36)

(

+2.6 4.7)E *1 17 (

2.9 s 5.8)E 1

(

8.7 :

T3.2)E 2

( 0)

(

5.7 -

3.8)E 0

(

2.9 -

3.8)E 0

(

3.7 -

3.8)E O

(

0/ 24)*

(

0/ 12)*

(

0/ 12)*

CE 144 ( 36)

(

5.8 a 14.2)E 1 16 (

6.2 s 21.2)E 1

(

4.2 a 1.8)E O

( 0)

(

1.2 1.1)E 1

(

9.7 -

10.6)E O

(

1.5 -

0.6)E 1 g-v

(

0/ 24)*

(

0/ 12)*

(

0/ 12)*

J t

NON ROUTINE REFER $ TO THE BAmstR Of SEPARATE MEASUREMENTS WHICH WERE GREATER TNAN TEN (10) TIMES THE AvtRAGE SACKGROUND FOR THE PERIOD OF THE REPORT.

THE FRACTION OF $ AMPLE ANALY$t$ YltLDING DEf tCTAtti MEASUREMENT $ '

(1.E. >3 STD DEVIAfl0NS) 18 INDICAftD WITM *(

)*.

l

-24

- i

.=

s 304 Mixed venetation s

Though not required by plant Technical Specifications, mixed

\\

vegetation samples were collected in June and September from TG-11. The vegetation consisted of various types of grasses and were analyzed for gamma emitting radionuclides. Only naturally occurring Be-7 and K-40 were detected in the samples.

L i

~ ~

WPP12/27

g s

ENVIRONMENTAL RADIOLOGICAL PROGRAM SWMARY MAINE TANKit ATONIC POWtt STAfl0N, WISCAS$tt, ML (JANUART DECtMDER 1999)

MCDIUNI MINED VEGETAfl0N UNIT $t PCl/KG W(T INDICATOR STATTON$

$ FAT 10M WITH 111GNtti NE,N CONTA0L $ TAT 10Ns nuquesesnneee unseseneeveneesenne nennnenens RADIONUCLIDt$

NEAN MEAu MEAN (No. ANALYl(5) Rt0UlktD kANGE STA.

RANCE RANGE (NON ROUTINE)*

LLD N0. DETECitD**

Mo.

20. DtitCit0 "

NO. DtitCTED" et*7 ( 2)

(

1.5 0.9)t 3 11 <

1.5 0.9)t 3 NO DA1A

( 0)

(

6.2 24.2 st 2

(

6.2 24.2)t 2

( 2/ 2)*

t 2/ 2)*

.K 40 ( !)

(

6.2 a 1.2)E 3 11

(

6.2 a 1.2)t 3 NO DATA

( 0)

(

5.1 7.4)E 3

(

5.1 7.4)t 3

( 2/ 2)*

(

2/ 2)*

MN 54 ( !)

(

,3.7 e 15.2W( 0 11

(

3.7 t 15.2)E 0'

No DA1 A

( 0)

(

1.1 1.9)g 1

(

1.1 1,9) 1

( 0/ 2)*

'*( 0/ 2)*

l

.[

Co 58 ( 2)

(

2.2 e 5.3)E C 11

(. 2.2

5.3)E O NO DATA

( 0)

-t 7.5 3.1)t 0

(

7.5 3.1)E O

( 0/ 0)*

(

0/ 2)*

Ft 59 ( 2)

(

7.5 t 9.7)E D 11

(

F.5 9.7)E 0 No DATA k

( 0)

(

2.2 -

17.2)E O

(

2.2 17.2)t 0

(

0/ 2)*

(

D/ 2)*

Co 60 ( 2)

(

1.5 0.3)E 1 11

(

1.5 t 0.3)E 1 NO DATA

( 0)

{

1.8 1.2)E 1

(

1.8 -

1.2)E 1

(

0/ 2)*

(

0/ 2)*

ZN % ( 2)

(

6.5 t 7.4)E 0 11

(

6.5 t 7.4)E o NO DATA

( 0)

(

9.4 139.0)E.1

(

9.4 - 139.0)E.1

(

0/ 2)*

( 0/ 2)* '

ZR 95 ( 2)

(

1.4 a 1.7)E 1 11

(

1.4 a 1.7)E 1 NO DATA

( 0)

(

2.8 31.3)E O

(

2.8 31.3)E O

(

0/ 2)*

( 0/ 2)*

AG 110M( 2)

(

9.2

10.8)E D 11

(

9.2

10.8)E D NO DATA

( 0)

(

2.0 0.2)E 1

(

2.0 0.2)E 1

(

0/ 2)*

(

0/ 2)*

NON ROUTINE REFERS TO THE NWBER OF SEPARATE MEASUREMENT $ WHICH WERE GREATER THAN TEN (10) TIMES THE AVERAGE BACKGROUND FOR THE PERIOD OF THE REPORT.

THE FRAETION OF SAMPLE ANALYtts 'iltLOING DEftC!A*.E KEASUREMENTS (i.t. >3 STD DEVIAfl0NS) 18 INDICATED WITH *(

)*. i

(NVIRONMENTAL RADIOLOGICAL PROGRAM SJieuRY s

Mikt YMEtt ATOMit POWtk $1AT!0N, WitCAt$tt, ME (JANUARY. CICEMett 1989)

MEDIUM: MIXT 0 VtGtfATION UN!!$8 PCI/KG Wtf IWDICATOR $1Atl0NS

$1Afl0N WifH NIGNtli MEAN CONTROL $1A110NS ere**eeeeeeee,*eee een*eeeeeeeeeeete*****eee eeeeeeeeeeeeeee.

RADIONUCLIDES MEAN MEAN MEAN (NO. ANALYtts) REQUlktD RANGE StA.

RANet RAliGE (NM+ROU11Nt)*

LLD tv0. DtitCitD**

0.

b0. DtitCitD**

NO. Dit!CitD**

{

RU+103 ( 2)

(

2.0 t 3.6)t 0 11

(

2.0 t 3.6)E 0 NO DATA

( 0)

(

1.6 +

5.6)t 4

(

+1.6 -

$.6)E O

(

0/ 2)*

(

0/ 2)*

RU 106 ( 2)

(

9.2 a 3.5)E 1 11

(

9.2 s 3.5)E 1 No DATA

( 0)

(

5.7 - 12.7)t 1

(

5.7 -

12.7)E 1

(

0/ 2)*

(

0/ 2)*

SB 12A ( 2)

(

+7.7 s 23.5)t 0 11

(

7.7 s 23.5)E O NO DATA

( 0)

(

3.1 -

1.6)E 1

(

+3.1 --

1.6)E 1

(

0/L2)*

(

0/ 2)*

l-131 ( 2)

(

3.5 a 2.1)! i 11

(

3.5 a 2.1)E i NO DATA

( 0)

(

1.5 -

5.6)E 1

(

1.5 -

5.6)E 1

(

0/ 2)*

(

0/ 2)*

CS 134 ( 2)

(

1.5 t 0.1)E 1 11

(

1.5 a 0.1)E 1 No DATA

( 0)

(

1.5 1,4)E 1

(

1.5 1.4)E 1

(

0/ 2)*

(

0/ 2)*

CS 137 ( 2)

(

6.0 e 2.5)E O 11

(

6.0 s 2.5)E D No DATA

( 0)

(

3.5 -

8.5)E 0

(

3.5

8.5)E D

(

0/ 2)*

(

0/ 2)*

{

SA 140 ( 2)

(

2.2 1.6)E 1 11

(

2.2 a 1.6)t 1 No CATA

( 0)

(

6.0 - 38.5)E O

(

6,0 + 38.5)t 0

(

C/ 2)*

f( 0/ 2)*

CE 141 ( 2)

(

2.0 a 0.1)E O 11

(

2.0 s 0.1)E D No DATA

( 0)

(

1.9 -

2.0)t 0

(

1.9 -

2.0)g 0

( 0/ 2)*

(

0/ 2)*

Ct 144 ( 2)

(

4.0 e 4.5)E 1 11

(

4.0 4.5)E 1 No DATA

( 0)

(

+4.9 - 85.2)E O

(

4.9 -

85.2)E O

(

0/ 2)*

(

0/ 2)*

NON ROUTlWE REFERS 10 THE NUMett OF SEPARAft MEASUREMENTS WHICH WERE GREATER THAN TEN (10) IIMES THE AVERAGE BACKGROUND FOR THE Ptt10D OF THE REPORT.

THE FRAtilt* OF SAMPLE ANALYSf 8 YIELDING DtitCTABLE MEASUREMENTS l'

(1.E. >3 STD DEVIAf!0NS) 15 INDICATED WITH *(

)*.

5 2J.

1

- m

a 305 TskLCrmy Pursuant to Technical Specification Table 4.8-1, food crop 5

sampling is not required, provided that milk sampling is being performed. Since allk sampling was performed in 1989, no food crop samples were collected.

I I

l i

I I

l l

i t WPP12/27 i

1 i

i i

i

I 3.6 Croundwater I

l=

Groundwater grab samples were collected from one indicator and one l

control station on a quarterly basis, although not. required by 4.

plant Technical Specifications; These samples were analyzed for I

j H-3 and samma emitting radionuclides. The results show that there l

were no radionuclides detected in groundwater samples during 1989.

f i

' I lI

~

!I

)

I 4

I J

j I

i i

't

?,

WPP12/27 E

ENVIRONMENTAL RADIOLOGICAL PROGRAD

SUMMARY

MAINE TANKEE ATOMIC POWER $1Afl0N, WISCA$$tt, NE (JANUARY DECENSFP 1989)

C ' ** EenuVND WATER UNITS: PCl/KG s

INDICATOR STAfl0NS

$1ATION WITH NIGHE$f MEAN CONTROL $1AT!ONS E

...........c......

3 RAD 1DWUCLIDE$

MEAN MEAN MiAN

{

(NO. ANALYSES) REQUIRED RANGE

$1A.

RANGE RANGE J

(WON ROUTINE)*

LLD N0. DETECTED **

WO.

NO. DETECTED **

No. DETECTED **

l MN 54 ( 8)

(

8.9 e 3.2)E 1 24

(

3.6 s 2.9)E 1

(

3.6 a 2.9)E 1

( 0)

(

1.4 -

0.4)E 0

(

8.6 -

4.1)E 1

(

8.6 -

4.1)E 1

(

0/ 4)*

(

0/ 4)*

(

0/ 4)*

Co 58 ( 8)

(

6.6 t 4.8)E 1 13

(

6.6 a 4.8)E 1

(

1.0 a 0.6)E O

( 0)

(

1.5 -

0.7)E D

(

1.5 -

0.7)E O

(

2.2 -

0.5)E O l-

(

0/ 4)*

(

0/

4)*

(

0/ 4)*

FE 59 ( 8)

(

1.0 s 2.1)E O 13

(

1.0 a 2.1)E D

(

4.2 15.8)E 1

( 0)

(

3.5 -

6.7)E 0

(

3.5 -

6.7)E O

(

2.9 -

4.3)t 0

(

0/ 4)*

(

0/ 4)*

(

0/ 4)*

l Co 60 ( 8)

(

2.9 :

5.5)E 1 13

(

2.9 5.5)E 1

(

3.1 s 6.0)E 1

( 0)

(

1. 0 -

1. 4 ',E D

(

1.0 -

1.4)E 0

(

1.9 -

0.8)E 0

(

0/ 4)*

(

0/ 4)*

(

0/ 4)*

ZN 65 ( 8)

(

1.5 s 0.5)E O 24

(

1.4 a 2.4)E O

(

1.4 e 2.4)E O

( 0)

(

2,3 -

-0.4)E O

(

3.3 -

6.4)E O

(

3.3 -

6.4)E O

l

(

0/

4)*

(

0/

4)*

(

0/ 4)*

$E 75 ( 8)

(

-1.0 t 7.7)E 1 13

(

1.0 a 7.7)E 1

(

7.4 a 3.2)E 1 l

( 0)

(

1.5 -

1.6)E O

(

1.5 -

1.6)E O

(

1.7 -

0.4)E O

(

0/

4)*

(

0/ 4)*

(

0/ 4)*

ZR 95 ( 8)

(

1.1 a 0.6)E O 13

(

1.1 0.6)E O

(

1.7 a 1.3)E O

( 0)

(

4.4 -

24.7)E 1

(

4.4 -

24.7)E -1

(

5.1 -

0.9)E O

(

0/ 4 )*

(

0/ 4)*

(

0/ 4)'

AG 110M( 8)

(

7.7 :

39.3)E -2 13

(

7.7 a 39.3)E 2

(

1.0 t 0.4)E O

( 0)

(

9.2 -

7.6)E 1

(

9.2 -

7.6)E 1

(

2.3 -

0.3)E O

(

0/ 4)*

(

0/ 4 )*

(

0/ 4)*

RU 103 ( 8)

(

8.1 a 6.3)E 1 24

(

6.8 s 3.2)E -1

(

6.8 a 3.2)E -1

( 0)

(

2.0 -

0.3)E O

(

1.3 -

0.2)E D

(

1.3 -

0.2)E O

(

0/ 4)*

(

0/ 4 )*

(

0/ 4)*

NON-ROUTINE REFERS TO THE Nt.h8ER OF $EPARATE MEASUREMENTS WHICH WERE GREATER THAN TEN (10) TIMES THE AVERAGE BACKGROUND FOR THE PERIOD OF THE REPORT.

THE FRACTION OF $ AMPLE ANALYSES YlELDING DETECTABLE MEASUREMENTS (1.E. >3 STD DEVIAfl0N1) 1$ INDICATED WITH *(

)*.

m _

s ENVIRONMENTAL kAD10 LOGICAL PROGRAM stemARY MAINE TANKEE ATOMIC POWER STAfl0N, WISCAttET, ME s

(JANUARY DECEMBER 1989)

[

MEDIUM: GROUND WATER UNIT $t PCl/KG L

INDICATOR STAfl0NS STAfl0N WITH HIGNEST MEAN-CONTROL STAtl0NS eeeeeeeeeeeeeeeeee eeeeeeeeeeeeeeeeeeeeeeeee eeeeeeeeeeeeeeee AADIONUCLIDE$

MEAN MEAN MEAN (NO. ANAlf tts) REQUIRED RANGE STA.

kANGE RANGE (NON* ROUTlWE)*

LLD NO. DETECTED **

NO.

NO. DETECT 60**

NO. DETECTED **

f.

RU 106 ( 8)

(

5.3 e 6.4;E 0 13

(

5.3 a 6.4)E O

(

5.5 a 3.7)E 0

( 0)

(

1.2 1.8)E 1

(

1.2 -

1.8)E 1 1.3 -

0.3)E 1

(

0/ 4)*

(

0/ 4)*

(

0/ 4)*

$t 124 4 8)

(

1.6 e 0.8)E O 13 (

1.6's 0.8)E D

(

1,6 a 2.0)E O

( 0)

(

7.5 - 28.4)E 1

(

+7.5 -

28.4)E 1

(

+4.3 -

'4.3)E O

(

0/ 4)*

(

0/ 4)*

(

0/ 4)*

l 131 ( 8)

(

3.9 e 10.4)E 1 24

(

1.7 a 2.0)E O

(

1.7 a 2.0)E O

( 0)

(

2.3 -

2.4)E O

(

1.8 -

6.4)E O

(

1.8 -

6.4)E O

(

0/ 4)*

(

0/ 4)*

(

0/ 4)*

CS 134 ( 8)

(

5.4 a 6.9)E 1 13

(

5.4 s 6.9)E 1

(

5.5 a 38.3)E 2

( 0)

(

9.2 - 23.0)E *1

(

9.2 - 23.0)E 1

(

8.7 4 8.3)E 1

(

0/ 4)*

(

0/ 4)*

(

0/ 4)*

i CS 137 ( 8)

(

7.1 a 2.2)E *1 24

(

3.7 e 8.9)E 1

(

3.7 8.9)E *1 j

( 0)

(

1,3 -

0.3)E O

(

2.2 -

1.3)E 0

(

2,2 -

1.3)E O

(

0/ 4)*

(

0/ 4)*

(

0/ 4)*

BA 140 ( 8)

(

1.4 a 0.8)E D 13

(

1.4 a 0.8)E 0

(

5.7 a 10.6)E 1

( 0)

(

9.3 -

28.3)E 1

(

9.3 -

28 3)E 1

(

2.6 -

2.3)E O

(

0/ 4)*

(

0/ 4)*

(

0/ - 4)*

CE 161 ( 8)

(

1.5 a 10.2)E 1 24 (

2.7 72.5)E 2

(

2.7 72.5)E 2 l

( 0)

(

2.0 -

2.7)E O

(

2.0 -

1.4)E O

(

2.0 -

1.4)E O

(

0/ 4)*

(

0/ 4)*

(

0/ 4)*

CE 144 ( 8)

(

1.1 0.3)E 0 24

(

3.5 a 63.6)E *1

(

3.5 t 63.6)E 1

( 0)

(

1.8 -

0.4)f 0

(

1.1 -

1.8)E 1

(

1.1 1.8)E 1

(

0/ 4)*

(

0/ 4)*

(

0/ 4)*

H3

( 8)

(

6.9 s 10.8)E 1 24

(

4.7 a 11.8)E 1

(

4.7 s 11.8)E 1

( 0)

(

2.C -

1.6)E 2

(

2.3 -

3.4)E 2

(

2.3 -

3.4)E 2

( 0/ 4)*

(

/ 4)*

(

0/ 4)*

NON ROUTINE REFER $ TO THE NUMBER OF SEPARATE MEASUREMENTS WICH WERE GREATER THAN TEN (10) TIMES THE AVERAGE BACKGROUND FOR THE PERIOD OF THE REPORT.

THE FRACTION OF SAMPLE ANALYSES YlELDING DETECTABLE MEASUREMENTS (1.E. >3 STD DEVIAtl0NS) !$ INDICATED WITH *(

)*..

-I s.m

-3.7 Es ttary Water s

r.

Estuary water is analyzed monthly for gamma emitting radionuclides and quarterly for H-3.

The one indicator station has a composite sampler from which samples are collected on a weekly basis.

Weekly grab samples are taken from the control location. All of the weekly samples are composited (by station) at the laboratory f

and analyzed monthly. All monthly samples are composited (by station) at the Yankee Environmental 1,aboratory for quarterly H-3

(

analyses.

H-3 was detected at Station WE-12 (plant outfall) in the third quarter composite samps at 960 1 240 pCi/kg. This sample was collected in the discharge forebay and does not represent actual environmental levels. When a dilution factor of 10 (Reference 1) 1 is applied to estimate environmental levels after passing through the diffusers in the Back River, the concentrations would be reduced by approximately a factor of ten. The above concentrations do not exceed any reporting level in Technical Specification Table 4.8-3 when summed in accordance with Technical Specification 4.8.A.3.

Naturally-occurring K-40 was also detected in most samples.

Between February 3 and 10, 1989, the water flow into the ccejosite sampler at WE-12 was interrupted dus to a frozen line, which, in turn, was caused by a heater f ailure in the sampling shed. A grab sample was collected on February 10, and this was added to the composite volume.

The sampler was put back into service on February 10.

On December 15, 1989, the sample flow was again interrupted due to ice blockage. The system was put back into operation on December 18, 1989.

1

! l WPP12/27 i

l

'i

s ENVIRONMENTAL RADIOLOGICAL PROGRAM SLBMARY MAINE TANKEE ATOMIC POWER STATION, WitCA$$ET, NE (JANUART

DECEMN R 1989)

H MEDIUN ESTUARY WATER UNIT $t PCl/KG W

INDICATOR $1Afl0NS

$1Afl0N WITN HIGHEST MEAN CONTROL STAfl0N$

p AADIONUCLlDES MEAN MEAN MEAN (No. ANALYMB) REQUlkED kANGE STA.

RANGE RANGE u

(NON ROUTINE)*

ELD NO. DETECTED **

N0.

NO. DETECTED **

I K 40 ( 24)

(

2.1 a 0.1)E 2 12 (

2.1 0.1)E 2

(

2.6 0.7)E i

( 0)

(

1.3 -

2.6)E 2

(

1.3 2.6)E 2

~(

i.5 -

6.6)E 1

( 12/ 12)*

( 12/ 12)*

(

4/ 12)*

MN*$4 ( 24) 1$.

(

1.2 3 2.9)E *1 12 (

1.2 e 2.9)E *1

(

1.9 t 1.9)E *)

( 0)

(

2.0 -

2.0)E O

(

2.0

2.0)E 0

(

1.6

0.7)E O j

(

0/ 12)*

(

0/ 12)*

(

0/ 12)*

l q

l C0 58 ( 24) 15.

(

5.8 e 22.4)E *2 12

(

5.8 e 22.4)E 2

(

1.5 e 2.2)E 1

( 0)

(

+1.4 -

1.3)E O

(

1.4 -

1.3)E O

(

1.3 1.0)E O

(

0/ 12)*

(

0/ 12)*

(

0/ 12)*

fE 59 ( 24) 30.

(

2.5 4 4.6)E *1 2D (

7.5 525.2)E 3

(

+7.5

$25.2)E 3

( 0)

(

2.8 -

2.2)E O

(

3.2 -

4.2)E O

(

3.2 +

4.2)E O

(

0/ 12)*

(

0/ 12)*

(

0/ 12)*

1 CD 60 ( 24) 15.

(

1.2 s 0.3)E O 20 (

+3.3

1.9)E *1

(

3.3 a 1.9)E 1

( 0)

(

3.2

0.1)E 0

(

1.2 -

0.9)E O

(

1.2 -

0.9)E O

(

0/ 12)*

(

0/ 12)*

(

0/ 11/)*

2N 65 ( 24) 30.

(

3.7 4.0)E *1 12 (

3.7 a 4.0)E *1

(

6.3 4.3)E *1

( 0)

(

2.5 -

1.9)E 0

(

2.5 -

1.9)E 0

.(

3.7 -

1.9)E- 0

(

0/ 12)*

(

0/ 12)*

(

0/ 12)*

1 SE 75 ( 24)

(

3.5 a 3.5)E *1 12 (

3.5 t 3.5)E *1

(

2.2 2 2.4)E 1

( 0)

(

1.2 -

3.2)E 0

(

1.2 +

3.2)E D

(

1. 2 -

1.6)E 0

(

0/ 12)*

(

0/ 12)*

(

0/ 12)*

ZR 95 ( 24) 15.

(

7.4 a 5.9)E 1 12 (

7.4 3 5.9)E 1

(

8.2 2 3.7)E 1 t

l

( 0)

(

+2.9 -

3.9)E 0

(

2.9 -

3.9)E O

(

3.7 -

1.0)E 0 1

(

0/ 12)*

(

4 12)*

(

0/ 12)*

AG 110M( 24)

(

5.0

2.7)E 1 20 (

1.1 2.8)E *1

(

1.1 s 2.8)E 1 1

( 0)

(

2.0 -

0.5)E O

(

1.7 -

2.4)E 0

(

1.7

2.4)E 0

(

0/ 12)*

(

0/ 12)*

(

0/ 12)*

l NON ROUTINE REFERS TO THE NUMBER Of SEPARATE MEAtuREMENTS WHICH WERE GREATER 4

THAN TEN (10) TIMES THE AVERAGE BACKGROUND FOR THE PERIOD OF THE REPORT.

I THE FRACTION OF $ AMPLE ANALYSES YlELDING DETECTABLE MEASUREMENTS (i.E. >3 STD DEVIAfl0NS) l$ INDICATED WITH *(

)*. i

s ENVIRONMENTAL RADIOLOGICAL PROGAAM BLNMART MAlWE YANKEE ATOMlt POWER STAfl0W, W!kCA$$ET, ME (JANUART + DECEMBER 1989)

MEDIUM: ESTUART WATER UNITS PCl/KG 7-L f

INDICATOR STAtl0NS

$1Atl0N WITN HIGNEST MEAN CONTROL STAfl0NS eeeeeeteeeeeeeeeee eeeeeeeeeeeeeeeeeeeeeeeee eeeeeeeeeeeeeeee kAD10NUCLIDE$

MEAN MEAN MEAN I

(NO. ANALYSES) REQUlkED RANGE STA.

kANGE RANGE (NON ROUTINE)*

LLD N0. DETECTED **

N0.

No. DETECTED **

NO. DETECTED **

l ku 103 ( 24)

(

8.7 a 2.0)E *1 20 (

3.8 a 20.3)E +2

(

3.8 a 20.3)E *2 B

( 0)

(

2.2 -

0.3)E O

(

8.7 17.0)E 1

(

8.7 -

17.0)E 1

(

0/ 12)*

(

0/ 12)*

(

0/ 12)*

RU 106 ( 24) 7.8 a 14.4)E *1 20 (

1.9 a 2.1)E 0

(

1.9 a 2.1)E D

(

( 0)

(

+8.4 +

4.7)E O

(

1.0

1.7)E 1

(

1.0 -

1.7)E 1

(

0/ 12)*

(

0/ 12)*

(

0/ 12)*

I<

88 124 ( 24)

(

2.7 4.7)E *1 20 (

+7.5 40.3)E *2

(

+7.5 a 40.3)E 2

( 0)

(

+4.2 -

2.2)E 0

(

1.8 -

2.3)E O

(

+1.8 -

2.3)E O

(

0/ 12)*

(

0/ 12)*

(

0/ 12)*

l*131 ( 24) 15.

(

3.1 8.9)t 1 20 (

+7.2 s 96.9)E 2

(

7.2 96.9)E 2

( 0)

(

6.6 -

5.2)t 0

(

7.9 -

5.4)E D

(

7.9 -

5.4)E 0

(

0/ 12)*

(

0/ 12)*

(

0/ 12)*

l C$*134 ( 24) 15.

(

+9.7 s 1.7)E 1 20 (

8.1 1.6)E 1

(

8.1 s 1.6)E 1

( 0)

(

2.0 -

0.1)E 0

(

1.9 -

0.0)E D

(

1.9 -

0. Mt 0

(

0/ 12)*

(

0/ 12)*

(

0/.12)*

C5 137 ( 24) 18.

(

5.7 s 20.3)E 2 to (

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0/ 4)s NON ROUTINE REFERS TO THE NLMBER OF SEPARATE MEASUREMENTS WN!*H WERE GREATER

)

THAN TEN (10) TIMES THE AVERAGE BACKGROUND FOR THE PERIOD OF THE REPORT.

THE FRACil0N OF SAMPLE ANALYSES YlEl. DING DETECTABLE MEASUREMENTS (1.E. >3 STD DFV!Afl0HS) 15 INDICATED WITH *(

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3.8 MarineAlfhe 7

Although not required by plant Technical Specifications, samples L

of mixed fucus and ascophyllum saarine algae were collected f rom i

two locations during June and September and from an additional *,wo locations in January. Each sample was analyzed for gamma emitting radionuclides.

In addition to naturally-occurring K-40, Be-7, and Th-232, low levels of' Co-60 and Ag-110m verte detected at AL-29 (Maine Yankee dock) on January 13, 1989 and AL-11 (Long Ledge) on September 18, 1989.

These samples were taken in the general area of the plant diffusers and are a result of controlled plant discharges. Marine algae is not consumed in any way from this area, however, so there would be no' impact on man. Although there are no reporting levels for marine algae, each of the detected levels is well below Technical Specification reporting' levels for edible fish and invertebrates.

1 I

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MEDitM MARINE ALGAE UNITS: PCl/KG WET INDICATOR STAfl0NS

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(

4.4 e 1.0)t i 29 (

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(

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(

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(

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(

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( 2)

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(

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(

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( 0)

(

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(

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i WON ROUTINE REFERS TO THE NUMBER OF SEPARATE MEAiiUKEMENTS WHICH WERE GREATER THAN TEK (10) TINES INE AVERAGE SACKGROUND FOR THE PERIOD OF THE REPORT.

THE FRACTION OF SMPLt AN81'SES YIELDING DETECTABLE MEASUREMENTS (l.t. >3 STD DEVI Afl06 8) !$ INC'ICATED WITH *(

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RU 103 ( 6)

(

4.5 a 7.6)E *1 19 (

1.1 e 2.7)t 0

(

2.1 a 3.1)t 0

( 0)

(

1.8 +

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(

5.2 -

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(

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(

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4.0 a 0.5)E i

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(

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_1 NON ROUTlWE REFERS TO THE NUMBER OF SEPARATE MEASUREMENTS WHICH WERE GREATER THAN TEN (10) TIMES THE AVERAGE SACKGROUND FON THE PER100 0F THE REPORT.

=

THE TRACTION OF SAMPLE ANALYSES YttLDING DETECTABLE MEASUREMENTS (1.E. >3 STD DEVIAtl0NS) !$ INDICATED WITH *(

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' i

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s 3.9 Sediment Sediment core samples were collected from two locations during May and November. At each location, several cores are taken in the same general area.

Each core is frozen to preserve its structural I

integrity during shipping and is then cut into 5 cm layers at the laboratory. All of the cores from a single site are then composited by depth segment.

The Os-137 detected in sediment at SE-16 is partly due to early plant operation, when' routine liquid offluents from the plant were discharged in this area.

Due to poor diffusion, a discharge diffuser was installed and. liquid effluents are now' discharged I

into the Back River. Some of the Os-137 is likely due to nuclear weapons testing fallout.

Levels have generally decreased over the-past several years.

Cobalt-60 was detected in stueral samples (maximum concentration of 92 pCi/kg) from both locations and-is due to plant discharges.

I There is no reporting level for Cs-137 or Co-60 in sediment, but one might appreciate the negligible dosimetric consequence when conservatively compared against the reporting levels for edible fish of 10,000 pCi/kg for Co-60 and 2,000 pCi/kg for Cs-137.

Furthermore, these sites are not occupied, nor are they used for recreational purposes, since they are within'the site boundary.

In a:'iition to the above radionue' ides, naturally occurring X-40 and Th-232 were detected in=all sediment samples, and naturally occurring Be-7.was detected in several samples.

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(

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NON ROUTINE REFERS TO THE NUMBER OF SEPARAft MEASUREMENTS WHICH WEkE GREATER THAN TEN (10) TIMES THE AVERAGE BACKGROUND FOR INE PERIOD OF THE REPORT.

THE FRACTION OF $ AMPLE ANALYSES YIELDING DETECIABLE MLASUREMENTS (1.E. 3 STD DEVIAtl0NS).' $ 'NDICATED WITH *(

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Fish sarnples were collected at two locations during July and L'

September of 1989.

Each sample was analyzed for gamma-emitting radionuclides.

Except for naturally occurring K-40, no radioactivity was detected.

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(

4.3 : 13.8)t 0 11 (

4.3 :

N 3)E 0

(

2.9. 11.3)E D

( 0)

(

+9.4 +

18.1)E 0

(

9.4 *

4. < t 0

(

1.4 -

0.8)E 1

t 0/ 2)*

( 0/ 2)*

( 0/ 2)*

NON ROUTINE REFERS 10 THE NUMett OF SEPARAft MEASUREMENT $ WHICH WERE OktATER THAN TEN (10) TIMES THE AVERAGE BACKGROUND FOR INE PERIOD OF THE REPORT.

THE FRACTION OF SAMPLE ANALT$ts YlELDING DETECTABLE MEASUREMENTS (1.E. e3 STD OtVIAtl0NS) 18 INDICATED WifN *(

P..

ENVIRONMENTAL ROl0 LOGICAL PROGRAM SWN4ARY MAINI 1ANKEt ATOMIC POWER $1Afl0N, WISCAlltT, Mt tJAWuARY, DECEMB&R 1989)

~

NieluM: Fi$u UN!18: PCI/KC WET INDICATOR $1Afl0NS

$fAfl0N WifH HIGHT $f MEAN CONTROL $1Afl0NS r

RADIONUCLIDtl MLAN MEAN MEAN (NO. ANALY$t$) ktoulktD RANGC

$1A.

RANot kANGE (NON R0utlNE)*

LLD M0. DtittitD" NO.

No. DtittilD**

Wo. DtittitD"

}

AG.110M( 4)

(

+7.5 e 1.0)t 0 24 (

3.0 t 6.6)E 0

(

+3.0 a 6.6)t 0

( 0)

(

8.5 6.5)E D

(

+9.6 3.7)t 0

(

9.6 -

3.7)E D

(

0/ 2)*

(

0/ 2)*

( 0/ 2)*

RU.103 ( 4)

(

5.7 s 11.5)E O 11

(

5.7 e 11.5)E O

(

1.2 a 0.2)E 1

( 0)

(

1.7 0.6)t 1

(

1.7 -

0.6)E 1

(

1.5 -

1.0)E 1

(

0/ 2)*

( 0/ 2)*

( 0/ 2)*

RU 106 ( 4)

(

3.5 a 2.0)E 1 11

(

3.5 e 2.0)t 1

(

6.6 5.3)t 1

( 0)

(

1.6 -

5.5)E 1

(

1.6 -

5.5)E i

(

1.2 -

+0.1)E 2

(

0/ 2)*

( 0/ 2)*

( 0/ 2)*

u

$8 124 ( 4)

(

!.S :

28.4)t 0 it

(

2.5 e 28.4)E 0

(

2.7 a 2.7)E i

( 0)

(

2.6 -

3.1)t 1

(

2.6 -

3.1)E 1

(

5.5 -

0.0)E 1

(

0/ 2)*

(

0/ 2)*

(

0/ 2)*

1*131 ( 4)

(

9.2 8 8.8)E 1 11

(

9.2

8.8)E 1

(

4.6 s 6.1)E 1

( 0)

(

3.4 180.0)E O

(

3.4 - 180.0)t 0

(

1.5 10.7)E 1

(

0/ 2)*

(

0/ 2)*

(

0/ 2)*

Cl*134 ( 4) 130.

(

1.4 0.4)E 1 24

(

9.6 9.t.)E O

(

9.6 9.4)t 0

( C)

(

1.8 -

1.0)E 1

(

1.9 -

.,0)t 1

(

1.9 +-

0.0)E 1

(

0/ 2)*

(

0/ 2)*

(

0/ 2)*

l CS 137 ( 4) 150.

(

1.5 0.3)E O 24

(

1.22 0.1)E 1

(

1.2 a 0.1)t 1

( 0)

(

1.1 -

1.8)E O

(

1.1 1.3)E 1

(

1.1 1.3)E 1

( 0/ 2)*

( 0/ 2)*

(

0/ 2)*

CE 141 ( 4)

(

1.5 0.4)t 1 it

(-

1.5 4 0.4)E 1

(

6.1 e 3.0)t 0

( 0)

(

i.1 -

2.0)E 1

(

1.1 -

2.0)E 1

-(

3.1

9.1)E 0 I

(

0/ 2)*

(

0/ 2)*

(

0/ 2)*

CE 144 ( 4)

(

5.1

'91.7)E 0 24 (

2.7 : 57.4)E *1

(

2.7 57.4)E 1

( 0)

(

9.7 8.7)t 1

(

5.5 -

6.0)E O

(

+5.5 -

6.0)r 0

(

0/ 2)*

(

0/ 2)*

(

0/ 2)*

f NON ROUTINE REFtt$ 10 THE NUMBtt OF SEPARATE MEASUREMENTS WHICH WERE GktAttR l

THAN f tN (10) TIME $ THE AVERAGE BACKGR0uuo FOR Tht PERIOD OF THE kEPORT.

THE FRACTION OF $4MPLE ANALY$tt YitLDlWG DtitCTABLE MEASUREMENi$

(1.E. >3 $1D (,tVIAfl0NS) 18 INDICATED WITH *(

)*.

, 1 l

i

l.

LI 3.11 linatala I

Mussel body samples were collected from each of two locations in June and September of 1989.

Each sample was analyzed for I

gamma-omitting radionuclides.

Except for naturally occurring K-40, no radionuclides were detected in any sample.

I I

I J

E I

I I

I 3

E WPP12/27

'1

(MVikONMENTAS RADIOLOGl&AL PROGAAM StastARY MAlWE TAWKEt AT(stlC POWER $1ATION, WISCAllti, Mt (JANUARY DECENstR 1989)

MEDluM MUS$tL 80Dit$

UNitti PCl/KG WET

~

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$f Afl0N WITH NIGNt$f MEAN CONTROL $1Afl0NS p.

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MtAN MtAN MEAN (NO ANALT$t$) Rieu! RED RANet

$1A.

RANot RANGE (NON ROUTINE)*

LLD NO Dti!CfED**

N0.

No. DtiECitD'*

N0. DEitCitD'*

I DE*7

( 4)

(

3.5 a 4.7)t 0 24 (

3.7 e 7.1)t 1

(

3.7 :

7.1)t 1

( 0)

(

4.2 +

1.2)E 0

(

+3.4 +

10.8)t 1

(

3.4 -

10.8)E 1

(

0/ 2)*

(

0/ 2)*

(

0/ 2)*

K 40 ( 4)

(

1.0 t 0.1)E 3 11

(

1.0 e

'0.1)t 3

(

9.5 a 2.3)E 2

( 0)

-(

9.6 +

11.2)E 2

(

9.6 +

11.2)E 2

(

7.2 +

11.8)t 2

(

2/ 2)*

(

2/ 2)*

(

2/ 2)*

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(

9.1 s 100.9)E *1 24 (

3.4 a 1.9)E O

(

3.4 e 1.9)t 0

( 0)

(-

9.2 11.0)L 0

(

1.4 -

5.3)t 0

(

1.4 -

5.3)E 0

(

0/ 2)*

(

0/ 2)*

( 0/ 2)*

Co 58 ( 4) 130.

(

9.9 e 2.7)E D 11

(

9.9 e 2.7)E O

(

2.1 s 1.3)t 0

( On

(

7.3 -

12.6)E O

(

7.3 -

12.6)E D

(

8.4 -

33.6)f.*1

(

0/ 2)*

(

0/ 2)*

(

0/ 2)*

1 ft 59 ( 4) 260.

(

1.1 0.3)E 1 11

(

1.1 0.3)E 1

(

6.5 a 180.5)E 1

( 0)

(

8.2

14.0)E D

(

8.2 -

14.0)E D

(

1.7 -

1.9)E 1

(

0/ 2)*

(

0/ 2)*

( 0/ 2)*

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(

6.1 a 4.2)E O 11

(

'6.1 a 4.2)E O

(

2.7 0.7)E O

( 0)

(

1.9 10.3)E O

(

).9 10.3)E D

(

+3.5 2.0)E 0

(

0/ 2)*

(

0/ 2)*

(

0/ 2)*

ZW 65 ( 4) 260.

(

1.0 s 0.8)E 1 24 (

3,2 a 1.0)E 1

(.

3.0 a 1.0)E 1

( 0)

(

1.8 0.3)2 i

(

2.0 -

4.0)E 1

(

2.0 -

4.0)E 1

(

0/ 2)*

(

0/ 2)*

(

0/ 2)*

St*75 ( 4)

(

4.8 9.7)E D 11

(

4.8

9.7)E O

(

8.1 12.0)t 0

( 0)

(

1.5 -

0.5)E 1

(

i.5 -

0.5)E 1

(

2.0 -

0.4)E 1 1

(

0/ 2)*

(

0/ 2)*

(

0/ 2)*

2R 95 ( 4)

(

1.7 s 1.4)E 1 24 (

3.7 e 2.6)E 0

(

3.7 a 2.6)E O

( 0)

(

3.2 -

0.4)t 1

(

6.3 -

1.2)E 0

(

6.3 -

1.2)[ 0

(

0/ 2)*

(

0/ 2)*

(

0/ 2)*

1 NON ROUTINE REFERS TO THE NUN $tt OF $EFARATE MEASUREMENTS WHICH WERE GREATER THAN ftN (10) 11MES THE AVERAGE SACKGROUND FOR THE PERIOD OF THE REPORT.

- - THE IRACTION OF SAMPLE ANALY$tt Yl[LDING DtitCTABLE MEASUREMENTS (1.E. >3 STD DEVIAtl0N$) 1$ INDICAftD WITH *(

)*... _.... _ _ _ _ _ _... _

(CVIkONMENTA!, kA010 LOGICAL PROGRAM

SUMMARY

~

MAINE TANKEt A10MIC POWik $1Afl0N, W18CA$$ti, ME (ilAJUARY + DECEMstk 1999)

{

MEDIUM: It.ftttL 600lt$

UNils: PCl/tG WEI 5

INDICATUR STAfl0NS

$1Afl0N WITH NIGNE$1 NEAN CONTROL $TATION$

e...eeeee....e**e R@l0NUCLIDil MEAN MEM MEAN (NO. ANALYST $) Rt0VIRED RANQt

$fA.

RANGE RANGE (NON*kOUTlut)*

LLD NO. DtitCit0**

No.

M0. DtitCit0" N0. Dtittit0"

{

L AG 11DM( 4)

(

1.5 a 5.2)t 0 it

(

1.5 e 5.2)t 0

(

+2.7 3.3)E 0

( 0)

(

+3.7 +

6.7)t 0

(

+3.7 6.7)t 0

(

5.9 -

0.6)t 0

(

0/ 2)*

(

0/ 2)*

( 0/ 2)*

ku 103 ( 4)

(

3.1 4 13.6)E O 11

(

3.1 a 13.6)E D

(

$.2 9.1)t 0

[

( 0)

( + 1. 7 -

1.1)t 1

(

1.7 -

1.1)E 1

(

1.4 -

0.4)t 1

( 0/ 2)*

( 0/ 2)*

(

0/ 2)*

RU 106 ( 4)

(

+3.3 s 19.4)E 0 11

(

+3.3

-19.4)E 0

(

1.0 a 0.1)t 2

{

( 0)

(

2.3 +

1.6)E 1

(

+2.3 -

1.6)E i

(

1.1 *

1.0)E 2

(

0/ 2)*

(

0/ 2)*

(

0/ 2)*

$C 124 ( 4)

(

1.1 0.A)E 1 24

(

1.8 a 1.4)E 1

(

1.8 e 1.4)t 1

=

( 0)

(

1.5 -

0.7)E 1

(

3.3

31.9)E 0

(

3.3 - 31.9)E O

(

0/ 2)*

( 0/ 2)*

( 0/ 2)*

=

[

l'131 ( 4)

(

+7.2 a 16.6)E O 24 (

2.4 a 2.8)E 1

(

2.4 t 2.8)E i

(

( 0)

(

2.4 +

0.9)E 1

(

3.7 51.3)E D

(

+3.7 *

$1.3)t 0

(

0/ 2)*

( 0/ 2)*

(

0/ 2)*

CS 134 ( 4) 130.

(

9.6 s 65.4)E *1 24

(

+6.1 a 42.3)E +1

(

+6.1 42.3)E *1

( 0)

(

7.5 -

5.6)E D

(

4.8 -

3.6)E D

(

+4.8

3.6)E O

(

0/ 2)*

(

0/ 2)*

( 0/ 2)*

CS 137 ( 4) 150.

(

+2.7

7.1)E O 24

(

1.6 8.0)E O

(

1.6

8.0)E D

( 0)

(

9.8 -

4.4)E O

(

6.4 -

9.6)E O

(

6.4 +

9.6)E 0

(

0/ 2)*

( 0/ 2)*

(

0/ 2)*

CE 141 ( 4)

(

2.9 8.7)E O 24

(

7.0 a 5.8)E O

(

7.0 e 5.8)E 0

( 0)

(

5.8 -

11.6)E o

(

i.2 -

12.8)E 0

(

1.2 -

12.8)E O

(

0/ 2)*

( 0/ 2)*

(

0/ 2)*

(

CE*144 ( 4)

(

1.8 e 2.4)E 1 11

(

1.8 e 2,4)E 1

(

1,7 0,5)g 1

( 0)

(

6.2 + 42.1)E O

(

6.2 - 42.1)E O

(

2.0 -

1.4)t 1

(

0/ 2)*

( 0/ 2)*

(

0/ 2)*

NON ROUTlWE ktFERS TO THE tRMBER OF SEPARATE MEASUREMENTS WHICH WEkt GREATER THAN TEN (10) f!MES THE AVERAGE SACKGROUND FOR THE PERIOD OF THE REPORT.

THE FRACTION OF SAMPLE ANALY$ts YIELDING DETECTABLE MEAtuREMENTS (I.E. >3 STD DEVIAfl0NS) 18 INDICATED WITN *(

)*.

~

3.12 Crus.taceans Crustacean samples consisted of four crab samples and four lobster samples collected from each of two locations.

Each sample was analyzed for gamma-emitting radionuclides.

Silver-110m was detected in one crab sample collected on June 22, 1989 at Station CA-11, which is located in the immediate vicinity of the discharge.

The concentration was 20.6 14.6 pCi/kg. This is well below the reporting level of 8000 pCi/kg for Ag-110m in fish and invertebrates.

(This reporting level was calculated based on 100FR50, Appendix 1 design objectives for dose.) To calculate an upper bound to the potential dose impact to man from I

consumption of crabs and lobsters, Regulatory Guide 1.109 (Reference 2) methodology was used with an annual average Ag-110m concentration of 16.0 pCi/kg. The critical organ dose for the maximally exposed individual, consuming 5 kg/ year of crab and lobster meat at this concentration, was approximately 1

0.005 mrem / year to the edult GI tract.

This is insignificant with

~ - -

I respect to the estimated background whole-body exposure from natural sources of over 200 mrem / year.

In addition to the above, naturally-occurring K-40 was detected in each sample.

I I WPP12/27

(

h-EkVIR00 MEN 7AL RADl0LCCICsL PROGRAM $UMMARY MAINE TAWKEE ATOMIC POWER $1A110el, WISCAllti, ME 7

(JANUARY DECEMBER 1989)

MEDIUM: CRUSTACEAk$

UW118: PC1/KC WET 4

INDICATOR $1Atl0N$

$1ATION WITN NIGHE$1 NEAN CONTROL STA110NS eeeeeeeeeeeeeeeee, eeeeeeeeeeeeeeeeeeeeeeeee eeeeeeeeeeeeeee.

RADIONUCLlDES MEAN MEAN MEAN (NO. ANALYSES) kt0UltED RANGE

$1A.

RANGE RANGE (NON ROUllWE)*

LLD NO. DETECTED **

NO.

NO. DETECTED **

NO. DETEtitD**

i i

BE 7 ( 8)

(

2.9 a 1.7)E 1 11

(

2.9 1.7)E 1

(

3.9 4.9)E 1

( 0)

(

6.4 -

71.7)E D

(

6.4 -

71.7)E O

(

1.3 -

0.6)E 2

(

0/ 4)*

(

0/ 4)*

(

0/ 4P K 40

( 8)

(

2.1 0.3)E 3 11

(

2.1 0.3)E 3

(

2.0 a 0.3)E 3

( 0)

(

i.7 -

2.9)E 3

(

i.7 -

2.9)E 3

(

1.6 -

2.8)t 3

=

l

(

4/ 4)*

(

4/

4)*

(

4/

4)*

MW 54 ( 8) 130.

(

2.2 s 0.6)E O 24

(

1.7 s 3.7)E O

(

1.7 a 3.7)E O

( 0)

(

4.0 -

1.2)E 0

(

9.1 -

8.2)E O

(

91 8.2)E O

(

0/ 4)*

(

0/ 4)*

(

0/ 4)*

C0 58 ( 8) 130.

(

2.7 s 3.3)E D 11

(

2.7 3.3)E O

(

1.9 a 3.0)E O

( 0)

(

6.6 -

7.9)E O

(

6.6 -

7.9)E 0

(

1.0 -

0.7)E i

(

0/ 4)*

(

0/ 4P

(

0/ 4)*

i FE 59 ( 8) 260.

(

1.7 0.1)E 1 11

(

1.7 :

0.1)E 1

(

3.3 18.6)E O

( 0)

(

1.4 -

2.0)E 1

(

1.4 -

2.0)E 1

(

3.2 -

4.1)E 1

(

0/ 4)*

(

0/ 4)*

(

0/

4)*

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(

4.6

5.1)E O 24

(

2.1 a 5.0)E D

(

2.1 a 5.0)E O

( 0)

(

1.4 -

0.5)E 1

(

1.7 -

0.5)E 1

(

1.7 -

0.5)E 1

(

0/

4)*

(

0/

4)*

(

0/

4)*

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(

3.0 a 105.1)E 1 11

(

3.0 s 105.1)E 1

(

7.7 e 2.0)E O

0)

(

2.6 -

2.2)E 1

(

2.6 2.2)E 1

(

-1.2 -

0.4 )E 1

(

0/

4)*

(

0/ 4)*

(

0/ 4)*

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(

8.3 7.7)E O 11

(

B.3 7.7)E O

(

9.0 a 5.3)E D

( 0)

(

2.5 -

1.0)E 1

(

2.5 -

1.0)E 1

(

1,6 -

0.7)E 1 1

(

0/ 4)*

(

0/ 4)*

(

0/ 4)*

ZR 95 ( 8)

(

3.7 4.0)E O 11

(

3.7 4.0)E O

(

8.2 2.8)E O I

( 0)

(

5.8 - 158.0)E 1

(

$.8 - 158.0)E 1

(

1.4 -

-0.3)E 1

(

0/ 4)*

(

0/ 4)*

(

0/ 4)*

WON RouilhE REFER $ 10 THE NUMBER OF SEPARATE MEASUREMENTS WHICH WERE GREATER THAN TEN (10) TIMES THE AVERAGE BACKGROUND FOR THE PERIOD 0F THE REPORT.

THE FRAtil0N OF SANPLE ANALYSES YlELDING DETECTABLE MEASUREM6NTS (1.E. >3 $fD DEvlAfl0NS) It INDICATED WifM *(

)*.

l a

gp

~

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r r

EWIRONECi$. RA010 LOGICAL PR0eRAM SkNMARY 1.*lNE TAKfE Al MIC Pd 6R STATION, Wltt.$$l:f, ME (M UARV ' DECEM1ER 1989) l NEDILM t tim : \\CEuS

\\

UNMS: PCl/KG WET IND)C COR W tics.6

$fAfl0N WlfN MIGMh6 NtA0 CONT 4CL $1A110NS o... coee o.eeeee.

e eeeeeeeeeeeeeeeeee,seee eeeeeeeee**eseee RAD:0NUCLIDEs MDSI MEAk

0 AN (NO. ANALYSE $) kEeulRED

$ # i. i tlA.

kANGE RANGE

)

(NON RoutlWE)*

(l?

No. DETECf W

M WO. DETFCYED**

NO. DETECTED **

A1 11DN( 8)

(

?. &.

9. 2 ),

t 11

(

l.; e 0.2)E 1

(

i.5 a 290.8)E 2 t J)

(

1.1 !

eY )E 1

(

1. ' -

2.1)E i

(

6.7 -

5.3)E O

(

t/

ss

(

1, 4)*

(

0/ 4)*

RU 103 ( A)

(

4. 5 k.7)E 0 11

(

4.9 a 2.7)E O

(

5.7 4.6)E D

( 0)

(

1.1 -

0. 1E 1

(

1.1 0.1)E 1

(

1.5 -

0.7)E 1

(

0/ 4)*

(

0/ 4)*

(

0/ 4)*

RU 106 ( B)

(

1.0 a 2.8)E i 11

(

1.0 a 2.8)E i

(

4.5 s 1.2)E i

( 0)

(

74-5.4)E 1

(

7.4 -

5.4)E i

(

7.3 2.0)E 1

(

0/

4)*

(

0/ 4)*

(

0/ 4)*

p

$8 124 ( 8)

(

4.1 7.3)F 0 11

(

4.1 a 7.3)E 0

(

9.2 a 15.1)E 0

( 0)

(

2.5 -

0.9)t 1

(

2.5 -

0.9)E 1

(

4.6 -

2.8)E 1

(

0/ 4)*

(

0/ 4 )*

(

0/ 4)*

l 131 ( 8)

(

1.3 e 2.3)E 1 24

(

5.2 a 11.5)E O

(

5.2 :

11.5)E 0 l

( 0)

(

7.8 -

2.1)E i

(

3.2 -

2.3)E 1

(

3.2 -

2.3)E 1

(

0/ 4)*

(

0/ 4)*

(

0/ 4 )*

C$ 134 ( 8) 130.

( 4.5 a 1.8)E O 11

(

9.5 a 1.8)E O

(

1.7 0.2)E i

( 0)

(

1.4 -

0.6)E 1

(

1.4 -

0.6)E 1

(

2.2 -

-1.1)E i

(

0/ 4)*

(

0/ 4)*

(

0/

4)*

CS 137 ( 8) 150.

(

1.8 1.2)E D 24

(

3.3 a 3.0)E D

(

3.3 a 3.0)E O

( 0)

(

5.3 -

0.3)E 0

(

4.0 -

10.6)E O

(

4.0 -

10.6)E O

(

0/ 4 )*

(

0/ 4)*

(

0/ 4)*

CE 141 ( 8)

(

5.6 a 10.6)K 0 11

(

5.6 10.6)E D

(

2.5 9.7)E O 1

( 0)

(

2.0 -

2.7)E 1

(

2.0 -

2.7)E 1

(

3.1 -

1.1)E 1 1

(

0/ 4)*

(

0/ 4)*

(

0/ 4)*

CE 144 ( 8)

(

6.8 a 103.4)E 1 11

(

4.8 a 103.4)E 1

(

6.0 a 25.9)E O l

( 0)

(

-2.7 -

2.0)E 1

(

2.7 -

2.0)E i

(

3.9 -

7.0)E 1

(

0/ 4)*

(

0/ 4)*

(

0/ 4)*

WON-ROUTINE REFER $ TO THE N M ER OF SEPARATE MEASUREMENTS WHICH WERE GREATER THAN TEN (10) flMES THE AVERAGE SACKGROUND FOR THE PERIOD OF THE REPORT.

THE FRACTION OF SAMPLE ANALYSES YlELDING DETECTABLE MEASUREMENTS (I.E. >3 sfD DEvl AtloNs) is IN01CATED WITH *(

)*..

, ja I

3.13 DirectMiCliCD

-Direct annuna radiation exposure was determined' by the use of '

~

thermolun.inescent ' dosimeters (TLDs). Six calcium sulfate TLD-

~

dosimeters were placed at each of the monitoring stations and read out.on a quarterly. schedule.

I

Summaries of the'results can be seen in the table below and in

~

Figures 3.5 through 3.11~.

Complete data for-the TLD Program are' 9-given in Table 3.1.

As can be seen on Figures.3.5 through 3.11, there'is~a distinct: annual' cycle at both; indicator and control locations. The lowest point-of. Lt.e cycle occurs during the wieter-months. This is due primarily to the attenuating effect of the

q snow cover on-radon' emissions and on direct irradiation by naturally occurring radionuclides.

n i

The mean exposure rates at the inner ring and outer ring stations'

]

are statistically the same, as shown in Table 3.1.

Additionally,-

the station with the highest mean is a control location.. All of j

the above indicates.that there were no detectable increases in

}

direct gamma radiation to-off-site locations due-to'the operation-.

j of Maine Yankee.

'l One TLD badge set was lost during 1989. This was at TL-07-in the i

second quarter and was due apparently to' theft in,the. field.

]

-i

. i i

WPP12/27 U

s I

~

use usw Environmsntal Radiological Prcgram Summary Maine Yankt; Atomic Power Station, Wiscasset, Maino

'Januarv - Decamber 1989

- Medium:- Direct Radiation Measurements.(TLD)

' Units: Micro-R per Hour 7

=

Station With Control Inner Ring Outer Ring Ifighest !$1&n Stations Mean Mean Mun -

Mean Range Range Station Rango Range (No. Maas.)*

_(No. Meas. )*

No.

(No; Hg m j*

(No._Mg M

6.8 10.8 7.0 *1 0 9.3,t0.3' 7.5 kl.4 5.0 - 8.7 4.7 - 9.6 37 9.0 - 9.7 6.2 - 9.7 (71)

(68)

(4)

(12)-

i m

5 3

L t

B

=

=34 aY

\\

.3

=

4 W

j Most measurements based on quarterly readings from six TLD chips.

F -

'WPP12/27

$s 4

K' Table 3.1

?

Environmental Direct Radiation Measurements Maine Yankee Alggic Power Station (Micro-R per Hour) 1989

-Yearly 1, prat. inn -

Iygg*

Ouarter_1 Ouarter 2 Quarter 3 Ouarter 4 Mean

-i TL-1 1

5.5-6.3 7.2 6.9 6.5' d

TL 1 5.9 5.9 6.9

'6.9

-6.4 TL-3=

-I 6.0 6.3 7.0 6.8 6.5-j TL-4' I-4.6 5.3 6.5 5.5-5.5 TL-5 I

6.6 6.9 7.3-7.5 7.1 TL-6 I-6.8

7.4 7.4'-

-7.2

'7.2

.j

'TL-7 I

6.3 7.2 6.9 6.8 TL-8 I-6;2 6.3 6.9i 6.8 6.5 4

'IL-9.

I 7.0

7. 9 -

8.6' 8.3~

'8.0 TL-10 I

-5.9 6;7 6.6

~7.1

6. 6 ~

TL-11 0-6.9 7.3 7.8 7.6, 7.4

^

TL-12 I.

6.0 6.9-7.1

-6.7 6.7 TL-13 I

7.2 7.8 -

.7.9 7.9' 7.7 i

-TL-14 I

5.2

6. 6' 8.7 6.9

~ 6.8-1 TL-15 I

5.0 5.8 6J3 6.0

'5.7 TL-16 I

6.0 7.4 7.4 6.8

,6.9.

.i TL-17 I-6.9

,8.4 8.4 8.0-7.9

-j TL-18 I

6.0 6.9 7.2 7.1=

6.8 TL-19 I

5.6 6.1 6.9 6,6:

6.3 y

TL-20 0

5.2 6.0 6.6-

.6.3 6.0 j

TL-21 0

7 6.0 6.6 6.B:

6.3 TL -22 0

5.9 7.0

'717'

' 7. 2 -

7.0 i

TL-23 0

8.0 9.1 9.6.

8.9

_8. 9 '

l TL-24 0

6.6 7.1

'7.7-7.6

.7.3 TL-25 0

6.4-7.3 7.6 7.3

' 7. 2 -

TL-26 0

6.8

- 7. 3 7.5 7.3 7.2 TL-27 0

5.9 6.5 6.9-6.8 6.5-TL-28 0

5.8 7.9 7.0 6.5 6.8 TL-29 0

5.9 6.2 6.6 6'. 6 6.3

. i TL-30 0

7.4 8.5 8.5

. 8.0 -

8.1 i'

TL 0 7.2 7.9 8.6 8.6 8.1 TL-32 0

6.8 7' ?

7.9 7.2

-7.4 TL-33 0

5.9 6.7 7.1 6,0 6.4 TL-34 0

5.4 6.5 7.6 6 ~. 0 6.4 TL-35 0

4. 7 -

6.2 6.8 5,6 5.8 TL-36 C

6.2 6.,3 6.' ti-6.2 6.3

{

1 TL-37 C

9.1 9.0

.9.7 9.4 9.3 TL-38 C

6.3 6'. 7

.7.7.

6.4 6.8

I -;Innet 5 ting; O = Outer Ring; ~ C = Control.

- No data.-

! WPP12/27 f@

lQg;ffh[ ~

j).$

I

^

1 FIGURE-3.5

' EXPOSURE RATE RT. INNER RING TLDS, TL 01-06 MRINE YANKEE RTOMIC POWER STATION, HISCHSSET, ME 20 18-D - TL-01 OLD FERRY RD.

17 -

o - TL-02 OLD FERRY RD.

A - TL-03 BflILEY HOUSC (ESL) 1s-

+- TL-04 HESTPORT ISL., RT.144 1s-X - TL-05 MY INFORMflTION CENTER o - TL-06 RT. 144 & GREENLEflF RD.

11-E S 12-

. I 11 -

e n.

10-E$

.9-E e-4'

^

E l

7-6-

s-1-

3-2-

1-I ' II II' IV ' IL' II II-" IV LI: " II II ' IV ' I II II - IV I ' II II ~IY -

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Sme P'%' ' '

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a amE

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SCECO I

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DOA+X0 I

II58

, - 9 1

I e

I m

.-y X

p ma I

~

9 7

s 5 H 3 2

1 0

9 e 7 6 5

4 3 2 1

0 s

1 1

i 8

1 1

m r

&E rSz g o

.e_

E c

e m

m n._.

s u

a.

l W

i'W M

M M

M-W : m W,- W.. W ~ '

W. W~

ML-m; M W

mW 4

' FIGURE 3.9 EXPOSURE RATE'RT DUTER RING TLDS, TL 25 MRINE YANKEE HTOMIC PDHER STATION, HISCASSET,.ME 20 19 -

18-0 - TL-25 RIVER RD..& RT. 27-o - TL-26 RT. '271 BOOTHBRY RR 11USEUM 37 _

A - TL-27 BARTERS ISLAND 1s-

+ - TL-28 ht.diruni ISL., E. SHORE RD.

X - TL-29 HRRRISONS TRAILER.

is-o - TL-30 LEEMAN FARM, HOOLHICH.

14-13-12-4 g ' 11-

?

N 10

.e 69-h 8-I^

~

a 7

t r

n.

8-5-

4-3-

3-1.

i I

'I ' II-III' IV ' I II-III 'IV " I ' II III IV I

.II III IV ' '

I' 'II III' IV-1985 1986 1967 1988 1989

-_a

. = - - - ~ _

ww p: w mi FIGURE 3.10-EXPOS!9E RATE AT DUIER RING TLDS, TL 31 MAINE YANKEE FITONIC POWER STATION, HISCASSET, NE:

m 19-1e -

H00LWICH D - TL BARLEY NECK RD.,HICH -

37

-O

.TL-32 BAKER FARM, H00L 1s-A - TL-33 RT. 127, WOOLHICH

+ - TL-34 RT.3127,'N00LHICH.

15-X - TL-35 RT. 127, UMt.dtAN 14-13-5_12-g 4

- e 11-Y 10-

.e 9-l '-

5,_

E X

~

5-4

~

3-2-

1-II'I.III'Iy[.I

.II 'III' IV I- ' II III IV I ' II III' IV ' I II II - IV

,g 1985.

1986 1987

-1988

= - -. _.,,. - -

.-n--,-

AL -

,:-----~~~~~""""~-~""~g^-'

" ' ' ' ^ ^ ^ ^ ^ ' ^ ^ ' ' ~ ~ ' ' ' ' " " " ' ' ^ ^ ~ ~ ~ ~ ~ ' ' " ~

g

U L_J t I;

.m.

FIGURE.3.11 EXPOSURE RATE RT CONTROL TLDS, TL 36-38 MAINE Yf1NKEE f1TOMIC POWER STf1 TION, HISCASSET,' IE

{

2o 19-to-o - TL-36 BOOTHBRY HRBR FIRE STR.

0 - TL-37 BRTH FIRE STA.

so-A - TL-38 DRESDEN SUBSTR.

15-14-13-

~

s 3_

?

w

~

_f 9-x.

. e e-2 A 7-i 6-

.S-4-

3-2-

1-I ' II 'III IV. ' I- " II "IIIIV I' - II -III.' IV " I ' II III IV ' I ' II "III' IV 1985 1986 1997 ISOS -

1989'

.1-

.~h-4_ - - -

w,m

.---__~=---,.aw~

,--w.

-s

~ ~., - -. - -

._.~.-.--s--..

~ --.-_.

__-m__.

W 4.0 QUALITY ASSURANCE PROGRAM Three separate Quality Assurance programs were performed during 1989 to

~l

' demonstrate the validit. of laboratory analyses s.c the-Yankee Atomic Environmental Laboratory (YAEL).

l YAEL 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. en investigationLis made to determine the cause of the problem 1 A

and corrective measures are taken, as appropriate.

. YAEL 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, and analysis of-blank and spiked samples. The records of the quality control program are reviewed by the responsible cognizant it !Pridual, and corrective measures are taken whenever applicable.

A blind duplicate program is maintained in which paired samples from five nuclear plants, including Maine Yankee, are prepared from homogeneous:

media and sent to the laboratory for analysis.

The results from this blind duplicate program are used to check for precisien in laboratory analyses.

l e

EPA Interlaboratory and Intralaboratory Results 4

i The Quality Assurance Program implemented at the analytical laboratory indicated good precision and eccuracy in reported values.

Table 4.1 shows;the results of eccuracy and precision for laboratory analyses in 1989 for 1

intralaboratory analyses and EPA interlaboratory cross-check analyses.

The results of the EPA Interlaboratory Comparison 'Togram, when considered apart from-the remaindor of the Quality Assurance Program, were satisfactory with respect to accuracy and precision in 1989.

One hundred and j

fifty-nine analyses were performed on air particulate filters, milk, and water. The sample analyses that'did not meet the mean value criteria were a WPP12/27 l

s.

' Sr-89 eted o'Sr-90 cn:1ysis on a milk-samplo sot, Th3 mounted;samplos woro.

reanalyzed for Sr-90, and the new Sr-90 mean value fell within the EPA' control

. limits. Details of this may be found in References 3 and 4..

.The above EPA Interlaboratory Comparison Program results are provided in compliance with Technical Specification 4.12.3.

Blind Duplicate Progrrr s

l j

A total of 51 paired. samples were submitted by the five participating q

plants for analysis during 1989. 'The do.a bas'e used for the duplicate y

l analysis consisted of_ paired measurements-of 26 gamma-emitting nuclides, H 3.-

Sr-89, Sr-90, low level I-131. and gross beta.- A. dual level criteria for I

agreement was established.-'If'the paired measurements fall within i 15 percent of their average value,' then agreement'between the measurements has been met.

If the value falls outside of.the'i.15 percent,-then a two standard deviation range (95 percent confidence level) is established for each of 'the '

analyses.

If the ranges overlap, agreement is obtained.

One thousand three hundred and fourteen paired duplicate measurements I

were analyzed for 1989. A total of-99.2 percent of'all measurements fell-j within the established criteria discussed above.

The' eleven measurements that-didnotmeetthecriteriaweremeasurements}ofMo-99inmilk,Be-7inmilk, Np-239 in milk, Ba-140 in milk, Sr-89 in milk, Co-57 in groundwater,~Ba-140 in groundwater, Co-60 in estuary water, 2n-65 in milk, Ce-144 in seawater, and

. Np-239 in estuary w ttr.

I In all of the above cases, the radionuclide in question was-not-j detected in the sample (i.e., the concentration was less than three standard' i

deviations) and the three standard deviation rangea'of the paired measurements.

overlapped. The eleven duplicate measurements represent 0.8 percent of al1~

o the blind duplicate paired measurements made during 1989. No-trend was q

evident with respect to repeated' failings of measurements for the above j

radionuclides.

.62-i

'WPP12/27 i

i

?

l ( ':

b.

,y

~

r,

m p

7, s

4 k

}.

"ti a

Table 4 1 3

,1

.g

. EPA Interlaboratory and Intralaboratory Results - 1989.

.v

- \\,

X Accuraev

'f

^

. Total Number

_of Samples

'0 to 5%

0-to'10%=

- O to-15%*

7).7:'

448' 619 689Ni s

(62.5%)-

(86.3%).

(96.1%)

1 Precision

'l Total-Number

-1

^ gLt; unples -

'O to 5%

0,to 10%

0 te! 15%*'

~

s s.

j 714

-599 1675 710 1

(83.9%)

(94.5%)

J(99.4%)

'\\'

q N,

V i

s s.

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

l

, WPP12/27 I

. f.

5

.y 5.0 LAND USE CENSUS Specification 4.8.B of the Radiological Effluent Technical

(

Specificattor,e requires that a Land Use Census be conducted annually between the dates of June 1 and October 1.

The 1989 census was completed within this time frame. The census is used to identify the location of the nearest milk I

animal, the. nearest residence,-and the nearest garden of 50 square meters within five miles of the plant. The distance from the plant. for each of the above lecations is shown in Table 5.1.

4.

v Only two locations were identified where milk is produced for human consumption. Both locations are currently used as sampling. locations (IN-16 and TM-17). Consequently, no changes were made.in the Milk Sampling.i.

Program as a result of the land use census, pursuant to Technical Specification 4.8.B.2.

j 1

l

)

i l

t

1 N

I 1

i Il WPP12/27 I

2

' - o

,h E

A,

iti Sj Table 5.1 t

j 1989 Land Use censua Resulta.

Maine,Xankee Atomic Power Station

'\\

Nearest Nearest Nearest-l Residence Garden Milk Animal-Seetor-'

(km)

(km)-

N 1.3 1.3

.q NNE 2.3

.2.5 i

s

-NE.

1.3-

'1.3 ENE-O!9 (summer only) 1.2

n j

1.2 (year-round)-

c, -

\\

1 E

0.9 0.9-i ESE

.1.4 7. '3

\\,

s SE s 0.7 7. 8.1 1

SSE' O.9 0. 9,,

0 1.7 2.7 i

+

-)

]

SSW 3.0

-5.2 SW 1.4 3.8 7.9l 4 ;

ll WSW 1.0 3.0 i

M W

2.6 2.7 7.2

'I 4'

WN\\1 0.8 2' 8

[

i NW 2.0 2.0 e.

s NNW.

1.1 1.4.

i k

\\.

.y u,'

r i

'l 4

i

.\\.

. WPP12/27 o

' \\'

.j

-}.

a i

. -y 4 4

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.n w.

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\\~

o.1 s.

,y.m 6.0

SUMMARY

AND CONCLUSIONS During 1989, Maine Yankee's environmental monitoring program detected trace levels of man-made radionuclides in the vicinity of the Maine Yankee plant. Most of this radioactivity resulted from nuclear weapons testing and the Chernobyl nuclear accident.

Plant operations contributed to the trace amounts of radioactivity in several samples.

In all cases, the levels of radioactivity detected were much less than the applicable Technical Specification reporting levele, and are judged to have no environmental or health impact.

v.4 WPP12/27 H.

ugg yng gyggggggggggggggggg

700 REFERENCES

,i 1.

Maine Yankee Atomic Power Company, Off-Site Dose Calculation Manual,

~

J Table 4.1.

2.

USNRC Regulatory Guide 1.09, Revision 1, " Calculation of Annual Dones to j

Man From Routine Dal:A es of Reactor Effluents for the Purpose of Evaluating Compliat ith 10CFR50, Appendix I."

s u__

3.

2nkee Atomic Environmental Laboratory Semiannual Quality Assurance Status Report, January - June 1989, Yankee Atomic Electric Company.

3 4.

Yankee Atomic Environmental Laboratory Semiannual Quality Assurance 4

Status Report, July - December 1989, sakee Atomic Electric Company.

M 1

M y

II h=

e 2

R 4

i#

- WPP1P./27 f

nt d

I inassens i

,

ML20034C791

Contents

Text

SUMMARY

SUMMARY

SUMMARY

7.0 REFERENCES

1.0 INTRODUCTION

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

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ML20034C791

Text

SUMMARY

SUMMARY

SUMMARY

7.0 REFERENCES

1.0 INTRODUCTION

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

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