ML20209H829

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Annual Radiological Environ Operating Rept,1986
ML20209H829
Person / Time
Site: Yankee Rowe
Issue date: 12/31/1986
From: Papanic G
YANKEE ATOMIC ELECTRIC CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
2918R, FYR-87-46, NUDOCS 8705040130
Download: ML20209H829 (84)
v • d • e


Text

, _ _

YANKEE ATOMIC ELECTRIC COMPANY MTAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT January - December 1986 April 1987 l'

i Prepared By:

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

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2918R fh h

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l TABLE OF CONTENTS Page LIST OF TABLES....................................................

iii LIST OF FIGURES...................................................

iv

1.0 INTRODUCTION

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

2 3.0 SUte!ARY OF 1986 ENVIRONMENTAL DATA................................

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

15 3.2 Charcoal Filter.............................................

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

22 3.4 Food Crop...................................................

29 3.5 Broad Leaf Vegetation.......................................

32 3.6 Mkple Syrup.................................................

34

'2 '

v 3.7 Groundwater.................................................

37 3.8 River Water.................................................

40 3.9 Sediment....................................................

43 3.10 F1nfish.....................................................

46 s

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

49 4.0 ENVIRONMENTAL RADIOACTIVITY FROM THE CHERNOBYL ACCIDENT...........

59 5.0 QUALITY ASSURANCE PR0 GRAM.........................................

71 c <

6.0 LAND US E C ENS U S...................................................

75

(

7.0

SUMMARY

77 t

8.0 REFERENCES

78

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LIST OF TABLES Number Title Pm 2.1 Yankee Atomic Radiological Environmental Monitoring Program 3

2.2 Yankee Atomic Radiological Environmental Monitoring Locations 4

3.1 Summary of Direct Radiation Measurements - 1986 58 4.1 Chernobyl-Related Radioactivity in Precipitation 61 4.2 Iodine-131 In Precipitation EPA ERAMS Network 62 5.1 Intralaboratory and EPA Interlaboratory Results - 1986 72 6.1 1986 Land Use Census Results 76 t

r 4

5

-111-2918R

1 LIST OF FIGURES Number Title Past 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 4,

Ingestion Pathways) 7 2.3 YankeehlantRadio1'ogicalEnvironmentalMonitoring Locatfoss Outside 12 Miles (Airborne, Waterborne, and Ingestien Patt says) 8 2.4 Yankee Plant Radiological Environmental Monitoring Locations at the Restricted Area' Fence (Direct Radiation Pathway) 9 L

2.5 Yankee Plant Radiological Envigonmental Monitoring Locations Within 1 Mile (rfrect-Radiation Pathwny) 10 4

2.6 Yankee Plant Radiological Environmental Monitoring A

Locations Within 12 Miles (Direct Radiation Pathway) 11 2.7 Yankee Pladt Radtolohical Environmental Monitoring Locations Outside '12 Miles (Direct Radiation Pathway) 12 I

3.1 Gross-Beta Measurements of Air Particulate Filters 16 3.2 Iodine-131 on Charecal Filters 20 3

3.3 Cesium-137 in Mill!- Yankee Atomic 23

)

3,4 Cesium-134 in Milk - Yankee Atomic 24 3.5 Strontium-90 in Milk - Yankee Atomic 25 3.6 Iodine-131 in Milk - Yankee Atoairi-26

/

3.7 Exposure Rate at Indicator TLDsi;GM 01-07 51 3.8 Exposure Rate at Indicator TLDs, GM 08-12, 40 52 3.9 Exposure Rate at Guter Ring TLDs, GM 24-31 53 3.10 Exposure Rate at Outer Ring TLDs, GM 32-39 54 3.11 Exposure Rate at Fenceline TLDs, GM 13-21 55

-iv-

' 2918R

LIST OF FIGURES (Continued)

Number Title Page 3.12 Exposure Rate at Control TLDs, GM 22-23 56 4.1 Gross-Beta Measurements of Air Particulate Filters -

Mean of All Stations 63 4.2 Cesium-134 on Air Particulate Filters - New England Controls 64 4.3 Cesium-137 on Air Particulate Filters - New England Controls 65 4.4 Ruthenium-103 on Air Particulate Filters - New 66 England Controls 4.5 Iodine-131 on Charcoal Filters - Mean of All Stations 67 4.6 Cesium-134 in Milk - New England Controls 68 4.7 Cesium-137 in Milk - New England Controls

~

69 4.8 Iodine-131 in Milk - New England Controls 70 1

-v-2918R w..

1.0 INTRODUCTION

The radiological environmental surveillance program at Yankee Atomic has been designed and carried out with specific objectives in mind. They are cs follows:

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.

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 1986, as in the past, the plant staff collected the bulk of the snvironmental samples and processed all environmental thermoluminescent dosimeters (TLDs) fer direct radiation measurements. After the initial processing, all non.;D samples were sent to the Yankee Atomic Environmental l

l Laboratory in Westborough, Massachusetts for further processing and rcdionuclide analysis.

l This report is a summary of the findings of the Radiological Environmental Surveillance Program for 1986.

It is being provided in compliance with plant Technical Specification 6.9.5.a. 2918R l

2.0 ENVIRONMENTAL MONITORING PROGRAM In this section, Table 2.1 outlines the monitoring program as required by the plant Technical Specifications. Table 2.2 lists the sampling stations cnd 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.

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

AP Air Particulate CF Charcoal Filter TM Milk WG Groundwater WR River Water TF Food Crop TV Broad Leaf Vegetation MS Maple Syrup SE Sediment FH Finfish GM Direct Radiation (TLD) l l

1 2918R i

~

  • L

Table 2.1 Yankee Atomic Radiological Environmental Monitoring Program Media Sampling Frequency Required Analyses Air Particulate (AP)

- Weekly Gross beta

- Quarterly Composite Gamma spectroscopy Charcoal Filter (CF)

- Weekly 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)

I-131 Groundwater (WG)

- Quarterly Gamma spectroscopy, H-3 Monthly (Composite)

Gross beta, River Water (WR)

Gamma spectroscopy.

I-131*

- Quarterly Composite H-3 Sediment (SE)

- Semiannually Gamma spectroscopy Finfish (FH)

- Seasonal or Gamma spectroscopy Semiannually Direct Radiation (GM)

- Quarterly De-dose only (Outer ring TLDs)

- Quarterly Integrated gamma (All other TLDs) dose i

o I-131 analysis requirement was removed from Radiological Effluent Technical Specifications with Amendment 99 on September 23, 1986. 2918R

(

Table 2.2 Yankee Atomic Radiological Environmental Monitoring Locations Distance Station Code From Plant Direction (Media - Sta. No.)

Station Description Zone *

(km)

From Plant AP/CF-11 Observation Stand 1

0.5 NW AP/CF-12 Monroe Bridge 1

1.1 SW 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**

Furlon House 1

0.8 SW AP/CF-32**

Heartwellville, VT 2

12.6 NNW TM-11 Heath, MA 1

5.8 E

TM-12 Readsboro, VT 1

6.1 N

TM-13 Whitingham, VT 1

8.4 ENE TM-21 Williamstown, MA 2

21.0 WSW TF-11 Monroe Bridge 1

1.3 SW TF-12 Ford Hill Road 1

2.3 S

TF-13 Monroe, MA 1

1.9 WNW TF-21 Williamstown, MA 2

21.0 WSW TF-43**

Harriman Station 1

3.2 N

TF-45**

Hazelton Road 1

3.9 S

TV-11 Monroe Bridge 1

1.3 SW MS-31**

Readsboro, VT 1

6.1 N

MS-41**

Heath, MA 1

5.3 E

MS-42**

Williamstown, MA 2

28.3 WSW WG-11 Plant Potable 1

On-Site 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 GM-3 Rowe School 1

4.2 SE GM-4 Harriman Station 1

3.2 N

GM-5 Monroe Bridge 1

1.1 SW 2918R W~~

Table 2.2 (Continued)

Yankee Atomic Radiological Environmental Monitoring Locations Distance Station Code From Plant Direction (Media - Sta. No.)

Station Description Zone *

(km)

From Plant 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

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

0.08 WSW GM-14 Restricted Area Fence F

0.11 WNW 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 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 Heartwellville, VT 2

12.6 NNW GM-23 Williamstown Substation 2

22.2 W

GM-24 Harriman Dam 0

7.3 N

GM-25 Whitingham, VT 0

7.7 NNE GM-26 Sadoga Road 0

7.6 NE GM-27 Number 9 Road O

7.6 ENE GM-28 Number 9 Road 0

6.0 E

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 GM-32 Rowe Road O

7.9 S

GM-33 Zoar Road O

6.9 SSW GM-34 Fife Brook Road 0

6.4 SW GM-35 Whitcomb Summit 0

8.6 WSW 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 GM-39 Route 100 0

6.8 NNW GM-40 Readsboro Road 1

0.5 W

1 = Indicator Stations; 2 = Control Stations; O = Outer Ring Incident D

Response TLD; F = Fenceline.

co Not required by Radiological Effluent Technical Specifications. 2918R

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%s, Roa4 ksy Figure 2.1 Yankee Plant Radiological Environmental Monitoring Locations l

Within 1 Mile (Airborne, Waterborne and Ingestion Pathways) 1 l

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HEARTWELLVILLE AP/CF.32

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SE-21 FH-21.

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Figure 2.2 Yankee Plant Radiological Environmental Monitoring Locations Within 12 Miles (Airborne, Waterborne and Ingestion Pathways) t

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Figure 2.3 Yankee Plant Radiological Environmental Monitoring Locations Outside 12 Miles (Airborne, Waterborne and Ingestion Pathways) 1 __.

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

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

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@ GM-28 L-___i N

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Figure 2.6 Yankee Plant Radiological Environmental Monitoring Locations l

Within 12 Miles (Direct Radiation Pathway) t 1N 4.h 4

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I am!NGTON 10 Miles

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

3.0 SUMARY OF 1986 ENVIRONMENTAL DATA The following pages summarize the analytical results of all the cnvironmental samples which were collected during 1986. Each environmental media category is presented as a separate subsection. A discussion of the sampling program and results is followed by a table which summarizes the yIar'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 centrol station (s). The latter are classified as "non-routine" measurements.

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

(Requirements are not given for many of the radionuclides for which analyses are routined ccnducted.)

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 monitoring stations are broken down into two additional categories to aid in data analysis. These are fenceline stations and outer ring (emergency risponse) stations.

ERMAP calculates a set of statistical parameters for each rcdionuclide. This set of statistical parameters includes separate analyses l

fer (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:

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

o The standard error of the mean.

l 2918R

o The lowest and highest concentration.

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

greater than the standard deviation) divided by the total number of measurements.

Each single radioactivity measurement datum in this report is based on e single measurement and is reported as a concentration plus or minus a one stcndard deviation uncertainty. The quoted uncertainty term represents only tha random uncertainty associated with the radioactive decay process (counting statistics), and not the propagation of all possible uncertainties in the cnalytical procedure. Radioactivity is considered to be present in a sample wh;n the concentration exceeds three times its associated standard deviation. 2918R

3.1 Air

  • articulate 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 per minute. Airborne particulates are collected 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 and thoron daughter products.

Weekly composite air filters from each location are analyzed quarterly for gamma-emitting radionuclides.

Cross-beta analyses (Figure 3.1) show random fluctuations through much of the year at all sampling locations including controls, thereby indicating that any plant contribution is negligible.

The increase in gross-beta measurements, as well as the measurements of Cs-134, Cs-137, Ru-103, and Ru-106, during May and June of 1986 can be attributed to fallout from the Chernobyl accider.t and is discussed in Section 4.

Naturally occurring K-40 and Be-7 were also detected in many samples. 2918R

FIGURE 3.1 GROSS BETR MERSUREMENTS OF RIR PRRTICULRTE FILTERS YRNKEE RTOMIC ELECTRIC COMPANY, ROWE, MA 0.8 O - flP-11 OBSERVRTION STfND 0.7 -

o - fiP-12 NONROE BRIDGE a - f1P-13 R0WE SCHOOL

+ - flP-14 NfiRRINftN STRTION X - RP-21 WILLIfiMSTOWN CONTROL 0.s -

o - f1P-31 FURLON HOUSE g

v - AP-32 HERRTHELLVILLE CONTROL 6

h 0.5 -

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0.3 -

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0.2 -

0.1 -

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JRN FEB M:Vt ffR MflY JUN JUL fRJG SEP OCT NOV DEC 1986

i ENWRONMENTAL RADIOLCCICAL PROCW SttT%RY YANKEE N'ILEAR KNEP STATICN. R0WE. MA JANUARY - DECEf'BER 1986 EDF.M: AIF DMilCtLATE LMITS: PCI/CU M INDICATOR STATIONS STATION WITH HIGEST EAN CONTROL STATICNS nunneenenen nonenennuenennu neeneeenneet RADI(N R ICCS EAN KAN EAN (NO. ANALYSES) REQUIRED RANGE STA.

RANGE RANGE (NON-R0lrTINE)'

LLD NO. DETECTED *e NO.

NO. DETECTEDn NO. DETECTED **

05-9 (364)

.01

(

4.3

.5)E -2 13 ( 4.4 i 1.2)E -2

( 4.2 i

.8)E -2

( 4)

( 7.7 - 573.0)E -3

( 8.6 - 573.0)E -3

( 7.0 - 516.0)E -3

  • (260/260)*
  • ( 52/ 52)*

e(104/104)*

BE-7

( 28)

(

5.4f

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( 5.7 t

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( 5.1 t

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( 0)

( 3.8 -

7.4)E -2

( 4.5 -

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( 3.9 -

6.3)E -2

  • ( 20/ 20)e et 4/ 4)e
  • (

8/ 8)e K-40 ( 28)

(

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  • (

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  • (

0/ 8)*

i e NON-ROUTIE REFERS TO TE N.MBER OF SEPARATE EASLREENTS WHICH WERE GREATER l

THAN TEN (10) TIMES TE AVERACE BACXOROLND FCR TE PERIOD OF TT REPORT.

te TE FRACTION CF SAMPLE ANALYSES YIELDING DETECTABLE EARREENTS

(!.E. >3 STD DEVIAi!0NS) IS INDICATED WITH *(

le.

l EWIRONMEN74. R@lf100!CM. PROGRAM SUPf%RY V4*EE NUCLEAR P0WER STATION. R0WE. MA J W.lARY - DE IMBER 1986 EDRP': AIR PARTICtLATE UNITS: PCI/CU. M INDICATOR STATICNS STATION WITH HIGEST EAN CONTRCL STATIONC.

n**n**ne ue n n non mn***nen*++*u e

        • n** m u n RADIONUCLIDES TAN EAN EAN (NO. (AALYSESn RE0V! RED RANGE STA.

RANGE RANGE (NON-RCUTINEl' LLD NO DETECTED **

NO.

NO. DETECTED **

NO. DETECTED **

RV-103 ( 28)

(

2.1t

.8)E -3 31

( 2.2 1 2.2)E -3

( 1.9 t 1.2)E -3

( 0)

(-1.7 - 88.4)E -4

(-5.1 - 873.0)E -5

(-2.7 - 80.6)E -4

  • (

5/ 20),

  • (

1/ 4)*

( 2/ 8)*

RU-106 ( 28)

(

9.2t 4.81E -4 13 ( 1.9 1 1.3)E -3

( 4.4 t 2.7)E -4

( 0)

(-1.9 -

5.9)E -3

( 2.5 - 59.4)E -4

(-7.0 - 14.8)E -4

  • (

3/ 20)*

  • (

1/ 4)*

  • ( 0/ 8)*

CS-134 ( 28)

.05

(

2.4t 1.0)E -3 31

( 2.8 t 2.9)E -3

( 2.0 t 1.4)E -3

( 0)

(-2.1 - 115.01E -4

(-1.6 - 115.0)E -4

(-3.0 - 86.0)E -4

  • (

5/ 20)*

  • (

1/ 4)*

  • (

2/ 8)*

CS-137 ( 28)

.06

(

4.5t 1.8)E -3 31

( 5.1 t 5.2)E-3

( 4.0 t 2.6)E -3

( 0)

(-1.2 - 206.0)E -4

(-5.6 - 2060.0)E -5

(-3.3 - 1660.0)E -5

  • (

5/ 20)*

  • (

1/ 4)*

  • (

2/ 8)*

BA-140 ( 28)

(

6.6t 19.6)E-5 31

( 3.8 t 7.6)E -4

(-4.2 i 1.6)E -4

( 0)

(-1.1 -

2.2)E -3

(-1.1 -

2.2)E -3

(-9.0 -

1.5)E -4

  • (

O' 20)*

  • (

0/ 4)*

  • (

0/ 8)*

CE-141 ' 28)

(

l.11 7)E -4 21

( 3.0 t 1.9)E -4

( 1.6 1.1)E ~4

( 0)

(-3.0 -

8.1)E -4

(-1.5 -

6.5)E -4

(-2.6 -

6.5)E -4

  • (

0/ 20)*

  • (

0/ 4)*

  • (

0/ 8)*

E-144 ( 28)

( -1.2t 1.4)E -4 21

( 3.1 1 2.6)E -4

(-8.6 t 28.1)E -5

( 0)

(-9.5 - 10.4)E -4

(-4.0 -

7.6)E -4

(-1.2 -

.8)E -5

  • (

0/ 20)*

  • (

0/ 4)*

  • (

0/ 8)*

TH-232 ( 28)

( 8.3t 9.4)E -5 13 ( 3.1 i 1.6)E -4

(-1.1 i 1.7)E -4

( 0)

(-6.4 -

9.2)E -4

( 2.1 - 624.0)E -6

(-10. -

4.2)E -4

  • (

0/ 20)*

  • ( 0/ 4)*
  • ( 0/ 8)*

l

  • NON-ROUTIE RFFERS TO TE NUMBER OF SEPARATE EASLREENTS WHICH ERE GREATER TH#l TEN (10) TIES TE AVERACE BACK0ROLN) FOR TE PERIOD OF TE REPORT.
    • TE FRACTION OF SAffLE ANALYSES YIELDING DETECTABLE EASUREENTS (I.E. >3 STD DEVIATIONS) IS INDICATED WITH *(

)*. _ __

3.2 Charcoal Filters 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 approximately one cubic foot per minute.

Charcoal filters were collected and analyzed weekly for I-131 activity. During much of May and June of 1986, I-131 was detected in charcoal filter samples from all locations including controls, as can be seen in Figure 3.2.

This radioactivity originated from the Chernobyl accident and is discussed in Section 4.

l 2918R l

FIGURE 3.2 10 DINE-131 ON CHRRCORL FILTERS YRNKEE RTOMIC ELECTRIC COMPRNY, R0WE, MR j

0.s i

0 - T -11 OBSERVATION STfWD 0.7 -

o - AP-12 NONROE BRIDGE la - AP-13 R0WE SCHOOL h

+ - fiP-14 HRRRIMRN STATION X - RP-21 WILLIRMSTOWN CONTROL 0.s -

II o - RP-31 FURLON HOUSE V - RP-32 HERRTWELLVILLE CONTROL 6

-p c.s -

i

')

d O'

N 0.1 -

i taJ E

B o

0.3 -

2 l

i n.

i 0.2 -

i l

0.1 -

""=-- --

- - * -n

^-^ "

OCT 0.0. _ - - _ _ _ _- - - - - - - - -..

JUN JUL fluc:

SEP NOV DEC JfN FIB tifR fFR f1AY 1986 2

i

EWIRONTNTAL RADIOLOGICAL PROGRAM StrMARY YAWEE M.Q. EAR PCER STATION. R0WE, MA JANUARY - DECEMBER 1986 EDIUM: CW.RCtti r!LTER LMITS: PCI/CU. M INDICATOR STATIONS STATION WITH HIGEST EAN CONTROL STATION 3

      • eneenmeme enemenumne**enn uenue***mn RADIONUCLIDES EAN EAN EAN
00. ANALYSES) REQUIRED RANGE STA.

RAKE RANGE (NON-ROUTIE)'

LLD NO. DETECTEDn NO.

NO. DETECTED **

NO. DETECTEDee I-131 (364)

.07

(

!.81

.5)E -2 13 ( 2.0 t 1.3)E-2

( 1.7 i

.8)E -2

( 10)

(-1.6 - 63.6)E -2

(-1.1 - 63.6)E-2

(-1.4 - 55.2)E -2

  • ( 25/260)*
  • (

5/ 52)e

  • ( 10/104),

NON-ROUTIE REFERS TO TE N.9%ER CF SEPARATE EA9.REMENTS WHICH ERE GREATER THAN TEN (10) TIMES THE AVERAGE BACKGROLND FOR TE PERIOD OF TE REPORT.

THE FRACTION Or MMPLE ANALYSES YIELDIE [ETECTABLE MEASLREENTS (1.E. >3 STD DEVIATIONS) IS IND:CATED W:TH ef

)*,

' I i

1 i

3.3 Milk Milk samples were collected and analyzed by the schedule shown in Table 2.1.

Strontium 89 and Sr-90 analyses were performed on milk samples even though not required by Technical Specifications.

Detectable concentrations of Cs-137 and Sr-90 were measured in milk samples submitted from the indicator and control locations.

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 of vegetation that the cows are allowed to feed on) can cause large variations of Cs-137 and Sr-90 concentrations in milk. The mean Cs-137 and Sr-90 concentrations for indicator stations were lower in 1986 than they were in 1985. For control stations, the means were slightly higher in 1986 than in 1985.

/

Increases in Cs-137 concentrations during the pasture season were more accentuated than normal due to fallout from the Chernobyl accident. Other Chernobyl related radionuclides detected in milk were I-131 and Cs-134.

The impact of the Chernobyl accident on concentrations of radioactivity in milk is discussed in Section 4.

Plots for the concentrations of the above radionuclides can be found in Figures 3.3 to 3.6.

Unavailable Sample: A milk sample was not available for collection in May 1986 at Station TM-11 due to the dairy herd being sold. This location was replaced with Station TM-13, l

pursuant to Technical Specification 3.12.1.c.

Sampling began there in May 1986. 2918R

I lII l

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. S OR

+

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3. N C LUJ 3I 6

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+

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)

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1 004+

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g g

g g

gE E

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WES0l!M / S3!8n000!d b

4 FIGURE 3.5 STRONTIUM-90 IN MILK YANKEE RTOMIC ELECTRIC COMPANY, ROWE, MR 1s 1

1s-O - TM-11 tEf1TH tifi o - TM-12 REfiDS$0RO,VT l

23 o - TM-13 WHITINGtWiM VT

+ - TM-21 WILLIfittSTOON,Mfi 3, _

11 -

@ 10-a n

T S

8-l E

  • ~

s D

0 7-E 8

s-82 5-4-

3-2-

A A'

1-0 JfW FES

  1. 1Nt

&R tift!

JUN J0t.

fiUG SO' OCT NOV (EC 1986 1

/

F s

E WIi E

Ih o'

)la ae o

1 xz i

J CC M Q g

EE LO O

  • ZO MM O

I wM M i

M n 01 n

b g

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+

QOO M

E E

- M f

y5 '

m'.

,4 E l

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=uan u

kkbb o

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6 6

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a A

4 a

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W8S01DI / S318fTJ00!J.

6

ENVIR0 MENTAL RADIOLOGTCAL PRC6 RAM SUPf%RY YA W EE M R EAR POWER STATION, R0WE. MA JAMJARY - DECEMBEP 1986 EDIUM: MILK LNITS: P'!/r:.

INDICATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONS ne nu++++n* ***

n u e+++*e ne n++++++n n net wee n * *** *

  • RADICNRIES EAN MEAN EAN (NO. ANALvTS) RE@JIRED RANGE STA.

RANGE RANGE (NON-ROUTIEl' LLD NO. DETECTEDu NO.

NO. DETECTED **

NO. DETECTED **

SR-89 ( 15)

( 7.0t 14.9)E -2 12 ( 2.2 t 2.0)E -1

(-1.1 i 1.1)E 0

( 0)

(-6.9 -

7.1)E -1

(-3.4 -

7.1)E -1

(-5.3 -

.3)E O

  • (

0/ 10)*

et 0/ 5)*

  • ( 0/ 5)*

SR-90 ( 15)

(

3.41

.6)E O 11

( 7.8 i

.4)E 0

( 2.2 t

.2)E O

( 0)

( 2.0 -

7.8)E O

( 1.9 -

2.8)E O

  • ( 10/ 10)*
  • (

1/ 11e

  • ( 5/ 5)*

V-40 ( 60)

(

1.3t

.0)E 3 21

( 1.4

.0)E 3

( 1.4 t

.0)E 3

( 0)

( 1.2 -

1.5)E 3

( 1.3 -

1.5)E 3

( 1.3 -

1.5)E 3

  • ( 40/ 40)*
  • ( 20/ 20)*
  • ( 20/ 20)*

9 '4

( 60)

( -1.0t 1.6 E -1 12 ( 1.8

  • 20.0)E -2

(-2.4 2.4)E -1

( 0)

(-2.3 -

2.2)E O

(-2.0 -

2.0)E O

(-1.8 -

3.1)E O

  • (

0/ 40)*

  • (

0/ 20)*

  • i O/ 20)*

CO-58 ( 60)

( -3.4t 1.6)E -1 2)

( 9.1 t 18.4)E -2

( 9.1 i 10.4)E -2

( 0)

(-2.4 -

1.6)E O

(-1.6 -

1.7)E O

(-1.6 -

1.71E o

  • (

0/ 40)*

  • (

0/ 20)*

  • (

0/ 20)*

FE-59 ( 60)

( -3.6t 48.2)E -2 21

( 7.9 t 5.8)E -1

( 7.9 i 5.8)E -1

( 0)

(-7.2 -

6.6)E O

(-4.0 -

6.4!E O

(-4.0 -

6.4)E O

  • (

0/ 40)*

  • (

0/ 20)*

  • (

0/ 20)*

CD-60 ( 60)

( -3.1t 2.1)E -1 13

(-2.3 i 3.8)E -1 f-5.8 2.4)E -1

( 0)

(-3.2 -

2.61E O

(-3.2 -

2.6)E O

(-3.0 -

1.5)E O

  • (

0/ 40)*

  • (

0/ 16)*

  • (

0/ 20)*

ZN-65 ( 60)

( -1.72 5.3)E -1 21

( 4.3 t 5.4)E -1

( 4.3 i 5.4)E -1 I,

( 0)

(-7.3 -

7.2)E O

(-3.7 -

5.1)E O

(-3.7 -

5.1)E O

  • (

0/ 40)*

  • (

0/ 20)*

  • (

0/ 20)*

ZR-95 ( 60)

(

4.0t 2.6)E -1 12 ( 5.3 t 3.5)E -1

( 5.8 t 40.0)E -2

( 0)

(-2.9 -

3.8)E 0

(-2.5 -

3.8)E O

(-2.8 -

3.7)E 0

  • (

0/ 40)*

  • (

0/ 20)*

  • (

0/ 20)*

  • NON-RCUTIE REFERS TO TE NUMBER OF SEPARATE EASLREENTS WHICH WERE CREATER TieN TEN (10) TIES TE AVERACE BACKGROLND FOR TE PERIOD OF TE REPORT.

n TE FRACTION OF SAffLE ANALYSES YIELDING DETECTABLE EASLREENTS c

I

(!.E. >3 STD DEVIATICNS) IS licICATED WITH *(

)*..-

EV.'IRONMENTfL Rf42;G.0GICA. PROMA1 SlWY YANVEE NUCLEAR POWER STATION. ROWE. MA JAMJARY - DECEMBER 1984 EDILM: MILK LNITS: PCI/LG t

INDICATOR STATIONS STATICN WITH HIGEST EAN CONTROL STAT 10P6 j

  • unennuuttu n***uuttuunnuun nunu*u**un RADIONUCLIDES EAN EAN EAN (NO. ANALYSES) REPJ1 RED RANGE STA.

RANCE RANGE (NON-ROUTINE)'

LLD NO. IETECTED**

NO.

NO. DETECTED **

NO. DETECTEDu RV-103 ( 60)

( -1.0t

.2)E 0 21

(-9.1 t 1.61E -1

(-9.1 t 1.6)E -1

( 0)

(-2.9 -

.7)E O

(-1.9 -

1.2)E O

(-1.9 -

1.2)E O et 0/ 40)*

  • (

0/ 20)*

  • (

0/ 20)*

Rlh106 ( 60)

(

1.6 12.7)E -1 12 ( 1.6 i 1.9)E O

( 8.5 t 155.9)E -2

( 0)

(-1.8 -

2.5)E 1

(-1.3 -

2.5)E 1

(-1.3 -

1.3)E 1

  • (

0/ 40)*

  • (

0/ 20)*

  • (

0/ 20)*

I-131 ( 60) 1.

(

5.5 2.3)E -1 21

( 8.7 t 5.4)E -1

( S.7 t 5.4)E -1

( 0)

(-!.9 - 79.4)E -1

(-9.8 - 1030.01E -2

(-9.8 - 1036.0)E -2

  • (

8/ 40)*

  • (

6/ 20)*

  • (

6/ 20)*

CS-134 ( 60) 15.

(

8.li 3.1)E -1 13 ( 1.0 t

.5)E O

( 2.1 t 4.0)E -1

( 7)

(-3.9 -

7.0)E O

(-3.9 -

3.2)E O

(-2.1 -

5.0)E O

  • (

8/ 40)*

  • (

5/ 16)*

  • (

3/ 20)*

CS-137 ( 60) 18.

t 7.0t

.8)E O 11

( 1.6 *

.1)E 1

( 2.7 i

.5)E O

( 0)

(-8.3 - 183.0)E -1

( 1.2 -

1.8)E 1

(-7.4 - 86.1)E -1

  • ( 33/ 40)*
  • (

4/ 4)*

  • (

8/ 20)*

BA-140 ( 60) 15.

( -4.0t 3.5)E -1 21

(-6.2 t 50.0)E -2

(-6.2 i 50.01E -2

( 0)

(-7.2 -

4.2)E O

(-3.8 -

7.0)E O

(-3.8 -

7.0)E O

  • (

0/ 40)*

  • (

0/ 20)*

  • (

0/ 20)*

CE-141 ( 60)

( -3.21 3.3)E -1 21

( 4.4 i 4.5)E -1

( 4.4 t 4.5)E -1

( 0)

(-5.4 -

4.1)E O

(-4.2 -

3.4)E O

(-4.2 -

3.4)E O

  • (

0/ 40)*

  • (

0/ 20)*

  • (

0/ 20)*

CE-144 ( 60)

(

2.0i 12.5)E -1 11

( 3.5 t 2.7)E O

( 1.1 t 1.1)E O

( 0)

(-2,2 -

1.7)E 1

(-1.4 - 11.1)E O

(-7.4 - 15.5)E O

  • (

0/ 40)*

  • ( 0/ 4)*
  • (

0/ 20)*

TH-232 ( 60)

(

3.61 6.0)E -1 21

( 2.3 t

.7)E O

( 2.3 i

.7)E O 1.0)E 1

(-2.0 -

9.5)E O

(-2.0 -

9.5)E O

( 0)

(-1.1

  • (

0/ 40)*

  • (

0/ 20)*

  • (

0/ 20)*

  • N0rH10VTIE REFERS TO TE NJMBER OF SEPARATE EASUREENTS WIICH ERE GREATER THAN TEN (10) TIES THE AVERADE BACX0ROUND FOR THE PERIOD OF TE REPORT.
    • TE FRACTION OF SAPPLE NMLYSES YIELDING DETECTABLE EASLREMENTS (I.E. >3 STD DEVIATIONS) IS INDICATED WITH *(

)*.

3.4 Food Crop Samples of Swiss chard or apples were collected at harvest time and analyzed for gamma-emitting nuclides. These crops were sampled from four indicator stations and one control station.

Other than naturally occurring K-40, no radionuclides were detected in the samples.

Unavailable Sample: During the 1986 Land Use Census, it was found that a garden no longer existed at Station TF-12.

This location was replaced with Station TF-13 following the census, pursuant to Technical Specification 3.12.2.b.

The required harvest sample was collected from Station TF-13.

Prior to the inclusion of TF-13 in the ODCM, an interim food crop sample was collected from TF-45 due to its close proximity to TF-12.

b l 2918R

ENVIRONENTAL RADICLOGICAL PROGRM SLEWSY YANKEE MJCLEAR PNER STATION. ROWE. MA JANUARY - DECEleER 1986 EDIUM: FOODCROP UNITS: FCl/K0 WET INDICATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIO W en***+++n * *n n e u ne n n e n n ee n u n ***

neut**un ne RADIOMJCLIDES MAN EAN EAN (NO. ANALYSES) RE0V! RED RANGE STA.

RANGE REE (NON-ROUTIE)'

LLD NO. DETECTED **

Ps).

NO. DETECTED +i NO. DETECTED **

BE-7 ( 5)

(

!.2t

.2)E 2 43 ( 1.7 i

.6)E 2

( 9.6 i 9.5)E 1

( 0)

( 6.7 - 16.6)E 1

  • (

0/ 4)*

  • (

0/ 1)*

  • (

0/ 1)*

K-40 ( 5)

(

2.7t 1.1)E 3 21

( 5.6 *

.4)E 3

( 5.6 i

.4)E 3

( 0)

( 8.3 - 48.1)E 2

  • (

4/ 4)*

  • (

1/ 1)*

  • (

1/ 1)*

t91-54 ( 5)

( -1.6t 3.2)E 0 45

( 4.8

  • 10.4)E O

(-1.3 i 1.3)E 1

( 0)

(-1.0 -

.5)E 1

  • (

0/ 4)*

e' 0/ 1)*

  • (

0/ lie CO-58 ( 5)

(

4.8t 4.8)E O 13 ( 1.8 t 1.3)E 1

(-1.4 i 12.5)E O

( 0)

(-2.8 - 17.9)E O

  • f 0/ 41*

ef 0/ 1)*

  • ' 0/ 1)*

FE-59 ( 5)

(

2.2f 1.3)E 1 13 ( 5.2 i 3.1)E 1

(-8.4 i 26.0)E O

( 0)

(-5.8 - 51.0)E 0

  • (

0/ 4)*

  • (

0/ 1)*

  • (

0/ 1)*

CO-60 ( 5)

( -6.St 4.0)E O 43

( 3.6 t 11.7)E O

(-S.6 f 18.4)E O

( 0)

(-1,3 -

4)E 1

  • (

0/ 4)+

  • (

0/ 1)*

  • (

0/ 1)*

ZN-65 ( 5)

(

8.6i 8.61E O 13

( 2.3 t 2.7)E 1

( 9.8 t 28.11E O

( 0)

(-1.6 -

2.31E 1

  • (

0/ 4)*

  • (

0/ 1)*

  • ( 0/ 1)*

ZR-95 ( 5)

( -1.92

.9)E 1 45

(-2.5 t 16.2)E 0

(-2.1 t 2.3)E 1

( 0)

(-4.5 -

.3)E 1

  • (

0/ 4)*

  • (

0/ 1)*

  • (

0/ 1)*

Rlh103 ( 5)

( -8.7f 11.4)E O

( 1.5 t

.9)E 1

( 7.7 t 10.3)E O

( 0)

(-3.5 -

1.5)f 1

  • ( 0/ 4)*
  • ( 0/ 1)*
  • ( 0/ 1)*

N0HOUTIE REFERS TO TE NUMBER OF SEPARATE EASLREENTS WHIOi WERE GREATER TMN TEN (10) TIES THE AVERACE BACKGROUND FCR THE PERIOD OF THE REPORT.

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

)*.

EN'JIR9NMENTAL RAD 10 LOGIC /4 PP0rAAM S.MmRY YAWEE MILEAR PWER STATION, RCHE, E JANUARY - DECEMBER 1986 E"te: FCr)D CFF LNITS: PCI/KG WET INDICATOR STATIONS STATION WITH HIGEST EAN CONTROL STAT:0NS e****e++++,eee++en eteesse++++eeee******,een e+++e++eese****e RADICNJCLIDES EAN EAN EAN (NO. ANALYSES) REQUIRED RANCE STA. RANGE RANGE (NON-ROUTIE)'

LLD NO. DETECTED +e NO.

NO. DETECTED **

NO. DETECTEDe*

RU-106 ( 5)

(

S.4i 2.9)E 1 21

( 1.1 t 1.2)E 2

( 1.1 i 1.2)E 2

( 0)

(-2.4 -

9.4)E 1

  • (

0/ 4)*

  • (

0/ 1)*

e( 0/ 11e I-131 ( 5)

(

2.3t 2.2)E 1 13 ( 8.6 t 7.2)E I

(-3.6 t 14.4)E O

( 0)

(-1.0 -

8.6)E 1 et 0/ 4)*

e( 0/ 1)*

  • (

0/ 1)*

CS-134 ( 5) 60.

( -1.9t 4.6)E O 45 ( 6.7 i 12.2)E O

(-3.0 t 13.0)E O

( 0)

(-1.5 -

.7)E 1

  • (

0/ 4)e

  • (

0/ 1)*

  • (

0/ 1)*

CS-137 ( 51 80.

(

9.61 2.8)E O 13 ( 1.6 t 1.4)E 1

( 1.3 13.41E O

( 0)

( 4.0 - 16.4)E O

  • (

0/ 4)+

  • (

0/ lie

  • (

0/ 11' BA-140 ( 5)

( -2.4t 1.3)E 1 43

(-5.0 t 14.8)E O

(-1.0 t 1.8)E 1

( 0)

(-6.0 -

.5)E 1

  • (

0/ 4)+

  • (

0/ 1)*

  • (

0/ 1)*

CE-141 ( Si

(

5.51 S.0)E O 43 ( 2.2 t 1.2)E 1

( 1.4 i 1.7)E 1

( 0)

(-1.5 -

2.2)E 1

  • (

0/ 4)*

  • ( 0/ 1)*
  • (

0/ 1)e CE-144 ( 5)

( -3.3t 1.7)E 1 21

( 9.5 t 7.2)E 1

( 9.5 t 7.2)E 1 l

1

( 0)

(-7.1

.7)E 1 l

  • (

0/ 4)+

  • (

0/ lie

  • (

0/ 1)*

l TH-232 ( 5)

(

l.92 2.0)E 1 11

( 6.4 t 4.5)E 1

( 8.9 t 63.7)E O

( 0)

(-3.3 -

6.4)E 1

  • (

0/ 4)e

  • ( 0/ 1)*
  • (

0/ 1)+

l' e NON-ROUTIE REFERS TO TE NLMBER OF SEPARATE EASLREENTS Wi!CH ERE GREATER T)MN TEN (10) TIES TE AVERAGE BACKGROLMD FOR TE PERIOD OF TE REPORT.

++ TE FRACTION OF SAPPLE ANALYSES YIELDING DETECTAR.E EASUREENTS (I.E. >3 STD DEVIATIONS) IS INDICATED WITH et le. l

3.5 Broad Leaf Venetation The Radiological Effluent Technical Specifications require that one-sample of broad leaf vegetation be sampled at harvest time.

In 1986, a Swiss chard sample was collected from Station TV-11 (Monroe Bridge). The required I-131 analysis showed no detectable radioactivity.

I l 2918R

EWIR0pMENTAL RADICLOGICAL PROGRAM SUrt%RY YAl#IE MJCLEAR POWER STATION, R0WE, t%

JANUARY - DECD SER 1986 EDIUM: GREEN LEAFY VEGETABLE UNIT 5: PCI/KG WET INDICATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIOPE M44HtHfM4HHf HHettif9HHHittetHH H HfM HitMete RADIONJCLIIES EAN EAN EAN (NO. ANALYSES) REQUIRED RANGE STA. RANGE RANGE (N0pt-ROUTIEl' LLD NO. DETECTED **

NO.

NO. DETECTEDH NO. DETECTED ++

I-131 ( 1) 60.

(

3.6f 6.0)E -1 11

( 3.6 t 6.0)E -1 NO DATA

( 0)

  • ( 0/ 1)*
  • (

0/ 1)*

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

TE FRACTION OF SAPFLE ANALYSES YIELDING DETECTABLE I G SUREMENTS

++

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

)*,

i.. -

3.6 Maple Syrup Maple syrup grab samples (not required by Technical Specifications) were collected during April and May 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 1986 had a higher Cs-137 level than detected at the indicator station.

s l

l I

{

l l 2918R

""^

FW'

==

"+m-wm'e m

El#IRONENTAL RADIOLOGICAL PROGRAM SUMARY YAWEE N. CLEAR POER STATION, ROE, MA JANJARY - DECEMBER 1986 ECIUM: MiP.E SYFitP LNITS: PCI/VG INDICATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONS nuunnen*nn unenennen****neun

  • *** n n**** n e RADIONUCLIDES EAN EAN EAN (NO. MALYSES) RE0JIRED RANGE STA. RANGE RANCE (NON-ROJTIE)'

LLD NO. DETECTED **

NO.

NO. DETECTED **

NO. DETECTED **

BE-7 ( 3)

( 7.6i 6.7)E 0 31 ( 7.6 i 6.7)E 0

( !.9 i 4.2)E O

( 0)

(-2.3 -

6.1)E O

  • (

0/ 1)*

  • (

0/ 1)*

  • ( 0/ 2)*

i(-40 ( 3)

(

2.0t

.0)E 3 31

( 2.0 t

.0)E 3

( !.5 i

.0)E 3

( 0)

( 1.5 -

1.5)E 3

  • (

1/ 1)*

  • (

1/ 1)*

  • (

2/ 2)*

MN-54 ( 3)

('-1.61 7.5)E -1 42 ( 2.3 t 7.7)E -1

(-3.0 i 5.3)E -1

( 0)

(-8.3 -

2.3)E -1

  • (

0/ 1)*

  • (

0/ 1)*

  • ( 0/ 2)*

CO-53 ( 31

( -2.01

.8)E O 42 ( !.4 i

.9)E O

( 4.4 i 9.2)E -!

( 0)

(-4.7 - 13.6)E -1

  • (

0/ 1)*

  • (

0/ 1)*

  • f 0/ 2)*

FE-59 ! 31

(

2.01 2.35E O 31

( 2.0 i 2.3)E O

( 3.6 i 3.9)E -1

( 0)

(-3.7 - 75.1)E -2

  • (

0/ 1)*

  • (

0/ 1)*

  • (

O! 2)*

CO-60 ( 3)

( -7.01 103.01E -2 41

( 2.1 i 1.8)E O

( 6.5 14.5)E -1

( 0)

(-S.O - 21.0)E -!

  • (

0/ 1)*

  • (

0/ 1)*

  • (

0/ 2)*

IN-65 ( 3)

(

-1.Ci 22.8)E -1 42

( 5.5 i 24.3)E -1

( 4.5 i 50.51E -2

( 0)

(-4.6 -

5.5)E -1

  • (

0/ 1)*

  • (

0/ 1)*

  • (

0/ 21*

ZR-95 ( 3)

( -1.7f 1.5;E O 41

( 3.0 t 2.7)E O

( 1.9 t 1.1)E O

( 0)

( 7.6 - 29.9)E -1

  • (

0/ 1)*

  • (

0/ 1)*

  • ( 0/ 2)*

RU-103 ( 3)

( -8.91 8.8)E -1 42 ( 1.1 i 10.3)E -1

(-2.8 t 3.9)E -1 l

( 0)

(-6.7 -

1.1)E -1

  • (

0/ 1)*

  • (

0/ 1)*

  • (

0/

.')

  • i I
  • NON-ROUTIE REFFRS TO TE NJMBER OF SEPARATE EASUREENTS WHICH WERE GREATER THAN TEN (10) TIES TE AVERAGE BACK0ROLND FOR TE PERIOD OF TE REPORT.

n TE FRACT!;N OF SAMPLE ANALYSES YIELDING DETECTABLE EASLREENTS (f.E. >3 STD DEVIATIONS) IS INDICATED WITH *(

1*.

ENi:RONMENTAL RADIOLOGICAL PRCCRAM SLMMARY YANFEE NJCLEAR POWER STATION, R0WE, MA JANUARY - ECEMBER 1986 EDIUM: t%PLE SYRUP UNITS: PCI/VG INDICATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONS e+enenunenen enten****u+une++ nee

      • enne e*
  • n n RADIONUCLIIES EAN EAN EAN (PF). ANALYSES) REPJ! RED RANGE STA.

RANGE RANGE (NON-ROUTINEl' LLD NO. DETECTEDn NO.

NO. ETECTED*+

NO. DETECTED **

RU-1% ( 3)

( -1.4f 6.6)E 0 31

(-1.4 i 6.61E O

(-9.4 i 3.3)E O

( 0)

(-1.3 -

.6)E 1 e( 0/ 1)*

  • (

0/ 1)*

e( 0/ 2)e I-131 ( 3)

( -1.0t 4.2)E O 42 ( 1.4 t

.9)E 1

(-3.9 t 17.8)E O

( 0)

(-2.2 -

1.4)E 1

  • (

0/ 1)*

e( 0/ 1)*

  • (

0/ 2)*

CS-134 ( 3)

( -6.2t 7.3)E -1 42 ( 4.8 i 8.8)E -1

(-1.6 i 6.4)E -1

( 0)

(-8.1 -

4.8)E -1

  • (

0/ 1)+

  • (

0/ 1)*

  • (

0/ 2)+

CS-137 ( 3)

(

1.92

.1)E 1 41

( 7.4 f

.3)E 1

( 4.2 i 3.2)E 1

( 0)

( 1.0 -

7.4)E 1

  • (

1/ 1)*

  • (

1/ 1)+

et 2/ 2)*

E4-140 ( 31

( -1,3t 2.0)E O 41

( 7.1 i 5.0)E O

( 3.5 t 3.6)E O

( 0)

(-1,6 - 70.H E -!

  • (

0/ 1)*

  • (

0/ 1)*

  • (

0/ 21*

CE-141 ( 3)

(

3.2t 167.0)E -2 41

( 4.8 t 2.9)E O

( 4.0

.8)E O

( 0)

( 3.2 -

4.8)E O

  • (

0/ 1)*

e( 0/ 1)*

  • (

0/ 2)+

CE-144 ( 3)

( -7.7f 4.9)E O 42 ( 4.6 i 5.2)E O

( 4.0 t

.6)E O

( 0)

( 3.4 -

4.6!E O

+(

0/ 1)*

  • (

0/ 1)*

  • ( 0/ 2)*

TH-232 ( 3)

(

2. 5t 3.0)E O 41

( 9.8 t 4.6)E O

( 8.7 t 1.0)E O

( 0)

( 7.7 -

9.8)E O e( 0/ 1)*

  • (

0/ 1)*

e( 0/ 2)*

NON-ROUTIE REFERS TO TE NUMBER OF SEPARATE EASLREENTS Wi!CH ERE GREATER IHAN TEN (10) TIES TE AVERAGE BA(XOROLMD FOR TE PERIOD OF TE REPORT.

  • e TE FRACTION OF SAPFLE ANALYSES Y!ELDING DETECTABLE EASLREENTS

(!.E. >3 STD DEVIATIONS) IS INDICATED WITH et le. '

3.7 Groundwater Groundwater 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 Station WC-11.

Since the water from WG-12 (Sherman Spring) is not used for drinking water, cnf 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 1986 concentration of 1100 pCi/ kilogram, would be approximately 0~.04 mrem, using USNRC Regulatory Guide 1.109 methodology (Reference 1).

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

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.

No gamma-emitting radionuclides were detected in the groundwater samples.

l l

l-l i 3918R

-,,. ~

a n

,p

ENVIRONTNTAL RAD 10LOGICfL PROAAM SUMMA %

YAWEE MJCLEAR POWEP STATION, RCWE, MA JANUARY - DECEMBER 1986 EDILM: CROLND WATER UNITS: PCI/r0 INDICATOR STATIONS STATION WITH H10EST EAN CONTROL STATIONS n ++n****ee n++ n

  • +++ n ew ++++++ne* ***ee n++++++e+n n+e RADIOMJCLIDES EAN EAN EAN (NO. ANALYSES) RE9)! RED RAN:E STA.

RANGE RANGE (NON-ROUTIE)'

LLD f(). DETECTED *e NO.

NO. DETECTEDn NO. DETECTED **

OR-B ( 24) 4.

( 3.51

.2)E O 11

( 4.2 i

.2)E O NO DATA

( 0)

( 2.2 -

5.3)E O

( 2.3 -

5.3)E O

  • ( 24/ 24)*
  • ( 12/ 12)*

K-40 ( 24)

(

2.6t 3.2)E O 11

( 6.3 t 3.6)E O NO DATA

( 0)

(-3.6 -

3.0)E 1

(-1.4 -

2.6)E 1

  • (

0/ 24)*

  • (

0/ 12)*

t9f-54 ( 24) 15.

( -2.lt 2.4)E -1 12

(-6.3 t 35.6)E -2 NO DATA

( 0)

(-2.3 -

2.8)E O

(-2.3 -

2.8)E O

  • (

0/ 24)*

  • (

0/ 12)*

CO-58 ( 24) 15.

(

-4.8 14.3)E -2 11

(-1.6 t 16.4)E -2 NO DATA

( 0)

(-1.2 -

1.3)E 0

(-6.7 - 12.9)E -1

  • (

0/ 24)*

  • (

0/ 12)*

FE-59 ( 24) 30.

( -5.4t 4.7)E -1 12

(-3.3 i 4.5)E -1 NO DATA

( 0)

(-4.6 -

4.1)E O

(-3.4 -

!.9)E O

  • (

0/ 24)*

  • (

0/ 12)*

CO-60 ( 24) 15.

( -1.7t 1.9)E -1

(-9.8 t 27.6)E -2 NO DATA

( 0)

(-2.0 -

2.6)E O

(-1.1 -

2.6)E O et 0/ 24)*

  • (

0/ 12)*

IN-65 ( 24) 30.

(

7.5 3.11E -1 11

( 9.3 f 5.0)E -1 NO DATA

( 0)

(-2.2 -

3.7)E O

(-1.4 -

3.7)E O

  • (

0/ 24)*

  • (

0/ 12)*

l l

ZR-95 ( 24) 15.

( -2.2t 4.3)E -1 11

( 2.5 i 6.0)E -1 NO DATA

( C'

(-3.7 -

4.2)E O

(-3.1 -

3.7)E O

  • (

0/ 24)*

  • (

0/ 121e 1

RU-103 ( 24)

( -6.41 2.4)E -1 12

(-5.5 t 3.9)E -1 NO DATA

( 0)

(-2.7 -

1.8)E 0

(-2.7 -

1.7)E 0

  • (

0/ 24)e

  • (

0/ 12)*

  • NON-ROUTIE REFERS TO TE M.MBER OF SEPARATE EASUREENTS lei!CH WERE OPIATER THAN TEN (10) TIES THE AVERAGE BACK0ROUND FOR THE PERIOD OF TE REPORT.
    • TE FRACTION OF SAPPLE ANALYSES YIELDING DETECTABLE EASLREENTS (i.E. >3 STD DEVIATIONS) IS INDICATED WIT 4 *(

)*, -

Et#1RCofENTAL RADIOLOGICAL PROGRAM SytlARY YAWEE MJCLEAR PtMR STATION. R0WE. HA JAMJARY - DECEMBER 1986 EDIUM: OROLND WATER UNITS: PCI/tG INDICATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONS nonun**nen+*

  • n un en*****
  • n; n * **

u*nennnene RADIONUCLIDES EAN EAN EAN iNO. ANALYE S) REQUIRED RANGE STA.

RANCE RANGE (N(W-ROJTIE)'

LLD NO. DETECTED **

NO.

NO. DETECTEDn NO. ETECTEDn RU-106 ( 24)

(

1.5t 1.5)E O 12 ( 2.9 t 2.2)E O NO DATA

( 0)

(-1.2 -

1.9)E 1

(-7.3 - 19.3)E O

  • (

0/ 24)*

  • (

0/ 12)*

I-131 ( 24) 1.

(

5.91 10.2)E -l

( 9.0 t 11.6)E -1 to DATA

( 0)

(-7.3 - 14.6)E O

(-6.1 -

8.5)E 0

  • (

0/ 24)*

  • (

0/ 12)*

CS-134 ( 24) 15.

( -3.41 1.8)E -1 12

(-2.3 i 1.8)E -1 NO Dt.TA

( 0)

(-2.9 -

1.1)E O

(-1.2 -

.9)E O

  • (

0/ 24)*

  • (

0/ 12)*

CS-137 ( 24) 18.

( -3.01 19.5)E -2 12 ( 4.1 t 2.8)E -1 NO DATA

( 0)

(-1.6 -

1.8)E 0

(-1.3 -

1.8)E O

  • (

0/ 24)*

  • (

0/ 12)*

BA-140 ( 24) 15.

( -6.81 5.2)E -1 11

( 2.9 t 56.6,E -2 NO DATA

( 0)

(-6.9 -

4.5)E O

(-2.8 -

4.5)E O

  • (

0/ 24)*

  • (

0/ 12)*

CE-141 ( 24)

(

5.52 5.1)E -1 12 ( !.1 i

.7)E 0 Nn DATA

( 0)

(-4.1 -

4.7)E 0

(-2.7 -

4.4)E O

  • (

0/ 24)*

  • (

0/ 12)*

CE-144 ( 24)

(

2.5f 1.0)E O

( 2.7 t 1.7)E O NO DATA

( 0)

(-8.3 -

13.6)E O

(-8.3 - 13.6)E O l

  • (

0/ 24)*

  • (

0/ 12)*

i TH-232 ( 24)

(

!.8t

.7)E O

( !.9

  • 1.1)E O NO DATA

(

( 0)

(-7.5 -

9.2)E O

(-2.4 -

9.2)E 0

  • (

0/ 24)*

  • (

0/ 12)*

H-3

( 24) 2000.

(

5.91 1.2)E 2 12 ( l.1 i

.1)E 3 NO DATA I

( 12)

(-2.6 - 14.4)E 2

( 6.7 - 14.4)E 2

  • ( 12/ 24)*
  • ( 12/ 12)*

r

  • EN-ROUTIE REFERS TO TE NLMBER OF SEPARATE EASLREENTS WHICH WERE GREATER l

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

    • TE FRACTION OF SAPFLE ANALYSES YIELDING DETECTABLE MEAc.WiMENTS (1.E. >3 STD DEVIATIONS) IS INDICATED WITH *(

)*..

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

Quarterly composites were analyzed for H-3.

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

If one was to calculate, however, the dose to an adult who consumed his entire yearly intake of water (370 kilograms per year) from the Deerfield River at the above sampling location, with the average concentration of 510 pCi/ kilogram, it would be shown that the dose would be approximately 0.02 mrem per year, using USNRC Regulatory Guide 1.109 methodology (Reference 1).

The maximum concentration of 930 pCi/ kilogram during the third quarter of 1986 did not exceed the 30,000 pCi/ kilogram reporting level.

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 approximately equal in 1986.

l Iodine-131 was detected in both locations in May of 1986. This was caused by fallout from the Chernobyl accident, which is discussed in Section 4.

With the exception of I-131, no gamma-emitting radionuclides were detected in the 1986 river water samples. l 2918R l

i

-+

- -. - - ~ -

ENV!R0pfNTAL RADIMICAL PROGR4M SlfmARf YAEEE W.lCLEAR FMR STATION. R0WE MA JAMJARY - K CEMBER 1986 EDILM: RIVER WATER LNITS: PC1/VG INDICATOR STATIONS STATION W!Trf HIGEST EAN CONTRG. STATIONS

      • m e*** m e m t
                        • m e n m m e
              • m ******

RADIONUCLIDES EAN EAN EAN (NO. ANALYES) REQVIRED RAEE STA.

RAEE RANT (NON-ROUTIEl' LLD NO. CETECTEDH NO.

NO. DETECTED **

NO. DETECTED **

OR-B ( 24) 4.

(

1.91

.2)E O 21

( 2.1 i

.2)E O

( 2.1 i

.2)E O

( 0)

( 8.6 - 42.2)E -1

( 8.7 - 40.0)E -1

( 8.7 - 40.0)E -1

  • ( !!/ 12)*
  • ( 11/ 12)*
  • ( !!/ 12)*

BE-7

( 24)

(

3.2 2.8)E O 11

( 3.2 t 2.8)E O

( l.8 t 1.5)E O

( 01

(-1.3 -

1.7)E 1

(-1.3 -

1.7)E I

(-7.8 - II.2)E O

  • (

0/ 12)*

  • (

0/ 12)*

  • (

0/ 121*

L-40 ( 24)

(

3.2t 4.9)E O 11

( 3.2 t 4.9)E 0

( 2.4 t 5.81E O

( 0)

(-1.7 -

4.0)E 1

(-1.7 -

4.0)E 1

(-4.0 -

3.4)E 1

  • (

0/ 12)*

  • (

0/ 12)*

  • (

0/ 12)*

P91-54 ( 24) 15.

(

-9.7 30.0)E -2 11

(-9.7 t 30.0)E -2

(-4.3 t 2.5)E -1

( 0)

(-2.7 -

1.1)E O

(-2.7 -

1.1)E 0

(-2.1 -

1.2)E O

  • (

0/ 12)*

  • (

0/ 12)*

  • (

0/ 12)*

CD-58 ( 24) 15.

( -1,6f 3.2)E -1 21

( 3.3 t 3.7)E -1

( 3.3 t 3.7)E -1 2.3)E O

(-9.9 - 36.8)E -1

(-9.9 - 36.81E -1

( 01

(-2.1

  • (

0/ 12)*

  • (

0/ 12)*

  • (

0/ 12)*

FE-59 ( 24) 30.

(

2.2t

.7)E 0 11

( 2.2 t

.7)E O

( 8.1 t 6.0)E -!

( 0)

( 1.3 - 71.2)E -1

( l.3 - 71.2)E -1

(-3.7 -

3.5:E O

  • (

0/ 12)*

  • (

0/ 12)*

  • (

0/ 12)*

CO-60 ( 24) 15.

( -6.0t 2.0)E -1 21

(-4.7 t 2.2)E -1

(-4.7 t 2.2!E -1

( 0)

(-2.1 -

.2)E O

(-1.9 -

1.4)E 0

(-1.9 -

1.4)E O

  • (

0/ 12)*

  • (

0/ 12)*

  • (

0/ 12)*

ZN-65 ( 24) 30.

( -3.11 7.5)E -1 21

( 3.3 t 3.7)E -1

( 3.3 t 3.7)E -1 4.2)E 0

(-1.7 -

2.6)E 0

(-1.7 -

2.6)E 0

( 0)

(-5.1

  • (

0/ 12)*

  • (

0/ 12)*

  • (

0/ 12)*

IR-95 ( 24) 15.

(

9.5*

6.1)E -1 21

( l.1 *

.6)E O

( l.1 t

.6)E O

( 0)

(-3.5 -

4.4)E 0

(-4.0 -

4.6)E O

(-4.0 -

4.6)E O

  • (

0/ 12)*

  • (

0/ 12)*

  • (

0/ 12)*

I r

  • NOM-ROUTIE REFERS TO THE NUMBER OF SEPARATE EASLREENTS WHICH WERE GREATER THAN TEN (10) T!ES TE AVERAGE BACK0R0lND F(R TE PERIOD OF TE REPCHT.
    • TE FRACTION OF SAPPLE ANALYSES Y!ELDING DETECTABLE EASUREENTS (i.E. >3 STD DEVIATIONS) IS INDICATED WITH *(

)*.

i E)NIRONENTAL RADIOLOGICAL PRCETW1 SlfmARY YANKEE R CLEAR POWER STATICN, R0WE. MA JANUARY - DECEl@ER 1986 EDILP.: RIVER W.TER LNITS: PCI/KO INDICATOR STATIONS STATION WITH HIGHEST EAN CCNTROL STATIOP6 neuennen+++n n++nennun++nnun ennununne RADICN.0LIDES EAN EAN EAN (NO. ANALYSES) REQUIRED RANCE STA. RANGE RANGE (NON-ROUTIE)'

LLD NO. DETECTED **

NO.

NO. DETECTEDu NO. DETECTEI4+

RV-103 ( 24)

(

-5.7*

3.4)E -1 11

(-5.7 t 3.4)E-1

(-9.6 i 2.9lE -1

( 0)

(-2.4 -

1.4)E 0

(-2.4 -

1.4)E O

(-2.6 -

.9)E 0

  • (

0/ 12)*

et 0/ 12)e

  • (

0/ 12)*

RU-106 ( 24)

(

4.1 2.9)E O 11

( 4.1 t 2.9)E O

( 2.2 t 19.0)E -1

( 0)

(-8.0 - 29.5)E O

(-8.0 - 29.5)E O

(-1.0 -

1.2)E 1

  • (

0/ 12)*

  • (

0/ 12)*

  • (

0/ 12)*

I-131 ( 24)

(

4.52 3.6)E -2 11

( 4.5 t 3.6)E -2

(-9.2 i 23.2)E -3

( 1)

(-2.3 -

2.5)E -1

(-2.3 -

2.5)E -1

(-1.2 -

1.8)E -!

  • (

1/ 12)*

  • (

1/ 12)*

  • (

1/ 12)*

CS-134 ( 24) 15.

( -6.9t 1.9)E -1 21

(-4.6 t 2.1)E-1

(-4.6 t 2.1)E -1

( 0)

(-2.2 -

.3)E O

(-1.5 -

.8)E 0

(-1.5 -

.8)E 0

  • (

0/ 12)*

  • (

0/ 12)*

  • (

0/ 12)*

CS-137 ( 24) 18.

( 2.9t 2.5)E -1 11

( 2.9 i 2.5)E -1

( l.9

  • 2.9)E -1

( 0)

(-1.8 -

1.3)E 0

(-1.8 -

1.3)E O

(-1.3 -

2.4)E O

  • (

0/'!2)*

  • (

0/ 12)*

  • (

C/ 12)*

BA-140 ( 24) 15.

( -6.11 St.6)E -2 11

(-6.1 t 81.6)E -2

(-1.4 i

.5)E O

( 0)

(-5.2 -

4.4)E O

(-5.2 -

4.4)E O

(-4.9 -

.4)E O

  • (

0/ 12)*

  • (

0/ 12)*

  • (

0/ 12)*

CE-141 ( 24)

( -3.4t 7.8)E -1 21

( 2.9

  • 5.5)E -1

( 2.9 t 5.5)E -1

( 0)

(-6.8 -

2.81E O

(-4.6 -

3.7)E O

(-4.6 -

3.7)E O

  • (

0/ 12)*

  • (

0/ 12)*

  • (

0/ 12)*

CE-144 ( 24)

( 7.5t 21.9'i -1 21

( !.8 t 1.4)E O

( l.8 t 1.4)E O

( 0)

(-8.1 - 13.t!E 3

(-6.6 - 10.4)E 0

(-6.6 - 10.4)E 0 et 0/ 12)*

  • (

0/ 12)*

e( 0/ 12)*

H-3

( 8) 2000.

(

5.It 1.6)E 2 11

( 5.1

  • 1.6)E 2

( 1.8 t

.7)E 2

( 2)

( l.6 -

9.3)E 2

( l.6 -

9.3)E 2

(-3.5 - 30.5)E 1 l

  • ( 2/ 4)*
  • (

2/ 4)*

  • ( 0/ 4)*

1 NON-ROUTINE REFERS TO THE NLt9ER OF SEPARATE EASLREENTS I4i1CH WERE OREATER THAN TEN (10) TIES M AVERAGE BACK0ROUND FOR H PERIOD OF M REPCRT.

    • M FRACTION OF SMFLE ANALY!ES YIELDING DETECTABLE EASUREENTS

(!.E. >3 STD DEVIATIONS) l$ INDICATED WITH *(

)*.,. _ _.

3.9 Sediment Sediment cores were collected semiannually from two locations.

Each core was separated into 5 cm segments, which were analyzed for gamma-emitting radionuclides. Cesium-137 was detected in all samples. The levels measured at the indicator location were consistent with what has been measured in the previous several years and are attributed to nuclear weapons testing fallout.

Other than naturally occurring K-40, Be-7, and Th-232, no other gamma-emitting radionuclides were detected in 1986 sediment samples.

l i

i

! 2918R i

s

_ = - _, _.

ENVIROWENTA' RADIOLOGICAL PROGRAM SLM%RY YAWIE NUCLEAR POER STATION, R0WE, f%

JAWARY - DECEMBER 1986 ffDDr: $ EDICT UNITS: PCI/VG DRY INDICATOR STATIONS STATION WITH HIGEST EAN CONTROL STATICN3

    • ++++++++++****+++***+++
  • +++++++++++****

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

RANGE RANGE (NLN-ROUTIE)'

LLD NO DETECTED ++

NO.

NO. DETECTED ++

NO. DETECTED ++

BE-7 ( 13)

(

7.7f 5.6)E 1 11

( 7.7 i 5.6)E 1

(-3.4 i 4.5)E I

( 0)

(-1.5 -

2.5)E 2

(-1.5 -

2.5)E 2

(-2.0 -

1.6)E 2

  • ( 0/ 6)*
  • ( 0/ 6)*
  • (

0/ 7)*

K-40 ( 13)

(

!.41

.1)E 4 21

( !.7 i

.1)E 4

( 1.7 i

.11E 4

( 0)

( 1.0 -

1.7)E 4

( 1.0 -

2.2)E 4

( 1.0 -

2.2)E 4

  • (

6/ 6)*

  • (

7/ 7)*

  • (

7/ 7)*

!W-54 ( 13)

( -1.9t

.5)E 1 21

(-9.2 i 4.2)E 0

(-9.2 t 4.2)E O

( On

(-3.4 -

.4)E 1

(-2.3 -

1.1)E 1

(-2.3 -

1.1)E 1

  • (

0/ 6)*

  • (

0/ 7)*

  • (

0/ 7)*

CO-58 ( 13)

(

3.02 8.3)E O 11

( 3.0 8.3)E O

( 1.1 i 6.3)E O

( 0)

(-2.0 -

3.7)E I

(-2.0 -

3.7)E 1

(-2.5 -

1.9)E 1 of 0/ 6)*

  • (

0/ 6)*

  • ( 0/ 7)*

FE-59 ( 13)

(

1.21 1.8)E 1 11

( 1.2 i 1.8)E 1

( 5.4 i 14.9)E O

( 0)

(-3.3 -

9.7)E 1

(-3.3 -

9.7)E 1

(-5.8 -

5.6)E 1

  • (

0/ 6)*

  • (

0/ 6)+

ef 0/ 7)*

C0-60 ( 13)

(

6.21 5.2)E O 11

( 6.2 t 5.2)E O

( 3.2 1 3.3)E 0

( 0)

(-1.3 -

1.8)E 1

(-1.3 -

1.8)E 1

(-9.8 - 18.8)E O

  • (

0/ 6)*

  • (

0/ 6)*

  • ( 0/ 7)*

IN-65 ( 13)

( -9.8i 15.1)E O 21

(-4.7 i 17.4)E O

(-4.7 t 17.4)E O 3.5)E 1

(-8.0 -

3.5)E 1

(-8.0 -

3.5)E 1

( 0)

(-7.4

  • (

0/ 6)*

  • ( 0/ 7)*
  • (

0/ 7)*

ZR-95 ( 13) 2.3t 1.1)E 1 11

( 2.3 i 1.1)E 1

(-2.8 i 12.4)E O

( 0)

(-2.3 -

5.7)E 1

(-2.3 -

5.7)E 1

(-3.3 -

5.6)E 1

  • ( 0/ 6)*
  • (

0/ 6)*

  • ( 0/ 7)*

R)-103 ( 13)

( -2.2t 10.0)E O 21

( 6.4 t 90.7)E -1

( 6.4 t 90.7)E -1

( 0)

(-3.3 -

2.5)E 1

(-4.8 -

2.4)E 1

(-4.8 -

2.4)E 1

  • (

0/ 6)*

  • ( 0/ 7)*
  • ( 0/ 7)*
  • PON-RotrTINE REFERS TO TE NLMBER OF SEPARATE EASUREMENTS WHICH ERE GREATER THAN TEN (10) TIMES THE AVERAGE BACX0ROUND FOR TE PERIOD OF T E REPORT.

++ TE FRACTION OF SAPPLE ANALYSES Y!ELDING DETECTABLE EASLREENTS (I.E. >3 STD IEVIATIONS) IS INDICATED WITH *(

)*. _

EWIKNTNTfL RADIOLOGIC 5L PROGRAM StrMARY YAWEE MJCLEAR POWER STATION. R0WE. MA JANJARY - DECEP'PER 1986 E Dilm: SEDIMENT LNITS: PCI/KG DRY INDICATOR STATICNS STATION WITH HIGEST EAN CONTROL STATIONS eennenennene eenneennenneneetu

      • +nn en* n n RADIONUCLIDES EAN EAN EAN (10. ANALYSE 5) REQUIRED RANGE STA. RMGE RANGE (NON-ROUTIEl' LLD NO. DETECTED **

NO.

NO. DETECTEDet NO. DETECTEDee RU-106 ( 13)

( -4.8f 5.4)E 1 21

( 7.7 i 43.0)E O

( 7.7 i 43.0)E O

( 0)

(-3.0 -

.9)E 2

(-1.1 -

2.2)E 2

(-1.1 -

2.2)E 2

  • (

0/ 6)*

  • ( 0/ 7)*
  • ( 0/ 7)*

I-131 ( 13)

( -3.6t 33.4)E I 11

(-3.6 t 33.4)E 1

(-4.1 t 39.0?E I 1.3)E 3

(-1.2 -

1.3)E 3

(-1.6 -

1.9)E 3

( 0)

(-1.!

  • (

0/ 6)*

  • (

0/ 6)*

  • (

0/ 7)*

CS-134 ( 13) 150.

(

3.0t 10.4)E 0 21

( 3.8 t 5.7)E O

( 3.8 i 5.7)E O

( 0)

'-4.5 2.41E 1

(-2.0 -

2.1)E 1

(-2.0 -

2.1)E 1

  • (

0/ 6)*

  • ( 0/ 7)*
  • ( 0/ 7)*

CS-137 ( 13) 180.

(

2.9t

.5)E 2 21

( 7.7 f 1.8)E 2

( 7.7 t 1.81E 2

( 0)

( l.7 -

5.2)E 2

( 2.3 - 15.1)E 2

( 2.3 -

15.!!E 2

  • (

6i 6)*

  • (

7/ 7)*

  • (

7/ 7)*

BA-140 ( 13)

( -8.2t 7.4)E 1 11

(-8.2 t 7.4)E I

(-1.5 t

.6)E 2

( 0)

(-3.2 -

2.0)E 2

(-3.2 -

2.01E 2

(-4.6 -

.1)E 2

  • (

0/ 6)*

  • (

O! 6)*

  • (

0/ 7)*

CE-141 ( 13)

(

l.8t 1.21E 1 21

( 3.1 f 1.9)E 1

( 3.1 t 1.91E I

( 0)

(-1.5 -

5.4)E 1

(-2.1 - 12.5)E 1

(-2.1-12.5)E 1

  • (

0/ 6)*

  • (

0/ 7)*

  • (

0/ 71*

CE-144 ( 13)

( -5.7t 4.4)E 1 21

(-4.9 i 3.5)E I

(-4.9 t 3.5)E I

( 0)

(-1.6 -

1.2)E 2

(-1.5 -

1.4)E 2

(-1.5 -

1.4)E 2

  • (

0/ 6)*

  • (

0/ 71*

  • ( 0/ 7)*

TH-232 ( 13)

(

8.0t

.7)E 2 11

( 8.0 t

.7)E 2

( 5.4 t

.7)E 2

( 0)

( 6.3 - 10.4)E 2

( 6.3 - 10.4)E 2

( 3.4 -

9.2)E 2

  • (

6/ 6)*

  • (

6/ 6)*

  • ( 7/ 7)*
  • NON-fl0VTIE REFERS TO TE NUMBER OF SEPARATE MEASUREENTS WHICH ERE GREATER THAN TEN (10) TIES TE AVERAGE BACX0R0(M) FOR TE PERIOD OF TE REPORT.
    • TE FRACTION OF SAPPLE ANALYSES Y!ELDING DETECTABLE EASLREENTS

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

)*..

3.10 Finfish Fish samples were collected semiannually from two locations.

Each was analyzed for gamma-emitting radionuclides.

Cesium-137 was detected in all but one sample. Over the past several years, the levels have been comparable between Station FH-11 and Station FH-21 fish.

In 1986, the mean of the control samples was about twice that of the indicator samples. These levels are consistent with well-documented environmental levels and are attributed to nuclear weapons testing fallout.

Additionally, Cs-134 was detected in the FH-21 (control) sample taken in October 1986. This is attributable to fallout from the Chernobyl accident discussed in Section 4.

Other than Cs-137, Cs-134, and naturally occurring K-40, no gamma-emitting radionuclides were detected in 1986 fish samples.

I

. 2918R-I

{

EWIRCNENTAL RADIOLCGIC/L PROGRM 9)MMARY YAMCEE 10 CLEAR POWER STATION, RGdE, IM JAf0ARY - DECEMBER 1986 EDILP.: FIEIDI UNITS: PCI/KO WET INDICATOR STATIONS STATION WITH HIGHEST EAN CONTROL STATIONS u n ne n ne n ee n nenneueeenneensee, une****** n e *

  • RADION.CLIDES EAN TAN EAN (NO. ANALYSES) REQUIRED RANGE STA.

RANGE RANGE (NON-ROUTIEl' LLD NO. DETECTEDH NO.

NO. DETECTEDee NO. DETECTEDee E-7

( 4)

( -2.lt 9.4)E i 21

( 3.5 t 2.9)E 1

( 3.5 1 2.9)E 1

( 0)

(-1.2 -

.7!E 2

( 5.7 - 64.5)E 0

( 5.7 - 64.5)E O

  • (

0/ 2)*

  • ( 0/ 2)*
  • ( 0/ 2)*

K-40

( 4)

(

2.7t

.1)E 3

( 2.7 i

.1)E 3

( 2.6 t

.1)E 3

( 0)

( 2.6 -

2.7)E 3

( 2.6 -

2.7)E 3

( 2.5 -

2.7)E 3

  • (

2/ 2),

  • (

2/ 2)e et 2/ 2)*

IW-54 ( 4) 130.

( -2.0t 9.6)E O

(-2.0 t 9.6)E O

(-2.4 t 14.8)E O

( 0)

(-1.2 -

.8)E 1

(-1.2 -

.8)E 1

(-1.7 -

1.2)E 1

  • (

0/ 2)e et 0/ 2)*

  • (

0/ 2),

00-58 ( 4) 130.

( -2.0:

4.2)E 0 11

(-2.0 t 4.2)E 0

(-4.8 t 9.1)E O

( 0)

(-6.2 -

2.2)E 0

(-6.2 -

2.2)E 0

(-1.4 -

.4)E 1

  • (

0/ 2)*

  • (

0/ 216 et 0/ 2)*

FE-59 ( 4) 260.

( -1.52

.0)E 1 21

( 2.8 t

.0)E 1

( 2.8 i

.0)E 1

( 0)

(-1.6 -

-1.5)E 1

( 2.7 -

2.8)E 1

( 2.7 -

2.8)E 1

  • f 0/ 2)*

et 0/ 2)*

  • ( 0/ 2)*

CD-60 ( 4) 130.

( -2.2t

.7)E O 21

( 2.9 i

.9)E O

( 2.9 t 9)E O

( 0)

(-2.9 -

-1.5)E O

( ?.0 -

3.8)E O

( 2.0 -

3.8)E O et 0/ 2)*

  • (

0/ 2)e

  • (

0/ 2)*

ZN-65 ' 4) 260.

(

5.0t 7.4)E O 11

( 5.0 t 7.4)E O

(-1.9 t 14.0)E O

( 0)

(-2,3 - 12.4)E O

(-2.3 -

12.3)E O

(-1.6 -

1.2)E 1

  • (

0/ 2)e et 0/ 2)*

  • (

0/ 2)*

IR-95 ( 4)

( -8.6i 10.4)E 0 21

( !.6 i

.2)E 1

( !.6 t

.2)E 1

( 0)

(-1.9 -

.2)E 1

( !.3 -

1.8)E 1

( 1.3 -

1.8)E 1 et 0/ 2)*

  • (

0/ 2)e

  • ( 0/ 2)*

l l

RU-103 ( 4)

( -4.7k 9.6)E O 21

( 8.5 t 7.7)E 0

( 8.5 t 7.7)E O

( 0)

(-1.4 -

.5)E 1

( 8.6 - 162.0)E -1

( 8.6 - 162.0)E -1

  • (

0/ 2)*

  • (

0/ 2)e

  • ( 0/ 2)*

4

  • NON-ROUTIE REFERS TO TE NUMBER OF SEPARATE EARREENTS WHICH WERE GREATER THAN TEN (10) TIMES TE AVERAGE BACKGROLMD FOR TE PERIOD CF TE REPORT.
    • TE FRACTION OF SAffLE ANALYSES Y!ELDING DETECTABLE EASLREENTS (i.E. )3 STD DEVIATIONS) IS INDICATED WITH et

)*.

Ein!RONMEtRAL RADiCLOGICAL PROCRAM StrMARY vAWEE NUCt.EAP POER STATION. R0WE. MA JANJARY - DE GMBER 1986 EDIUM: FINr1SH UNITS: PCI/KG WET INDICATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONS nu m u m nee **

eneenne**+neneenen e*+eneneenete RADIONln.IIES EAN EAN EAN (NO. ANALYSES) REQUIRED RANCE STA.

RANGE RANGE (NON-ROUTIE)'

LLD NO. DETECTED **

NO.

NO. DETECTEDee NO. DETECTED *n RU-106 ( 4)

( 7.8t 4.5)E 1 11

( 7.8 i 4.5)E I

( 1.5 t 2.8)E 1

( 0)

( 3.4 -

12.3)E 1

( 3.4 - 12.3)E 1

(-1.3 -

4.3)E 1 et 0/ 2)*

e( 0/ 21e et 0/ 2)*

I-131 ( 41

( 5.8t 4.3)E 1 11

( 5.8 i 4.3)E 1

( 2.3 t 3.4)E 1

( 0)

( 1.5 -

10.llE 1

( !.5 - 10.1)E 1

(-1.1 -

5.7)E !

et 0/ 2)*

  • (

0/ 2)e et 0/ 2)e CS-134 ( 4) 130.

( -1.lt

.2)E 1 21

( 2.5 t 17.3)E O

( 2.5 t 17.3)E O

( 0)

(-1.3 -

.8)E 1

(-1.5 -

2.01E 1

(-1.5 -

2.0)E 1

  • (

0/ 2)e

  • (

1/ 2)e

  • (

1/ 2)*

CS-137 ( 4) 150.

(

3.51 1.1)E 1 21

( 7.0 t 1.5)E 1

( 7.0 t 1.5)E I

( 0)

( 2.3 -

4.6)E 1

( 5.5 -

8.5)E 1

( 5.5 -

8.5)E 1 et 1/ 2)*

  • (

2/ 2)*

a( 2/ 2)*

E4-140 ( 4)

I -6.61 7.5)E 1 21

(-3.1 i 3.5)E 1

(-3.1 t 3.5)E I

( 0)

(-1.4 -

.1)E 2

(-6.6 -

.3)E 1

(-6.6 -

.3)E 1

  • (

0/ 2)e

  • (

0/ 2)*

  • (

0/ Ole G-141 ( 4)

( -6.4f 5.5)E 0 21

( 2.3 t

.3)E 1

( 2.3 i

.3)E 1

( 0)

(-1.2 -

.1)E i

( 2.0 -

2.6)E 1

( 2.0 -

2.6tE 1

  • (

0/ 21e

  • (

0/ 2)e

  • (

0/ 2)e CE-144 ( 4)

(

!.2t 1.9)E I 11

( !.2 t 1.9)E I

(-1.6 i 2.9)E 1

( 0)

(-7.0 - 30.9)E O

(-7.0 - 30.9)E O

(-4.4 1.3)E 1

  • (

0/ 2)e

  • (

0/ 21e

  • ( 0/ 2)*

TH-232 ( 4)

(

2.02 3.7)E 1 11

( 2.0 t 3.7)E 1

(-1.8 t 1.2)E 1

( 0)

(-1.8 -

5.7)E 1

(-1.8 -

5.7)E i

(-3.0 -

.6)E 1

  • ( 0/ 2)*
  • ( 0/ 2)*
  • (

0/ 2)e 1

e NON-ROUTIE REFERS TO M NUMBER OF SEPARATE EASUREENTS WHICH ERE OREATER TieN TEN (10) TIES TE AVERAGE BACKGROUND FOR M PERIOD OF M REPORT.

n M FRACTION OF SAtFLE ANALYSES Y!ELDING DETECTABLE EASUREENTS

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

1*.,

3.11 Direct Radiation Direct gaama radiation exposure was determined from the use of thermoluminescent dosimeters (TLDs). One CaSO @ m -

4 dosimeter was placed'at each of the monitoring stations.. (Esch dosimeter has 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 f rom 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 1986, all TLDs were routinely readout on a quarterly schedule. Table 3.1 provides a summary of the results.

The results for 1986 are not significantly different than those in previous years. This can be seen in the data summary table, Figures 3.7 to 3.12, and Table 3.1.

During 1986, 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 3.7 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 l-fenceline TLDs, since the plant contribution to radiation levels

(

at these sites tends to obscure seasonal fluctuations in the i

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

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

Figure 3.7.

This is consistent with the results of the in situ analysis at the station performed in October of 1984.

, 2918R l

As can be seen in Figure 3.11, elevated exposure rates were noted at several on-site locations during the first quarter of 1981.

During that period, correction factors were determined for each TLD by calibration. The corrected values are shown in the figure.

Ion chamber surveys conducted during shutdown in the second quarter of 1981 at those locations did not identify any cause for the anomalous measurements. Neither was deposition indicated by air sampling and measurements of terrestrial media. Furthermore, fission gas releases for the period did not correlate with the increased TLD measurements.

It is suspected that the badges or the TLD reader itself may have caused erroneous measurements since a number of reader and badge problems were encountered and dealt with during 1980 and 1981.

Missing TLDs: The following measurements were missing due to apparent theft in the field or destruction by wildlife:

a.

GM-17, fourth quarter; b.

GM-33, second quarter; GM-34, approximately first two months of third quarter c.

(replaced during last month of third quarter);

l d.

GM-34, fourth quarter.

1 In the latter three cases, the TLDs were at outer ring-incident response stations where readout is not required (unless a gaseous release LCO was exceeded during the period). 2918R

FIGURE 3.7 EXPOSURE RATE RT INDICRTOR TLOS, GM 01-07 YRNKEE RTOMIC ELECTRIC COMPANY, ROWE, MR 20 te-0 - GM-01 FURLON HOUSE o - GM-02 OBSERVATION STANO a - GM-03 R0WE SCHOOL

+ - GM-04 HARRIMAN STRION is-X - GM-OS MONROE BRIDGE o - GM-06 REROSBORO RO. BARRIER v - GM-07 HHITINGHAM LINE 1e_

12 -

21

' 10-

?

i g

j S

s-r 6-4-

2-0 1976 1977 1970 1979 1980 1981 1982 1983 1984 1985 1986

FIGURE 3.8 EXPOSURE RATE AT INDICATOR TLOS, GM 08-12,40 YRNKEE ATOMIC ELECTRIC COMP 8NY, ROWE, MR 20 3'~

O - GM-08 MONROE HILL BARRIER o - GM-09 DUNBAR BROOK a - GM-10 CROSS R080 1s-

+ - GM-11 RDBMS HIGH LINE l

X - GM-12 REBOSBORD, VT I

o - GM-40 RE80S80R0 R080 11-12-

!sA 10-Y I'

og..

=

s-4-

2-0 1977 1978 1979 1980 1981 1982 1983 1981 1985 1986

FIGURE 3.9 EXPOSURE RATE RT GUTER RING TLDS, GM 24-31 YBNKEE RTOMIC ELECTRIC COMPRNY, ROWE, MR m

~

D - GM-21 HRRRIMRN DRM o - GM-25 WHITINGHRM, VT a - GM-26 S8DOGA ROAD 16 -

+ - GM-27 NtJMBER 9 ROAD X - GM-28 NUMBER 9 R08D o - GM-29 ROUTE 88 V - GM-30 ROUTE 88 1s-m - GM-31 LEGRTE HILL R000 5g 12 -

w a:

6-2-

0 i

i ii 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986

FIGURE 3.10 EXPOSURE RATE AT GUTER RING TLDS, GM 32-39 Y8NKEE STOMIC ELECTRIC COMP 8NY, ROWE, MA m

O - GM-32 ROWE RTO o - GM-33 ZOAR ROAD A - GM-34 FIFE BROOK ROAD l

ts -

+ - GM-35 WHITCOMB SUMMIT l

l X - GM-36 TILDR ROAD l

0 - GM-37 TURNER HILL RORD V - GM-38 WEST HILL ROAD te-E - GM-39 ROUTE 100 i

f 12-s i

Y E

g s-

)

1 6-4-

2-0 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986

(

FIGURE 3.11 EXPOSURE RRTE RT FENCELINE TLOS, GM 13-21 YRNKEE RTOMIC ELECTRIC COMPRNY, ROWE, MR so 0 - GM-13 HSW 0.08 KM ss-o - GM-14 W?M 0.11 KM a - GM-IS NNW 0.08 KM

+ - GM-16 NNE 0.13 KM so -

X - GM-17 ENE 0.14 KM o - GM-18 ESE 0.14 KM

$5 -

V - GM-19 SE 0.16 KM a - GM-20 SSE 0.16 KM M - GM-21 SSW 0.11 KM 40 -

5 T

2 35 -

$ w_

l T

$ 2s-l E

i 1

1 20 -

4"

[

is -

)

10-5-

0 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986

FIGURE 3.12 EXPOSURE RATE AT CONTROL TLOS, GM 22-23 YRNKEE RTOMIC ELECTRIC COMPRNY, ROWE, MR mo 38' O - Grt-22 HE N THELLVILLE, VT o - GM-23 WILLIArtSTOWN SUBSTFITION 1s-11-E p

g 12-5 Q-10-a:

)

a e-x:

6-t-

2-0 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986

Environmental Radiological Program Summary Yankee Nuclear Power Station, Rowe, Massachusetts p

January - December 1986 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.)*

8.5 9.3 17.7 9.0 6.2 - 11.4 6.3 - 12.5 11.8 - 26.5 7.3 - 10.6 (52)

(62)

(36)

(8)

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

  • 2918R

Table 3.1 Yankee Atomic Summary of Direct Radiation Measurements - 1986 Micro-R Micro-R Station Per Hour

  • Station Per Hour
  • 1 8.9 21 17.6 2

8.8 22 8.7 3

6.9 23 9.2 4

7.7 24 11.3 5

10.2 25 8.3 6

9.3 26 9.2 7

7.6 27 7.9 8

8.6 28 10.1 9

8.7 29 7.4 10 7.2 30 8.9 11 9.0 31 8.8 12 9.5 32 8.7 13 19.0 33 8.3**

14 13.8 34 9.9**

15 14.3 35 9.2 16 15.1 36 9.5 17 15.1**

37 9.8 18 25.7 38 10.3 19 21.7 39 10.7 20 17.3 40 8.5

  • Annual mean.
    • Mean based on data from three quarters only. One quarter's data lost due to missing or destroyed TLD, as discussed in text. 2918R

4.0 ENVIRONMENTAL RADIOACTIVITY FROM THE CHERNOBYL ACCIDENT Following the Chernobyl nuclear plant accident, increased levels of fission-related radionuclides were measured in fresh fallout throughout much of the northern hemisphere, including New England. The amount and type of radioactivity seen in this fallout were roughly comparable to that observed in fallout from the most recent atmospheric nuclear weapons tests conducted by the Peoples' Republic of China during the late 1970's and in 1980.

Chernobyl-related f allout was seen during 1986 in many types of environmental samples, both near the nuclear power plants and at distant control locations, including the Yankee Atomic Environmental Laboratory in Westborough, Massachusetts. An in-depth discussion of this entire subject may be found in Reference 2.

This section of this report contains a brief summary of the measured radiological environmental impact in northern New England during 1986 f rom the Chernobyl accident. Selected monitoring results from several of the plants in New England have been compiled for this summary.

Many of the measurements were previously reported to the Nuclear Regulatory Commission (via telephone) in response to a request in IE Information Notice 86-32 (Reference 3).

Airborne radioactivity levels measured by gross-beta analysis (see Figure 4.1) show a marked increase during the first week in May. Although the magnitude of the measured concentrations varied slightly across New England, the curves were virtually identical. Very evident in the curves are the first Chernobyl release, measured during the first week of May, and the second release, measured during the last week of May and the first week of June.

Several radionuclides were identified on air particulate filters by gamma spectroscopy. These were Cs-134, Cs-137, and Ru-103. Ruthenium-106 was also detected at one location at this same time. They are shown in Figures 4.2, 4.3, and 4.4, respectively.

Iodine-131 was detected on charcoal filters at all monitoring stations.

Its curve, shown in Figure 4.5, is similar to that for gross-beta measurements for air particulate filters.

Several radionuclides were detected in milk samples shortly after their detection on air particulate or charcoal filters. These were Cs-134 Cs-137, 2918R

cnd I-131. Since the deposition of this radioactivity occurred after the start of pasture season (for those cows that are pastured), it was incorporated into the milk pathway readily. Due to its short half-life (8 days), the I-131 was not very persistent in the environment, however (see Figure 4.8).

Cesium-137 has for many years been detected in cow milk from many locations around New England and the world as a result of the nuclear weapons tests in the 1970's and in 1980. Cesium-137 levels (see Figure 4.7) at most locations increased during May due partly to the start of the pasture season (if applicable) and the consequent re-introduction of old Cs-137 into the food chain, and partly due to an increase of Cs-137 levels on pasture vegetation from Chernobyl-related fallout. Cesium-134 is entirely attributable to Chernobyl, since its relatively short (2 years) half-life has effectively removed any left over from previous weapons testing fallout. A Cs-137/Cs-134 ratio of approximately 2.0 was noted on air particulate filters, and as one would expect to follow, in milk. The virtual absence of Sr-89 or Sr-90 in the fallout was notable. This was due to the small amount of strontium released during the accident.

Unlike the gross-beta on air particulate f11ters and I-131 on charcoal filters, the Cs-134. Cs-137, and I-131 levels in milk varied considerably from location to location due to differences in farming practices. Specifically, types of vegetation fed on by cows and the amount of stored feed given them, as well as localized differences in deposition of fallout and many other less important factors, have a marked effect on the levels of radioactivity in milk. With respect to milk samples in the winter of 1986/1987, it is expected that the Cs-134 and Cs-137 levels might increase at some locations during the winter months when cows are given feed that was contaminated by fallout during the spring of 1986. Figures 4.6 and 4.7 show some early evidence of this during the fall of 1986 at several locations.

As one would expect, fallout from Chernobyl was measured in other environmental media such as precipitation and vegetation. Measurements for selected radionuclides in precipitation are shown in Table 4.1 and 4.2 for the Yankee Atomic Environmental Laboratory and the EPA ERAMS Netsors, respectively. 2918R

Table 4.1 Chernobyl-Related Radioactivity in Precipitation Yankee Atomic Environmental Laboratory. Westborough. Massachusetts (pCi/kg i one standard deviation)

Collection Rainfall Period (1986)

Cs-134 Cs-137 Ru-103 I-131 (inches)

May 7-9

(-0.3 2 1.4)

(0.9 2 1.4)

(-1.5 1 1.3) 20.4 2.8

.13 May 12 6.9 2 0.3 12.6 2 1.4 15.4 1 1.6 472 1 5

.027 May 17 6.1 1 1.1 11.9 ! 1.2 11.4 1 1.2 68.4 2.2

.31 May 21-22

(-0.6 ! 0.5) 1.7 i 0.4 (0.1 1 0.4) 8.9 1 0.6

.06 May 23-25 2.1 1 0.6 5.0 ! 0.9 9.1 1 1.1 49.6 2 3.4

.79 May 30-June 1 2.5 1 0.5 7.3 2 0.8 6.6 1 0.8 14.8 1 1.4

.74 June 5-8

(-1.6 2 0.9) 1.9 1 0.6 (0.8 2 0.8)

(0.6 1.2) 5.10 June 11-13 (2.7 t 1.0)

(0.4 2 1.2)

(-0.3 1.2)

(3.0 2 1.7) 1.16 June 22-24

(-1.0 1 1.3)

(2.2 2 1.3)

(-2.3 2 2.0)

(-6.0 i 14.)

.07 July 2

(-0.5 ! 0.8)

(1.1 3 0.8)

(0.1 1 1.1)

(1.3 ! 8.7) 1.79 Measurements in parentheses indicate radionuclide was not detectable at the three-sigma level. 2918R

Table 4.2*

fodine-131 In Precipitation EPA ERAMS Network Date Montpelier. Vermont Concord, New Hampshire (1986) pCi/ liter pCi/m pCi/ liter pC i /rn, May 2 ND ND ND h3 May 5 ND ND ND ND May 6 ND ND ND h3 May 7 120 480 May 8 ND ND 63 20 May 9 ND ND 33 99 May 11 1,660 12.300 May 12 870 1.740 May 13 53 14 May 17 93 750 160 130 May 19 57 230 May 20 May 21 May 22 13 78 May 23 14 430 ND hT May 24 29 161 May 25 18 240 May 28 ND ND 80 11 June 2 ND ND ND ND 2

TOTAL 15,930 pCi/m TOTAL 803 pCi/m

  • Taken from Table 20 of Reference 2. 2918R

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5.0 QUALITY ASSURANCE PROGRAM Three separate Quality Assurance programs were performed during 1986 to 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 measures are taken, as appropriate.

YAEL maintains an intralaboratory quality control program to assure the validity and reliability of the data.

This program includes quality control of laboratory equipment, use of reference standards for calibration, and analysis of blank and spiked samples. The records of the quality control program are reviewed by the responsible cognizant individual, and corrective measures are taken whenever applicable.

A blind duplicate 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.

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 1986 for intrataboratory analyses and EPA interlaboratory cross-check analyses.

For accuracy, 66.4 and 88.5 percent of the results were within 5 and 10 percent of the known values, respectively, with 96.8 percent of all results falling within the laboratory criteria of 15 percent.

For precision, 85.9 and 96.0 percent of the results were within S and 10 percent of the mean, respectively, with 100 percent of all results meeting the laboratory criteria of 15 percent. 2918R

Table 5.1 Intralaboratory and EPA Interlaboratory Results - 1986 Accuracy Total Number 0 to 51 0 to 10%

0 to 15%*

of Measurements 840 558 743 813 (66.4%)

(88.5%)

(96.8%)

Precision Total Number 0 to 51 0 to 101 0 to 15%*

of Measurements 815 700 782 815 (85.9%)

(96.0%)

(100%)

  • This category also contains those samples having a verified r.oro concentration which were analysed and found not to contain the isotope of interest. 2918R

i The results of the EPA Interlaboratory Comparison program, when considered apart f rom the remainder of the Quality Assurance program, were satisfactory with respect to accuracy and precision in 1986. Two hundred and twenty-two analyses were performed on air particulate filters, milk, and water. Of these 222 analyses, 15 were not included in the overall summary of accuracy statistica due to what the Yankee Atomic Environmental Laboratory considers questionable media. The analyses in question represent four sets of samples, all of which are considered questionable from the standpoint of EPA preparation and known-value calculation. These cases are documented in References 4 and 5.

Based upon the corrected sample analysis total (i.e.,

207), 206 analyses (i.e., 99.5 percent) met the EPA's definition of mean value criteria. The single sample analysis that did not meet the criteria was a Ru-106 analysis in a water sample. A recount of the sample yielded a measurement that met the above criteria.

(Details of this may be found in Reference 5.)

Blind Duplicate Progry A total of 55 paired samples were submitted by the five participating plants for analysis during 1986. 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 1-131 and gross beta. A dual level criteria for agrcement was established.

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

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

If the ranges overlap, agreement is obtained.

One thousand three hundred and sixty-four paired duplicate measurements were analysed for 1986. A total of 99.1 percent of all measurements fell within the established criteria discussed above. The twelve measurements that did not meet the criteria were measurements of 2n-65 in milk Mo-99 in milk, C0-58 in allk, Mn-54 in seawater, co-141 in seawater, Ba-140 in seawater, Zr-95 in seawater So-75 in mussel bodies, Co-57 in milk, Ru-103 in groundwater, Ba-140 in milk, and K-40 in Irish mosa.

In all but the last 291HR

case, the radionuclide in question was not detected in the sample and a three standard deviation acceptance criteria was met.

In the last case, the reason for the erroneous K-40 concentration was ascertained, and the data was corrected. The twelve duplicate measurements represent 0.9 percent of all the blind duplicate paired measurements made during 1986. No trend was evident with respect to repeated failings of measurements for the above radionuclides.

74 2918R

6.0 LAID USE CENSUS 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 cixteen meteorological sectors within a distance of five miles. The 1986 census was completed within the above dates. The distance from the plant for each of the above locations is shown in Table 6.1.

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 samples are currently being obtained in accordance with Technical Specification 3.12.1.

Specifically, such milk animal locations were found at WNW, 1.9 km and NE, 3.7 km.

Neither location, however, would be able to provide samples of sufficient size over an extended period due to the small number of allking cows owned. Consequently, the two existing locations, TM-12 and TM-13, were kept as official sampling locations (see Technical Specification 3.12.2.b).

With respect to food crop sampling locations, Station TF-13, Monroe, was added to the program based on the above dosimetric criterion.

Station TF-12, Ford Hill Road, was deleted from the program following October 31, 1986, pursuant to Technical Specification 3.12.2.b.

Following the census Technical Specification 3.12.2.a requires the identification in the Semi-Annual Effluent Release Report of any location (s) which yle1ds 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

1 Table 6.1 Yankee Atomic 1986 Land Use Census Results Nearest Nearest Nearest Residence Milk Animal Garden Sector (km)

(km)

(km)

N 2.4 6.1 3.5 NNE 4.7 4.7 NE 3.7 3.7 3.7 ENE 3.1 8.4 3.1 3.1 E

3.1 3.4 ESE 3.4 2.3 SE 2.3 2.1 SSE 2.1 S

2.3 2.9 SSW SW 1.3 1.3 1.3 WSW 1.3 2.7 W

1.9 WNW 1.9 1.9 1.9 NW 0.45 4.6 3.9 NNW 2.9

- 2918R m

7.0

SUMMARY

During 1986, samples collected as part of the radiological environmental monicoring program at Yankee Atomic showed detectable levels of man-made radionuclides in air particulate and charcoal filters, cow milk, groundwater, river water, sediment, finfish, and maple syrup. The H-3 detected in groundwater (Station WG-12, Sherman Spring) and river water (Station WR-il, Bear Swamp Lower Reservoir) was the only radionuclide 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 quantities 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 groundwaters), the dose to man was negligible when compared to natural background radiation and its yearly fluctuations.

The other man-made radionuclides were due to either fallout 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 impact on the environment f rom plant operations. 2918R

8.0 REFERENCES

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 I," 1977.

2.

S. Farber, " Evaluation of Ei.vironmental Radioactivity Resulting from the Chernobyl Accident Measured by the Yankee Atomic Electric Company Environmental Laboratory," Yankee Atomic Electric Company, March 26, 1987.

3.

USNRC IE Information Notice 86-32, " Request for Collection of Licensee Radioactivity Measurements Attributed to the Chernobyl Nuclear Plant Accident," dated May 2,1986.

4.

Yankee Environmental Radiation Measurement Laboratory Quarterly Status Report, April-June 1986, Yankee Atomic Electric Company.

5.

Yankee Environmental Radiation Measurement Laboratory Quarterly Status Report October-December 1986, Yankee Atomic Electric Company. 2918R

l Telephone (617) 872-8100 TWX 710-380u7619 YANKEE ATOMIC ELECTRIC COMPANY

' ff

. d$'

1671 Worcester Road, Framingham, Massachusetts 01701

' YANKEE.

%. /

April 30, 1987 FYR 87 -46 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

References:

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

Subject:

Annual Radiological Environmental Operating Report

Dear Sir:

Enclosed heredith please find the Annual Radiological Environmental Monitoring Report for the Yankee Nuclear Power Station. This report contains a sumcary and analysis of the radiological environmental data collected for the year 1986 and is submitted as required by Technical Specification 6.9 5(a).

He trust that you will find this submittal satisfactory; ho.tever, if you have any questions, please contact us.

Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY Georg Papanic, Senior Project Engineer - Licensing GP/gbc Eaclosures cc: USNRC Region I USNRC Resident Inspector, YNPS

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