Text

Annual Radiological Environ Operating Rept,1985
	ML20202E830
Person / Time
Site:	Yankee Rowe
Issue date:	12/31/1985
From:	Papanic G; YANKEE ATOMIC ELECTRIC CO.
To:	Murley T; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
	DCC-86-042, DCC-86-42, FYR-86-047, FYR-86-47, NUDOCS 8607150025
	Download: ML20202E830 (68)
	v • d • e

_. _ _

I I

l l

YANKEE ATOMIC ELECTRIC COMPANY l

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT January - December 1985 lI

'I April 1986 I

I I

I

/

I Prepared By:

Yankee Atomic Electric Company Environmental Engineering Department 1671 Worcester Road Framingham, Massachusetts 01701 i

)

8607150025 851231 PDR ADOCK 05000029 R

PDR

\\,

I T ABl F OF CONTENTS Page LIST OF TABLES.

iii LIST OF FIGURES......

iv

1.0 INTRODUCTION

1 i

2.0 ENVIRONMENTAL MONITORING PROGRAM.......................

2 I

3.O

SUMMARY

OF 1985 ENVIRONMENTAL DATA.

13 A.

Air Particulate..

15 B.

Charcoal Filter.

'19 i

l C.

Milk.

21 D.

Food Crop.

27 E.

Broad Leaf Vegetation.

30 I

F.

Maple Syrup.

32 G.

Ground Water...

35 H.

River Water.

38 I.

Sediment.

41 E

J.

Finfish.

44 K.

Direct Radiation..

47 4.0 QUALTTY ASSURANCE PROGRAM.

56 5.0 LAND USE CENSUS.

60 1

6.0

SUMMARY

62 7.O REFERENCES.

63 i

l I

I I

g I

I LIST OF TABLES I

Number Title Page 2.1 Yankee Atomic Radiological Environmental Monitoring Program 3

2.2 Yankee Atomic Radiological Environmental Monitoring Locations.

4 I

3.1 Yankee Atomic Summary of Direct Radiation Measurements - 1985..

55 4.1 Intralaboratory and EPA Interlaboratory Results - 1985.

57 5.1 1985 Land Use Consus Results.

61 I

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i i

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-u i-I I

I LIST OF FIGURES Number Title Page 2.1 Yankee Plant Radiological Environmental Monitoring Locations Within 1 Mile ( Airborne, Waterborne, and I

Ingestion Pathways).

6 1

l 2.2 Yankee Plant Radiological Environmental Monitoring Locations Within 12 Miles (Airborne, Waterborne, and

'E Ingestion Pathways).

7 g

2.3 Yankee Plant Radiological Environmental Monitoring g

Locations Outside 12 Miles (Airborne, Waterborne, and Ingestion Pathways).

8 2.4 Yankee Plant Radiological Environmental Monitoring Locations at the Restricted Area Fence (Direct Radiation Pathway).

9 2.5 Yankee Plant Radiolegical Environmental Monitoring Locations Within 1 Mile (Direct Radiation Pathway)....

10 2.6 Yarakee Plant Radiological Environmental Monitoring Locations Within 12 Miles (Direct Radiation Pathway)..

11 1

2.7 Yankee Plant Radiological Environmental Monitoring Locations outside 12 Miles (Direct Radiation Pathway).

12 3.1 Gross Beta Measurements of Air Particulate Filters at Yankee Atomic.

16 3.2 Cesium-137 in Cow Milk at Yarkee Atomic.

22 3.3 Strontium-90 in Cow Milk at Yankee Atomic..

23 3.4 Cosium-137 in Cow Milk at Station TM-11..

24 3.5 Exposure Rate at Indicator TLDs, GM 01-07...

48 3.6 Exposure Rate at Indicator TLDs, GM 08-12, 40..

49 3.7 Exposure Rate at Outer Ring TLDs, GM 24-31.

50 3.8 Exposure Rate at Outer Ring TLDs, GM 32-39..

51 3.9 Exposure Rate at Fenceline TLDs, GM 13-21..

52 3.10 Exposure Rate at Control TLDs, GM 22-23..

53 I

l

-iv-I

1.0 INTRODUCTION

I The radiological environmental surveillance program at Yankee Atomic has been designed and carried out with specific objectives in mind.

They are as follows:

I 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.

i I

To provide assurance to regulatory agencies and the public that the station's environmental impact is known and within anticipated limits.

To verify the adequacy and proper functioning of station effluent controls and monitoring systems.

To provide standby monitoring capability for rapid assessment of risk to the general public in the event of unanticipated or 3

accidental releases of radioactive material.

During 1985, as"in the past, the plant staff collected the bulk of the environmental samples and processed all environmental thermoluminescent dosimeters (TLDs) for direct radiation measurements.

After the initial processing, all non-TLD samples were sent to the Yankee Atomic Environmental Laboratory in Westboro, Massachusetts for further processing and radionuclide analysis.

I This report is a summary of the findings of the Radiological Environmental Surveillance Program for 1985.

It is being provided in compliance with plant Technical Specification 6.9.5.a.

I I

I 2.0 ENVIRONMENTAL MONITORING PROGRAM I

In this section, Table 7.1 outlines the monitoring program as required by the plant Technical Specifications. Table 2.2 lists the sampling stations and their specific locations (distances are measured from the center of the containment building). The sampling locations are shown on maps in Figures 2.1 through 7.7.

E Below are listed the two-letter media codes and what they represent:

I AP Air Particulate CF Charcoal Filter TM Milk WG Ground Water WR River Water I

TF Food Crop TV Broad Leaf Vegetation MS Maple Syrup I

GE Sediment FH Finfish GM Direct Radiation (TLD) f I

I i

I

~

I I

_ p._

I

I Table 2.1 Yankee Atomic Radiological Environmental Monitoring Program I

Media Samplinq Frequency Required Analyses I

Air Particulate (AP)

- Weekly Gross beta

- Quarterly Composite Gamma spectroscopy Charcoal Filter (CF)

- Wookly I-131 Milk (TM)

- Monthly; once per Gamma spectroscopy, 2 weeks from June 1 I-131 to Nov. 1 Food Crop (TF)

- Annually (Harvest)

Gamma spectroscopy Broad Leaf Vegetation (TV)

- Annually (Harvest) 1-131 l

Ground Water (WG)

- Quarterly Gamma spectroscopy, H-3 River Water (WR)

I

- Monthly (Composite)

Gross beta, Gamma spectroscopy, I-131

- Quarterly Composite H-3 Sediment (SE)

- Semiannually Gamma spectroscopy Finfish (FH)

I

- Seasonal or Gamma spectroscopy Semiannually Direct Radiation (GM)

- Quarterly De--dose only I

- Quarterly Intergrated gamma (Outer ring TLDs)

(All other TLDs) dose i

I I

I Table 2.2 Yankee Atomic Radiological Environaontal Monitoring Locations i

Distance From Direction Station Code Station Plant From (Media - Sta. No.)

Description Zone *

(km)

Plant E

AP/CF-11 Observation Stand 1

0.5 NW AP/CF-12 Monroe Bridge 1

1.1 SW I

AP/CF-13 Rowe School 1

4.2 SE AP/CF-14 Harriman Station 1

3.2 N

AP/CF-21 Williamstown, MA 2

22.2 W.

AP/CF-31*M Furlon House 1

0.8 SW I

AP/CF-32M*

Heartwellville, VT 2

12.6 NNW TM-11 Heath, MA 1

5.8 E

I.

TM-12 Readsboro, VT 1

6.1 N

TM-21 Williamstown, MA 2

21.0 WSW I

TF-11 Monroe Bridge 1

1.3 SW TF -12 F-ord Hill Road 1

3.5 E

TF-21 Williamstown, MA 2

21.0 WSW TV-11 Monroe Bridge 1

1.3 SW MS-31MM Roadsboro, MA 1

6.1 N

I MS-41MM Heath, MA 1

5.3 E

MS-42MM Williamstown, MA 2

28.3 WSW I

WG-11 Plant Potable 1

On-S i te WG-12 Sherman Spring 1

0.2 NW WR-- 11 Bear Swamp Lower Res.

1 6.3 Downriver WR-21 Harriman Reservoir 2

10.1 Upriver SE-11 No. 4 Station 1

36.2 Downriver SE-21 Harriman Reservoir 2

10.1 Upriver FH-11 Sherman Pond 1

1.5 N

FH-21 Harriman Reservoir 2

10.1 Upriver GM-1 Furlon House 1

0.8 SW GM-2 Observation Stand 1

0.5 NW I

GM-3 Rowe School 1

4.2 SE GM-4 Harriman Station 1

3.2 N

GM-5 Monroo Bridge 1

1.1 SW I

GM-6 Readsboro Road Barrier 1

1.3 N

GM-7 Whitingham Line 1

3.5 NE GM-8 Monroe Hill Barrier 1

1.0 S

g

-4

I I

Table 2.2 (Continued)

I Yankee Atomic Radiological Environmental Monitoring Locations I

Distance From Direction I

Station Code Station Plant From (Media - Sta. No.)

Description ZonoM (km)

Plant GM-9 Dunbar Brook 1

3.2 SW GM-10 Cross Road 1

3.5 E

GM-11 Adams High Line 1

2.1 WNW GM-12 Readsboro, VT 1

5.5 NNW GM -13 Restricted Area Fence F

O.08 WSW GM-14 Restricted Area Fence F

O.11 WNW I

GM-15 Restricted Area Fence F

O.08 NNW GM-16 Restricted Area Fence F

O.13 NNE GM-17 Restricted Area Fence F

O.14 tNE GM-18 Restricted Area Fence F

O.14 ESE 5

GM-19 Restricted Area Fence F

O.16 SE GM-20 Restricted Area Fence F

O.16 SSL GM-21 Restricted Area Fence F

O.11 SSW I

GM-21 Heartwellville, VT 2

12.6 NNW GM-23 William *stown Substation 2

22.2 W

GM-24 Harriman Dam O

7.3 N

I GM-25 Whitingham, VT O

/.7 NNE GW 26 Sadoga Road O

7.6 NE GM-27 Number 9 Road O

7.6 ENE GW 28 Number 9 Road O

6.0 E

I GM-29 Route 8A O

8.2 ESE GM-30 Route 8A O

9.4 SE GM-31 Legate Hill Road O

7.6 SSE I

GM-32 Rowe Road O

7.9 S

GM-33 Zoar Road O

6.9 SSW GM-34 Fife Brook Road O

6.4 SW I

GM-35 Whitcomb Summit O

8.6 WSW GM-36 Tilda Road O

6.6 W

GM-37 Turner Hill Road O

6.7 WNW GM-38 West 'ill Road O

6.6 NW I

G4-39 Route 100 0

6.8 NNW GM-40 Readsboro Road 1

0.5 W

I 1 = 3ndicator Stations; ~2 = Control Stations; O = Outer Ring Incident Response TLD; F = Fencoline.

MX Not required by Radiological Effluent Technical Specifications.

I g

i E

/

FH-11

__ /

P.assachusetts

/

N 0

soo I

e e

t METERS l sxtRMAN roxD ;

\\//

/

I

/

AP/CF-11 0 i f@ wc-12 /p;-

9 f,

9 S,,

~

wc-11 E

s,,

~'

o,

=

AP/CF-31 I

Monroe Bridge e AP/cF-12 1

--11 g

% e.,,, # *<f krg,.,

0 4;

I I

~

(

Figure 2.1 Yankee Plant Radiological Environmental Monitoring Locations I

Within 1 Mile (Afrborne, Waterborne and Ingestion Pathways) i

E I

\\

I 7

I C

Hauunan Ruu.voir HEARTWELLVILLE

@ AP/CF-32 j n I

f=_=

I M

~ SE-21 3 FH-21

WHITINGHAM MS-31 READSBOR0 I

WR-21

@ AP/CF-14 SittAmn Pond E

L5

~_.

5 VERMONT

=,

I MASSACHUSETTS HONROE BRIDGE I

i E lWe SEE ENEARCEMENT IN FIGURE 2.1 I

PLA.NT l l---

_q

@ IN-Il 8

MS-41 8 tat Semp losaer guezvo;g,_

@TF-12

@AP/CF-13 I

R0WE

@ WR-11 I

HEATH E

e44h 4 et CHARLEMONT o

8 1

t i

e ir KILOMETERS SE-Il @

SHELBURNE FALLS,

Figure 2.2 Yankee Plant Radiological Environmental Monitoring Locations within 12 Miles (Airborne, Waterborne and Ingestion Pathways) g I

I BENNINGT0h o

i I

HEARTWELLVILLE e

I l

l l

e WHITINGHAM READSBORO '

\\

-[------

VT.

ys-42 MONROE BRIDGE e PLANT MSS.

c1

- ' f WILLIAMSTOWN A ^5

@ AP/CF-21 R0WE 1

TF-21 HEATH l

l 5

%g et.

CHARLEMONT e

SHELBURNE FALLS

I I

O 5

10 15 20 t

i e

i I

PITT5 FIELD KILOMETERS e

Figure 2.3 Yankee Plant Radiological Environmental ?fonitoring Locations Outside 12 Miles (Airborne, Wa'.crborne and Ingestion Pathways) I

I I

E N

0 50 100

,t f

I

,,,, I

,,f I i,,, f

.,,,,y, METERS

-- 9_i- ';.s. A;

'U

[*.;-

l; v.

t E

7, '.'.

/

g..

y

,,. n. v..

sy x y!ga SHEDVN POND E

J.'

o' GM-14 @' - : : - -- -::p g GM.i5 cate Hou5e Sw!tch

offices

,' yardg l gj,j g,

I e

l l '.

Turbine Service Information Gh-13..,'

,,,, g,y 37,,

Center e

Uhse.

'.g I

L,,

,-~~p

,o e r,e JAv ' a,, **....' #N".

C a

e a

~.

lo;,*'

m

~

q

~

G l PAB s

i e

3

/

'g n

00 O

O p

5 i)O Ol ::

/

@ GM-21 W'5

Disposal

[

l

/

s I

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I e

i

\\

l t

s,

, -@ GM-18 ~ ~ ~

I

,,,@ GM-19 s

I I

\\

l Figure 2.4 Yankee Plant Radiological Environmental Monitoring Locations at the Restricted Area Fence (Direct Radiation Pathway) _

I

\\

4 i

I 4

veivo n j

Gn.s @

M4554Chuset I

%ig.

l t

0 5oo k

I e

i e

e I

g METERS

{NERMN MN

\\

I e

/

I a.z. r W

=-

P E

I p GM.40

+

S.

b R

~

s E

=

GM-1 @

Monroe Bridge gs~

nro e g,,

N A

ta,

ry d

4,_ -

I 4

SStv

@ GM 8 I

Figure 2.5 Yankee Plant Radiological Environmental Monitoring Locations Within 1 Mile (Direct Radiation Pathway) I

I D

/

N SSY

/

l

/

j t.

I Ew HEARTWiltVI LE

/

GM-22 i

[

~*~

l

'/

l P~r*

E h

5 Hiles ~

GM-24 @ T

' _ @ GM-25

-

WHl '1 N GH AM I

GM-39 gg

,REA BORO

@GM-38

UM*20 g

I

. GM-4 kenc Pond

@CM-37 GM-ll l

8 b bM-7

~"~

VERMONT j

gg R,IDG[

IN T URE 4-$

. I g

PLANT l GM-10

@GM-28 t_____i j

/

@GM-9 I

8tM vp Lw Ru oir GM-35 GM-3

@GM-29 GM-34@

R0WE

@GM-33 HEATH

@GM-30

@GM-31 o

GM-32 4

ct CHARLEMONT l

0 5

to 8

1 1

i f

a i

1 1

KILOMETERS

}

I 6

SHELBURNEFALLS,(

I Figure 2.6 Yankee Plant Radiological Environmental Monitoring Locations Within 12 Miles (Direct Radiation Pathway) 1 _

E I

s

\\

u N

I

)

0Wu EMN!NGTON g

s.

l HEARTWELLV LLC E

\\

i I

e W LTINGHAM d'

DSBORO

t

\\

VT.

E

) M40 e

~ TH I

4 CHARLC T

u BURNE FALLS *

\\

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%y SY s

o 5

to 15 20 i

e i

PITTSFIELO I

Figure 2.7 Yankee Plant Radiological Environmental Monitoring Locations I

Outside 12 Miles. (Direct Radiation Pathway)

E 3.0

SUMMARY

OF 1985 ENVIRONMENTAL DATA The following pages summarize the analytical results of all the I

environmental samples which were collected during 1985.

Each environmental media category is presented as a separate subsection.

A discussion of the sampling grogram and results is followed by a table which summarizes the year's data for each category.

The tables were generated by the computer program, ERMAP.

At the top of each table, ERMAP lists the units of measurement for each medium.

The left 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 for the control station (s).

The latter are classified as "non-routine" measurements.

Er The next column lists the lower Limit of Detection (LLD) for those radionuclides which have detection capability requirements as specified in the plant's Radiological Effluent Technical Specifications.

(Requirements are not given for many of the radionuclides routinely measured and reported herein.)

E Those sampling stations which are within the range of influence of the plant and which could conceivably be affected by its operation are called

" Indicator" or " Zone I" stations.

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

Direct radiation I

monitoring stations are broken down into two additional categories to aid in data analysis.

These are fenceline stations and outer ring (emergency response) 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:

I The mean value of all concentrations including negative values and o

values below LLD.

g o

>he stanea,e e,,o,of the mean.

The lowest and highest concentration.

o E

o The number of positive measurements (activity which is three times greater than the standard deviation) divided by the total number of measurements.

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 quoted uncertainty term represents only I

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.

Expressed in another way, the measurement is considered to be statistically different than normal instrument background when the ples or minus three standard deviation range surrounding the measurement does no. include zero.

During the second quarter, the TLD badges at Station Gl%24, Harriman 8

Dam and GM-3 2, Rowe Road, were apparently stolen.

During the fourth quarter, the TLD badge at Station GM-24, Harriman Dam, was apparently stolen.

The badge at Station CM-24 was moved to a nearby but less conspicuous location.

The annual average exposure rate, as reported in Table 3-1, is based on available data only.

I I

I E

I

~

I I

I A) Air Particulate Air monitoring stations are established at a total of seven locations, five of which are required by the Radiological Effluent Technical Specifications. The air pumps at these locations operate continuously at a flow rate of approximately one cubic foot por minute.

Airborne particulates are collected by passing the air through a glass-fiber filter.

These filters are collected weekly I

and held for at least 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> before being analyzed for gross-bets mctivity (indicated as GR-B in tables) to allow for the decay of radon and thoron daughter products. Weekly composite air filters from each location are analyzed quarterly for gamma-omitting radionuclides.

I Gross-beta analyses (Figure 3.1) show random fluctuations at all sampling locations including controls, thereby indicating that any plant contribution is negligible.

For the gamma analyses, no activity was detected at either the indicator or control locations, with the exception of naturally occurring K-40 and Be-7.

I I

I I I

M M

M mW M

M FIGURE 3.1 l

GROSS BETA MERSUREMENTS OF RIR PRRTICULRTE FILTERS f

YRNKEE RTOMIC ELECTRIC COMPRNY, R0WE, MR f

0.06 0- STATION 11 O-STATION 12 o,m _

A - STATION 13

+ - STATION 14 X-STATION 21 0 - STATION 31 v - STATION 32

~

L i

a N

0.03 -

0 5

/

l1 8

f 0.02-0.01-Jag ' rm ' mR ffR (18Y ' JUN JUL ' BUG SEP OCT NOV DEC

5 EWIROMNTAL RADIOLOGICAL PROGRAM SumARY YAPGCEE NUCLEAR POWER STATION R0WE MA I

JARIARY - DECEISER 1985 EDIlM: AIR PARTICtLATE tNITS: PC!/CU. N INDICATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONS e..

e.

..e.....

I RADIONUCLIDES EAN EAN EAN (NO. ANALYSES) REQUIRED RANGE STA.

RANGE RANGE (NDHOUTIE)*

LLD NO. DETECTED *.

NO.

NO. DETECTED.*

NO. DETECTED *e I

c e OR-B (364)

.01

(

2.2

.0)E -2 21

( 2.4 i

.1)E -2

( 2.2 i

.1)E -2

( 0)

( 8.4 - 39.8)E -3

( 1.1 -

4.3)E -2

( 9.8 - 43.3)E -3 a(260/260)e

( 52/ 52)e e(104/104)*

l BE-7 ( 28)

(

5.li

.2)E -2 11

( 5.8 i

.7)E -2

( 5.2 i

.3)E -2 l

( 0)

( 3.7 -

7.8)E -2

( 4.5 -

7.8)E -2

( 4.4 -

6.8)E -2 I

a( 20/ 20)*

(

4/ 4)*

( 8/ 8)e K-40 ( 28)

( 3.St

.5)E -3 12 ( 6.2 i

.5)E -3

( 4.1 i

.8)E -3 i

( 0)

(-4.8 - 70.4)E -4

( 4.8 -

7.0)E -3

(-3.1 - 68.01E -4 et 2/ 20)*

(

1/ 4)*

(

1/ Sie PW-54 ( 28)

(

!.6t 2.4)E -5 14

( 9.4 i 5.1)E -5

(-1.8 i 1.8)E -5

( 0)

(-1.8 -

1.8)E -4

(-5.2 - 18.3)E -5

(-9.6 -

3.9)E -5

(

0/ 20)e et 0/ 4)*

(

0/ Ole C0-58 ( 28)

(

1.31 3:0)E -5 13

( 6.6 i 6.5)E -5

(-1.2 i 6.3)E -5

( 0)

(-1.9 -

2.8)E -4

(-6.1 - 21.4)E -5

(-4.1 -

1.5)E -4 et 0/ 20)*

(

0/ 4)*

( 0/ 8)*

FE-59 ( 28)

(

1.11

.9)E -4 12 ( 4.1 1 2.5)E -4

(-1.1 1 1.3)E -4

( 0)

(-5.6 -

8.6)E -4

(-2.7 -

8.6)E -4

(-6.6 -

4.4)E -4

(

0/ 20)*

( 0/ 4)*

( 0/ 8)*

CO-60 ( 28)

( -4.li 4.0)E -5 14 ( 1.2 i 1.0)E -4

( 5.7 i 5.5)E -5

( 0)

(-4.2 -

3.5)E -4

(-1.3

. 3.5)E -4

(-1.5 -

2.9)E -4 et 0/ 20)*

( 0/ 4)*

( 0/ 8)*

ZN-65 ( 28)

( -5.9i 5.4)E -5 13

( 6.3 i 22.2)E -5

(-9.5 i 8.8)E -5 I

( 0)

(-5.5 -

4.8)E -4

(-3.6 -

4.8)E -4

(-4.0 -

4.3)E -4

(

0/ 20)e e( 0/ 4)*

et 0/ 8)*

ZR-95 ( 28)

( 8.2i 6.0)E -5 11

( 1.6 i 2.2)E -4

(-1.7 i

.6)E -4 I

( 0)

(-3.6 -

6.7)E -4

(-3.3 -

6.7)E -4

(-4.0 -

.5)E -4 el 0/ 20)*

a( 0/ 4)*

s( 0/ 8)*

I e NON-ROUTIE REFERS TO TE NUMBER OF SEPARATE EASUREENTS lei!CH WERE GREATER I

TMN TEN (10) TIES TE AVERAGE BACKGROLN) FOR TE PERIOD W TE REPORT.

.* TE FRACTION OF SAPFLE ANALYSES YIELDING DETECTABLE EASUPIENTS (I.E. >3 STD DEVIATIONS) IS INDICATED WITH *(

le. I

B ENVIR0ffENTAL RADI(LOGICAL PROGRAM SlfftARY YAM (EE NUCLEAR POIR STATION R0WE. M4 I

JANJARY - DECEMBER 1985 EDILM: AIR PARTIClLATE LNITS: PCI/CU. M I

IM)ICATOR STATIONS STATION WITH HIGEST EAN CCNTROL STATIONS musum*+++m e m e+e** m u m *we++ee e*+e u se m e m e I

RADIONUCLIDES MEAN EAN MEAN (ND. ANALYSES) REQUIRED RANGE STA.

RANGE RANCE (N0HOUTIE)*

LLD NO. DETECTED **

NO.

NO. DETECTEDee NO. I)ETECTEDee I

AG-110M( 28)

( -4.9t 3.2)E -5 14

( 5.0 i 5.4)E -5

(-3.3 1 6.9)E -5

( 0)

(-3.5 -

2.0)E -4

(-5.0 - 20.2)E -5

(-2.8 -

2.1)E -4

(

0/ 20)e et 0/ 4)e a( 0/ 8)*

RU-103 ( 28)

( -7.7f 32.5)E -6 32 ( 1.4 i 1.3)E -4

( 7.1 i 6.6)E -5

( 0)

(-2.5 -

3.9)E -4

(-1.7 -

3.5)E -4

(-1.7 -

3.5)E -4 I

(

0/ 20)*

( 0/ 4)*

a( 0/ Ble RU-106 ( 28)

( -9.7t 26.0)E -5 21

( 3.8 i 5.2)E -4

( !.3 1 33.9)E -5 I

( 0)

(-1.8 -

1.7)E -3

(-1.2 -

1.1)E -3

(-1.2 -

1.1)E -3

(

0/ 20)e

( 0/ 4)e et 0/ 8)*

I CS-134 ( 28)

.05

( -0.lt 3.4)E -5 14

( 6.1 t 10.1)E -5

(-6.5 i 4.1)E -5

( 0)

(-4.1 -

3.5)E -4

(-8.8 - 35.4)E -5

(-1.8 -

1.7)E -4

(

0/ 20)e et 0/ 4)e s( 0/ 8)e CS-137 ( 28)

.06

( -3.0i 36.1)E -6 32 ( 1.9 i

.9)E -4

( 9.6 i 6.5)E -5

( 0)

(-3.0 -

3.9)E -4

(-7.4 - 347.0)E -6

(-2.3 -

3.5)E -4

(

0/ 20)e

(

0/ 4)e

(

0/ 8)e BA-140 ( 28)

( -5.0i 10.4)E -5 13 ( 5.3 i 1.9)E -4

( 1.6 t 2.4)E -4

( 0)

(-8.2 -

9.8)E -4

( 1.9 -

9.8)E -4

(-8.2 - 13.8)E -4

(

0/ 20)e

(

0/ 4)e

( 0/ 8)*

CE-141 ( 28)

( 3.5i 4.3)E -5 14 ( 1.4 i 1.1)E -4

( 2.2 i 8.2)E -5

( 0)

(-2.4 -

3.3)E -4

(-1.4 -

3.3)E -4

(-3.5 -

4.4)E -4

(

0/ 20)*

s( 0/ 4)e

( 0/ 8)*

CE-144 ( 28)

( -2.11 1.2)E -4 14

( 9.7 1 29.7)E -5

( 4.0 t 15.8)E -5 I

( 0)

(-1.6 -

1.0)E -3

(-3.2 -

9.6)E -4

(-6.1 -

5.2)E -4

(

0/ 20)*

(

0/ 4)e

( 0/ Sie TH-232 ( 28)

(

1.9i 1.1)E -4

( 5.3

2.9)E -4

( 9.1 1 18.9)E -5 I

( 0)

(-8.9 - 14.0)E -4

( 1.4 - 14.0)E-4

(-4.3 -

8.6)E -4 et 0/ 20)*

(

0/ 4)e

( 0/ 8)*

I I

NDHOUTIE REFERS TO TE NUMBER OF SEPARATE EASUREENTS kHICH WERE GREATER e

THAN TEN (10) TIES TE AWRAGE BACKGROLN) FOR TE PERIOD OF TE REPORT.

- TE FRACTION OF SAWLE ANALYSES YIELDING DETECTABLE EASLREENTS (I.E. >3 STD DEVIATIONG) IS INDICATED WITH *(

le.

I

- I

E B) Charcoal Filters I

Charcoal filter cartridges are situated in series with the air particulate glass-fiber filters. Monitoring stations were located at a total of seven stations, five of which were required by the Radiological Effluent Technical Specifications.

The air pumps at these locations operate continuously at a flow rate of lI approximately one cubic foot per minute.

l Charcoal filters were collected and analyzed weekly for 1-131 m

activity.

No I-131 was detected in charcoal filter samples during 1985.

I I

I ENVIR0l# ENTAL RADIOLOGICAL PROGRAM SLM%RY YApe(EE NUCLEAR POWER STATION. ROE, MA I

JAIGRY - DECEl@ER 1985 ED!lM: OMRC0AL FILTER LMITS: PCI/CU. M Ile!CATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONS RADIONUCLIDES EAN EAN EAN I

(NO. ANALYSES) REQUIRED RANGE STA.

RANGE RANGE (NON-ROUTIE).

LLD NO. DETECTED..

NO.

NO. DETECTED..

NO. DETECTED l

I-131 (364)

.07

( -7.4t 2.9)E -4 21

(-2.4 t 5.3)E -4

(-1.3 i

.5)E -3

)

( 0)

(-1.6 -

1.0)E -2

(-1.1 -

.9)E -2

(-1.6 -

.9)E -2

.(

0/260).

.(

0/ 52).

.(

0/104).

l I

. NON-ROUTIE REFERS TO TE IUSER OF SEPARATE EASLREENTS leIICH ERE GREATER THAN TEN (10) TIES TE AVERAGE BACK0R0lN) FOR TE PERIOD OF TE REPORT.

I TE FRACTION OF SAPPLE ANALYSES YIELDING DETECTABLE EASUREENTS (I.E. >3 STD DEVIATIONS) IS INDICATED WITH.(

)..

I I

~

I I

E C) Milk Milk samples were collected and analyzed by the schedule shown in Table 2.1.

I Detectable concentrations of Cs-137 and Sr-90 were measured in milk I

samples submitted from the indicator and control locations. The mean concentrations of Cs-137 and Sr-90 in milk samples from the indicator location were greater by a factor of 10 and 3.2, I

respectively, than from the control location (see Figures 3.2 and 3.3).

The higher concentration in indicator station samples has been noted for several years.

It has been shown in previous reports that the radionuclides in the cows' food, particularly pasture grass, are a result of atmospheric nuclear weapons testing fallout, and that farming practices (amount of vegetation and type I

of vegetation that the cows are allowed to feed on) can cause large variations of Cs-137 and Sr-90 concentrations in milk.

The characteristic annual fluctuations for Cs-137 seen at Station TM-11 (Heath, Massachusetts) are soon in Figure 3.4.

The concentrations peak during the summer months when animals are on pasture. Mean concentrations and ranges for the control station and indicator station, for Cs-137 and Sr-90, were similar to those measured for 1983 and 1984 (References 1 and 2).

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I EWIR0ffENTAL RADIOLOGICAL PROGRAM S(MMRY YAPtIE MJCLEAR POER STATION, ROE MA JANUARY - DECEMER 1985 l

EDIUM: MILK LNITS: PCI/KG I

IISICATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONS ennuneuenne neutuennunnenne annueeseenee RAD 10NI2. IDES MEAN MEAN MEAN I

(NO. AMLYSES) REQUIRED RANGE STA. lWNDE RANGE (NON-ROUTIEle LLD NO. DETECTEDee NO.

NO. DETECTED *e NO. DETECTEDes SR-89 ( 12)

( -7.0i 41.1)E -2 12 ( 2.8 1 1.3)E -1

(-3.5 t 4.2)E -1

( 0)

(-2.6 -

1.4)E 0

(-4.1 - 58.0)E -2

(-1.2 -

.6)E 0 at 0/ Ble a( 0/ 4)e

(

0/ 4)e SR-90 ( 12)

( 6.lt 1.0)E 0 11

( 8.5 i

.6)E 0

( !.9 i

.2)E 0

( 0)

( 3.0 - 10.2)E O

( 7.6 - 10.2)E 0

( !.4 -

2.6)E O at 8/ 8)e

(

4/ 4)*

(

4/ 4)e K-40 ( 57)

(

1.3t

.0)E 3 21

( !.4 t

.0)E 3

( l.4 i

.0)E 3 I

( 0)

( !.2 -

1.5)E 3

( !.3 -

1.4)E 3

( 1.3 -

1.4)E 3

( 38/ 38)e

( 19/ 19)*

( 19/ 19)e 19i-54 ( 57)

( -8.5i 12.3)E -2 12 ( 9.4 t 18.8)E -2

( 2.2 t 18.8)E -2

( 0)

(-2.1 -

1.3)E O

(-2.1 -

1.3)E 0

(-1.2 -

1.3)E O

(

0/ 38)e e( 0/ 19)e

(

0/ 19)*

C0-58 ( 57)

( -1.71 1.5)E -1 21

(-7.1 i 20.9)E -2

( 0)

(-2.6 -

1.8)E O

(-2.1 -

1.9)E O

(-2.1 -

1.9)E O

(

0/ 38)*

(

0/ 19)*

(

0/ 19)*

FE-59 ( 57)

(

9.0f 4.5)E -1 11

( 1.3 i

.7)E O

( 2.6 i 4.4)E -1

( 0)

(-4.0 -

7.4)E O

(-3.7 -

6.1)E 0

(-5.0 -

3.5)E O

(

0/ 38)e e( 0/ 19)e

(

0/ 19)e CO-60 ( 57)

( -3.2i 1.3)E -1 11

(-2.9 i 1.6)E -1

(-3.6 i 1.7)E -1

( 0)

(-2.1 -

1.3)E O

(-1.5 -

1.0)E 0

(-1.7 -

.8)E O l

(

0/ 38)*

a( 0/ 19)*

(

0/ 19)*

IN-65 ( 57)

( -3.9i 3.6)E -1 21

( 4.9 i 46.8)E -2

( 4.9 i 46.8)E -2 I

( 0)

(-4.4 -

4.8)E O

(-4.6 -

2.7)E O

(-4.6 -

2.7)E 0 at 0/ 38)e et 0/ 19)e et 0/ 19)*

ZR-95 ( 57)

(

!.7i 2.6)E -1 12

( 3.0 i 3.6)E -1

(-3.7 t 3.5)E -1 I

( 0)

(-3.7 -

3.7)E 0

(-3.7 -

3.0)E 0

(-3.8 -

2.4)E O

(

0/ 38)*

(

0/ 19)e

(

0/ 19)e e NON-ROUTIE REFERS TO TE NUMBER OF SEPARATE EASLREMENTS WHICH ERE CREATER I

TW TEN (10) TIES TE AVERAGE BACK0R0lN) F(R TE PERIOD OF TE PEPORT.

en TE FRACTION OF SAPPLE ANALYSES Y!ELDING DETECTABLE EASLEEENTS (I.E. >3 STD [EVIATICNS) IS INDICATED WITH et le.

I ENVIR0 MENTAL RADIOLOGICAL PROGRAM Slft%RY YAMCEE MJCLEAR POER STATION, ROE, MA JANJARY - DEEMBER 1985 EDILM: MILX 1MITS: PCI/KG IM)!CATOR STATIONS STATION Wim HIGEST EAN CONTROL STATIONS u su eeeen ee*****

euenen usensuenen u esenennunee I

RADIONUCLIDES EAN EAN EAN (NO. ANALYSES) REQUIRED RANGE STA. RANGE RANGE (NON-ROUTIEle LLD NO. DETECTEDee NO.

NO. DETECTEDen NO. DETECTEDei I

AG-110M( 57)

( -1.62 1.7)E -1 21

( 1.4 t 2.5)E -1

( 1.4 1 2.5)E -1

( 0)

(-2.4 -

1.9)E o

(-1.7 -

1.9)E O

(-1.7 -

1.9)E O

(

0/ 38)e

(

0/ 19)e e( 0/ 19)e RU-103 ( 57)

( -8.1t 1.7)E -1 12

(-6.8 i 1.5)E -1

(-9.9 i 1.7)E -1

( 0)

(-2.6 -

1.6)E 0

(-2.0 -

1.0)E 0

(-2.1 -

.5)E O a( 0/ 38)*

et 0/ 19)e

(

0/ 1918 RD-106 ( 57)

( -8.51 !!.9)E -1 21

( 6.9 t 141.5)E -2

( 6.9 i 141.5)E -2

( 0)

(-1.4 -

1.3)E I

(-1.1 -

1.51E 1

(-1.1 -

1.5)E 1

(

0/ 38)*

(

0/ 19)*

et 0/ 19)*

I I-131 ( 57) 1.

( 6.5i 5.4)E -3 11

( l.2 i

.7)E -2

(-2.1 t 1.3)E -2

( 0)

(-5.6 -

7.4)E -2

(-2.9 -

7.0)E -2

(-2.0 -

.6)E -1 et 0/ 331s e( 0/ 19)e e( 0/ 19)*

CS-134 ( 57) 15.

( -3.91 1.01E -1 12

(-2.7 f 1.2)E -1

(-5.8 t 2.1)E -1

( 0)

(-1.5 -

1.1)E O

(-1.0 -

1.1)E O

(-2.3 -

1.0)E O a( 0/ 38)*

et of 19)e et 0/19)e CS-137 ( 57) 18.

(

1.lt

.2)E 1 11

( 2.0 i

.3)E 1

( 1.1 i

.1)E O

( 13)

( 1.1 - 42.8)E O

( 6.2 - 42.8)E O

( 2.5 - 19.5)E -1 e( 32/ 38)*

( 19/ 19)e et 1/ 19)e BA-140 ( 57) 15.

( -1.8t 2.4)E -1 11

( 1.8 t 2.4)E -1

(-5.8 t 2.4)E -1

( 0)

(-4.0 -

2.6)E O

(-1.9 -

2.0)E O

(-2.4 -

1.4)E 0 I

(

0/ 38),

(

0/ 19)e

(

0/ 19)e CE-144 ( 57)

( -1.lt

.9)E O 12 ( 2.4 i 12.3)E -1

(-1.6 1 7.7)E -1 I

( 0)

(-1.5 -

1.0)E 1

(-1.5 -

1.0)E 1

(-6.8 -

5.2)E O

(

0/ 38)e e( 0/ 19)e e( 0/ 19)e TH-232 ( 57)

( 7.lt 5.0)E -1 12 ( !.2 i

.5)E O

( 4.6 i 5.4)E -1 I

( 0)

(-7.4 - 10.;)E 0

(-3.2 -

5.6)E 0

(-2.8 -

7.1)E 0

(

1/ 38)*

(

0/ 19)e et 0/ 19)e I

e NON-ROUTIE REFERS TO TE NUMBER OF SEPARATE EASUREENTS WHICH ERE GREATER THM TEN (10) TIES TE AERAGE BACKGROUND FOR TE PERIOD OF TE REPORT.

u TE FRACTION OF SMf'LE ANALYSES YIELDING DETECTABLE EASLREENTS (I.E. >3 STD IEVIATICflS) IS INDICATED WITH *(

le.

I l

D) Food Crop Samples of Swiss chard or spinach were collected at harvest time and analyzed for gamma-emitting nuclides.

These crops were sampled from two indicator and one control station. Other than naturally occurring K-40, no radionuclides were detected in the samples.

I

I I

I I

r I

I I

I g

. l

I ENVIR0pfENTAL RADIOLOGICAL PROGRAN SLfMARY I

YAKEE NUCLEAR POWER STATION. R0WE. M4 JANUMY - DECOSER 1985 EDILM: FOOD CR0P LMITS: PCI/KG ET I WICATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONS n +e+ n ee n u n ene seneeenowneue**enu u tene** *****e RADIORJCL! DES M

EAN EAN (NO. ANALYSES) EQUIRED RANGE STA.

RANGE RANGE (NON-ROUTIE)*

LLD NO. DETECTED *e NO.

NO. DETECTED **

NO. DETECTED +e I

BE-7 ( 3)

(

1.2i

.3)E 2 12

( !.5 i

.8)E 2

( !.2 i

.9)E 2

( 0)

( 9.2 - 15.3)E 1 et 0/ 2)*

et 0/ 11e

(

0/ 1)e K-40 ( 3)

( 3.9i

.7)E 3 21

( 4.9 i

.3)E 3

( 4.9 i

.3)E 3 I

( 0)

( 3.3 -

4.6)E 3 et 2/ 2)e

(

1/ 1)e

(

1/ 1)*

PW-54 ( 3)

( -2.6i 5.0)E O 11

( 2.4 i 14.1)E 0

(-1.4 i 1.0)E 1 I

( 0)

(-7.6 -

2.4)E O

(

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

(

0/ lie CO-58 ( 3)

(

2.81 71.7)E -1 12

( 7.4 10.5)E 0

(-1.0 i 9.2)E O

( 0)

(-6.9 -

7.4)E 0 et 0/ 2)*

et 0/ 1)s

( 0/ 1)*

FE-59 ( 3)

( -2.9t 2.4)E 1 21

( 2.5 i 24.6)E 0

( 2.5 i 24.6)E O

( 0)

(-5.3 -

.4)E 1 et 0/ 2)e

(

0/ 1)e e( 0/ 1)*

CD-60 ( 3)

( -1.61 5.2)E 0 12 ( 3.5 i 13.4)E O

(-3.0 i 1.5)E 1

( 0)

(-6.8 -

3.5)E 0 e( 0/ 21e

( 0/ 1)*

(

0/ 1)*

ZN-65 ( 3)

( -1.7i

.4)E 1 21

(-1.3 1 2.4)E 1

(-1.3 i 2.4)E 1

( 0)

(-2.1 -

-1.4)E 1

(

0/ 2)*

( 0/ 1)*

( 0/ 1)*

ZR-95 ( 3)

( -9.9i 6.6)E 'O 21

( 1.8 i 1.8)E 1

( 1.8 1 1.8)E 1

( 0)

(-1.6 -

.3)E 1

(

0/ 2)*

et 0/ 1)e

(

0/ 1)e I

AG-110M( 3)

(

3.3i 28.0)E -1 12 ( 3.1 i 14.0)E O

(-1.2 i 1.4)E 1

( 0)

(-2.5 -

3.1)E 0 et 0/ 2)e a( 0/ 1)e et 0/ 1).

I e NON-ROUTIE REFERS TO TE RMBER OF SEPANATE EASUREENTS WHICH ERE GREATER THAN TEN (10) TIES TE AVERAGE BAD:0ROUND FOR TE PERIOD CF TE REPORT.

- TE FRACTION OF SAffLE ANALYSES YIELDING DETECTABLE EASLREENTS I

(I.E. >3 STD IEVIATIONS) IS !@!CATED WITH *(

le.

ENVIR0fflENTAL RADIOLOGICAL PROGRAM St# MARY YNG'IE NILEAR POER STATION, ROE MA JANUMY - DECEMBER 1985 EDILM F000 CROP LMITS: PCI/KG ET IM)!CATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONS anuneeueenne nennunenuseneun uneuneeuees RADIONJCLIDES EAN EAN EAN (NO. ANALYSES) REQUIRED RANGE STA.

RANCE RANDE (NON-ROUTIEle LLD NO. DETECTEDet NO.

WJ. DETECTEDee NO. DETECTEDee I

RU-103 ( 3)

( -10.0i 8.2)E O 21

( 2.2 i 1.1)E 1

( 0)

(-1.8 -

.2)E 1

( 0/ 2)*

( 0/ 1)*

(

0/ 1)*

RU-106 ( 3)

( -1.51

.5)E 2 21

(-8,5 i 8.7)E 1

( 0)

(-2.0 -

-1.0)E 2

(

0/ 2)*

( 0/ 1)*

(

0/ 1)*

I-131 ( 3)

( -1.0t

.5)E 1 11

(-4.8

22.9)E 0

(-2.6 k 1.6)E 1

( 0)

(-1.6 -

.5)E 1 e( 0/ 2)e

( 0/ 1)*

( 0/ 1)*

I CS-134 ( 3) 60.

( -1.9t

.1)E 1 21

(-1.8 1 11.3)E O

( 0)

(-1.9 -

-1.8)E 1

( 0/ 2)*

( 0/ 1)*

(

0/ lie CS-137 ( 3) 80.

( -1.11 1.0)E 1 21

( !.0 t 1.1)E 1

( 1.0 t 1.1)E 1

( 0)

(-2.0 -

.1)E 1

( 0/ 2)*

et 0/ 1)*

( 0/ 1)*

BA-140 ( 3)

( -1.51 2.3)E O 11

( 7.6 i 201.0)E -1

(-2.7 1 1.7)E 1

( 0)

(-3.8 -

.8)E 0 et 0/ 2)*

et 0/ 1)*

( 0/ 1)*

CE-141 ( 3)

( -4.5i 63.6)E -1 21

( 9.5 13.7)E O

( 9.5 i 13.7)E O j

( 0)

(-6.8 -

5.9)E O a( 0/ 2)*

( 0/ 1)*

a( 0/ 1)e CE-144 ( 3)

( -3.0t 4.3)E O 21

( 2.0 1 5.2)E 1

( 2.0 1 5.2)E 1 i

I

( 0)

(-7.3 -

1.2)E O

(

0/ 2)e e( 0/ 1)*

(

0/ 1)*

Tli-232 ( 3)

( 5.0t 4.2)E 1 12 ( 9.2 i 4.0)E 1

( 4.4 i 4.5)E 1

( 0)

( 8.9 - 92.1)E O s( 0/ 2)*

a( 0/ 1)*

e( 0/ 1)*

I

,l e NON-ROUTIE REFERS TO TE MJMBER OF SEPARATE EASLREENTS WHICH ERE GREATER m

THAN TEN (10) TIES TE AVERAGE BAO'OR0lMD FOR TE PERIOD CF TE REPORT.

- TE FRACTION OF SAMDLE ANALYSES YIELDING DETECTABLE EASUREENTS (I.E. >3 STD DEVIATIONS) IS INDICATED WITH *(

le. !

I E) Broad Leaf Vegetation The Radiological Effluent Technical Specifications require that one sample of broad leaf vegetation be sampled at harvest time..In 1985, a Swiss chard sample was collected from Station TV-11 (Monroe Bridge). The required I-131 analysis showed no detectable radioactivity.

I I

I

- I

I EWIROMOTAL RADIOLOGICAL PROGRAM

SUMMARY

I YN#IE NUQ. EAR POER STATION, R0WE. MA JAWARY - DECEMBER 1985 EDRM: BROADLEAF VEGATATION LMITS: PCI/KG WET INDICATOR STATIONS STATION WITH HIGEST EAN CONTROL STATICNS emm+memm m ee+ m m ee+ m **** m e m e++esee m ee RADIOMJCLIDES EAN EAN EAN (NO. ANALYSES) REQUIRED RANGE STA. RANGE RANGE

)

LLD NO. DETECTED ++

NO.

NO. DETECTED ++

NO. DETECTED **

I (NON-ROUTIEle I-131 ( 1) 60.

( -1.St 1.0)E 0 11

(-1.5 i 1.0)E O NO DATA I

( 0) et 0/ 1)*

et 0/ 11e I

e NON-ROUTIE REFERS TO TE MNER 0F SEPARATE EASLEEENTS lHICH ERE GREATER I

THAN TEN (10) TIES TE AVERAGE BACKGROUND FOR TE PERIOD OF TE REPORT.

e TE FRACTION OF SMPLE ANALYSES YIELDING DETECTABLE EASLREENTS (I.E. >3 STD DEVIATIONS) IS IM)!CATED WITH *(

)*.

I I

I

I F) Maple Syrup Maple syrup grab samples (not required by Technical Specifications) were collected during April at one indicator and two control locations.

In addition to naturally occurring K-40 and Th-232, Cs-137 was detected in each sample.

Attributed to nuclear weapons testing fallout, this Cs-137 has been detected in most samples since collection was started in 1972.

Both control stations in I

1985 had a higher Cs-137 level than detected at the indicator s ta' ion.

I I

i i

~

I I

I

- i

I ENVIR0 MENTAL RADIOLOGICAL PROGRAM SLfMAR7 I

YAM (EE NUCLEAR POWER STATION, R0WE. MA JAW ARY - DECO 9ER 1985 EDILM: MAPLE SYRLF LN1TS: PCI/KG I

IM)ICATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONS m m m e** m mmmmemmme, m m m ** m es I

RADIONUCLIDES EAN MEAN EAN (NO. ANALYSES) REQUIRED RANGE STA. RANGE RANCE (NON40UTIE)*

LLD NO. DETECTED **

NO.

NO. DETECTEDet NO. DETECTED **

I BE-7 ( 3)

( 4.31 9.2)E 0 42 ( 9.2 i 5.9)E 0

( 4.9 i 4.3)E O

( 0)

( 5.7 - 92.0)E -1

(

0/ 1)*

(

0/ 1)*

( 0/ 2)*

K-40 ( 3)

(

1.7f

.0)E 3 42 ( 2.1 i

.0)E 3

( 1.8 i

.3)E 3 I

( 0)

( !.5 -

2.1)E 3

(

1/ 11e

(

1/ lie et 2/ 2)*

IW-54 ( 3)

(

4.91 12.6)E -1 31

( 4.9

12.6)E -1

(-3.0 t 4.4)E -1 I

( 0)

(-7.4 -

1.3)E -1 et 0/ 1)e a( 0/ 11e

( 0/ 2)*

I C0-58 ( 3)

( -2.5i 10.8)E -1 41

( 3.3 i 8.0)E -1

(-4.2 i 7.5)E -1

( 0)

(-1.2 -

.3)E O

( 0/ 1)*

a( 0/ 1)*

e( 0/ 2)e FE-59 ( 3)

( 3.5i 3.1)E O 31

( 3.5 i 3.1)E O

(-1.2 i 3.5)E O

( 0)

(-4.8 -

2.3)E O

(

0/ lie

( 0/ 1)*

(

0/ 2)*

CO-60 ( 3)

( -8.3t 14.81E -!

41

( !.7 i 10.8)E -1

(-3.4 t 5.1)E -1

( 0)

(-8,5 -

1.7)E -1 a( 0/ 1)*

(

0/ !)*

(

0/ 2)e ZN-65 ( 3)

(

3.91 3.1)E 0 31

( 3.8 i 3.1)E O

( 9.9 f 10.1)E -1

( 0)

(-2.7 - 200.0)E -2 I

(

0/ 11e

(

0/ 1)*

( 0/ 2)*

ZR-95 ( 3)

( 2.11 2.0)E O 31

( 2.1

2.0)E 0

( 6.3 t 5.1)E -1 lI

( 0)

( 1.2 - 11.4)E -1 st 0/ 1)*

(

0/ 1)e et 0/ 2)*

'g AG-110M( 3)

(

4.32 2.0)E O 31

( 4.3 t 2.0)E 0

(-8.9 i 14.3)E -1

'3

( 0)

(-2.3 -

.5)E 0

(

0/ 11e

(

0/ 1)*

a( 0/ 2)e i

,l

NON40VIIE REFERS TO TE IUSER OF SEPARATE EASUREENTS WHICH WERE GREATER

'E THAN TEN (10) TIES TE AVERAGE BACX0ROLND FOR TE PERIOD OF TE REPORT.

.* TE FRACTION OF SAfFLE ANALYSES YIELDING DETECTABLE EASLREENTS I

(I.E. >3 STD DEVIATIONS) IS INDICATED WITH *(

)*.

i 1 : I

I ENVIR0 MENTAL RADIOLOGICAL FROGRAM SlfftARY YAM (EE NUCLEAR POWER STATION. R0WE. MA I

JAf0ARY - DE & MBER 1985 EDILM: MAPLE SYRlP LMITS: PCI/KG j

INDICATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONS

- ueeeneesenen neenunteeneenneen nunneenens I

RADIONUCLIDES EAN EAN EAN (NO. ANALYSES) REQUIRED RANGE STA.

RANGE RANGE (NON-ROUTIE)*

LLD NO. DETECTEDen NO.

NO. DETECTED **

I RU-103 ( 3)

( -1.11 12.0)E -1 31

(-1.1 1 12.0)E -1

(-i.1 i

.3)E 0

( 0)

(-1.4 -

.7)E 0 ei 0/ lie e( 0/ 1)*

et 0/ 2)*

RU-106 ( 3)

( -2.1f 9.9)E 0 42

( 1.1 i

.6)E 1

( 7.4 i 4.1)E O I

( 0)

( 3.3 - 11.5)E O

(

0/ 1)e

(

0/ lie et 0/ 2)*

I-131 ( 3)

(

1.71 18.5)E -1 41

( 1.1 i 1.3)E 0

( 1.2 i 9.6)E -1 I

( 0)

(-8.4 - 10.8)E -1

(

0/ 1)e a( 0/ 1)*

( 0/ 2)*

I CS-134 ( 3)

( -2.0i 1.1)E 0 42

(-1.5 i

.9)E 0

(-1.6 i

.1)E 0

( 0)

(-1.7 -

-1.5)E O

(

0/ 1)*

e( 0/ 1)*

( 0/ 2)*

CS-137 ( 3)

(

1.11

.1)E 1 41

( 7.7 i

.2)E 1

( 5.6 1 2.1)E 1

( 0)

( 3.6 -

7.7)E 1

(

1/ 1)*

(

1/ 1)*

(

2/ 2)*

BA-140 ( 3)

(

!.6i 1.3)E O 31

( 1.6 t 1.3)E O

(-6.6 i 9.1)E -1

=

( 0)

(-1.6 -

.3)E O a( 0/ 1)e et 0/ 1)e

(

0/ 2)e E-141 ( 3)

( -7.31 19.1)E -1 41

( 1.5 i 1.4)E O

(-4.0 i 19.5)E -1

( 0)

(-2.3 -

1.6)E O I

( 0/ 1)*

(

0/ lie

(

0/ 2)*

CE-144 ( 3)

( -5.41 7.5)E *0 41

( 5.3 1 5.5)E 0

(-6.1 i 59.01E -1 h

( 0)

(-6.5 -

5.3)E 0 E

(

0/ 1)e

( 0/ 1)*

( 0/ 2)*

TH-232 ( 3)

( -0.3i 52.8)E -1 42 ( 1.0

.3)E 1

( 6.8 i 3.5)E O I

( 0)

( 3.3 - 10.3)E 0

(

0/ 1)*

(

1/ 1)*

(

1/ 2)*

I I

e NON-ROUTIE REFERS TO TE NJMBER OF SEPARATE EASUREENTS WHICH WERE GREATER T)MN TEN (10) TIES TE AVERAGE BACKGROLND FOR TE PERIOD OF TE REPORT.

- TE FRACTION OF SAPPLE ANALYSES YlELDING DETECTABLE EASLREENTS (1.E. >3 STD DEVIATIONS) IS INDICATED WITH *(

)*. I 4

I G) Ground Water Ground water grab samples were collected from two indicator stations on a monthly basis.

(Technical Specifications require a quarterly collection. ) Each of these samples was analyzed for gross-beta, H-3, and gamma-emitting radionuclides.

Tritium (H-3) was detected in all of the Station WG-12 samples and

)

none of those from Sta'; ion WG-11.

Since the water from WG-12 (Sherman Spring) is not used for drinking water, and since the Deerfield River into which it empties is also not used for drinking, there would be no impact on man from the low levels detected.

In any case, the calculated total body dose to an average adult who is assumed to ingest 370 kilograms per year of this water (undiluted) at the average 1985 concentration of I

1400 pCi/ kilogram, would be approximately 0.05 mrem, using USNRC Regulatory Guide 1.109 methodology (Reference 3).

The annual mean i

H-3 concentration has decreased steadily for most of the past ten years.

Gross-beta radioactivity was detected in all ground water samples.

Caused primarily by naturally occurring radionuclides in ground water, the gross-beta levels were similar to those of the past j

soveral years.

No gamma-emitting radionuclides were detected in the ground water I

samples.

I I

I.I l

I ENVIRO M NTAL RADIOLOGICAL PR00PAM SlNIARY I

YANKEE N.lCt. EAR POWER STATION, R0WF:. MA JANJARY - DECEMBER 1985 EDILE: GROUND WATER LMITS: PCI/KG I

INDICATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONS eueenenneeene ese n n e usenesen neeses eenunenusse I

RADIONUCLIDES EAN MEAN EAN (NO. ANfLYSES) REQUIRED RANGE STA.

RANGE RM0E (NON-ROUTIEle LLD NO. DETECTED **

NO.

NO. DETECTEDee NO. DETECTED **

GR-B ( 24) 4.

( 3.5i

.2)E 0 11

( 4.3 i

.2)E 0 NO DATA

( 0)

( 2.1 -

5.2)E O

( 3.5 -

5.2)E O

( 24/ 24)*

e( 12/ 12)*

BE-7 ( 24)

( -6.7i 20.2)E -1 12 ( 1.1 1 2.5)E O NO DATA I

( 0)

(-1.9 -

1.6)E 1

(-1.1 -

1.6)E 1

(

0/ 24)*

(

0/ 12)*

K-40 ( 24)

( 5.81 2.9)E O 11

( 6.1 i 5.2)E O NO DATA I

( 0)

(-2.4 -

4.4)E 1

(-2.4 -

4.4)E 1 et 0/ 24)e e( 0/ 12)e I

m-54 ( 24) 15.

(

1.4i 2.5)E -1 12 ( 2.9 i 2.3)E -1 NO DATA

( 0)

(-3.8 -

2.2)E O

(-8.8 - 15.2)E -1

(

0/ 24)*

(

0/ 12)*

C0-58 ( 24) 15.

( -6.2t 2.0)E -1 12

(-1.9 t 2.4)E -1 NO DATA

( 0)

(-2.4 -

1.5)E 0

(-1.3 -

1.5)E O

(

0/ 24)e

(

0/ 12)e I

FE-59 ( 24) 30.

( -2.41 49.5)E -2 11

( 2.0 i 7.5)E -1 NO DATA

( 0)

(-4.4 -

4.3)E 0

(-4.4 -

4.3)E O

(

0/ 24)e

(

0/ 12)*

C0-60 ( 24) 15.

( -5.91 2.2)E -1 11

(-4.4 i 2.3)E -1 NO DATA

( 0)

(-2.7 -

1.5)E O

(-1.9 -

1.5)E 0 I

(

0/ 24)e et 0/ 12)e ZN-65 ( 24) 30.

( -1.51 462.5)E -3 11

( 4.1 i 60.5)E -2 NO DATA I

( 0)

(-3.8 -

5.4)E 0

(-2.3 -

3.8)E O

(

0/ 24)*

(

0/ 12)*

I ZR-95 ( 24) 15.

(

1.51 3.2)E -1 12 ( 5.0 i 3.9)E -1 NO DATA

( 0)

(-3.5 -

2.7)E 0

(-1.9 -

2.6)E O

(

0/ 24),

et 0/ 12)e I

I NON-ROUTIE REFERS TO TE NhtBER OF SEPARATE EASUREENTS WHICH WERE GREATER e

THAN TEN (10) TIES TE AVERAGE BACXOROUND FOR TE PERIOD OF TE REPORT.

- TE FRACTION OF SAWLE ANALYSES YIELDINO DETECTABLE EASLREENTS I

(I.E. >3 STD IEVIATICH3) IS IOICATED WITH *(

le.

. I

I ENVIR0ptIENTAL RADIOLOGICAL PROGRAM SlMIARY I

YANEE M.lCLEAR POWER STATION. R0WE. MA JANUE Y - DECE}eER 1985 EDIlM: GROLMD WATER LMITS: PCI/KG I

INDICATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONS m e n n e m e m **

- - - mmusmemutu

mmmmm j

RADIONUCLIDES EAN EAN EAN W

(NO. ANALYSES) REQUIRED RANGE STA.

RANGE RANGE (NON-ROUTIE)*

LLD NO. DETECTED **

NO.

NO. DETECTED **

I AG-110M( 24)

(

2.71 2.8)E -1 11

( 5.0 t 4.7)E -1 NO DATA

( 0)

(-2.1 -

4.3)E O

(-2.1 -

4.3)E 0

(

0/ 24)*

(

0/ 12)*

RU-103 ( 24)

( -9.01 2.1)E -1 11

(-7.8 i 3.2)E -1 NO DATA

{

( 0)

(-2.4 -

1.01E O

(-2.4 -

1.0)E 0 I

(

0/ 24)*

(

0/ 12)*

RU-106 ( 24)

( -1.5i 13.1)E -1 12 ( 5.6 t 14.4)E -1 NO DATA I

( 0)

(-1.7 -

1.2)E 1

(-7.0 - 11.5)E O

(

0/ 24)*

(

0/ 12)*

I I-131 ( 24) 1.

( 3.2i 4.4)E -1 12 ( 4.9 i 6.5)E -1 NO DATA

( 0)

(-4.7 -

3.7)E O

(-4.7 -

3.7)E O

(

0/ 24)*

(

0/ 12)*

CS-134 ( 24) 15.

( -4.3i 1.9)E -1 11

(-2.7 i 3.4)E -1 NO DATA

( 0)

(-3.4 -

.9)E O

(-3.4 -

.9)E O

(

0/ 24)*

(

0/ 12)*

CS-137 ( 24) 18.

( -6.91 2.1)E -1 12

(-7.7 i 25.0)E -2 NO DATA

( 0)

(-2.7 -

.9)E O

(-1.7 -

.9)E O

(

0/ 24)*

(

0/ 12)*

BA-140 ( 24) 15.

( -3.8t 41.7)E -2 11

( 1.1 i 6.4)E -1 NO DATA

( 0)

(-2.7 -

3.6)E O

(-2.4 -

3.6)E O

(

0/ 24)*

(

0/ 12)*

CE-141 ( 24)

( -6.21 4.6)E -1 12

(-2.0 i 6.0)E -1 NO DATA I

( 0)

(-6.8 -

2.5)E 0

(-5.1 -

2.5)E 0

(

0/ 24)*

(

0/ 12)*

CE-144 ( 24)

(

4.9t 136.7)E -2 12 ( 1.3 1 1.3)E O NO DATA I

( 0)

(-1.0 -

1.2)E 1

(-4.7 -

8.9)E O

(

0/ 24)*

(

0/ 12)*

I H-3

( 24) 2000.

( 7.21 1.6)E 2 12 ( !.4 i

.1)E 3 NO DATA

( 12)

(-?.1 - 20.1)E 2

( 9.9 - 20.1)E 2

( 12/ 24)*

( 12/ 12)*

I I

NON-ROUTIE REFERS TO TE NUMBER OF SEPARATE EASUREENTS WHICH WERE GREATER THAN TEN (10) TIES TE A'ERACE BACKGROUND FOR TE PERIOD OF TE REPORT.

- TE FRACTION OF SAELE ANALYSES YIELDING DETECTABLE Elk %REENTS I

(I.E. >3 STD DEVIATIONS) IS INDICATED WITH *(

)*.,

lI H) River Water 8

Composite samplers were used at the two required sampling locations and samples from each of those wore collected monthly and analyzed for gross-beta, gamma-emitting radionuclides, and I-131.

Quarterly composites were analyzed for H-3.

I The second, third, and fourth quarter composite samples showed detectable levels of H-3 at Station WR-11 (Bear Swamp Lower Reservoir).

Since the Deerfield River is not used for drinking i

water, the low levels of H-3 found will have no impact on man.

If I

one was to calculate, however, the dose to an adult who consumed

{

his entiro yearly intake of water (370 kilograms per year) from the Deerfield River at the above sampling location, with the average concentration of 610 pCi/ kilogram, it would be shown that the doso would be approximately 0.02 mrem per year, using USNRC Regulatory i

Guide 1.109 methodology (Reference 3).

The RETS reporting level of 30,000 pCi/kg was not exceeded.

Gross beta radioactivity, primarily from naturally occurring radionuclides in river water, was detected in most samples.

The mean and range were similar to those measured in previous years.

The control and indicator station mean concentrations were also equal in 1985.

No gamma-emitting radionuclides were detected in the 1985 river I

water samples.

I I

I

~

I E I

I ENVIR0ffENTAL RADIOLOGICAL PROGRAM S(MIARY I

YANKEE NUCLEAR POWER STATION, ROWE. MA JANUARY - DECEMER 1985 EDIW: RIVER WATER lNITS: PCI/KG I

IM)!CATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONS nesunnennen eenuweseuueuunus

- - - - ue n n I

RADIONUCLIDES MEAN EAN MEAN (NO. ANALYSES) REQLJIRED RANGE STA.

RANGE RANGE (NON-R0llTIE)e LLD NO. DETECTEDet NO.

NO. DETECTEDet NO. DETECTEDee I

GR-B ( 24) 4.

(

1.8t

.1)E 0 21

( 1.8 i

.2)E 0

( 1.8 i

.2)E 0

( 0)

( 7.4 - 25.0)E -1

( 8.4 - 26.9)E -1

( 8.4 - 26.9)E -1 e( 10/ 12)e e( 9/ 12)e

(

9/ 12)*

BE-7 ( 24)

( -9.0t 15.8)E -1 11

(-9.0 i 15.8)E -1

(-1.8 i 2.5)E O I

( 0)

(-1.1 -

.6)E 1

(-1.1 -

.6)E 1

(-2.1 -

1.3)E 1

(

0/ 12)e et 0/ 12)e

(

0/ 12)*

K-40 ( 24)

( -4.3t 3.9)E O 21

(-2.4 i 2.6)E O

(-2.4 i 2.6)E 0

( 0)

(-2.8 -

1.4)E 1

(-1.7 -

1.0)E 1

(-1.7 -

1.0)E 1

(

0/ 12)*

f( 0/ 12)*

(

0/ 12)*

I IW-54 ( 24) 15.

( -2.11 2.4)E -1 21

(-1.1 t 4.1)E -1

( 0)

( '.6 -

1.7)E O

(-4.0 -

1.1)E O

(-4.0 -

1.1)E O

(

0/ 12)*

a( 0/ 12)*

(

0/ 12)e CG-58 ( 24) 15.

( -6.01 1.7)E -1 21

(-5.3 i 347.4)E -3

( 0)

(-1.4 -

.3)E O

(-3.0 -

1.0)E O

(-3.0 -

1.0)E O at 0/ 12)*

(

0/ 12)*

(

0/ 12)*

FE-59 ( 24) 30.

(

1.41 4.4)E -1 11

( 1.4 i 4.4)E -1

(-1.2 i 741.5)E -3

( 0)

(-2.5 -

2.5)E 0

(-2.5 -

2.5)E O

(-4.7 -

4.1)E O

(

0/ 12)*

(

0/ 12)e

(

0/ 12)e C0-60 ( 24) 15.

( -7.31 2.4)E -1 21

(-3.7 i 2.5)E -1

(-3.7 t 2.5)E -1

( 0)

(-2.1 -

.8)E O

(-1.9 -

1.2)E O

(-1.9 -

1.2)E O I

e( 0/ 12)e

(

0/ 12)*

(

0/ 12)e ZN-65 ( 24) 30.

( -3.31 5.0)E -1 21

(-7.8 i 488.8)E -3

(-7.8 i 488.8)E -3 I

( 0)

(-2.3 -

3.6)E 0

(-2.8 -

3.5)E O

(-2.8 -

3.5)E O

(

0/ 12)*

a( 0/ 12)*

ZR-95 1 24) 15.

( -4.31 4.7)E -1 21

( 3.4 i 4.2)E -1

( 3.4 i 4.2)E -1 I

( 0)

(-2.8 -

2.4)E O

(-1.4 -

3.4)E O

(-1.4 -

3.4)E O

(

0/ 12)e

(

0/ 12)*

(

0/ 12)e I

I e NON-R0llTIE REFERS TO TE NUMBER OF SEPARATE EASLREMENTS WHICH WERE GREATER THAN TEN (10) TIES TE AVERAGE BACKGROLND FOR TE PERIOD OF TE REPORT.

- TE FRACTION OF SAWLE ANALYSES YIELDING DETECTABLE EAS'JOENTS (1.E. >3 STD DEVIATIONS) IS INDICATED WITH *(

)*. I

I ENVIR0ffENTAL RADIOLOGICAL PROGRAM SLMIARY YANKEE NUCLEAR POWER STATION. R0WE. MA I

JANUARY - DECEMBER 1985 EDILM: RIVER WATER LNITS: PCI/KG DE)ICATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONS

...e.......

e....

e.............

e..

RADIONUCLIDES EAN EAN EAN i

(NO. ANALYSES) REQUIRED RANGE STA. RANGE RANGE (NON-ROUTIEle LLD NO. DETECTED..

NO.

NO. DETECTED.e NO. DETECTED **

I AG-110M( 24)

( -1.9i 3.3)E -1 21

( 2.7 i 3.5)E -1

( 2.7 t 3.5)E -1

( 0)

(-2.5 -

1.7)E O

(-1.5 -

1.9)E 0

(-1.5 -

1.9)E 0

(

0/ 12)e

(

0/ 12)e

(

0! 12)*

RU-103 ( 24)

( -8.3i 3.3)E -1 11

(-8.3 i 3.3)E -1

(-1.4 i

.3)E 0

( 0)

(-2.7 -

.9)E O

(-2.7 -

.9)E O

(-3.4 -

.1)E O I

at 0/ 12)e

(

0/ 12)e et 0/ 12)*

RU-106 ( 24)

(

2.li 19.2)E -1 21

( 2.9 i 2.0)E O

( 2.9 2.0)E 0 I

( 0)

(-1.2 -

.8)E 1

(-6.8 - 12.7)E O

(-6.8 - 12.7)E 0

(

0/ 12)*

(

0/ 121e

(

0/ 12)*

I-131 ( 24)

(

1.2i 1.0)E -2 11

( 1.2 i 1.0)E -2

(-1.2 i 1.1)E -2 I

( 0)

(-3.1 -

6.9)E -2

(-3.1 -

6.9)E -2

(-7.9 -

5.2)E -2

(

0/ 12)*

(

0/ 12)e

(

0/ 12)*

I CS-134 ( 24) 15.

( -1.Si 1.8)E -1 11

(-1.5 1.8)E -1

(-5.4 i 2.5)E -1

( 0)

(-1.2 -

.8)E O

(-1.2 -

.8)E O

(-2.0 -

1.1)E O

.(

0/ 12)*

(

0/ 12)e

(

0/ 12)*

CS-137 ( 24) 18.

( 5.11 23.6)E -2 21

( 3.8 i 2.5)E -1

( 0)

(-1.2 -

1.9)E O

(-1.3 -

2.1)E O

(-1.3 -

2.1)E O

(

0/ 12).

(

0/ 12)*

(

0/ 12)e BA-140 ( 24) 15.

( -8.0t 4.9)E -1 11

(-8.0 i 4.9)E -1

(-1.1 i

.5)E O

( 0)

(-4.6 -

1.1)E 0

(-4.6 -

1.1)E O

(-3.5 -

1.5)E O

(

0/ 12)*

(

0/ 12)e

(

0/ 12)*

CE-141 ( 24)

(

1.3i

.5)E.0 11

( 1.3 i

.5)E O

(-1.9 i 3.7)E -1

'g

( 0)

(-1.1 -

3.9)E 0

(-1.1 -

3.9)E 0

(-2.2 -

1.7)E O g

(

0/ 12)e

(

0/ 12)*

(

0/ 12)e CE-144 ( 24)

( -2.51 1.3)E O 21

(-4.2 i 12.2)E -1

( 0)

(-9.4 -

3.2)E O

(-7.5 -

6.6)E O

(-7.5 -

6.6)E O at 0/ 121s

(

0/ 12)*

(

0/ 12)e lI H-3

( 8) 2000.

( 6.11 1.2)E 2 11

( 6.1 i 1.2)E 2

( 7.5 i 4.9)E 1

( 3)

( 3.0 -

8.5)E 2

( 3.0 -

8.5)E 2

(-2.6 - 21.0)E 1 l

st 3/ 4)*

(

3/ 4)*

( 0/ 4)*

I I

e NOPHt00 TIE REFERS TO TE NLMBER OF SEPARATE EASUREENTS IMICH WERE GREATER THAN TEN (10) TIES TE AERACE BACKGROLND FOR TE PERIOD OF TE REPORT.

n TE FRACTION OF SAPPLE ANALYSES YIELDD0 DETECTABLE EASUREENTS I

(I.E. >3 STD [EVIATIONS) IS INDICATED WITH *(

le...

E I) Sediment I

Sediment cores were collected semiannually from two locations.

Each core was separated into 5 cm segments, which were analyred for gamma-emitting radionuclides.

Cesium-137 was detected in most samples. Tne levels measured at the indicator location were consistent with what has been measured in the previous several 8

years and are attributed to nuclear weapons testing fallout.

I -

Other than naturally occurring K-40, Be-7, and Th-232, no other gamma-emitting radionuclides were detected in 1985 sediment samples.

t I

I I

I E _

I ENVIR0 E NTAL RADIOLCGICAL PROGRAft SLM1ARY YAft:EE NUCLEAR POWER STATION, R0WE ItA I

JANUARY - DECEMBER 1985 EDIlft: SEDIENT LMITS: PCI/KG DRY IM)!CATOR STATIONS STATION WITH HIOEST EAN CONTROL STATIONS ee....e RADIONUCLIDES MEAN MEAN EAN I

(NO. ANALYSES) REQUIRED RANGE STA. RfM0E RANGE (NON-ROUTIE)*

LLD NO. DETECTED.e NO.

NO. DETECTED.*

NO. DETECTED..

BE-7 ( 15)

( 2.2t 11.8)E 1 21

( 4.0 t 4.7)E 1

( 4.0 i 4.7)E 1

( 0)

(-4.5 -

6.8)E 2

(-10. - 25.0)E 1

(

1/ 8)*

(

0/ 7)*

(

0/ 7)*

K-40 ( 15)

(

1.5t

.1)E 4 11

( !.5 i

.1)E 4

( 1.2 i

.1)E 4

( 0)

( 1.0 -

1.8)E 4

( 1.0 -

1.8)E 4

( 1.0 -

1.5)E 4

(

8/ Ble

(

8/ 8)*

( 7/ 7)*

IW-54 ( 15)

(

-1.5*

.3)E 1 21

(-1.0 i

.2)E 1

(-1.0 i

.2)E 1 I

( 0)

(-3.4 -

.8)E 1

(-2.0 -

.2)E 1

(-2.0 -

.2)E 1

( 0/ 8)*

( 0/ 7)*

(

0/ 7)*

l 3 C0-58 ( 15)

( -5.91 5.4)E 0 21

(-4.2 1 3.8)E 0

(-4.2 i 3.8)E O g

( 0)

(-2.0 -

1.3)E 1

(-1.7 -

1.2)E 1

(-1.7 -

1.21E 1

(

0/ Ble et 0/ 7)*

( 0/ 7)*

I FE-59 ( 15)

( -1.3i 1.0)E 1 21

(-5.3 i 8.1)E O

(-5.3

8.1)E O

( 0)

(-5.6 -

2.01E 1

(-2.4 -

3.0)E 1

(-2.4 -

3.0)E 1

(

0/ 8).

(

0/ 7)*

(

0/ 7)e C0-60 ( 15)

( -1.71 6.5)E O 21

(-1.1 i 3.3)E O

( 0)

(-3.8 -

1.8)E 1

(-1.4 -

1.0)E 1

(-1.4 -

1.0)E 1

(

0/ 8).

a( 0/ 7)*

(

0/ 7)*

ZN-65 ( 15)

(

8.41 6.4)E O 11

( 8.4 i 6.4)E O

(-2.0 i

.9)E 1

( 0)

(-1.6 -

4.5)E 1

(-1.6 -

4.5)E 1

(-5.6 -

2.1)E 1

( 0/ 8)*

(

0/ 8)*

(

0/ 7)*

ZR-95 ( 15)

(

1.71

.7)E 1 11

( 1.7 i

.7)E 1

( 1.4 t 1.0)E 1 I

( 0)

(-2.5 -

3.8)E 1

(-2.5 -

3.8)E 1

(-4.2 -

3.4)E 1

( 0/ 8)*

et 0/ 8)*

( 0/ 7)*

AG-!!0M( 15)

( -5.7i 77.0)E -1 11

(-5.7

77.0)E -1

(-1.4 i

.4)E I

( 0)

(-2.9 -

3.3)E 1

(-2.9 -

3.3)E I

(-2.2 -

.8)E 1 a( 0/ Ble et 0/ 8)e

(

0/ 7)e I

e NON-fl0UTIE REFERS TO TE NUMBER OF SEPARATE EASlREENTS WHICH WERE GREATER I

THAN TEN (10) TIES TE AVERAGE BACKGR0lND F(R TE PERIOD OF TE EPORT.

- TE FRACTION OF SAtFLE ANALYSES YIELDING DETECTABLE EASUREENTS (I.E. >3 STD DEVIATICNS) IS INDICATED WITH *(

)*.

42-I

E l

ENVIROWENTAL RADIOLOGICAL PROGRAM SLMtARV I

YA M E NUCLEAR POWER STATION. R0WE, MA JANUARY - DECEMBER 1985 EDItM: SEDIENT LMITS: PCI/KG DRY I

INDICATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONS m m e m **+e++ee

m m + m +++ m nee m e m e+++++ m *+n i

RADIONUCLIDES EAN EAN EAN (NO. ANALYSES) REQUIRED RANGE STA.

RANGE RANGE (NON-ROUTIE)*

LLD NO. DETECTED **

NO.

NO. DETECTED **

NO. DETECTED +e I

RU-103 ( 15)

(

1.0i

.9)E 1 11

( 1.0 t

.9)E 1

(-9.3 t 8.1)E 0

( 0)

(-1.9 -

6.2)E 1

(-1.9 -

6.2)E 1

(-4.0 -

1.8)E 1 et 0/ 8)e et 0/ Ble

( 0/ 7)*

RU-106 ( 15)

(

1.91 3.5)E 1 11

( 1.9 t 3.5)E 1

(-3.3 i 1.9)E 1 I

( 0)

(-1.6 -

1.9)E 2

(-1.6 -

1.9)E 2

(-1.1 -

.2)E 2 a( 0/ 8)*

e( 0/ 8)*

( 0/ 7)*

I-131 ( 15)

( 7.11 6.1)E 1 11

( 7.1 i 6.1)E 1

(-3.6 i 620.8)E -1

( 0)

(-1.6 -

3.0)E 2

(-1.6 -

3.0)E 2

(-2.7 -

2.8)E 2 a( 0/ Ble et 0/ 8)*

( 0/ 7)*

I CS-134 ( 15) 150.

( 5.5i 7.7)E O 11

( 5.5 i 7.7)E 0

( 3.8 i 4.2)E 0

( 0)

(-4.3 -

2.9)E 1

(-4.3 -

2.9)E 1

(-1.5 -

2.3)E 1

( 0/ Ble

(

0/ Ble

( 0/ 7)*

CS-137 ( 15) 180.

(

2.li

.4)E 2 11

( 2.1 i

.4)E 2

( 9.0 1 5.3)E O

( 7)

(-1.0 - 386.0)E O

(-5.4 - 28.4)E O

(

7/ 8)*

(

7/ 8)*

(

1/ 7)e BA-140 ( 15)

( -1.0i

.3)E 2 21

(-4.7 i 2.8)E 1

( 0)

(-2.2 -

.2)E 2

(-1.9 -

.4)E 2

(-1.9 -

.4)E 2

(

0/ 8)e a( 0/ 7)*

( 0/ 7)*

CE-141 ( 15)

(

1.4c

.9)E 1 11

( 1.4 i

.9)E 1

( 9.2 i 10.5)E O l

( 0)

(-2.1 -

5.1)E 1

(-2.1 -

5.1)E 1

(-3.8 -

4.4)E 1

( 0/ 8)*

(

0/ Ble a( 0/ 7)*

CE-144 ( 15)

( 10.01 44.4)E O 11 (10.0 i 44.4)E O

(-5.0 i 2.7)E 1 ll

( 0)

(-2.4 -

2.1)E 2

(-2.4 -

2.1)E 2

(-1.0 -

.3)E 2 W

( 0/ 8)*

('0/ 8)*

et 0/ 7)*

TH-232 ( 15)

( 8.6i

.7)E 2 11

( 8.6 i

.7)E 2

( 4.6 i

.4)E 2 I

( 0)

( 6.1 - 12.8)E 2

( 3.6 -

6.6)E 2

( 8/ 8)*

( 8/ 8)*

(

7/ 7)e I

1 g NON-ROUTIE REFERS TO TE NLMBER OF SEPARATE EASLEEENTS INICH IDE GREATER a

g THAN TEN (10) TIES TE AVERAGE BACK0R0lND FOR TE PERIOD OF TE REPORT.

- TE FRACTION OF SAPPLE ANALYSES YIELDING DETECTABLE EASUREENTS l

(I.E. >3 STD DEVIATIONS) IS INDICATED WITH *(

le.

i 5

J) Finfish I

Fish samples were collected semiannually from two locations.

Each was analyzed for gamma-emitting radionuclides.

Cesium--137 was detected in all samples.

Over the past several years, the levels have been comparable between Station FH-11 and Station FH-21 fish. These levels are consistent with i

i well-documented environmental levels and are attributed to nuclear lI weapons testing fallout.

Other than Cs-137 and naturally occurring K-40, no gamma-emitting radionuclides were detected in 1985 fish samples.

I

~

l I

I I

il I

I I

~

I I I

8 E)NIR0 MENTAL RADIOLOGICAL PROGRAM

SUMMARY

YAM (EE NUCLEAR POWER STATION. R0WE, MA I

JANUARY - DECEMBER 1985 EDIUM: FIFISH LNITS: PCI/KG ET I

INDICATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONS neeeneneueun ununneeuuneee**u u n ne** *** * *u I

RADIONLICLIDES EAN EAN MEAN (NO. AMLYSES) REQUIRED RANGE STA.

RANGE RANGE (NON40UTIEle LLD NO. DETECTEDet NO.

NO. DETECTEDee NO. DETECTED **

BE-7 ( 4)

( 5.81 4.9)E 1 21

( 6.9 i 8.1)E 1

( 6.9 t 8.1)E 1

( 0)

( 8.1 - 107.0)E 0

(-1.2 - 15.0)E 1

( 0/ 2)*

(

0/ 2)*

( 0/ 2)*

K-40 ( 4)

(

3.41

.2)E 3 11

( 3.4 i

.2)E 3

( 2.4 i

.5)E 3

( 0)

( 3.3 -

3.6)E 3

( 3.3 -

3.6)E 3

( 1.9 -

2.9)E 3 I

(

2/ 2)*

(

2/ 21e e( 2/ 2)e Pti-54 ( 4) 130.

( 3.2i 6.7)E O 21

( 1.4 t

.4)E 1

( 1.4 i

.4)E 1 I

( 0)

(-3.5 -

9.9)E 0

( 9.4 - 18.0)E O

(

0/ 2)*

(

0/ 2)*

( 0/ 2)*

I CO-58 ( 4) 130.

(

1.li

.1)E O 11

( 1.1 i

.1)E 0

(-3.2 i 4.2)E O

( 0)

( 1.1 -

1.2)E O

( 1.1 -

1.2)E O

(-7.3 -

1.0)E 0

( 0/ 2)*

(

0/ 2)e

(

0/ 2)e FE-59 ( 4) 260.

( 3.91 1.1)E O 11

( 3.9 i 1.1)E O

(-9.6 i 11.4)E O

( 0)

( 2.8 -

4.9)E O

( 2.8 -

4.9)E 0

(-2.1 -

.2)E 1

(

0/ 2)*

e( 0/ 2)e

( 0/ 2)*

CO-60 ( 4) 130.

( -4.11 4.5)E O 11

(-4.1 i 4.5)E O

(-5.4 1 2.4)E O

( 0)

(-8.6 -

.4)E 0

(-8.6 -

.4)E O

(-7.8 -

-3.0)E O at 0/ 2)*

e( 0/ 2)*

( 0/ 2)*

ZN-65 ( 4) 260.

( -1.3t 1.9)E 0 11

(-1.3 i 1.9)E O

(-2.6 t

.5 E 1

( 0)

(-3.3 -

.6)E 0

(-3.3 -

.6)E 0

(-3.1 -

-2.1)E 1 5

(

0/ 2)*

(

0/ 2)e

(

0/ 2)e ZR-95 ( 4)

(

1.21

.6)E 1 11

( 1.2 i

.6)E 1

( 3.4 i 11.4)E O I

( 0)

( 5.9 - 17.4)E O

( 5.9 - 17.4)E 0

(-8.0 - 14.8)E O

(

0/ 21e

( 0/ 2)*

( 0/ 2)*

AG-110M( 4)

( -2.5i 12.6)E O 21

( 4.3 i 7.7)E O

( 4.3 i 7.7)E O I

( 0)

(-1.5 -

1.0)E 1

(-3.4 - 12.0)E 0

(-3.4 - 12.0)E O

(

0/ 21e et 0/ 2)e

( 0/ 2)*

I I

e NON-ROUTIE REFERS TO TE NUMBER OF SEPARATE EASUREENTS WHICH WERE GREATER THAN TEN (10) TIES TE AVERAGE BACKGROUND FOR TE PERIOD OF TE REPORT.

- TE FRACTION OF SAPFLE ANALYSES YIELDING DETECTABLE EASLREENTS (I.E. >3 STD DEVIATIONS) IS INDICATED WITH *(

le. 8

5 ENVIR0 MENTAL RADIOLOGICAL PROGRAM SUPMARY I

YAM (EE NUC1. EAR POWER STATION. R0WE. MA JAMJARY - DECEMBER 1985 EDILM: FIWISH LMITS: PCI/KG ET INDICATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONS e

e e.

.e.

ee......ee ee.

RADIOMXX.! DES EAN EAN EAN

,l B (NO. ANALYSES) EQUIRED RANGE STA.

RANGE RANGE (NON-ROUTIE)*

LLD NO. DETECTED NO.

NO. DETECTED *.

NO. DETECTED.e I

RU-103 ( 4)

(

4.71 73.01E -1 21

( !.4 i

.8)E 1

( !.4 i

.8)E 1

( 0)

(-6.8 -

7.8)E O

( 5.9 - 22.0)E O

( 5.9 - 22.0)E 0

(

0/ 2)e

(

0/ 2)e

(

0/ 2)*

RU-106 ( 4)

( -1.4i ~

.0)E 1 21

( 3.9 i 1.0)E 1

( 3.9 t 1.0)E 1 8

( 0)

(-1.5 -

-1.4)E 1

( 2.9 -

5.0)E 1

( 2.9 -

5.0)E 1

( 0/ 2)*

( 0/ 2)*

e( 0/ 2)*

I-131 ( 4)

( 5.21 1.9)E 1

( 5.2 i 1.9)E 1

(-3.3 i 3.7)E 1

( 0)

( 3.2 -

7.1)E 1

( 3.2 -

7.1)E 1

(-7.0 -

.3)E 1

( 0/ 2)*

( 0/ 2)e

( 0/ 2)*

I CS-134 ( 4) 130.

( -4.li

.2)E 0 11

(-4.1 i

.2)E 0

(-1.1 *

.4)E 1

( 0)

(-4.3 -

-4.0)E O

(-4.3 -

-4.0)E 0

(-1.5 -

.7)E 1

( 0/ 2)*

( 0/ 2)*

(

0/ 2)e CS-137 ( 4) 150.

(

8.lt

.3)E 1 11

( 8.1 i

.3)E 1

( 4.8 i

.1)E 1

( 0)

( 7.8 -

8.3)E 1

( 7.8 -

8.3)E 1

( 4.7 -

4.9)E 1

( 2/ 2)*

a( 2/ 2)e et 2/ 2)e BA-140 ( 4)

( -2.91 1.7)E 1 21

(-2.9 1.2)E 1

(-2.9 i 1.2)E 1

( 0)

(-4.6 -

-1.3)E 1

(-4.1 -

-1.8)E 1

(-4.1 -

-1.8)E 1 et 0/ 2)e

( 0/ 2)*

(

0/ 2)e CE-141 ( 4)

( 8.2t 92.8)E -1 21

( 1.7 i

.2)E 1

( 1.7 i

.2)E 1

( 0)

(-8.5 - 10.1)E O

( 1.6 -

1.9)E 1

( !.6 -

1.9)E 1 8

et 0/ 2)*

e( 0/ 2)*

( 0/ 2)*

CE-144 ( 4)

( -5.41 3.6)E 'l 21

( 1.8 i 3.3)E 1

( 1.8 i 3.3)E 1 8

( 0)

(-9.0 -

-1.8)E 1

(-1.5 -

5.1)E 1

(-1.5 -

5.1)E 1 e( 0/ 2)e e( 0/ 2)*

( 0/ 2)e TH-232 ( 4)

(

2.11 35.3)E 0 21

( 4.6 i

.9)E 1

( 4.6 i

.9)E 1 I

( 0)

(-3.3 -

3.7)E 1

( 3.7 -

5.5)E 1

( 3.7 -

5.5)E 1 et 0/ 2)e

( 0/ 2)e e( 0/ 2)*

I I

e NDN-ROUTIE REFERS TO TE NUMBER OF SEPfeATE EASUREENTS WHICH WERE GREATER THAN TEN (10) TIES TE AVERAGE BACKGROUND FOR TE PERIOD OF TE REPORT.

TE FRACTION OF SAPPLE ANALYSES YIELDING DETECTABLE EASLREENTS (I.E. >3 STD DEVIATIONS) IS INDICATED WITH *(

le.

I I

I K) Direct Radiation Direct gamma radiation exposure was determined from the use of thermoluminescent dosimeters (TLDs).

One CaSO :Dy TLD dosimeter 4

was placed at each of the monitoring stations.

(Each dosimeter has I

four readout areas.) A total of thirty-eight stations is required by the Radiological Effluent Technical Specifications. TLDs from twenty-two must be read out quarterly, while those from the remaining sixteen incident response (outer ring) stations need only be de-dosed quarterly, unless a gaseous release LCO was exceeded during the period.

During 1985, all TLDs were routinely readout on a quarterly schedule. Table 3.1 provides a summary of the results.

The results for 1985 are not significantly different than those in I

previous years. This can be seen in the data summary table, Figures 3.5 to 3.10, and Table 3.1.

During 1985, the mean of the indicator stations was below that of the control stations and outer ring stations.

Distinct annual cycles can be seen in the TLD data from each category of monitoring station (see Figures 3.5 to 3.10).

The lowest point of the cycle occurs during the winter months.

This is I

due primarily to the attenuating effect of the snow cover during those months. The effect is not as noticeable with the fenceline TLDs, since the plant contribution to radiation levels at those sites tends to obscure seasonal fluctuations in the environment.

The fenceline where TLDs are situated is located well within the site boundary.

Station GM-5 had a significantly higher exposure rate than other non-site boundary stations, as can be seen in Table 3.1 and Figure 3.5.

This is consistent with the results of the in situ I

analysis at the station performed in October of 1984.

The anomalous TLD results for the first quarter of 1981, seen at several on-site stations (see Figure 3.9), are currently being evaluated and will be reported on in a subsequent Annual Radiological Environmental Operating Report, g

W W

W M

M M

M FIGURE 3.S EXPOSURE RATE AT INDICATOR TLDS, GM 01-07 YANKEE RTOMIC ELECTRIC COMPANY, ROWE, MR e

ss-O - STATION GM-01 0 - STRTION GM-02 a - STATION GM-03

+ - STATION GM-04 X - STATION GM-OS so-o - STATION GM-06 V - STATION GM-07 e

N E as-L 8

w e

8 ao-E M

i 4

I 15 -

s m

n 10-5-

0 1978 1977 1978 1979 1980 1981 1982 1983 1984 1985

E M

M M

mmmM m

FIGURE 3.6 EXPOSURE RATE AT INDICATOR TLDS, GM 08-12,40 YANKEE RTOMIC ELECTRIC COMPRNY, ROWE, MR to

ss-D - STATION GM-08 o - STATION GN-09 A - STATION GN-10 m-

+ - STATION GM-11 X - STATION GM-12 0 - STATION GN-40 e

N E as-y 8

i l

8 20-1 E

l 5

7 l

!5

' 13 i

a, g

s,

10 -

5-0 1978 1977 1978 1979 1980 1981 1982 1983 1984 1985 l

M M

W W

M M

M I

FIGURE 3.7 EXPOSURE RATE AT GUTER RING TLDS, GM 24-31 YANKEE ATOMIC ELECTRIC COMPANY, ROWE, MA to ss-O - STATION GN-24 0 - STATION GN-25 A - STATION GM-28

~

+ - STATION GM-27 X - STATION GN-28 23 0 - STATION GN-29 Q

v - STATION GN-30 g 2s -

N - STATION GN-31

,(n a

10 -

5-0 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 e

M em W

W W

m W

W W

m mW W

W FIGURE 3.8 EXPOSURE RATE AT OUTER RING TLDS, GM 32-39 YRNKEE RTOMIC ELECTRIC C0t1PRNY, ROWE, MR 40 35 -

0 - STATION GM-32 0 - STATION GM-33 A - STATION GM-34 30 ~

+ - STATION GM-35 X - STATION GM-36 5

o - STATION GM-37 g

V - STATION GM-38 g 2s-R - STATION GM-39 e

e>

o l l 5

s-1 m

10 -

5-G

..............................iu.iie.

sis'sisii'senio"sisiiausi'ia*'iasia'"'a**"'"a

1978 1977 1978 1979 1980 1981 1962 1983 1981 1985 l

---r 1

mm W

W W

m m

m a

em e

e m -m e

m. m a

FIGURE 3.9 EXPOSURE RATE AT PENCELINE TLDS, GM 13-21 i

YANKEE ATOMIC ELECTRIC COMPANY, ROWE, MA 150 O - STATION GM-13 te-o - STATION GM-14 A - STATION GM-15 1"~

+ - STATION GM-16 X - STATION GM-17 12-o - STATION GM-18 v - STATICN GM-19 110 -

m - STATION GM-20 M - STATION GM-21 e

N t=-

E i

a 8 "-

Q m-a k 70 -

ti g so-a.

(

v, l

m-t )

E-10 -

0

......................'....'..""..i's">+""*'"'''""'""""'"'''''

1976 1977 1978 1979 1960 1981 1982 1983 1981 1985

mW W

W W

FIGURE 3.10 EXPOSURE RATE RT CONTROL TLDS, GM 22-23 YANKEE ATOMIC ELECTRIC COMPANY, ROWE, MR e

ss -

0 - STATION GM-22 o - STATION GM-23 so -

!2 e 2s-3 i

O U1 Y

a fd k ac) a o

y f

1 6 pI o_

e N

w-G-

n,,,,,,,

0

,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,3,,,,,,,,,,,,,,

1976 1977 1978 1979 1980 1981 1962 1963 1964 1985

I I

Environmental Radiological Program Summary Yankee Nuclear Power Station, Rowe, Massachusetts January - December 1985 iI l

Medium:

Direct Radiation Measurements (TLD)

Units: Micro-R per Hour Indicator Outer-Ring Restricted Control i

Stations Stations Area Fence Stations Mean Mean Mean Mean

]

Range Range Range Range iW (No. Meas.)M (No, Meas.)M (No. Meas.)M (No. Meas.)*

ig 8.1 9.0 16.3 8.7 Ig 5.2 - 11.3 6.3 - 12.7 9.9 - 27.5 6.6 - 10.3 I

(52)

(61)

(36)

(8) i a

1 l

All measurements based on the average of four determinations per dosimeter.

I I

E

--5 4 -

I Table 3.1 Yankee Atomic Summary of Direct Radiation Measurements - 1985 Micro-R Micro-R Station Per HourM Station Per HourM 1

8.0 21 17.2 2

7.9 22 8.4 3

7.0 23 9.1 4

7.1 24 11.3MM 5

10.1 25 7.7 I

6 8.7 26 8.8 7

7.4 27 7.9 8

8.1 28 8.2 9

9.1 29 7.3 10 6.8 30 9.0 11 8.6 31 8.0 12 9.5 32 8.8M*M 13 18.6 33 9.1 14 12.6 34 9.2 15 13.6 35 9.8 16 14.8 36 9.4 17 13.9 37 9.7 I

18 21.8 38 11.1 19 20,3 39 10.8 20 15.1 40 8.4 I

229 0 jg?. 2

Annual average.

M Second and fourth quarter TLDs stolen.

Annual average based on data from I

first, third quarters only.

m Second quarter TLD stolen.

Annual average based on data from three quarters only.

(:.. J %O - dif.)

~55-A ; : ~ / O. 5" I

4.0 QUALITY ASSURANCE PROGRAM Three separate Quality Assurance programs were performed during 1985 to I

demonstrate the validity of laboratory analyses by the Yankee Atomic Environmental Laboratory (YAEL).

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, an investigation is made to determine the cause of the problem and corrective mt.'sures are taken.

I YAEL maintains an intralaboratory quality control program to assure the I

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 individual, and corrective measures are taken whenever applicable.

I A blind duplicate program is maintained in which paired samples are prepared from homogenous media and sent to the laboratory for analysis.

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

Intralaboratory and EPA Interlaboratory Results The Quality Assurance Program implemented at the analytical laboratory indicated good precision and accuracy in reported values.

Table 4.1 shows the results of accuracy and precision for laboratory analyses in 1985 for EPA samples, intralaboratory analyses, and interlaboratory cross-check analyses.

For accuracy, 60.4 and 84.3 percent of the results were within 5 and 10 percent of the known values, respectively, with 96.6 percent of all results falling within the labcratory criteria of 15 percent.

For precision, 82.3 and 95.9 percent of the results were within 5 and 10 percent of the mean, respectively, with 100 percent of all results meeting the laboratory criteria of 15 percent.

I lI l

I Table 4.1 Intralaboratory and EPA Interlaboratory Results - 1985 I

Accuracy I

Total Number 0 to 5%

0 to 10%

0 to 15%M of Measurements 743 449 626 718 (60.4%)

(84.3%)

(96.6%)

I Precision I

Total Number O to 5%

0 to 10%

0 to 15%*

of Measurements 682 561 654 682 (82.3%)

(95.9%)

(100%)

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

I

- e z.

The results of the EPA Interlaboratory Comparison program, when considered apart from the remainder of the Quality Assurance program, were satisfactory with respect to accuracy and precision in 1985.

Ninety-nine samples were analyzed (air particulate filters, food, milk, and water).

A total of 204 analyses were performed (beta, Sr-89, Sr-90, I-131, Ba-140, K, Cs-137, Cr-51, Co-60, Zn-65, Ru-106, Cs-134, Ra-226, Ra-228, and H-3).

I Of the 204 analyses, 2 (1.0 percent) did not meet the EPA acceptance criteria for accuracy. The first of these was a Sr-90 analysis of food.

Since a blank food sample was not provided with the spiked sample to allow for the correction for stable strontium, the results were biased high.

Such blank samples have bonn requested by the laboratory and agreed to in concept by EPA.

The secono was an 1-131 analysis of water.

In this case, iodine carrier was inadvertently not added at the time of the sample preparation, causing a consistent low bias in the laboratory results.

The operator was subsequently informed of the proper preservation methodology.

I All of the analyses met the EPA acceptance criteria for precision.

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I Blind Duplicate Pro.3 ram A totri of 57 paired samples were submitted by the five participating plants for analysis during 1985.

The data base used for the duplicate 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 agreement was established. If the paired measurements fall within 15 I

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 star.dard deviation range (95 percent confidence level) is established for each of the analyses.

If the ranges overlap, agreement is obtained.

One thousand four hundred and forty-four paired duplicate measurements were analyzed for 1985.

A total of 99.7 percent of all measurements fell I

within the established criteria discussed above.

The five measurements that did not meet the criteria were measurements of Np-239 in ground water, Sb-124 in ground water, Se-/5 in sea water, Be-7 in marine algae, and Sr-90 in milk.

All but the Sr-90 were single measurements in a 26-radionuclide gamma spectrometry analysis.

The fi,ve duplicate measurements represent 0.3 percent of all the blind duplicate paired measurements made durin3 1985.

In the first three cases, the radionuclide in question was not present at a detectable level in the sample, and in the last two cases it was.

In all cases, a three standard deviation acceptable criteria was met.

With respect to the Sr-90 analysis, a reanalysis met the acceptance criteria.

No reason could be found for the initial failing. No trend was evident with respect to repeated I

failings of measurements for the above radionuclides.

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I 5.0 LAND USE CENSU_G Specification 3/4.12.2 of the Radiological Effluent Technical specifications requires that a land use census be conducted after June 1 and before October 1 of each year. The census is used to identify the location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 square feet producing fresh leafy vegetables in each of the sixteen meteorological sectors within a distance of five miles.

The 1985 census was completed on September 3.

The distance from the plant for each of the above locations is shown in Table 5.1.

Based on the dosimetric comparisons required by the plant Radiological Effluent Technical Specifications, no changes were found to be necessary in the radiological environmental sampling locations.

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E

I Tablo 5.1 1

Yankee Atomic 1985 Land Use Consus Results Nearest Nearest Nearest I

Residence Milk Animal Garden Sector (km)

(km)

(km) i N

2.4 6.1 3.5 NNE 4.7 4.7 NE 3.7 3.7 ENE 3.1 7.7 E

3.1 5.8 3.1 ESE 3.4 3.4 SE 2.3 3.2 2.3 SSE 2.1 2.1 S

2.3 2.3 GSW SW 1.3 1.3 WSW 1.3 1.3 W

1.9 1.9 WNW 1.9 1.9 1.9 NW 0.45 0.45 NNW 2.9 3.9 lI 4

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6.0

SUMMARY

During 1985, as in previous years, samples collected as part of the radiological environmental monitoring program at Yankee Atomic showed detectable levels of man-made radionuclides in cow milk, ground water, river water, sediment, finfish, and maple syrup.

The H-3 detected in ground water (Station WG-12, Sherman Spring) and river water (Station WR-11, Bear Swamp I

Lower Reservoir) were the only radionuclides possibly related to plant operations.

Since water from the spring or the Deerfield River is not consumed by man, there would be no impact on man from the low levels detected. The dose to an imaginary person who consumed large quantitics of the above water was calculated, however, to set an upper bound to the possible consequences of the measured environmental levels of H-3.

In both cases (river and ground waters), the dose to man was negligible when compared to natural background radiation and its yearly fluctuations.

The Cs-137 detected in cow milk, sediment, finfish, and maple syrup, as well as the Sr-90 detected in cow milk, originated from atmospheric nuclear weapons testing fallout and not from pla e operations.

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7.0 REFERENCES

l 1.

Radiological Environmental Monitoring Report, 1983, Yankee Atomic Electric Company.

2.

Radiological Environmental Monitoring Report, 1984, Yankee Atomic I

Electric Company.

3.

USNRC Regulatory Guide 1.109, " Calculation of Annual Doses to Man from

.g R utine Re eases f React r Effluents for the Purpose of Evaluating E

Compliance with 10CFR50, Appendix I",

1977.

I I

I I - - - -.

YANKEE ATOMIC ELECTRIC COMPANY Te'epho""(6 ")8' -*'oo TWX 710-380-7619 1671 Worcester Roact Framingham, Massachusetts 01701 FYR 86-047

,.L _

/

2.C2.1

.I/11KEj.

DCC 86-042 April 30, 1986 United States Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406 Attention:

Dr. Thomas E. Murley

)

Regional Administrator

References:

(a) License No. DPR-3 (Docket. No. 50-29)

Subject:

Annual Radiological Environmental Report

Dear Sir:

Enclosed herewith please find three copies of the Annual Radiological Environmental Monitoring Report for the Yankee Nuclear Power Station. This report contains a summary and analysis of the radiological environmental data collected for the year 1985 and is submitted as required by Technical Specification 6.9.5(a).

Very truly yours, t-b, I

YANKEE ATOMIC ELECTRIC COMPANY l

a om George P anic Jr.

Senior Project Engineer - Licensing l

GP/dps Enclosures S

/

ML20202E830

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