Text

Yankee Nuclear Power Station Annual Radiological Environ Operating Rept for Jan-Dec 1988
	ML20245F218
Person / Time
Site:	Yankee Rowe
Issue date:	12/31/1988
From:	Papanic G; YANKEE ATOMIC ELECTRIC CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	BYR-89-79, NUDOCS 8905020301
	Download: ML20245F218 (72)
	v • d • e

. - _ - - _ _. - - _ -..

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YANKEE NUCLEAR POWER STATION

. ANNUAL RADIOLOGICAL' ENVIRONMENTAL OPERATING REPORT

. January '- December 1988 i

Apri'. 1989 i

k s

Prepared By:

Yankee Atomic Electric Company Environmental Engineering Department l'

580 Main Street l-Bolton, Massachusetts 01740 i

890bO20301 881231 B

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29 DR ADOCK O gg h

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I TABLE OF CONTENTS li l

l Ea&B I

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

iii l

l LIST OF FIGURES...................................................

iv

1.0 INTRODUCTION

1 2.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PR0 GRAM.....................

2

SUMMARY

OF RADIOLOGICAL ENVIRONMENTAL DATA........................

13 3.0 3.1 Air Particulate.............................................

15 3.2 Charcoal Filter...

19 3.3 M11k........................................................

21 j

3.4 Food Crop...................................................

25 1

3.5 Broad Leaf Vegetation.......................................

28 l

'i 3.6 Maple Syrup..................................

30 3.7 Groundwater.................................................

33 I-3.8 River Water.................................................

38 3.9 Sediment....................................................

41 3.10 Finfish.....................................................

45 3.11 Direct Radiation............................................

49 4.0 QUALITY ASSURANCE PR0 GRAM.........................................

59 f

5.0 LAND USE CENSUS...................................................

63 6.0'

SUMMARY

65

7.0 REFERENCES

66 I

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I LIST OF TABLES I

Number Title lage 2.1 Radiological Environmental Monitoring Program 3

2.2 Radiological Environmental Monitoring Locations 4

-3.1 Summary of Direct Radiation Measurements - 1988 58 4.1 Intralaboratory and EPA Interlaboratory Results - 1988 60-J 1

5.1 1988 Land Use Census Results 63

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IJST OF FIGUR I

Number Title Eage

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I 2.1 Yankee Plant Radiological Environmental Monitoring Locations Within 1 Mile (Airborne, Waterborne, and Ingestion Pathways) 6

)

2.2 Yankee Plant Radiological Environmental Monitoring Locations Within 12 Miles (Airborne, Waterborne, and Ingestion Pathways) 7 2.3 Yankee Plant Radiological Environmental Monitoring 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 Radiological Environmental Monitoring Locations Within 1 Mile (Direct Radiation Pathway) 10 2.6 Yankee Plant Radiological Environmental Monitoring Locations Within 12 Miles (Direct Radiation Pathway) 11 2.7 Yankee Plant Radiological Environmental Monitoring Locations Outside 12 Miles (Direct Radiation Pathway) 12 3.1 Gross-Beta Measurements of Air Particulate Filters 16 3.2 Cesium-137 in Milk 22 3.3 Tritium in Sherman Spring Water (WG-12) 34 3.4 Gross Beta Measurements of Ground Water 35 3.5 Cesium-137 in Sediment 42 3.6 Cesium-137 in Fish 46 3.7 Exposure Rate at Indicator TLDs, GM 01-07 51 3.8 Exposure Rate at Indicator TLDs, GM 08-12, 40 52 3.9 Exposure Rate at Outer Ring TLDs, GM 24-31 53 3.10 Exposure Rate at Outer Ring TLDs, GM 32-39 54

.g 5

3.11 Exposure Rate at Fenceline TLDs, GM 13-21 55 3.12 Exposure Rate at Control TLDs, GM 22-23 56 I

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1.0 INTRODUCTION

l I

The radiological environmental surveillance program for the Yankee

~

Nuclear Power Station (YNPS) has been designed and carried out with specific objectives in mind. They are as follows:

5 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.

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

I.

I 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 accidental releases of radioactive material.

During 1988, the plant staff collected all environmental samples,

'I including environmental thermoluminescent dosimeters (TLDs). All samples were aent to the Yankee Atomic Environmental Laboratory in Westborough, Massachusetts for further processing and radionuclides analysis. TLDs were also sent to this laboratory for processing.

This report is a summary of the findings of the Radiological Environmental Surveillance Program fcc 1988.

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

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'2.0. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM In this section, Table 2.1 outlines the monitoring program as required by plant Technical Specification 3/4.12.1.

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 2.7.

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Table 2.1 Radiological Environmental Monitoring Program Yankee Nuclear Power Station Media Sampling Frequency

.EfLquired Analyses g

' Air Particulate (AP)

Weekly Gross beta

,-g

- Quarterly Composite Gamma spectroscopy Charcoal Filter (CF)

- Weekly I-131 Milk (DI)

- Monthly; once per Gamma spectroscopy, 2 weeks from June 1 I-131 to Nov. 1

{

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Food Crop (TF)

- Annually (Harvest)

Gamma spectroscopy Broad 1,eaf Vegetation (TV)

- Annually (Harvest)

I-131 Groundwater (WG)

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

- Monthly (Composite)

Gross beta, Gamma spectroscopy I-

- Quarterly Composite H-3 I

- Semiannually Gamma spectroscopy Sediment (SE) i Fish (FH)

- Seasonal or Gamma spectroscopy Semiannually Direct Radiation (GM)

- Quarterly De-dose only (Outer ring TLDs)

I

- Quarterly Integrated gamma (All other TLDs) dose I

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I-Table M Radiological Environmental Monitorine Locations Yankee Nuclear Power Station Distance Station Code From Plant Direction (Media - Sta. No.)

Station Description Zone *

(km)

From Plant AP/CF-11 Observation Stand 1

0.5 NW I

AP/CF-12 Monroe Bridge 1

1.1 SW AP/CF-13 Rowe School 1

4.2 SE AP/CF Harriman' Station 1

3.2 N

AP/CF-21 Williamstown, MA 2

22.2 W

AP/CF-31**

YAEC Visitor's Information Center (Furlon House) 1 0.8 SW I

AP/CF-32**

Heartwellville, VT 2

12.6 NNW TM-12 Readsboro, VT 1

6.1 N

IN-13 Whitingham, VT 1

8.4 ENE IN-21 Williamstown, MA 2

21.0 WSW I

TF-11 Monroe Bridge, MA 1

1.3 SW I

TF-13 Monroe, MA 1

1.9 WNW TF-21 Williamstown, MA 2

21.0 WSW TF-32 Whitingham, VT 1

8.4 ENE I

(Maple Syrup)**

TF-33 Rowe, MA 1

2.4 S

(Maple Syrup)**

l I.

TF-42 Wi111amstown, MA 2

28.3 WSW (Maple Syrup)**

TV-11 Monroe Bridge, MA 1

1.3 SW WG-11 Plant Potable 1

On-Site 1

WG-12 Sherman Spring 1

0.2 NW I

WR-11 Bear Swamp Lower Res.

1 6.3 Downriver q

WR-21 Harriman Reservoir 2

10.1 Upriver J

I 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 I

GM-1 YAEC Visitor's Information Center (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

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ll Table 2.2 (Continued)

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Radiological Environmental Monitoring Locations Yankee Nuclear Power Station Distance g-g Station Code From Plant Direction (Media

_S.ta. No.)

Station Description Inng*

(km)

From Plant I

GM-5 Monroe Bridge 1

1.1 SW GM-6 Readsboro Road Barrier 1

1.3 N

GM-7 Whitingham Line 1

3.5 NE GM-8 Monroe Hill Barrier 1

1.8 S

[I 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 I

GM-12 Readsboro, VT 1

5.5 NNW GM-13 Restricted Area Fence F

0.08 WSW GM-14 Restricted Area Fence F

0.11 WNW I

GM-15 Restricted Area Fence F

0.08 NNW GM-16 Restricted Area Fence F

0.13 NNE GM-17 Restricted Area Fence F

0.14 ENE GM-18 Restricted Area Fence F

0.14 ESE I

GM-19 Restricted Area Fence F

0.16 SE GM-20 Restricted Area Fence F

0.16 SSE GM-21 Restricted Area Fence F

0.11 SSW GM-22 Heartwe11ville, VT 2

12.6 NNW GM-23 W1111amstewn Substation 2

22.2 W

GM-24 Harriman Dam 0

7.3 N

GM-25 Whitingham, VT 0

7.7 NNE I

GM-26 Sadoga Road 0

7.6 NE GM-27 Number 9 Road 0

7.6 ENE GM-28 Number 9 Road 0

6.0 E

I GM-29 Route 8A 0

8.2 ESE GM-30 Route 8A 0

9.4 SE GM-31 Legate Hill Road 0

7.6 SSE I

GM-32 Rowe Road 0

7.9 S

GM-33 Zoar Road 0

6.9 SSW GM Fife Brook Road 0

6.4 SW GM-35 Whitcomb Summit 0

8.6 WSW

,I GM-36 Tilda Road 0

6.6 W

GM-37 Turner Hill Road 0

6.7 WNW GM-38 West Hill Road 0

6.6 NW I

GM-39 Route 100 0

6.8 NNW GM-40 Readsboro Road 1

0.5 W

I 1 = Indicator Stations; 2 = Control Stations; O = Outer Ring Incident Response TLD; F = Fenceline.

Not required by Radiological Effluent Technical Specifications or the Off-Site Dose Calculation Manual.

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Figure 2.1 Yankee Plant Radiological Environmental Monitoring Locations iI Within 1 Mile (Airborne, Waterborne and Ingestion Pathways)

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SHELBURNE FALLS,j Figure 2.2 Yankee Plant Radiological Environmental Monitoring Locations O thin 12 Miles (Airborne, Waterborne and Ingestion Pathways) _

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I Figure 2.3 Yankee Plant Radiological Environmental Monitoring Locations outside 12 Miles (Airborne, Waterborne and Ingestion Pathways) I

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Figure 2.4 Yankee Plant Radiological Environmental Monitoring Locations at I

the Restricted Area Fence (Direct Radiation Pathway) j

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

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Figure 2.6 Yankee Plant Radiological Environmental Monitoring Locations Within 12 Miles (Direct Radiatic' Oathway),

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Figure 2.7 Yankee Plant Radiological Environmental Monitoring Locations I

Outside 12 Miles (Direct Radiation Pathway) _ _

L 3.0 S M ARY OF RADIOLOGICAL ENVIRON 1-lENTAL DATA The following pages summarize the analytical results of the environmental samples which were collected during 1988. Each environmental media category is presented as a separate subsection. A discussion af the t

sampling program and results is followed by a table which summariza year's data for each category. At the top of each table are listed the u.

s of measurement for each medium.

The left hand column contains the radionuclides which is being reported, total number of analyses of that radionuclides, and the number of measurements which exceeds ten times the yearly average for the control station (s). The latter are classified as "nonroutine" measurements. 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 (Table 4.12-1).

LLD requirements are not sp6.cified in the Technical g

5 Specifications for many of the radionuclides for which analyses are routined conducted.

Those sampling stations which are within the racge of influence of the plant and which could conceivably be affected by ita operation are called

" indicator" or " Zone I" stations. Distant stations, which are beyond plant influence are called " Control" or " Zone II" stations. Direct radiation monitoring stations are broken down into two additional categories to aid in data analysis. These are fenceline stations and outer ring (emergency I

response) stations.

A set of statistical parameters is calculated for each radionuclides.

These include separate analyses for (1) the indicator stations, (2) the control stations, and (3) the station having the highest annual mean concentration for that radionuclides. For each of these three groups of data, these parameters are:

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

values below LLD.

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The standard error of the mean.

I o

The lowest aad highest concentration.

I The number of positive measurements (activity which is three times

)

o greater than the standard deviation) divided by the total number of I

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 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.

I With respect to the plots, all values less than three standard deviations (i.e., those where no radioactivity was detected) were plotted as zero.

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I-l 3.1 Air Particulate l.

Air monit.oring stations are establist.ed 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 I.

one cubic foot per minute. Airborne particulate are collected i

by passing the air through a glass-fiber filter. These filters are collected weekly 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-beta activity (indicated as GR-B in tables) to allow for the decay of radon daughter products. Weekly composite air filters from each location are analyzed quarterly for gamma-emitting radionuclides.

Gross-beta analyses (Figure 3.1) show environmentally-induced fluctuations through much of the year at all sampling locations, s

including controls, thereby indicating that any plant contribution is.,egligible. One exception to this is a three-week period in February 1988 at Station AP-32 (Heartwellville Control) when the gross-beta measurements were unusually low. The first and lowest of the three weekly measurements was due apparently to a torn fiM er, which would I

allow some of the airborne particulate matter to bypass the filter. No explanation was arrived at for the other two weeks.

(Station AP-32 is not required by Technical Specifications or the Off-Site Dose Calculation Manual.) Naturally occurring Be-7 was also detected in many samples.

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C jf ED VON T

CO g

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V FR M g!3 STD DEV!ATIONS) l$ INDICATED WITH *(

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EWIRONMENTAL RADIOLOGICAL PROGRAM SUMMAR7 YANKEE NUCLEAR POWER STATION, ROWE, MA I

(JANUARY - DECEMBER 1986) i MEDIUM: AIR PARTICULATE UNITS: PCl/CU. M i

INDICATOR STATIONS STATION WITH HIGHEST MEAN CONTROL STATIONS e**ee...........e*

eeeeeeeeeeeeeeeeeeeeeee**

ee. *****ee **e RADIONUCLIDES MEAN MEAN MEAN (NO. ANALYSES) REOUIRED RANCE STA.
RANGE RANGE (NON ROUTINE)*
LLD NO. DETECTED" NO.
NO. DETECTED **
NO. DETECTED **
GR B (364)
.01
(
2.0 2 0.0)E -2 21
(
2.1 t 0.1)E 2
(
2.0 2 0.1)E 2
( 0)
(
4.9 -
38.0)E -3
(
8.9 -
40.7)E -3
(
2.7 -
40.7)E -3 I
(260/260)*
( 52/ 52)*
(104/104)*
BE-7
( 28)
(
5.4 2 0.3)E -2 21
(
6.1
0.9)E 2
(
5.6 t 0.6)E -2 I
( 0)
(
3.2 -
8.0)E 2
(
4.1 -
8.5)E -2
(
3.5 -
8.5)E 2
( 20/ 20)*
(
4/ 4)*
(
8/ 8)*
K 40 - ( 28)
(
1.0 2 0.8)E -3 13
(
2.8 2.8)E -3
(
1.5 2 0.7)E -3 I
( 0)
(
-6.2 -
10.2)E -3
(
-3.0 -
10.2)E -3 f
1.6 -
3.5)E -3
(
0/ 20)*
(
0/ 4)*
(
0/ 8)*
I MN-54 ( 28)
(
4,5 t 3.4)E -5 21
(
4.4 2 14.0)E 5
(
-8.5 t 75.7)E -6
( 0)
(
-4.4 -
1.6)E -4
(
-3.6 -
2.6)E -4
(
-3.6 -
2.6)E -4
(
0/ 20)*
(
0/ 4)*
(
0/ 8)*
CO 58 ( 28)
(
4.0 t 53.0)E -6 31 '(
1.0 2 0.9)E 4
(
-1.8 2 6.1)E 5
( 0)
(
4.7 -
3.5)E -4
(
-9.4 -
35.1)E -5
(
2.5 -
1.8)E -4 j
(
0/ 20)*
(
0/
4)*
0/ 8)*
FE 59 ( 28)
(
2.6 2 1.5)E -4 12
(
5.7 2 4.0)E 4
(
-1.7 31.5)E -5
( 0)
(
1.4 -
1.7)E -3
(
9.9 - 170.0)E -5
(
-2.0 -
0.8)E -3
(
0/ 20)*
(
0/ 4)*
(
0/ 8)*
Co-60 ( 28)
(
5.6 t 587.5)E -7 13
(
9.3 2 10,5)E -5
(
5.0 t 5.0)E -5
( 0)
(
7.8 -
4.4)E 4
(
1.4 -
3.7)E -4
(
-2.1 -
2.5)E -4 I
(
0/ 20)*
(
0/ 4)*
(
0/ 8)*
2N 65 ( 28)
(
9.4
92.8)E -6 11
(
2.6 x 3.1)E -4
(
1.9
1.4)E 4
( 0)
(
6.2 -
11.6)E -4
(
-2.1 -
11.6)E -4
(
-4.0 -
7.7)E -4
(
0/ 20)*
(
0/ 4)*
(
0/ 8)*
fl 2R 95 ( 28)
(
2.2 2 0.7)E -4 13
(
-7.3 2 164.3)E -6
(
1.1 2 0.9)E -4 g
( 0)
(
-8.5 -
3.7)E 4
(
4.3 -
3.7)E 4
(
-4.7 -
2.6)E -4
(
0/ 20)*
(
0/ 4)*
(
0/ 8)*
I
NON ROUTINE REFERS TO THE NUMBER OF SEPARATE MEASUREMENTS WHICH WERE GREATER THAN TEN (10) TIME 3 THE AVERAGE BACKGROUND FOR THE PERICD OF THE REPORT.
I
THE FRACTION OF SAMPLE ANALYSES YIELDING DETECTABLE MEASUREMENTS (1.E. >3 STD DEV!ATIONS) IS INDICATED WITH *(
)*. I l
4
l 3e2 Charcoal Filters i
Charcoal filter cartridges are held in the air sampling filter head, downst. ream from the air particulate glass-fiber filters.
Monitoring stations were located at a total of seven stations, five of which were required by the Technical Specifications. The I
air pumps at these locations operate continuously at a flow rate of approximately one cubic foot per minute.
Charcoal filters were collected and analyzed weekly for I-131 radioactivity.
During 1988, no such radioactivity was detected.
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ENVIRCMECTAL RADIOLOGICAL PROGRAM
SUMMARY
YANKEE NUCLEAR POWER STATION, ROWE, MA (JANUARY DECEMBER 1988)
MEDIUM: CHARCOAL FILTER UNITS: PCl/CU. M I
INDICATOR STATIONS STATION WITH HIGHEST MEAN CONTROL STATIONS
....... ee*****eeeeeee **
eeee***...e*
RADIONUCLIDES MEAN MEAN MEAN (WO. AW' YSES) REQUIRED RANCE STA.
RAN'GE RANCE (NON-ROUTINE)*
LLD NO. DETECTED **
NO.
NO. DETECTED **
NO. DETECTED **
1 131 (364)
.07
(
-4.7 t 531.9)E -6 21
(
1.9 t 1.2)E -3
(
6.4 7.3)E -4 I
( 0)
(
2.4 -
2.2)E 2
(
1.6 -
2.9)E 2
(
-1.9 -
2.9)E 2 l
(
0/260)*
(
0/ 52)*
(
0/104)*
I.
NON RtUTINE REFERS TO THE NUMBER OF SEPARATF MEASUREMENTS WHICH WERE GREATER THAN TEN (10) TIMES THE AVERACE BACKGROUND FOR THE PERIOD OF THE REPORT.
THE FRACTION OF SANPLE ANALYSES YlELDING DETECTABLE MEASUREMENTS I
(I.E. >3 STD DEVIATIONS) l$ INDICATED WITH *(
)*.
I I
I I
I I
I I
I l
k 3.3 tiilk j
Milk samples were collected and analyzed by the schedule shown in Table 2.1.
Strontium 89 and Sr-90 analyses were also performed I
on quarterly composite milk samples (not required by Technical Specifications).
Detectable concentrations of Cs-137 and Sr-90 were measured in many milk samples submitted during 1988. The higher concentration in indicator station samples has been noted for many years.
It has been shown in previous reports that the radioactivity in the cows' milk is a result of atmospheric nuclear weapons testing radionuclides that persist in the
- I environment (Cs-137 and Sr-90 in particular). Differences in farming practices (amount of vegetation and type of vegetation that the cows are allowed to feed on) can cause significant variations in these radionuclides in n; ilk. The levels of Cs-137 detected at indicator stations during 1988 is consistent with that detected in previous years. Additional Cs-137 was introduced into the environment in mi.d-1986 following the Chernobyl accident. A slight rise in Cs-137 levels in milk can f
be seen for this period in Figure 3.2.
E I
I I
I E 2918R f
l
'I
1 m
7 8
0 8
O 1
9 1
m 7
O 89
.j 1
n m
RM
0.,,,
1 6
U g
8 m
E U
9 I
W 7
O R
s&.
m 5
K N 8
L O 9
1 I I
- M T 2
A m
.N T
u 3I S 4
8 E 7 R 9
R 3 E 1
m U 1 W G -
O I M P FU -
I R 3
m S R 4
8 E E R
9 1
C L M,
C T
U T V,W N
N V,M O m
DAT 2
E RHS 8
E OGM 9
BNA 1
K SII N
DTL m
A RIL EHI u
Y RWW 231 e
112 MMM TTT DoA m
/
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0 B
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8 s
4 2
0 8
4 2
0 s
3 2
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2 2
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@EOdxNEE5OE m
m e
iN" eb t
ENVIRONMENTAL RADIOLOGICAL PROGRAM SUMMAR7 YANKEE NUCLEAR POWER STATION, ROWE, MA (JANUARY - DECEMBER 1988)
MEDIUM: MILK UNITS: PCI/KG I
INDICATOR STATIONS STATION WITH HIGHEST MEAN CONTROL STATIONS e.,eeeeeeeeeee**eee
e******e*********eee ***
eeeee******ee RADIONUCLIDES MEAN MEAN MEAN (NO. ANALYSES) REQUIRED RANGE STA.
RANGE RANGE (NON ROUTINE)*
LLD NO. DETECTED **
NO.
NO. DETECTED **
NO. DETECTED **
SR 89 ( 12)
(
-1.4 s 3.8)E 1 13 (
8.0 2 44.0)E 2
(
-3.5 2 1.5)E 0
( 0)
(
1.5 -
1.4)E O
(
-9.0 -
12.3)E -1
(
-7.1 -
0.2)E O I
(
0/ 8)*
(
0/ 4)*
(
0/ 4)*
SR 90 ( 12)
(
3.0 2 0.4)E O 12 (
3.7 2 0.5)E O
(
2.3 2 0.8)E O I
( 0)
(
1.5 -
4.8)E 0
(
2.8 -
4.8)E O
(
3.0 -
42.4)E -1
(
8/ 8)*
(
4/ 4)*
(
3/ 4)*
I K 40
( 57)
(
1.4 2 0.J)E 3 13
(
1.4 2 0.0)E 3
(
1.3 2 0.0)E 3
( 0)
(
1.1 -
1.6)E 3
(
1.3 -
1.5)E 3
(
1.2 -
1.5)E 3
( 38/ 38)*
( 19/ 19)*
( 19/ 19)*
MN 54 ( 57)
(
1.6 2 2.4)E 1 12
(
4.7 2 3.0)E -1
(
4.4 t 3.7)E -1
( 0)
(
-4.5 -
4.7)E O
(
1.4 -
4.7)E O
(
-5.8 -
2.2)E 0
(
0/ 38)*
(
0/ 19)*
(
0/ 19)*
Co 58 ( 57)
(
5.2 2 19.0)E -2 13
(
1.2 2 2.6)E 1
(
-2.5 s 2.4)E 1
( 0)
(
-2.7 -
2.0)E O
(
-2.0 -
1.8)E O
(
-2.1 -
2.0)E O
(
0/ 38)*
(
0/ 19)*
(
0/ 19)*
FE 59 ( 57)
(
6.4 2 4.5)E -1 12
(
1.1 t 0.6)E O
(
3.5
6.5)E -1
( 0)
(
6.3 -
8.8)E O
(
3.4 -
8.8)E O
(
5.6 -
5.8)E O
(
0/ 38)*
(
0/ 19)*
(
0/ 19)*
Co 60 ( 57)
(
4.8 t 2.5)E -1 13
(
-2.2 1 3.5)E -1
(
-6.8 2 3.3)E -1 I
( 0)
(
4.9 -
2.9)E O
(
2.5 -
2.9)E O
(
2.7 -
2.9)E O
(
0/ 38)*
(
0/ 19)*
(
0/ 19)*
ZN 65 ( 57)
(
8.9 2 5.7)E -1 21
(
2.72 6.1)E 1
(
2.72 6.1)E *1
( 0)
(
-7.8 -
6.4)E 0
(
5.6 -
5.2)E 0
(
-5.6 -
5.2)E 0
(
0/ 38)*
(
0/ 19)*
(
0/ 19)*
2R 95 ( 57)
(
7.0 t 3.5)E 1 21
(
9.1 1 4.7)E 1
(
9.1 t 4.7)E -1
( 0)
(
5.0 -
3.8)E 0
(
-2.0 -
5.4)E O
(
-2.0 -
5.4)E O
(
0/ 38)*
(
0/ 19)*
(
0/ 19)*
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.
THE FRACTION OF SAMPLE ANALYSES YlELDING DETECTABLE MEASUREMENTS l
(1.E. >3 STD DEVIATIONS) IS INDICATED WITH *(
)*.
1 - -
E0VIRONMEUTAL RADIOLOGICAL PROGRAM
SUMMARY
YANKEE NUCLEAR POWER STATION, ROWE, MA (JANUARY - DECEMBER 1988)
MEDILW: MILK UNITS: PCl/KG I
. INDICATOR STATIONS STATION WITH HIGHEST MEAN CONTROL STATIONS
eeeeeeeeeeeeeee*e eeeeee***eeeeeeeeeeeeeee*
eeeeeeees RADIONUCLIDES MEAN MEAN MEAN (NO. ANALYSES) REQUIRED RANGE STA.
RANGE RANGE (NON ROUTINE)*
LLD NO. DETECTED **
NO.
NO. DETECTED **
Wo. DETECTED **
I.
AG-110M( 57)
(
5.3
305.2)E -3 12
(
3.6 t 4.5)E -1
(
1.7
3.2)E -1
( 0)
(
5.1 -
4.9)E 0
(
-3.3 -
.4.9)E O
(
-3.8 -
1.6)E O
(
0/ 38)*
(
0/ 19)*
(
0/ 19)*
RU 103 ( 57)
(
-1.2 2 0.2)E O 21
(
-2.2 t 3.6)E -1
(
-2.2 2 3.6)E -1 I
( 0)
(
3.5 -
1.1)E O
(
3.4 -
2.0)E O
(
-3.4 -
2.0)E O
(
0/ 38)*
(
0/ 19)*
(
0/ 19)*
RU 106 ( 57)
(
5.4
15.7)E 1 21
(
6.1 2 20.0)E -1
(
6,1 2 20.0)E -1 I
( 0)
(
-2.5 -
2.6)E 1
(
-2.7 -
1.2)E i
(
-2.7 -
1.2)E 1
(
0/ 38)*
(
0/ 19)*
(
0/ 19)*
I.
l-131 ( 57) 1.
(
8.4 1 2.4)E -2 12
(
9.3 2 3.2)E -2
(
-1.5 1 23.0)E -3
( 0)
(
1.5 -
6.1)E 1
(
-1.5 -
3.5)E -1
(
-3.2 -
1.3)E -1
(
0/ 38)*
(
0/ 19)*
(
0/ 19)*
CS-134 ( 57) 15.
(
-8.1 2 1.5)E -1 13
(
-7.8 t 2.3)E -1
(
-1.2 0.2)E D
( 0)
(
-3.0 -
1.0)E O
(
-3.0 -
0.9)E O
(
-2.4 -
0.2)E O
(
0/ 38)*
(
0/ 19)*
(
0/ 19)*
CS 137 ( 57) 18.
(
2.6 2 0.2)E O 12
(
3.0 2 0.4)E O
(
8.7 t 2.2)E -1
( 0)
(
1.1 -
69.3)E -1
(
1.1 -
69.3)E -1
(
-9.6 -
26.9)E -1
( 10/ 38)*
(
8/ 19)*
(
0/ 19)*
BA-140 ( 57) 15.
(
-3.1 i 4.2)E -1 21
(
-4.7 2 39.6)E -2
(
4.71 39.6)E -2
( 0)
(
-5.7 -
4.3)E O
(
3.7 -
3.2)E 0
(
-3.7 -
3.2)E O
(
0/ 38)*
(
0/ 19)*
(
0/ 19)*
CE 141 ( 57)
(
-3.3 2 2.9)E -1 21
(
1.5 2 6.1)E -1
(
1.5 2 6.1)E -1
( 0)
(
3.5 -
4.3)E O
(
5.8 -
4.3)E O
(
-5.8 -
4.3)E O
(
0/ 38)*
(
0/ 19)*
(
0/ 19)*
CE 144 ( $7)
(
2.32 1.2)E 0 21
(
2.2
15.1)E -1
(
2.2 2 15.1)E 1
( 0)
(
-2.2 -
1.7)E 1
(
-1.1 -
1.6)E 1
(
-1.1 -
1.6)E 1
(
0/ 38)*
(
0/ 19)*
(
0/ 19)*
i
NON ROUTINE REFERS TO THE NUMBER OF SEPARATE MEASUREMENTS WHICH UERE GREATER THAN 1EN (10) TIMES THE AVERAGE BACKGROUND FOR THE PERIOD OF THE REPORT.
THE FRACTION OF SAMPLE ANALYSES YlELDING DETECTABLE MEASUREMENTS E-(1.E. >3 STD DEVIATIONS) IS INDICATED WITH *(
)*. l l
3.4 E go L D r2 p Kale or tomato samples were collected at harvest time at the three locations and analyzed for gamma-emitting nuclides. Other than naturally occurring K-40, no radionuclides were detected in the samples. Three maple syrup samples were collected in 1988 and are discussed in Section 3.6.
1 I
I I.
I I
I LI
~ ~
2918R
c ENt41RONMENTAL RADIOLOGICAL PROGRAM
SUMMARY
YANKEE NUCLEAR POWER STATION, ROWE, MA (JANUARY - DECEMBER 1988)
MEDIUM: FOOD CROP UNITS: PCl/KG WET INDICATOR STAT!DNS STATION WITH HIGHEST MEAN CONTROL STATIONS
e ************ee
.....e***ee.......***
RADIONUCLIDES MEAN MEAN MEAN (NO. ANALYSES) REQUIRED RANGE STA.
RANGC RANGE (NON ROUTINE)*
LLD NO. DETECTED **
NC NO. DETECTED **
No. DETECTED **
BE-7
( 3)
(
7.3 1 48.4)E O 11
(
4.1 t 10.1)E 1
(
6.5 t 8.3)E 1 I
( 0)
(
5.6 -
4.1)E 1
(
0/ 2)*
(
0/ 1)*
(
0/ 1)*
K-40
( 3)
(
2.8 2 1.0)E 3 11
(
3.7 0.3)E 3
(
2.4 2 0.4)E 3
( 0)
(
1.8 -
3.8)E 3
(
2/ 2)*
(
1/
1)*
(
1/ 1)*
I MN 54 ( 3)
(
8.2 e 3.9)E 0 11
(
1.2 1 1.3)E 1
(
1.6 t 1.1)E 1
( 0)
(
4.4 -
12.1)E 0
(
0/ 2)*
(
0/ 1)*
(
0/
1)*
Co 58 ( 3)
(
-1.1 2 0.3)E 1 21
(
-2.7 2 9.5)E O
(
-2.7 9.5)E O
( 0)
(
1.4 -
0.8)E 1
(
0/ 2)*
(
0/ 1)*
(
0/ 1)*
FE-59 ( 3)
(
2.0 t 9.6)E 0 21
(
2.5 t 2.4)E 1
(
2.5 2.4)E 1
( 0).
(
1.1 -
0.8)E 1
(
0/ 2)*
(
0/
1)*
(
0/ 1 )'
Co-60 ( 3)
(
-2.0 1 1.2)E 1 21
(
2.6 t 18.8)E O
(
2.6 2 18.8)E O
( 0)
(
3.2 -
0.8)E 1 I
(
0/ 2)*
(
0/ 1)*
(
0/ 1)*
ZN 65 ( 3)
(
8.2 t 28.3)E O 11
(
2.0 3.1)E 1
(
4.9 2 26.4)E O
( 0)
(
-3.7 -
2.0)E 1
(
0/ 2)*
(
0/ 1)*
(
0/ 1)*
ZR-95 ( 3)
(
1.4 2 0.9)E 1 13
(
2.3
2.2)E 1
(
2.0 2 1.9)E 1
( 0)
(
5.1 -
23.6)E O
(
0/ 2)*
(
0/ 1)*
(
0/
1)*
AG-11DMC 3)
(
8.7 2 17.3)E O 11
(
2.6 2 2.0)E 1
(
-3.7 2 13.4)E O
( 0)
(
-8.6 -
26.1)E O
(
0/ 2)*
(
0/ 1)*
(
0/ 1)*
1 NON ROUTIKE REFERS TO Th[ NUMBER OF SEPARATE ME%SUREMENTS WHICH WERE GREATER THAN TEN (10) TIMES THE AVERACE BACKGROUND F04 THE PERIOD OF THE REPOR1.
I
THE FRACTION OF SAMPLE ANALYSES YlELDING DE7ecTABLE MEASUREMENTS (1.E. >3 STD DEVI ATIONS) IS INDICATED WITH *(
)*. - - _ - - - _ _ - _ _ - -
b
ENVIRONMENTAL RADIOLOGICAL PROGRAM
SUMMARY
YANKEE NUCLEAR POWER STATION, ROWE, MA (JANUARY DECEMBER 1988) f MEDIUM: FOOD CROP UNITS: PCI/KG WET INDICATOR STATIONS STATION WITH HIGHEST MEAN CONTROL STATIONS RADIONUCLIDES MEAN MEAN MEAN (NO. ANALYSES) REQUIRED RANGE STA.
RANGE RANGE (NON ROUTINE)*
LLD No. DETECTED **
NO.
NO. DETECTED **
No. DETECTED **
RU 103 ( 3)
(
-2.0 2 10.0)E 0 13
(
8.0 2 10.6)E O
(
3.6 2 9.4)E O
( 0)
(
-1.2 -
0.8)E 1
(
0/ 2)*
(
0/ 1)*
(
0/
1)*
RU 106 ( 3)
(
5.7 t 1.5)E 1 13
(
7.2 10.4)E 1
(
-7.7 2 9.4)E 1
( 0)
(
4.2 -
7.2)E 1
(
(
0/ 2)*
(
0/ 1)*
(
0/ 1)*
l l 131 ( 3)
(
5.4 17.6)E O 13
(
1.2 2 1.6)E 1
(
4.72 17.1)E O
( 0)
(
-2.3 -
1.2)E 1
(
0/ 2)*
(
0/ 1)*
(
0/ 1)*
CS 134 ( 3) 60.
(
-9.7 2 13.5)E 0 13
(
3.8 t 13.0)E 0
(
-3.3 2 1.3)E 1
( 0)
(
2.3 -
0.4)E 1
(
0/ 2)*
(
0/ 1)*
(
0/ 1)*
CS-137 ( 3) 80.
(
4.9 2 5.6)E 0 13
(
6.0 1 113.0)E -1
(
-2.3 2 1.0)E 1
( 0)
(
-1.0 -
0.1)E 1
(
0/ 2)*
(
0/ 1)*
(
0/
1)*
I.
BA 140 ( 3)
(
2.9 2 0.4)E 1 21
(
2.0 2 1.6)E 1
(
2.0 2 1,6)E 1
( 0)
(
-3.2 -
2.5)E 1
(
0/ 2)*
(
0/
1)*
(
0/ 1)*
CE 141 ( 3)
(
8.5 2 14.6)E O 11
(
2.3 2 1.9)E 1
(
1.1 2 1.5)E 1
( 0)
(
6.1 -
23.1)E O
(
0/ 2)*
(
0/ 1)*
(
0/ 1)*
CE 144 ( 3)
(
-2.4 t 2.8)E 1 11
(
3.9 1 69.2)E O
(
4.0 2 5.3)E 1 I
( 0)
(
5.2 -
0.4)E 1
(
0/ 2)*
(
0/ 1)*
(
0/ 1)*
I TH 232 ( 3)
(
1.8 2 1.8)E 1 13
(
1.1 2 523.0)E -1
(
-3.8 2 53.4)E O
( 0)
(
-3.6 -
0.0)E 1
(
0/ 2)*
(
0/
1)*
(
0/
1)*
NON ROUTINE REFFRS TO THE NUMBER OF SEPARATE MEASUREMENTS WHICH 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 DEVIATIONS) IS INDICATED WITH *(
)*.
3.5 Broad Leaf Vegetation j
i The Radiological Effluent Technical Specifications require that one sample of broad leaf vegetation be sampled at harvest time.
In 1988, a sample of kale was collected from Station TV-11.
The required I-131 analysis showed no detectable radioactivity.
I:
- I I
1 g.
1 I
I I 2918R
ENVIRONMENTAL RADIOLOGICAL PROGRAM
SUMMARY
YANKEE NUCLEAR POWER STATION, ROWE, MA (JANUARY - DECEMBER 1988)
MEDIUM: BROADLEAF VEGETATION UNITS: PCl/KG WET I
INDICATOR STATIONS STATION WITH HIGHEST MEAN CONTROL STATIONS
eeeeeeee*****eee.
RADIONUCLIDES MEAN MEAN MEAN I
(NO. ANALYSES) REQUIRED RANCE STA.
RANGE RANCE (NON ROUTINE)*
LLD NO. DETECTED **
NO.
NO. DETECTED **
N0. DETECTED **
1 131 ( 1) 60.
(
2.5 t 2.0)E O 11
(
2.5 t 2.0)E O NO DATA
( 0)
(
0/ 1)*
(
0/ 1)*
I
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.
THE FRACTION OF SAMPLE ANALYSES Y1ELDING DETECTABLE MEASUREMENTS i
(I.E. >3 STD DEVIATIONS) IS INDICATED WITH *(
)*,
i I
I I
I
' I I
I J
I 3.6 tigpie Syrup "I
l Maple syrup grab samples (not required by Technical Specifications) were collected during April at two indicator and one control location.
In addition to naturally occurring K-40 l
and Th-232, Cs-137 was detected in each sample. Attributed to nuclear weapons testing fallout, this Os-137 has been detected in I
most samples since collection was started in 1972. The control I
station in 1988 had a higher Cs-137 level than detected at either of the indicator stations.
I 4
I 2918R I
l l
l I
ENVIRONMENTAL RADIOLOGICAL PROGRAM
SUMMARY
YANKEE NUCLEAR POWER STATION, ROWE, MA l
(JANUARY - DECEMBER 1988) l I
MEDIUM: MAPLE SYRUP UNITS: PCl/KG I
INDICATOR STATIONS STATION WITH HIGHEST MEAN CONTROL STATIONS ee***ee........ee*
e.. ***ee **ee...........
ee..........
RADIONUCLIDES MEAN MEAN MEAN (NO. ANALYSES)
REQUIRED RANGE STA.
RANGE RANCE (NON ROUTINE)*
LLD NO. DETECTED **
NO.
NO. DETECTED **
NO. DETECTED **
I l
BE-7
( 3)
(
8.6 2 2.4)E O 42
(
2.0 t 1.0)E 1
(
2.0 1 1.0)E 1
( 0)
(
6.2 -
11.0)E O I
(
0/ 2)*
(
0/ 1)*
(
0/ 1)*
l K-40
( 3)
(
1.8 t 0.0)E 3 33
(
1.8 t 0.0)E 3
(
1.6 2 0.1)E 3
( 0)
(
1.7 -
1.8)E 3
(
2/ 2)*
(
1/ 1)*
(
1/ 1)*
I MN 54 ( 3)
(
2.0 t 0.0)E O 42
(
1.4 1 1.1)E O
(
1.4 t 1.1)E O
( 0)
(
2.0 -
2.0)E O
(
0/ 2)*
(
0/ 1)*
(
0/ 1)*
CO-58 ( 3)
(
7.7 t 4.3)E 1 32
(
1.2 t 1.0)E 0
(
-5.2 t 11.8)E -1
( 0)
(
3.3 -
12.0)E -1
(
0/ 2)*
(
0/
1)*
(
0/
1)*
FE-59 ( 3)
(
1.6 t 1.6)E 0 32
(
3.2 2 3.2)E D
(
1.5 2 2.7)E O
( 0)
(
3.2 - 315.0)E -2
(
0/ 2)*
(
0/ 1)*
(
0/
1)*
CO-60 ( 3)
(
5.6 t 3.2)E -1 33
(
8.8 t 13.1)E 1
(
5.1 t 14.4)F -1
( 0)
(
2.3 -
8.8)E 1
(
0/ 2)*
(
0/
1)*
(
0/
1)*
ZN-65 ( 3)
(
1.4 2 2.0)E O 32
(
3.5 t 3.1)E 0
(
-4.2 2 27.4)E -1 i
I
( 0)
(
-6.3 -
34.6)E ~1
(
0/ 2)*
(
0/ 1)*
(
0/ 1)*
2R 95 ( 3)
(
9.0 2 11.1)E 1 32
(
2.0 2 1.8)E 0
(
-2.6 2 2.0)E O I
( 0)
(
2.1 -
20.2)E -1
(
0/ 2)*
(
0/ 1)*
(
0/ 1)*
I AG 110M( 3)
(
1.7 2 1.0)E O 32
(
2.6 2 2.0)E O
(
7.0 2 15.5)E -1
( 0)
(
7.2 -
26.4)E -1
(
0/ 2)*
(
0/ 1)*
(
0/ 1)*
I
NON ROUTINE REFERS TO THE NUMPER OF SEPARATF MEASUREMENTS WHICH 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 DEV!ATIONS) IS INDICATED WITH *(
)*.
l ENVIRONMENTAL RADIOLOGICAL PROGRAM
SUMMARY
YANKEE NUCLEAR POWER STATION, ROWE, MA
(
(JANUARY DECEMBER 1988) l MEDIUM: MAPLE SYRUP UNITS: PCl/KG I
INDICATOR STATIONS STATION WITH HIGHEST MEAN CONTROL STATIONS
............**.e RADIONUCLIDES MEAN MEAN MEAN (NO. ANALYSES) REQUIRED RANGE STA.
RANCE RANGE (NON ROUTINE)*
LLD No. DETECTED **
NO.
NO. DETECTE0**
Wo. DETECTED **
RU 103 ( 3)
(
~3.7 2 6.2)E -1 33
(
2.5 a 8.7)E -1
(
-4.9 s 11.6)E -1
( 0)
(
-9.8 -
2.5)E -1
-I
(
0/ 2)*
(
0/ 1)*
(
0/
1)*
RU 106 ( 3)
(
1.72 2.9)E O 32
(
4.6
9.2)E O
(
1.7 a 10.6)E O I
( 0)
( - 1. 2 -
4.6)E O
(
0/ 2)*
(
0/ 1)*
(
0/
1)*
I 131 ( 3)
(
8.5 2 0.5)E -1 33
(
9.0 2 11.7)E -1
(
-8.7 2 177.0)E 2
( 0)
(
8.0 -
9.0)E 1
(
0/ 2)*
(
0/ 1)*
(
0/ 1)*
I CS-134 ( 3)
(
9.4 2 1.5)E -1 42
(
1.4 2 12.1)E -1
(
1.4 2 12.1)E -1
( 0)
(
-1.1 -
-0.8)E O l
(
0/ 2)*
(
0/ 1)*
(
0/
1)*
CS-137 ( 3)
(
2.2 s 0.8)E 1 42
(
1.2 2 0.0)E 2
(
1.2
0.0)E 2
( 0)
(
1.4 -
3.0)E 1
(
2/ 2)*
(
1/ 1)*
(
1/ 1)*
BA-140 ( 3)
(
1.2 t 5.5)E -1 42
(
7.8 t 12.5)E 1
(
7.8 2 12.5)E 1
( 0)
(
4.3 -
6.7)E -1
(
0/ 2)*
(
0/ 1)*
(
0/ 1)*
CE 141 ( 3)
(
-1.9 2 0.9)E O 33
(
-1.0 2 1.5)E O
(
2.4 2 2.0)E O
~I
( 0)
(
2.8 -
-1.0)E O
(
0/ 2)*
(
0/ 1)*
(
0/ 1)*
CE-144 ( 3)
(
-4.6 2 4.1)E 0 33
(
-5.7 1 63.8)E -1
(
-4.4 2 8.2)E O
( 0)
(
-8. 7 -
-0.6)E O
(
0/ 2)*
(
0/ 1)*
(
0/ 1)*
'I TM-232 ( 3)
(
9.5 2 3.9)E O 33
(
1.3 2 0.4)E 1
(
4.2 t 4.6)E O
( 0)
(
5.6 -
13.4)E O
(
1/ 2)*
(
1/ 1)*
(
0/
1)'
I
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 YlELDING DETECTABLE MEASUREMENTS (I.E. >3 STD DEVIATIONS) !$ INDICATED WITH *(
)*.
l
!(
3e7 Groundwater Groundwater grab samples were collected from two indicator stations on a monthly basis.
(Technical Specifications require a i
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' Station WG-11.
Since the water from WG-12
)
(Sherman Spring) is not.used for drinking water, and since the Deerfield River into which it emptieo is also not used for drinking, there would be no impact on man from the low levels detected.
In any case, the calculated critical organ (total I
body) dose to an average child who is assumed to ingest 260 kilograms per year of this water (undiluted) at the average 1988 concentration of 820 pC1/ kilogram, would be approximately 0.04 mrem, using USNRC Regulatory Guide 1.109 methodology (Reference 1).
The maximum monthly concentration of 1,260 pCi/kg in April of 1988 did not exceed the 30,000 pCi/kg reporting level for H-3 in water.
The annual mean H-3 concentration has decreased steadily for most of the past ten years (see Figure 3.3).
I Gross-beta radioactivity was detected in all groundwater samples. Caused primarily by naturally occurring radionuclides in groundwater, the gross-beta levels were similar to those of the past several years (see Figure 3.4).
Wo ga_ a-emitting raeionuc11ees.ere e.tectee in the groune. ate, g
f
samples, I
4 i 2918R I
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I s I
-I EN'f!RONMENVAL RADIOLOGICAL PROGRAM SUMMAR7 YANKEE NUCLEAR POWER STATION, ROWE, MA 3
l (JANUARY DECEMBER 1988)
MEDIUM: GROUND WATER LNITS: PCI/KG I
INDICATOR STATIONS STATION WITH HIGHEST MEAN CONTROL STATIONS ee**ee........eee.
.............e***e***ee..
e********e......
I RADIONUCLIDES MEAN MEAN MEAN (NO ANALYSLS) REQUIRED RANGE STA.
RANGE RANGE (NON ROUTINE)*
LLD NO. DETECTED **
NO.
NO. DETECTED **
NO. DETECTED **
GF.- B
( 24) 4
(
3.6 1
.1)E O 11
(
3.8 2 0.2)E O No DATA
( 0)
(
2.7 -
5.3)E 0
(
3.0 -
c.3)E O
( 24/ 24)*
( 12/ 12)*
K-40
( 24)
(
-5.1 2 25.5)E 1 11
(
-8.5 a 314.1)E -2 NO DATA I
( 0)
(
2.9 -
2.8)E 1
(
-2.1 -
1.4)E 1
(
0/ 24)*
(
0/ 12)*
l I
MN 54 ( 24) 15.
(
-3.3 2 1.8)E -1 11
(
-2.3 t 2.9]E -1 No DATA I
( 0)
(
2.3 -
1.3)E O
(
-2.3 -
1.3)E 9
(
0/ 24)*
(
0/ 12)*
I.
Co 58 ( 24) 15.
(
2.5 t 1.4)E 1 12 (
-1.5 t 1.9)E -1 No DATA
( 0)
(
-2.2 -
1.1)E D
(
1.0 -
1.1)E O
(
0/ 24)*
(
0/ 12)*
I FE 59 ( 24) 30.
(
1.4 2 6.1)E -1 12
(
1.2 1 0.9)E D NO DATA
( 0)
(
4.8 -
9.1)E O
(
1.6 -
9.1)E O
(
0/ 24)*
(
0/ 12)*
i Co 60 ( 24) 15.
(
-6.1 2 1.5)E -1 11
(
5.9 t 2.1)E 1 NO DATA
( 0)
(
2.0 -
0.7)E O
(
1.9 -
0.6)E O
(
0/ 24)*
(
0/ 12)*
ZN 65 ( 24) 30.
(
-2.6 1 5.2)E -1 11
(
3.7
9.6)E -1 NO DATA
( 0)
(
6.5 -
5.6)E O
(
6.5 -
5.6)E O I
(
0/ 24)*
(
0/ 12)*
j 2R 95 ( 24) 15.
(
1.1 2 5.1)E -1 12 (
2.2 2 6.9)E 1 NO DATA I
( 0)
(
6.5 -
6.5)E O
(
-1.8 -
6.5)E O
(
0/ 24)*
(
0/ 12)*
I~
AG-110M( 24)
(
1.6 t 2.2)E -1 12 (
2.1 2 2.5)E -1 NO DATA
( 0)
(
-1.8 -
2.6)E O
(
-1.0 -
1.6)E 0
(
0/ 24)*
(
0/ 12)*
I
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 YlELDING DETECTABLE MEASUREMENTS (1.E. >3 STD DEVIATIONS) IS INDICA 1ED WITH *(
)*.
I. I
i I
ENVIRONMENTAL RADIOLOGICAL PROGRAM
SUMMARY
YANKEE NUCLEAR POWER STATION, ROWE, MA i
(JANUARY - DECEMBER 1988)
MEDIUM: CROUND WATER UNITS: PCl/KG l
l INDICATOR STATIONS STATION WITH HIGHEST MEAN CONTROL STATIONS I
RADIONUCLIDES MEni MEAN MEAN (NO. ANALYSES) REQUIRED RANGE STA.
RANGE RANGE (NON ROUTINE)*
LLD NO. DETECTED **
NO.
NO. DETECTED **
NO. DETECTED **
j I
1 RU-103 ( 24)
(
8.9 s 2.1)E -1 12
(
-5.1
3.3)E -1 NO DATA
)
( 0)
(
2.4 -
1.')F 0
(
2.0 -
1.7)E D
(
0/ 24)*
(
0/ 12)*
i l
RU 106 ( 24)
(
1.6 2 1.3)E 0 11
(
-9.9 2 20.7)E -1 NO DATA I
( 0)
(
-1,1 -
1.3)E 1
(
9.6 -
12.8)E O
(
0/ 24)*
(
0/ 12)*
l 131 ( 24) 1.
(
-9.4 1 59.4)E 2 11
(
.'.4 2
10.2)E 1 NO DATA
( 0)
(
6.7 -
6.1)E 0
(
-6.'
6.1)E O
(
0/ 24)*
(
0/ 12)*
CS-134 ( 24) 15.
(
-2.1 2.5)E -1 11
(
3.2 2 4.2)E 1 NO DATA
( 0)
(
-1.9 -
3.8)E O
(
-1.2 -
3.8)E O
(
0/ 24)*
(
0/ 12)*
CS 137 ( 24) 18.
(
-1.1 t 2.6)E 1 12
(
1.5 3.1)E 1 NO DATA
( 0)
(
2.5 -
2.1)E O
(
1.8 -
1.8)E O
(
0/ 24)*
(
0/ 12)*
BA 140 ( 24) 15.
(
-2.8 3.5)E -1 12
(
1.6 t 6.5)E -1 NO DATA l
( 0)
(
-4.7 -
3.7)E 0
(
-4.7 -
3.7)E O
(
0/ 24)*
(
0/ 12)*
CE 141 ( 24)
(
1.0 2 4.4)E -1 12 (
5.3 7.0)E -1 No DATA
( 0)
(
4.0 -
6.7)E O
(
-2.6 -
6.7)E O
(
0/ 24)*
(
0/ 12)*
l CE-144 ( 24)
(
-1.9 1 1.3)E O 12
(
-8.6 s 17.0)E -1 NO DATA I
( 0)
(
-1.1 -
1.1)E 1
(
-1.1 -
0.6)E 1
(
0/ 24)*
(
0/ 12)*
i I
H3
( 24) 2000.
(
3.5 1.1)E 2 12
(
8.2 2 0.8)E 2 NO DATA
( 12)
(
-2.7 -
12.6)E 2
(
4.0 -
12.6)E 2
( 12/ 24)*
( 12/ 12)*
I NON-ROUTINE ' 'FERS TO THE NUMBER OF SEPARATE MEASUREMENTS WHICH WERE GREATER THAN TEN (1' TIMES THE AVERAGE BACKGROUND FC THE PERIOD OF THE REPORT.
THE FRACTION v SAMPLE ANALYSES YIELDING DETECTABLE MEASUREMENTS (1.E. >3 STD DEVIATIONS) IS INDICATED WITH *(
)*.
~. I m_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _.
4
3.8 River Water I'
Composite samplers were used at the two required sampling locations and samples from each of these were collected monthly and analyzed for gross-beta and gamma-emitting radionuclides.
Quarterly composites were analyzed for H-3.
The second and third 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 water, the low levels of H-3 found will have no impact on man.
If one was to
. calculate, however, the critical organ (total body) dose to an average child who consumed his entire yearly intake of water I
(260 kilograms per year) from the Deerfield River at the above sampling location, with the average concentration of 520 pCi/ kilogram over the entire year, the dose would be approximately 0.03 mrem per year, using USNRC Regulatory Guide 1.109 methodology (Reference 1).
The maximum quarterly concentration of 1,030 +210 pCi/ kilogram during the second I
quarter of 1988 did not exceed the 30,000 pCi/ kilogram reporting level for H-3 in water.
I Gross-beta radioactivity, primarily frou naturally occurring radionuclides in river water, was detected in most semples. The mean and range were similar to those measured in previous years.
The control and indicator station mean concentrations were again approximately equal in 1988. No gamma-emitting radionuclides were detected in the 1988 river water samples.
I i
I I
I 2918R I
I i
ENVIRONMENTAL RADIOLOGICAL PROGRAM
SUMMARY
YANKEE NUCLEAR POWER STATION, ROWE, MA
. JANUARY DECEMBER 1988)
(
MEDIUM: RIVER WATER UNITS: PCl/KG I
INDICATOW STATIONS STATION WITH HIGHEST MEAN CONTROL STATIONS I
RADIONUCLIDES MEAN MEAN MEAN (NO. ANALYSES) REQUIRED RANGE STA.
RANGE RANGE (NON-ROUTINE)*
LLD NO. DETECTED" NO.
NO. DETECTED **
No. DETECTED **
GR B ( 24) 4
(
1.7 2 0.2)E D 11
(
1.7
0.2)E O
(
1.6 2 0.1)E O
( 0)
(
8.9 -
32.0)E -1
(
8.9 -
32.0)E -1
(
1.2 -
2.0)E O
( 11/ 12)*
( 11/ 12)*
( 12/ 12)*
K-40
( 24)
(
~2.8 2 4.8)E O 21
(
1.2 2 3.5)E O
(
1.22 3.5)E O l
( 0)
(
2.7 -
1.9)E 1
(
1.8 -
2.0)E 1
(
1.8 -
2.0)E 1 f
I
(
0/ 12)*
(
0/ 12)*
(
0/ 12)*
NN-54 f 24) 15.
(
3.0 2 1.7)E -1 21
(
-7.1 2 26.6)E -2
(
7.1 1 26.6)E -2
( 0)
(
1,6 -
0.3)E D
(
1.0 -
1.6)E O
(
-1.0 -
1.6)E O
(
0/ 12)*
(
0/ 12)*
(
0/ 12)*
I CO 58 ( 24) 15.
(
-3.2 3.6)E -1 21
(
6.3 2 17.6)E 2
(
-6.3 2 17.6)E -2
( 0)
(
2.0 -
2.9)E 0
(
1.0 -
0.8)E O
(
1.0 -
0.8)E O
(
0/ 12)*
(
0/ 12)*
(
0/ 12)*
FE-59 ( 24) 30.
(
8.9 2 7.1)E 1 11
(
8.9 2 7.1)E 1
(
-1.4 2 0.7)E D
( 0)
(
2.8 -
6.2)E O
(
-2.8 -
6.2)E O
(
-5.4 -
2.7)E 0
(
0/ 12)*
(
0/ 12)*
(
0/ 12)*
Co 60 ( 24) 15.
(
-4.2 2 4.2)E -1 21
(
-3.6
32.0)E 2
(
-3.6 2 32.0)E -2
( 0)
(
-3.6 -
1.7)E 0
(
1.2 -
2.9)E O
(
1,2 -
2.9)E O I.
(
0/ 12)*
(
0/ 12)*
(
0/ 12)*
2N 65 ( 24) 30.
(
5.5 t 7.0)E 1 21
(
1.8 t 3.6)E ~1
(
-1.8 2 3.6)E -1
( 0)
(
-5.3 -
2.1)E U
(
1.4 -
2.8)E 0
(
1.4 -
2.8)E 0 I
(
0/ 12)*
(
0/ 12)*
(
0/ 12)*
2R 95 ( 24) 15.
(
1.0 2 63.5)E -2 11 (
1.02 63.5)E 2
(
-3.5 2 4.0)E *1
( 0)
(
4.5 -
3.3)E 0
(
-4.5 -
3.3)E O
(
-2.5 -
1.3)E O
(
0/ 12)*
(
0/ 12)*
(
0/ 12)*
I AG 110M( 24)
(
4,4 2 2.7)E -1 11
(
4.4 2 2.7)E 1
(
-6.3
42.1)E -2
( 0)
(
7.0 -
27.8)E -1
(
7.0 -
27.8)E -1
(
-1.7 -
3.8)E O
(
0/ 12)*
(
0/ 12)*
(
0/ 12)*
NON ROUTINE REFERS TO THE NUMBER OF SEPARATE MEASUREMENTS WHICH WERE GREATER THAN TEN (10) TIMES THE AVERAGE CACKGROUND FOR THE PERIOD OF THE REPORT.
I
THE FRACTION OF SAMPLE ANALYSES YlELDING DETECTABLE MEASUREMENTS (1.E. >3 STD DEVIATIONS) IS INDICATED WITH *(
)*.
l LI L
I ENVIRONMENTAL RADIOLOGICAL PROGRAM
SUMMARY
)
YANKEE NUCLEAR POWER STATION, ROWE, MA (JANUARY DECEMBER 1988)
MEDIUM: RIVER WATER UNITS: PCI/KG I
INDICATOR STATIONS STATION WITH HIGHEST MEAN CONTROL STATIONS eee.........e**ee.
.........e***ee.....eeee.
ee...........
RADIONUCLIDES MEAN MEAN MEAN (NO. ANALYSES) REQUIRED RANGE STA.
RANGE RANGE (NON ROUTINE)*
LLD No. DETECTED **
NO.
NO. DETECTED **
NO. DETECTED **
RU 103 ( 24)
(
-7.8 2 2.9)E 1 21
(
-6.9 3.6)E -1
(
6.9 2 3.6)E 1
( 0)
(
2.0 -
1.0)E 0
(
3.5 -
1.8)E D
(
3.5 -
1.8)E 0 I
(
0/ 12)*
(
0/ 12)*
(
0/ 12)*
RU 106 ( 24)
(
3.62 2.4)E O 21
(
-2,7 e 2.8)E D
(
-2.7 2 2.8)E 0
. I
( 0)
(
1.6 -
1.6)E 1
(
-2.4 -
0.9)E 1
(
2.4 -
0.9)E 1
(
0/ 12)*
(
0/ 12)*
(
0/ 12)*
I I-131 ( 24)
(
1.3 1 6.7)E -1 21
(
1.2 2 10.9)E -1
(
1.2 2 10.9)E -1
( 0)
(
5.0 -
3.0)E O
(
-6.7 -
5.5)E 0
(
6.7 -
5.5)E O
(
0/ 12)*
(
0/ 12)*
(
0/ 12)*
CS-134 ( 24) 15.
(
4.7 t 2.7)E -1 11
(
-4.7 2 2.7)E -1
(
1.1 0.2)E O
( 0)
(
-2.1 -
1.1)E O
(
-2.1 -
1.1)E O
(
-2.0 -
0.1)E O
(
0/ 12)*
(
0/ 12)*
(
0/ 12)*
CS*137 ( 24) 18.
(
4.7 2.7)E -1 11
(
4.7 2 2.7)E -1
(
-5.0 2 258.6)E -3
( 0)
(
5.0 -
30.2)E -1
(
5.0 -
30.2)E 1
( - 1. 7 -
1.0)E O
(
0/ 12)*
(
0/ 12)*
(
0/ 12)*
BA-140 ( 24) 15.
(
5.7 2 7.6)E 1 11
(
5.7 7.6)E -1 t
-7.3 2 7.2)E -1
( 0)
(
2.5 -
5.3)E O
(
-2.5 -
5.3)E D
(
-4.5 -
4.3)E O
(
0/ 12)*
(
0/ 12)*
(
0/ 12)*
CE 141 ( 24)
(
6.1 2 4.6)E 1 21
(
1.2 2 49.0)E -2
(
1.2 *
/.?.0)E -2 I
( 0)
(
3.4 -
1.6)E D
(
2.3 -
2.9)E O
(
2.3 -
2.9)E O
(
0/ 12)*
(
C/ 12)*
(
0/ 12)*
i CE 144 ( 24)
(
7.9 2 14.2)E 1 21
(
1.2 2 1.4)E O
(
1.2 e 1.4)E O
, I
( 0)
(
9.4 -
5.6)E D
(
5.9 -
8.0)E O
(
-5.9 -
8.0)E O
(
0/ 12)*
(
0/ 12)*
(
0/ 12)*
I H3
( 8) 2000.
(
5.2 2 2.6)E 2 11
(
5.2 2 2.6)E 2
(
6.8 2 5.9)E 1
( 2)
(
6.8 - 103.0)E 1
(
6.8 - 103.0;E 1
(
1.7 -
24.1)E 1
(
2/ 4)*
(
2/ 4)*
(
0/ 4)*
I NON-ROUT]NE 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 YlELDING DETECTABLE MEASU%MENTS (1.E. >3 $10 DEVIATIONS) IS INDICATED WITH *(
)*. l t
i 3.9 Sediment l
.I Sediment cores were collected semiannually from two locations.
Each core was separated into three 5 cm segments, which were analyzed for gamma-emitting radionuclides. Cesium-137 was detected in most samples. The levels reeasured at the indicator j
I..
location were consistent with what has been measured in the previous several years (see Figure 3.5) and are ettributed to nuclear weapone testing fallout that has persisted in the environment.
I Other than naturally occurring K-40 and Th-232, no other gamma-emitting radionuclides were detected in 1988 sediment samples.
I I
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1t
ENt*!RONMENTAL RADIOLOGICAL PROGRAM
SUMMARY
YANKEE NUCLEAR POWER STATION, ROWE, MA J
(JANUARY DECEMBER 1988)
MEDIUM: SEDIMENT UNITS: PCl/KG DRY j
INDICATOR STATIONS STATION WITH HIGHEST MEAN CONTROL STATIONS 1
RADIONUCLIDES-MEAN MEAN MEAN
)
(NO. ANALYSES) REQUIRED RANGE STA.
RANGE RANGE (NON ROUTINE)*
LLD No. DETECTED **
NO.
NO. DETECTED **
NO. DETECTED **
BE-7
( 12)
(
3.2
3.4)E 1 21
(
7.4 2 5.5)E 1
(
7.4 t 5.5)E 1
( 0)
(
-4.5 -
15.5)E 1
(
-1.7 -
2.2)E 2
(
-1.7 -
2.2)E 2 I.
(
0/ 6)*
(
0/ 6)*
(
0/ 6)*
r-40
( 12)
(
?.0 1 0.1)E 4 21
(
1.2 2 0.0)E 4
(
1.22 0.0)E 4 I
( 0)
(
6.5 -
13.9)E 3
(
1.0 -
1.4)E 4
(
1.0 -
1.4)E 4
(
6/ 6)*
(
6/ 6)*
(
6/ 6)*
I MN-54 ( 12)
(
8.0 t 71.4)E 1 11
(
8.0 t 71.4)E -1
(
-9.7 1 9.6)E O
( 0)
(
-1.7 -
3.2)E 1
(
-1.7 -
3.2)E 1
(
-4.8 -
2.5)E 1
(
0/ 6)*
(
0/ 6)*
(
0/ 6)*
Co-58 ( 12)
(
1.2 0.6)E 1 21
(
-9.2 5.6)E O
(
-9.2 2 5.6)E O
( 0)
(
2.3 -
1.5)E 1
(
-2.6 -
0.7)E 1
(
-2.6 -
0.7)E 1
(
0/ 6)*
(
0/ 6)*
(
"' 6)*
FE-59 ( 12)
(
2.4 2 1.9)E 1 11
(
2.4 2 1.9)E 1
(
-4.5 2 15.3)E O
( 0)
(
-5.3 -
6.8)E i
(
5.3 -
6.8)E 1
(
4.1 -
4.6)E 1
(
0/ 6)*
(
0/ 6)*
(
0/ 6)*
I CO-60 ( 12)
(
4.2 2 4.2)F 0 21
(
2.6 2 4.2)E O
(
2.6 1 4.2)E O
( 0)
(
1.5 -
1.3)E 1
(
1.3 -
1.2)E 1
(
-1.3 -
1.2)E i
(
0/ 6)*
(
0/ 6)*
(
0/ 6)*
ZN 65 ( 12)
(
6.4 2 10.9)E O 21
(
1.1 t 1.0)E 1
(
1.1 1.0)E 1 (g
l
( 0)
(
3.9 -
2.6)E 1
(
1.9 -
4.0)E 1
(
-1.9 -
4.0)E 1 3
(
0/ 6)*
(
0/ 6)*
(
0/ 6)*
ZR 95 ( 12)
(
-3.7 2 13.0)E O 21
(
6.6 t 6.9)E O
(
6.6 t 6.9)E O lI
( 0)
(
-2.7 -
5.2)E 1
(
-1.9 -
3.0)E 1
(
-1.9 -
3.0)E 1
(
0/ 6)*
(
0/ 6)*
(
0/ 6)*
l AG 110M( 12)
(
1.5 2 3.1)E O 11
(
-1.5 2 3.1)E O
(
-4.5 1 4.7)E O E
( 0)
(
-8.6 -
8.0)E O
(
8.6 -
8.0)E O
(
-1.3 -
1.7)E 1
(
0/ 6)*
(
0/ 6)*
(
0/ 6)*
II
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.
THE FRACTION OF SAMPLE ANALYSES YlELDING DETECTABLE MEASUREMENTS l
(1.E. >3 STD DEVIATTONS) IS INDICATED WITH *(
)*. 1 i
L i
1
^
l I
i ENVIRONMENTAL RADIOLOGICAL PROGRAM
SUMMARY
~
YANKEE NUCLEAR POWER STATION, ROWE, MA (JANUARY - DECEMBER 1988)
NEDIUM: SEDIMENT UNITS: PCl/KG DRY INDICATOR STATIONS 3TATION WITH HIGHEST MEAN CONTROL STATIONS eeeeeeeeeeeeeeeeee seeeeeeeeeeeeee..........
ee......e***ee I
RADIONUCLIDES MEAN MEAN MEAN j
(No. ANALYSES) REQUIRED RANGE STA.
RANGE kANrE I
(NON ROUTINE)*
LLD NO. DETECTED **
NO.
NO. DETECTED **
No. DETECTED **
RU-103 ( 12)
(
6.8
7.2)E O l '.
(
6.P
7.2)E O
(
3.5 1 5.6)E O
( 0)
(
1.9 -
2.2)E 1
(
1.9 -
2.2)E 1
(
-2.6 -
1.3)E 1
(
0/ 6)*
(
0/ 6)*
(
0/ 6)*
RU-106 ( 12)
(
2.8 t 4.1)E 1 11
(
2.8 t 4,1)E 1
(
-3.7 e 18.7)E O
-l
( 0)
(
-1.2 -
1.5)E 2
(
1.2 -
1.5)E 2
(
4.7 -
6.5)E 1
-M
(
0/ 6)*
(
0/ 6)*
(
0/ 6)*
I l 131 ( 12)
(
-1.7 e 1.2)E 2 21
(
2.8
10.1)E 1
(
2.8 2 10.1)E 1 I
I
( 0)
(
-6.6 -
1.1)E 2
(
2.7 -
4.1)E 2
(
2.7 -
4.1)E 2
(
(
0/ 6)*
(
0/ 6)*
(
0/ 6P I
CS 134 ( 12) 150.
(
6.2 2 4.2)E O 11
(
6.2 2 4.2)E 0
(
2.6 2 3.5)E O
( 0)
(
-7.4 -
18.3)E O
(
-7.4 -
18.3)E O
(
-1.1 -
1.3)E 1
(
0/ 6)*
(
J/ 6)*
(
0/ 6)*
CS 137 ( 12) 180.
(
1.6 2 0.3)E 2 11
(
1.6 2 0.3)E 2
(
1.4 2 5.7)E D
( 6)
(
6.1 -
27.3)E i
(
6.1 -
27.3)E 1
(
-1.5 -
2.7)E 1
(
6/ 6)*
(
6/ 6)*
(
1/ 6)*
BA-140 ( 12)
(
-2.2 1.6)E 1 11
(
2.2 2 1.6)E i
(
4.8
2.2)E 1
( 0)
(
-6.1 -
4.3)E 1
(
6.1 -
4.3)E 1
(
1.2 -
0.0)E 2
(
0/ 6)*
(
0/ 6)*
(
0/ 6)*
CE 141 ( 12)
(
1. 6
2.0)E 1 11
(
1.6 1 2.0)E 1
(
1.5 2 0.5)E 1
( 0)
(
2.3 -
10.0)E 1
(
T. 3 -
10.0)E 1
(
5.7 - 292.0)E -1
(
0/ 6)*
(
0/ 4)*
(
0/ 6)*
CE-144 ( 12)
(
7.9
22.9)E O 11
(
7.9 2 22.9)E O
(
-7.9 t 22.8)E O I
( 0)
(
7.6 -
7.2)E 1
(
-7.6 -
7.2)E
(
5.2 -
9.9)E 1
(
0/ 6)*
(
0/ 6)*
(
0/ 6)*
I TH 232 ( 12)
(
6.2 2 0.8)E 2 11
(
6.2 2 0.8)E 2
(
3.9 2 0.2)E 2 I
( 0)
(
3.9 -
8.3)E 2
(
3.9 -
8.3)E 2
(
3.2 -
4.8)E 2
(
6/ 6)*
(
6/ 6)*
(
6/ 6)*
I NON ROUTINE REFERS TO THE NUMBER OF SEPARATE MEASUREMENTS WHICH WERE GREATER THAN TEN (10) TIMES THE AVERACE BACKGROUND FOR THE PERIOD OF THE REPORT.
I THE FRACTION OF SAMPLE ANALYSES YlELDING DETECTABLE MEASUREMENTS (1.E. >3 STD DEVIATIONS) IS INDICATED WITH *(
)*.
l
_44 l
I
I l
3.10 Einh Fish samples were collected semiannually from two locations.
Each was analy'
for gamma-emitting radionuclides.
Cesium-137 was detected in all control samples and one of the
~
indicators.
Over the past several years, the levels have been comparable between Station FH-11 and Station FH-21 fish, as can be seen in Figure 3.6.
These levels are consistent with well-documented environmental levels and are attributed to nuclear weapons testing fallout.
Other than Cs-137 and naturally occurring K-40, no gamma-emitting I'
radionuclides were detected in 1988 fish samples.
I I
I I
4 I
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. ml
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~
ENVIRONMENTAL RADIOLOGICAL PROGRAM SUMMAR7 YANKEE NUCLEAR POWER STATION, ROWE, MA (JANUARY - DECEMBER 1988)
MEDIUM: FISH UNITS: PCl/KG WET I
INDICATOR STATIONS STATION WITH HIGHEST MEAN CONTROL STATIONS eeeeeeee*****ee***
ee......e**ee...eeeee
e *ee....
RADIONUCLIDES MEAN MEAN MEAN (NO. ANALYSES) REQUIRED RANGE STA.
RANGE RANGE (NON ROUTINE)*
LLD NO. DETECTED **
N0.
NO.' DETECTED **
NO. DETECTED **
BE 7
( 4)
(
9.2 t 90.0)E 0 11
(
-9.2 2 90.0)E 0
(
4.8 2 0.7)E 1
( 0)
(
9.9 -
8.1)E 1
(
-9.9 -
8.1)E 1
(
-5.5 -
-4.1)E 1
. I
(
0/ 2)*
(
0/ 2)*
(
K 40 ; 4)
(
2.9 2 0.2)E 5 11
(
2.9 2 0.2)E 3
(
2.7 2 0.2)E 3 I
( 0)
(
2.6 -
3.1)E 3
(
2.6 -
3.1)E 3
(
2.5 -
3.0)E 3
(
2/ 2)*
(
2/ 2)*
(
2/
2)*
I.
MN 54 ( 4) 130.
(
6.1 i 3.5)E O 11- (
6.1 2 3.5)E O
(
8.5 2
'7.5)E 2
( 0)
(
2.7 -
9,6)C 0
(
2.7 -
9.6)E O
(
-6.7 -
6.9)E O
(
0/ 2)*
(
C/ 2)*
(
0/ 2)*
I CO 58 ( 4) 130.
(
3.5 2 1.2)E O 11
(
3.5 t 1.2)E D
(
8.2.t 104.8)E 1
( 0)
(
2.3 -
4.7)E O
(
2.3 -
4.7)E O
(
-9.6 -
11.3)E O r
'(
0/ 2)*
(
0/ 2)*
(
0/
2)*
FE 59 ( 4) 260.
(
-4.0 2 4.8)E O 11
(
4.0 t 4.8)E 0
(
2.1 2 3.8)E 1
( 0)
(
-8.9 -
0.8)E 0
(
8.9 -
0.8)E o
(
-5.9 -
1.7)E 1
(
0/ 2)*
(
0/ 2)*
(
0/ 2)*
I.
CO 60 ( 4) 130
(
1.6 1 0.2)E 1 21
(
-6.1 2 5.2)E O
(
6.1 2 5.2)E O
( 0)
(
-1.8 -
-1.5)E 1
(
1.1 -
0.1)E 1
(
-1,1 -
0.1)E 1
( '0/ 2)*
(
0/ 2)*
(
0/ 2)*
ZN 65 ( 4) 260.
(
2.1 s 1.3)E 1 11
(
-2.1 1 i 3)E 1
(
-3.3 2 3.5)E 1 I.
( 0)
(
3.4 -
-0.8)E 1
(
-3.4 -
0.8)E 1
(
-6.8 -
0.2)E 1
(
0/ 2)*
(
0/ 2)*
(
0/ 27*
2R 95 ( 4)
(
-1.2 2 0.3)E 1 21
(
-7.52 0.5)E O
(
7.5 2 0.5)E O I
( 0)
(
1.5 -
-0.9)E 1
(
-8.0 -
7.0)E O
(
8.0 -
- 7.0)E O
(
0/ 2)*
(
0/ 2)*
(
0/ ?)*
I AG 110MC 4)
(
2.7 t 11.3)E O 11
(
2.7 2 11.3)E O
(
6.5 2 13.6)E O
( 0)
(
-8.6 -
14.0)E 0
(
8.6 -
14.0)E D
(
-2.0 -
0.7)E 1
(
0/ 2)*
(
0/ 2)*
(
0/ 2)*
I
NON ROUTINE REFERS TO THE NUMBER OF SEPARATE MEASUREMENTS WH]CH WERE GREATER THAN TEN (10) TIMES THE AVERAGE BACKGROUND FOR THE PERIOD OF THE REPORT.
I
THE FRACTION OF SAMPLE ANALYSES Y!ELDING DETECTABLE MEASUREMENTS (1.E. >3 STD DEVIATIONS) IS INDICATED WITH *(
)*.
E
1 l'
ENVIRONMENTAL RADIOLOGICAL PROGRAM SUMMAR7 l
YANKEE NUCLEAR POWER STATION, ROWE, MA 1
(JANUAL' - DE.9 EMBER 1988)
MEDIUM: FISH UNITS: PCl/KG WET I
INDICATOR STATIONS STATION WITH HIGHEST MEAN CONTROL STATIONS q
...............ene
e****e................
e e****e**eeeee.
i I
RADIONUCLIDES MEAN MEAN MEAN j
(NC. ANALYSES) REQUIRED RANGE STA.
RANGE RANGE
.(NON ROUTINE)*
LLD No. DETECTED **
NO.
No. DCTECTED**
NO. DETECTED **
RU-103 ( 4)
(
8.2
35.3)E 1 11
(
8.2 e 35.3)E -1
(
-2.0 1 1.0)E 1
( 0)
(
-2.7 -
4.3)E 0
(
2.7 -
4.3)E O
(
-3.0 -
-1.0)E 1 4
(
0/ 2)*
(
0/ 2)*
(
0/ 2)*
RU 106 ( 4)
(
3.9 e 3.2)E 1 11
(
3.9 t 3.2)E 1
(
-4.5 2 1.1)E 1
- I
( 0)
(
7.4 -
70.8)E O
(
7.4 -
70.8)E 0
(
5.7 -
-3.4)E 1
(
0/ 2)*
(
0/ 2)*
(
0/ 2)*
l 131 ( 4)
(
3.4 2 6.4)E 1 11
(
3.4 2 6.4)E 1
(
-5.9 2 35.2)E O
. I-( 0)
(
2.9 -
9.8)E 1
(
2.9 -
9.8)E 1
(
-4.1 -
2.9)E 1
(
0/ 2)*
(
0/ 2)*
(
0/ 2)*
I CS 134 (. 4) 130.
(
1.5 t 20.2)E -1 11
(
-1.5
20.2)E -1
(
-7.6 2 2.3)E O
( 0)
(
2.2 -
1.9)E 0
(
2.2 -
1.9)E O
(
9.9 -
-5.4)E O
(
0/ 2)*
(
0/ 2)*
(
0/ 2)*
CS-137 ( 4) 150.
(
4.6 1.2)E 1 11
(
4.6 2 1.2)E 1
(
4.3 2 1.0)E 1
( 0)
(
3.3 -
5.8)E 1
(
3.3 -
5.8)E 1
(
3.3 -
5.3)E 1
(
1/ 2)*
(
1/ 2)*
(
2/ 2)*
I BA 140 ( 4)
(
6.9 2 50.3)E 0 21
(
9.8 2 1.8)E O
(
9.8
1.8)E O
( 0)
(
4.3 -
5.7)E 1
(
8.0 -
11.6)E O
(
8.0 -
11.6)E O
(
0/ 2)*
(
0/ 2)*
(
0/ 2)*
CE 141 ( 4)
(
1.1 2 1.6)E 1 11
(
1.1 2 1.6)E 1
(
6.8 2 6.0)E O
( 0)
(
-4.7 -
27.3)E O
(
-4.9 -
27.3)E O
(
8.0 - 129.0)E -1 I-
t 0/ 2)*
(
0/ 2)*
(
0/ 2)*
CE 144 ( 4)
(
-1.4 2 1.0)E 1 21
(
3.5 t 3.7)E 1
(
3.5 t 3.7)E 1 I
( 0)
(
2.3 -
-0.4)E 1
(
-2.0 -
71.9)E O
(
-2.0 -
71.9)E O
(
0/ 2)*
(
0/ 2)*
(
0/ 2)*
I TH 232 ( 4)
(
4.8 a 23.3)E O 21
(
1.1 e 1.2)E 1
(
1.1 2 1.2)E i
( 0)
(
-1.9 -
2.8)E 1
(
-5.5 - 226.0)E -1
(
-5.5 - 226.0)E -1
(
0/ 2)*
(
0/ 2)*
(
0/ 2)*
I NON-ROUTINE REFERS TO THE NUMBER OF SEFARATE MEA'sVREMENTS WHICH WERE GREATER THAN TEN (10) TIMES THE AVERAGE BACKCRCVND FOR THE PERIOD OF THE REPORT.
l THE FRACTION OF SAMPLE ANALYSES Y!ELDING DETECTABLE MEASUREMENTS I
5' (1 4. >3 STD DEVIATIONS) IS INDICATED WITH *(
)*. 1 i
l -
L
'3.11 Direct Radiation Direct gamma radiation exposure was determined from the use of thermoluminescent dosimeters (TLDs). Specifically,
)
Panasonic UD-801AS1 and UD-814AS1 calcium sulfate dosimeters were 1
used, with a total of five elements in place at each moni;oring I
location. 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 f rom the remaining sixteen in;ident response (outer ring) stations need only be de-dosed (annealed) quarterly, unless a gaseous release LC0 was exceeded during the period. During 1988, all TLDs were routinely readout on a quarterly schedule. Table 3.1 provides a summary of the results. Figures 3.7 to 3.12 show the TLD results graphically.
Distinct annual cycles can be seen in the TLD data from each category of monitoring station (see Figures 3.7 to 3.12).
The lowest point of the cycle occurs during the winter months. This is 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 I
at these sites tends to obscure seasonal fluctuations in the environment. The fenceline where TLDs are situated is located well within the site boundary.
The natural background radiation level at each site varies for many reasons. The one that best explains the consistent differences between sites is the radioactive composition of the underlying and nearby soil and rock. Conspicuous deviations from any of these trends would indicate some abnormal condition, I
possibly a power plant contribution to the radiation levels. No such abnormalities were detected off-site during 1988, as can be seen in Figures 3.7 to 3.12.
I 2918R I!
E\\
i As can be seen in Figure 3.11, elevated exposure rates were noted at several.on-site locations during the first quarter of 1981.
This was believed not to have been caused by plant activities,.
{
and was discussed in Reference 4.
i i
Missing TLDs: Approximately halfway through the second quarter, the TLD at Station GM-12 was discovered to be missing, apparently due to theft. The TLD was replaced shortly afterward. The l
measurement in Table 3.1 is based on the accumulated exposure at that station for the last half of the quarter.
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Environmental Radiological Program Summary Yankee Nuclear Power Station, Rowe, Massachusetts Januarv - December 1988 Medium: Direct Radiation Measurements (TLD)
Units: Micro-R per Hour Indicator Outer-Ring Restricted Control Stations _
Stations Area Fence Stations Mean Mean Mean Mean Range Range Range Range
-(No. Meas.)*
(No. Meas.)*
(No. Meas.)*
(No. Meas.)*
]
7.4 i 1.1 7.3 i 1.3 16.5 i 4.2 7.9 + 0.9 5.4 - 10.3 5.0 - 10.4 10.8 - 25.9 6.1 - 8.8 (52)
(64)
(36)
(8)
All measurements based on the mean of five readings per station (quarterly readout).
I I-I 2918R I
I.
I il Table 3.1 Summary of Direct Radiat_lon Measurements - 1988 Yankee Nucienr Power Station (Micro-R Per Hour)
First Second Third Fourth Yearly Station Distance (km) Direction Ouarter Ouarter Quarter Ouarter Mean GM-1 0.8 SW 7.2 7.3 8.6 7.4 7.6 GM-2 0.5 NW 6.4 6.4 7.8 7.0 6.9 GM-3 4.2 SE 5.4 5.4 7.3 6.0 6.0 1
GM-4 3.2 N
6.7 6.1 7.7 7.0 6.9 GM-5 1.1 SW 8.4 8.5 10.3 8.7 9.0 GM-6 1.3 N
6.7 7.1 8.9 7.7 7.6 GM-7 3.5 NE 6.4 6.0 8.0 6.5 6.7 GM-8 1.8 S
7.3 6.2 8.7 6.6 7.2 GM-9 3.2 SW 7.0 6.6 9.1 7.3 7.5
)
I GM-10 3.5 E
6.8 6.5 8.5 6.6 7.1 GM-11 2.1 WNW 7.7 7.4 9.6 8.0 8.2 GM-12 5.5 NNW 8.3 6.7 9.2 7.6 8.4
- I GM-13 0.08 WSW 16.8 17.3 20.5 16.1 17.7 GM-14 0.11 WNW 11.8 11.7 13.9 11.4 12.2 GM-15 0.08 NNW 11.8 11.0 13.9 10.8 11.9 GM-16 0.13 NNE 13.0 11.8 14.4 12.6 13.0
- I GM-17 0.14 ENE 14.4 13.9 16.1 16.6 15.3 GM-18 0.14 ESE 22.4 21.2 24.8 25.4 23.5 GM-19 0.16 SE 21.7 20.2 23.2 25.9 22.8 I
GM-20 0.16 SSE 15.3 16.4 17.5 17.4 16.7 GM-21 0.11 SSW 13.8 16.4 17.0 15.2 15.6 GM-22 12.6 NNW 6.1 7.2 8.4 7.6 7.3 GM-23 22.2 W
8.3 8.6 8.8 8.4 8.5 GM-24 7.3 N
7.1 8.7 8.9 8.5 8.3 GM-25 7.7 NNE 6.3 6.5 7.2 6.6 6.7 GM-26 7.6 NE 5.7 6.6 7.6 7.1 6.8 I
GM-27 7.6 ENE 5.6 6.2 6.9 6.7 6.4 GM-28 6.0 E
6.7 7.0 7.6 7.2 7.1 GM-29 8.2 ESE 5.2 5.0 5.8 5.4 5.4 I
GM-30 9.4 SE 5.6 6.0 6.3 6.3 6.1 GM-31 7.6 SSE 6.3 6.5 7.2 6.8 6.7 GM-32 7.9 S
6.6 6.2 7.2 6.5 6.6 GM-33 6.9 SSW 7.1 6.9 7.4 9.4 7.7 I
GM-34 6.4 SW 9.0 8.9 10.0 9.7 9.4 GM-35 8.6 WSW 6.3 7.4 8.2 7.9 7.5 GM-36 6.6 W
6.6 7.4 8.1 7.8 7.5 I
GM-37 6.7 WNW 5.7 7.9 C.1 8.2 7.7 GM-38 6.6 NW 6.8 8.4 10.2 10.4 8.9 GM-39 6.8 NNW 7.5 8.8 9.9 8.9 8.8 GM-40 0.5 W
6.0 6.9 8.4 7.2 7.1 2918R l
I 4.0 QUALITY ASSURANCE PROGRAM r
..I Three separate Quality Assurance programs were performed during 1988 to demonstrate the validity of laboratory analyses by the Yankee Atomic Environmental Laboratory (YAEL).
I 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 detertnine the cause of the problem, and corrective measures are taken, as appropriate.
I YAEL maintains an intralaboratory quality control program to assure the validity and reliability of the data. This program includes quality control g
5 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 ate taken whenever applicable.
I A blind duplicete program is maintained in which paired samples from five nuclear plants, including Yankee Atomic, 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.
I 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 1988 for intralaboratory analyses and EPA interlaboratory cross-check analyses.
For I
accuracy, 65.0 and 86.5 percent of the results were within 5 and 10 percent of
)
the known values, respectively, with 96.6 percent of all results falling within I
the laboratory criteria of 15 percent. For precision, 84.7 and 96.7 percent of the results were within 5 and 10 percent of the mean, respectively, with 99.8 percent of all results meeting the laboratory criteria of 15 percent.
I
! 2918R I
4 7able 4.1 Intralaboratory and EPA Interlaboratory Results - 1983 t
t Accuracy Total Number 0 to 5%
0 to 10%
0 to 15%*
pf_ Measurements 654 425 566 632 (65.0%)
(86.5%)
(96.6%)
frecision Total Number 0 to 5%
0 to 10%
a to 15%*
of Measurement 633 536 612 632 (84.7%)
(96.7%)
(99.8%)
' I I
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This category also contains those samples having a verified zero concentration which were analyzed and found not to contain the i
.e of
{
interest.
)
. 1 2918R lI 1
lI The results of the EPA Interlaboratory Co:nparison Program, when considered apart from the remainder of'the Quality Assurance program, were satisfactory with respect to accuracy and precision in 1988. Two hundred and nineteen analyses were puformed on air particulate filters, milk, food, urine, and water.
Based upon this sample analysis total, 217 analyses (i.e., 99.1 percent) met the EPA's definition of mean value criteria.
The j
sample analyses that did not meet the criteria were a Sr-90 analysis on a milk sample and a Ra-226 analysis on a water sample. Two of the three milk samples I'
were remilked and analyzed for Sr-90 before the EPA results had been received. The new Sr-90 mean value, using the above results, fell within the EPA control limits. With respect to the Ra-226 results, no new radium analyses have been performed since the receipt of thece results, and the Beta-Gamma Coincidence System for Ra-226/Ra-228 is scheduled for recalibration.
(Details of this may be found in References 2 and 3.)
I The above EPA Interlaboratory Comparison Program results are provided in compliance with Technical Specification 4.12.3.
Blind Luplicate Progrmn A total of 51 paired samples were submitted by the five participating plants for analysis during 1988. 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, gross beta, Ra-226, and Ra-228.
A dual level I
criteria for 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 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.
I One thousand three hundred and seventeen paired duplicate measurements were analyzed for 1988. A total of 99.5 percent of all measurements fell I
within the established criteria discussed above.
The six measurements that did not meet the criteria were measurements of Zn-65 in groundwater, Mo-99 in 2918R f
I m._____________
n milk, TeI-132 in groundwater, Zr-95 in cranberries, Ba-140 in milk, and Sb-124 in milk.
In all of the above cases, the radionuclid.' in question was not detected in the sample and a three standard deviation acceptance criteria was met.
The six dupli.cate measurements represent 0.5 percent of all the blind duplicate paired measurements made during 1988. No trend was evident with respect to repeated failings of measurements for the above radionuclides.
- I I
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I 2918R I
I
q 5.0 LAND USE CMMS I
Specification 3/4.12.2 of the Radiological Effluent Technical specifications requires that a land use census be conducted af ter June 1 and before October 1 of each year. The census is used to identify the location of the nearest slik animal, the nearest residence, and the nearest garden of I
greater than 500 square feet producing fresh leafy vegetables in each of the sixteen meteorological sectors within a distance of five miles. The 1988 census was completed within the above dates. The distance and direction from the plant for each of the above locations are shown in Table 5.1.
The land use census for this reporting period identified two milk animal locations which yielded a calculated dose commitment (via the same exposure pathway) at least 20 percent greater than at a location from which 9
samples are currently being obtained in accordance with Technical I
Specification 3.12.1.
Specifically, these milk animal locations were found at
'WNW, 1.9 km and NE, 3.7 km.
Neither location, however, would be able to provide samp.es of sufficient size over an extended period due to the small number of milking cows owned. Consequently, the two existing locaticns, TM-12 and TM-13, were kept as official sampling locations in compliance with Technical Specification 3.12.2.b.
I No garden locations were identified that yielded a calculated dose or dose commitment at least 20 percent greater than that at the existing food I
crop sampling locations. Consequently, the food crop sampling locations were not changed in 1988 as a result of the Land Use Census.
Following the census, Technical Specification 3.12.2.a requires the identification in the Semi-Annual Effluent Release Report of any location (s) identified in the census which yields at least a 20 percent greater dose or dose commitment than the values currently being calculated in Technical Specification 4.11.2.3.
No such locations were identified. 2918R f
I i
1
Table 5.1 1988 Land _Usm_ Census _.Results Yankee Nuc.lgar Power Stalinn Nearest Nearest Nearest Residence Milk Animal Garden Sector (km)
(km)
(km)
N 2.4 6.1 3.5 l
NNE 4.7 4.7 NE 3.7 3.7 3.7 ENE 3.1 8.4 7.4 E
3.1 3.1 I
ESE 3.4 3.4 SE 2.3 2.3 SSE 2.1 2.9 S
2.3 2.3 SSW SW 1.3 1.3 WSW 1.3 1.3 W
t.9 2.7 WNW 1.9 1.9 1.9 I.
4.6 NW 0.45 NNW 2.9 3.9 I
4 1
I I 2918R I
1 4
6.0-
SUMMARY
During 1988, samples collected as part of the radiological environmental monitoring program at Yankee Atomic showed detectable levels of man-made radionuclides in cow milk, groundwater, river woter, sediment, finfish, and maple syrup. The H-3 detected in groundwater (Station WG-12, Sherman Spring) and river water (Station WR-11, Bear Swamp Lower Reservoir) was the only radionuclides possibly related to plant operations.
Since water f
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 child who consumed large quantities of the above water was calculated, however, to set an upper bound to the possible consequences of the measured environmental levels of 11-3.
In both cases (river and groundwater), the dose was negligible when compared to natural background radiation and its yearly fluctuations.
The other man-made radionuclides were due either to residual fallout 1
from nuclear weapons tests conducted in the 1970s and 1980, or fallout from the Chernobyl nuclear plant accident in April and May of 1986.
In summary, there was no observable radiological impact on the environment from plant operations.
I I
4 I
)
, 2918R I
i 7.0 B2ECEEES f
1.
USNRC Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix 1," 1977.
I 2.
Yankee Environmental Radiation Measurement Laboratory Semiannua) Quality Assurance Status Report, January-June 1988, Yankee Atomic Electric Company.
3.
Yankee Atomic Environmental Laboratory Semiannual Quality Assurance Status Report, July-December 1988, Yankee Atomic Electric Company.
I 4.
Yankee Atomic Electric Company, Annual Radiological Environmental Operating Report, January-December 1986.
I I
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I 2918R 1
.___ _.______________________ _ _ _ j
l '*
IYANKEEATOMICELECTRIC COMPANY
"'l$"l1%.s*go'7g;l"
'u ?V',.
580 Main Street, Bolton, Massachusetts 01740-1398 l
YAN KEE I
April 28, 1989 BYR 89-79 a
l l
l i
United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Reference:
(a) License No. DPR-3 (Docket No. 50-29)
Subj ect:
Annual Radiological Environmental Operating Report
Dear Sir:
Enclosed herewith please find 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 1988 and is submitted as required by Technical Specification 6.9.5(a).
l We trust.that you will find this submittal satisfactory; however, if you H
c..
have any questions, please contact us.
Very truly yours, YANKEE ATOMIC ELE G IC COMPANY a
e s
George apanic, Jr.
Senior Project Engineer - Licensing GP/gbc Enclosure cc:
USNRC Region I USNRC Resident Inspector, YNPS l
'p l

ML20245F218

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7.0 REFERENCES

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