Text

Annual Radiological Environ Monitoring Rept,1984
	ML20128D106
Person / Time
Site:	Yankee Rowe
Issue date:	12/31/1984
From:	Kay J; YANKEE ATOMIC ELECTRIC CO.
To:	Murley T; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
	FYR-85-50, NUDOCS 8505280500
	Download: ML20128D106 (67)
	v • d • e

_ _ _ _ _ - _ _ _ _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _

s i

~ YANKEE ATOMIC ELECTRIC COMPANY ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT i

January 1984 - December 1984 April 1985 Prepared By:

Yankea Atomic Electric Company Environmental Engineering Department 1671 Worcester Road Framingham, Massachusetts 10701 DR R

TABLE OF CONTENTS Page u

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

r l

iv I

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

1

1.0 INTRODUCTION

2 2.0 ENVIRONMENTAL MONITORING PR0 GRAM..................................

-3.0

SUMMARY

OF 1984 ENVIRONMENTAL DATA................................

14 17 A.

Air Particulate...............................................

21 B.

Charcoal Filter...............................................

23 C.

Milk..........................................................

28 D.

Food Crop.....................................................

31 E.

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

33 F.

Maple Syrup...................................................

36 C.

Ground Water..................................................

39 H.

River Water...................................................

42 1.

Sediment......................................................

45 J.

Finfish.......................................................

48 K.

Direct Radiation..............................................

51 L.

So11..........................................................

54 4.0 QUALITY ASSURANCE PR0 GRAM.........................................

58 5.0 LAND USE CENSUS...................................................

60 6.0

SUMMARY

61 REFERENCES........................................................

_ii.

LIST OF TABLES pueber Title Pm i

2.1 Yankee Atomic Radiological Environmental Monitoring Pro 5 ram....................................................

3

~

2.2 Yankee Atomic Radiological Environmental Monitoring Locations...................................................

4 3.1 Yankee Atomic Summary of Direct Radiation Measurements, 1984..........................................

50 f

3.2 Sununary of In Situ Soil Analyses - Exposure Rate............

52 3.3 Sunanary of In Situ Soil Analyses - Concentration............

53 4.1 EPA Interlaboratory and Intralaboratory Results.............

55 5.1 1984 Land Use Census Results................................

59

)

-lii-

r LIST OF FIGURES l

Number Title Page_

L 2.1 Yankee Plant Radiological Environmental Monitoring Locations Within 1 Mile (Airborne, Waterborne, and r

(

Ingestion Pathways).........................................

7 2.2 Yankee Plant Radiological Environmental Monitoring Locations Within 12 Miles (Airborne, Waterborne, and Ingestion Pathways).........................................

8 2.3 Yankee Plant Radiological Environmental Monitoring f

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

9 2.4 Yankee Plant Radiological Environmental Monitoring Locations at the Restricted Area Fence (Direct Radiation Pathway)...........................................

10 2.5 Yankee Plant Radiological Environmental Monitoring Locations Within 1 Mile (Direct Radiation Pathway)...........

11 2.6 Yankee Plant Radiological Environmental Monitoring Locations Within 12 Miles (Direct Radiation Pathway).........

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

13 3.1 Cross Beta Measurements of Air Particulate Filters at Yankee Atomic................................................

18 3.2 Cesium-137 in Cow Milk at Yankee Atomic......................

24 3.3 Strontium-90 in Cow Milk at Yankee Atomic....................

25

-iv-

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1.0 INTRODUCTION

The radiological environmental surveillance program at Yankee Atomic s -

has been designed and carried out with specific objectives in mind. They are I

as 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 an estimate of actual radiation exposure to the i

surrounding population.

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 1984, as in the past, the plant staff collected the bulk of the environmental samples and processad all environmental thermoluminescent dosimeters (TLDs) for direct radiation measurements. After the initial processing, all non-TLD samples were sent to the Yankee Atomic Environmental Laboratory in Westboro, Massachusetts for further processing and radionuclide analysis.

This report is a sunsery of the findings of the Radiological Environmental Surveillance Program for 1984. It is being provided in compliance with plant Technical specification 6.9.5.a.

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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 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.

(

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

AP Air Particulate CF Charcoal Filter TM Milk WG Ground Water WR River Water TF Food Crop i

TV Broad Leaf Vegetation

)

MS Maple Syrup SE Sediment FH Finfish GM Direct Radiation (TLD)

TS Soil

Table 2.1 Yankee Atomic Radiological Environmental Monitorint program Media Samplint Frequency Required Analyses k

Air Particulate (AP)

- Weekly Gross beta

- Quarterly Composite Gamma spectroscopy Charcoal Filter (CF)

- Weekly I-131 f

- Monthly; once per Gama spectroscopy, Milk (TM) 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 Ground Water (WG)

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

- Monthly (Composite)

Gross beta, Cama spectroscopy, i

I-131

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- Quarterly Composite H-3 Sediment (SE)

- Semiannually Gamma spectroscopy Finfish (FH)

- Seasonal or Gama spectroscopy Semiannually Direct Radiation (GM)

- Quarterly De-dose only (Outer ring TLDs)

- Quarterly Intergrated gamma (All other TLDs) dose 9.. _.

T:

Trbin 2.2 s

Yankee Atomic Radiological Environmental Monitoring Locations e

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

Description Zone *

(km)

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-21 Williamstown, MA 2

21.0 WSW TF-11 Monroe Bridge 1

1.3 SW TF-12 Rowe, MA 1

3.5 E

TF-21 Williamstown, MA 2

21.0 WSW TF-32**

Harriman Station 1

3.2 N

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-12 Harriman Reservoir 2

10.1 Upriver SE-11 No. 4 Station 1

36.2 Downriver SE-21 Harriman Reservoir 2

10.1 Upriver

. 1

___ _a

Table 2.2 (continued)

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

Description Zone *

(km)

Plant FH-11 Sherman Pond 1

1.5 W

FH-21 Harriman Reservoir 2

10.1 Upriver GM-1 Furlon House NA 0.8 SW i

GM-2 Observation Stand NA 0.5 NW GM-3 Rowe School NA 4.2 SE GM-4 Harriman Station NA 3.2 N

GM-5 Monroe Bridge NA 1.1 SW GM-6 Readsboro Road Barrier NA 1.3 N

GM-7 Whitingham Line NA 3.5 NE GM-8 Monroe Hill Barrier NA 1.d S

GM-9 Dunbar Brook NA J.2 SW i

GM-10

_ Cross Road NA 3.5 E

GM-11 Adams High Line NA 2.1 WNW GM-12 Readsboro, VT NA 5.5 NNW GM-13 Restricted Area Fence NA 0.08 WSW GM-14 Restricted Area Fence NA 0.11 WNW GM-15 Restricted Area Fence NA 0.08 NNW GM-16 Restricted Area Fence NA 0.13 NNE GM-17 Restricted Area Fence NA 0.14 ENE GM-18 Restricted Area Fence NA 0.14 ESE CM-19 Restricted Area Fence NA 0.16 SE GM-20 Restricted Area Fence NA 0.16 SSE GM-21 Restricted Area Fence NA 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 CM-27 Number 9 Road 0

7.6 ENE GM-28 Number 9 Road 0

6.0 E

GM-29 Route 8A 0

8.2 ESE Trbin 2.2 (continued)

Yankee Atomic Radiological Environmental Monitoring Locations s

N Distance I

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

Descriction Zone *

(km)

Plant 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 O

6.4 SW GM-35 Whitcomb Summit 0

8.6 WSW GM-36 Tilda Road 0

6.6 W

GM-37 Turner Hill Road O

6.7 WNW GM-38 West Hill Road O

6.6 NW GM-39 Route 100 0

6.8 NW GM-40 Readsboro NA 0.5 W

TS-Ol**

Furlon House 1

0.8 SW TS-02**

Monroe Bridge, MA 1

1.1 SW TS-03**

Observation Stand 1

0.5 NW TS-04**

Williamstown, MA 2

22.2 W

TS-05**

Heartwellville, VT 2

12.6 NNW~

TS-06**

Harriman Station 1

3.2 N

TS-07**

Rowe School 1

4.2 SE

1 = Indicator Stations; 2 = Control Stations; O = e. iter Ring Incident Response TLD; NA = Not Applicable.

Not required by Radiological Effluent Technical Specifications.

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

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L 3.0

SUMMARY

OF 1984 ENVIRONMENTAL DATA The following pages summarize the analytical results of all the environmental samples which were collected during 1984. Each environmental media category is presented as a separate subsection. A discussion of the sampling program and results is followed by a table which summarizes the year's data for each category. 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 f

which is being reported, total number of analyses of that radionuclide, and the number of measurements which exceeds ten times the yearly average background value. The latter are classified as "non-routine" 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.

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

These 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.

ERMAP calculates a set of statistical parameters for each radionuclide. This set of statistical parameters includes separate analyses for (1) the indicator stations, (2) the control stations, and (3) the station having the highest annual mean concentration. For each of these three groups of data ERMAP calculates:

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

o The square root of the mean square deviation. This is an estimate of the sample variance, o

The lowest and highest calculated 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 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.

Expressed in another way, the measurement is considered to be statistically different than normal instrument background when the plus or minus three standard deviation range surrounding the measurement does not include zero.

Direct radiation measurements from thermoluminescent dosimeters are discussed in Section 3.M.

During 1984, two environmental analyses did not meet their required LLDs. A burned out motor on an air sampling pump at Control Station AP/CF-21 during the week ending August 14, 1984 resulted in a total week's sample volume of 22 cubic meters. The low volume prevented the required LLDs for the air particulate filter (gross beta analysis) and its companion charcoal filter (I-131 analysis) from being reached.

A circuit breaker trip at Control Station AP/CF-21 resulted in a low sample volume of 197 cubic meters during the week ending May 1, 1984. The required LLDs for the air particulate and charcoal filters were achieved, however.

The required LLD for one non-environmental sample was not met as follows. On November 27,, 1984, the Yankee plant initiated a load reduction to affect boiler feed pump repairs. The rate of load reduction exceeded 15% of rated thermal power in one hour. Required sampling of plant systems was initiated in accordance with Technical Specifications 4.4.7 and 4.11.2.1.2 (Table 4.11-2, Notes c and d).

The results of the analysis required under 4.4.7 indicated that sampling and analysis under 4.11.2.1.2 were not - - -

required. However, the completed sampling produced a charcoal sample for I-131 of one-hour duration resulting in a lower limit of detection of 3E-11 uCi/mL versus the required IE-11 uCi/mL.

L e

The small sample size obtained was a function of using the PVS back-up sampling system to obtain the samples. At that point in time, the back-up system was in use as the primary sample system due to changes to the PVS monitoring system under EDCR 84-314.

Thus, the I-131 charcoal sample was a portion of the continuous sampling required under Table 4.11-2 and subject to f

the LLD requirement. The short duration of the sampling (approximately one hour) resulted in a low sample volume (mLs) and thus an increased LLD.

Please note that, this LLD was achieved only for that one-hour span of time. The required LLDs were achieved for the sampling periods before and after the one-hour period.

During the fourth quarter, the TLD badge at Station GM-9, Dunbar Brook, was apparently stolen. The annual average exposure rate, as reported in Table 3-1, is based on data from the first three calendar quarters only.

l

A) Air Particulate Air monitoring stations are established st a total of'seven locations, five of which are required by the Radiological Effluent Technical specifications. The air pumps at these locations operate I

continuously at a flow rate of approximately one cubic foot per minute. Airborne particulates are collected by passing the air f

'through a 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 ganuna-emitting radionuclides.

Gross-beta analyses (Figure 3.1) show random fluctuations at all sampling locations including controls, thereby indicating that any

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

4 - - - _ _ - ___ _ _ _ ____ _ _ ____ _ _________ - _ __-- ______-_______ __________ _ _________ _ ______

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FIGURE 3 i GROSS BETR MERSUREMENTS OF RIR PRRTICULRTE FILTERS YANKEE RTOMIC ELECTRIC COMPANY, ROWE, NR c.cs i

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e u esseee w eee+eee e++eeeeeeeeeeeeu weew ee weteveeeeeenee RADIONJCLIDES EAN EAN EAN (NO. ANALYSES) REQUIRED RANGE STA. RANGE RANGE (NON-ROUTIEle LLD NO. DETECTEDee E.

NO. DETECTEDee M). DETECTEDee (R-B (364)

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NON-ROUTIE REFERS TO TE MNER OF SEPARATE EASLREENTS leilDI ERE GREATER THM TEN (10) TIES TE AVERAE FLACK 0ROUND FOR TE PERIOD OF TE REPORT.

ee TE FRACTION OF SAffLE ANALYSES YIELDING DETECTABLE EASLREENTS (J.E. >3 STD DEVIATIONS) IS INDICATED WITH et H.

ENVIR0pfENTAL RADIOLOGICAL PROGRAM SurmARY YA*EE itCLEAR POER STATION. ROE. MA eftJARY - DECEPSER 1984 EDILM: AIR PARTICtLATE (MITS: PCI/CU. M IISICATOR STATIONS STATION NITH HIGEST EAN CONTROL STATIONS 444*HHe*4HeteH

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NO.

NO. DETECTED 64 NO. DETECTED *4 RU-103 ( 28)

(-1.3 1 2.6)E -5 32 ( 7.2 1 3.8)E -5

( 5.8 1 30.9)E -6

( 0)

(-3.0 -

2.0)E -4

(-8.9 - 170.0)E -6

(-2.0 -

1.7)E -4 et 0/ 20)s et 0/ 4)*

et 0/ 8)*

RU-106 ( 28)

(-3.4 1 2.1)E -4 13 ( 3.5 i 2.9)E -4

(-7.5 1 4.3)E -4

( 0)

(-2.4 -

1.4)E -3

(-3.7 - 10.0)E -4

(-3.0 -

.9)E -3

(

0/ 20)*

(

0/ 4)e

( 0/ 8)*

CS-134 ( 28)

.05

(-4.6 i 2.6)E -5 12

(-1.3

8.4)E -5

(-8.4 1 5.1)E -5

( 0) -

(-2.7 -

2.3)E -4

(-1.2 -

2.3)E -4

(-2.6 -

2.0)E -4

(

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

( 0/ 8)e CS-137 ( 28)

.06

( 5.3 1 2.6)E -5 14 ( 1.4 i

.5)E -4

(-3.5 1 2.7)E -5

( 0)

(-2.1 -

2.4)E -4

( 3.0 - 23.6)E -5

(-1.2 -

.8)E -4 e( 0/ 20)*

e( 0/ 4)*

et 0/ 8)e B&l40 ( 28)

(-1.4 1 1.0)E -4 13

(-1.6 i 8.1)E -5

(-3.2 1 1.3)E -4

( 0)

(-8.0 - 12.5)E -4

(-2.0 -

1.5)E -4

(-8.2 -

2.1)E -4 et 0/ 20)e

( 0/ 4)*

et 0/ 8)*

E-141 ( 28)

( 6.0 1 4.4)E -5 12 ( !.5 i 1.3)E -4

( 2.4 i 8.8)E -5

( 0)

(-2.7 -

4.9)E -4

(-1.2 -

4.9)E -4

(-3.1 -

5.1)E -4 et 0/ 20)e el 0/ 4)e e( 0/ 818 E-144 ( 28)

( 6.1 i 10.5)E -5 31

( 4.8 i 1.7)E -4

( !.8 i 1.5)E -4

( 0)

(-8.2 -

8.5)E -4

( !.4 -

8.5)E -4

(-2.7 -

9.1)E -4 et 0/ 20)e ef 0/ 4)e

( 0/ 8)*

TM-232 ( 28)

( 6.9 i 8.01E -5 21 ( 6.4 t 1.9)E -4

( 4.1 1 1.4)E -4

( 0)

(-7.3 -

9.5)E -4

( 2.0 - 10.4)E -4

(-1.2 - 10.4)E -4 e( 0/ 20)e et 0/ 4)*

(

0/ Ole e NON40UTIE REFERS TO TE MMBER OF SEPARATE EASUREENTS IMIDI ERE GREATER THAN TEN (10) TIES TE AVEPAGE BACKGROUND FOR TE PERIOD OF TE REP (RT.

Se TE FRACTION OF SAlf'LE ANALYSES YlELDING DETECTABLE EASLREENTS (I.E. >3 STD DEVIATIONS) IS INDICATED NITH et le.

B) Charcoal Filters l

Charcoal filter cartridges are situated in series with the air L

particulate 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. Concentrations of I-131 activity in both indicator and control station samples during 1984 were below minimum detectable levels.

l DNIROPffMTAL RADIOLOGICAL PRCRAM SlfmARY YAP 8IE MJCLEAR POER STATION, ROE, MA JAMJARY - ECDEER 1984 EDILM: OtMC0AL FILER tm!TS: PCI/QJ. M IE!CATOR STATIONS STATION WITH HIGEST EAN CONTRG. STATI(MS e*** we+++++++++++

neen*++eeeneun++n*+

e+nenen++ww RADIDMJQ.!KS EAN EAN EAN (NO. ANALYSES) EQUIED RANGE STA. RANGE RANGE (M3H10lfi!Els LLD ND. DETECTEDee NO.

NO. ETECTEDee ND. ETECTEDu I-131 (364)

.07

(-1.5 t

.3)E -3 14

(-1.0 t

.9)E -3

(-2.8 t 1.6)E -3

( 0)

(-4.4 -

1.2)E -2

(-2.7 -

.9)E -2

(-1.6 -

.1)E -1 et 0/260)e

(

0/ 52)*

(

0/104)e

NDH0VIIE REFERS TO TE MISER OF SEPARATE EASlREENTS IMICH ERE GREATER THAN TEN (10) TIES TE AVERAGE BACK0ROUhD FOR TE PERIOD OF TE REPORT.

H TE FRACTION OF SAPFLE ANALYSES YIELDING DETECTABLE EAST.REENTS (I.E. >3 STD DEVIATIONS) IS I E ICATED WITH *(

)*.

C) Milk

(

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

Detectable concentrations of Cs-137 and Sr-90 were measured in milk samples submitted from the indicator and control locations. The mean concentration of Cs-137 and Sr-90 in milk samples from the indicator location was greater by a factor of 12.0 and 3.1, respectively, than from the control location (see Figures 3.2 and 3.3).

The higher concentration in indicator station samples has been noted for several years. It has been shown in previous reports that the radionuclides in the cows' food, particularly pasture grass, are a result of atmospheric nuclear weapons testing fallout, and that farming practices (amount of vegetation and type of vegetation that the cows are allowed to feed on) can cause large variations of Cs-137 and Sr-90 concentrations in milk. Mean concentrations and ranges for the control station and indicator station, for Cs-137 and Sr-90, were similar to those measured for 1983 (Reference 1).

1 cec

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SI EN CO 121 T

112 R

a NNN e

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TTT K

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1111 {

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NU I ME J

F ULI E TNC YR OI 1f RM TO 121 ST 112 R

R NNN P

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TTT K

AAA N

TTT SSS R

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S 1

2 0

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E5gEs dsge' O8 ll,

,lll l

l i!

E)NIROMOTAL RADIOLOGICAL PROGRAM SIMWtY YAM (EE NUCLEAR P0ER STATION, ROE. N4 JAWARY - DECEMBER 1984

(

EDIlm: MILK (MITS: PCI/XG I E ICATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONS g

l

e H H H H H MetM

eHeM*HeHe64**HHMe eeHe***HeHMe RADIOKELIDES EAN EAN EAN (ND. ANALYSES) EQUIRED RAfE STA. RANGE RANGE

{

(IDHIOUTIEle LLD E. DETECTEDee W.

ND. DETECTEDee W. DETCCTEDee SR-89 ( 12)

( 1.2 i 3.0)E -1

( 4.3 i

.8)E -1

( 1.8 i

.4)E -1

( 0)

(-1.3 -

1.4)E 0

( 2.1 -

5.9)E -1

( 9.6 - 27.4)E -2

( 0/ 8)*

( 0/ 4)e et 0/ 4)e SR-90 ( 12)

( 6.5 i 1.1)E 0

( 9.1 i

.9)E O

( 2.1 i

.2)E 0

( 0)

( 2.1 - 11.0)E 0

( 7.2 - 11.0)E 0

( !.8 -

2.5)E 0 et 8/ 8)e et 4/ 4)e et 4/ 4)e E-7

( 57)

(-1.6 i 9.4)E -1 11 ( 3.8 1 15.3)E -1

(-1.6 i 1.3)E 0

( 0)

(-1.0 -

2.1)E 1

(-1.0 -

2.1)E 1

(-1.4 -

.8)E 1 el 0/ 3818

(

0/19)e

(

0/ 19)*

-K-40

( 57)

( 1.3 i

.0)E 3 21

( !.4 i

.0)E 3

( 1.4 i

.0)E 3

( 0)

( !.1 -

1.5)E 3

( !.1 -

1.5)E 3

( !.! -

1.5)E 3

( 38/ 38)*

( 19/ 19)e s( 19/ 1914 196-54 ( 57)

(-8.1 1 11.1)E -2 12 ( 2.7 1 16.7)E -2

( 2.0 i 14.5)E -2

( 0)

(-1.5 -

1.5)E 0

(-1.5 -

1.5)E 0

(-1.1 -

1.0)E O et 0/ 3Ble et 0/ 19)e

(

0/ 19)*

CD-58 ( 57)

(-1.1 i 1.5)E -1 12

(-3.7 i 24.2)E -2

(-3.0 i 1.7)E -1

( 0)

(-2.0 -

1.9)E 0

(-1.7 -

1.9)E 0

(-2.0 -

.8)E O et 0/ 3818

(

0/ 19)e

(

0/ 19)*

FE-59 ( 57)

( 2.7 i 2.9)E -1

!! ( 4.4 1 4.0)E -1

(-2.3 i 5.3)E -1

( 0)

(-3.0 -

4.7)E 0

(-2.2 -

3.6)E 0

(-4.1 -

5.2)E 0

(

0/ 38)e

(

0/ 19)e of 0/ 19)*

CD40 ( 57)

(-1.5 t 1.4)E -1 21 ( 4.1 i 1.7)E -1

( 4.1 i 1.7)E -1

( 0)

(-2.2 -

1.4)E 0

(-8.0 - 21.4)E -1

(-8.0 - 21.4)E -1 el 0/ 38)e et 0/ 19)e

(

0/19)*

2N-65 ( 57)

(-3.6 1 3.7)E -1 12 ( !.21 47.7)E -2

(-3.9 i 6.0)E -1

( 0)

(-9.1 -

3.3)E 0

(-4.4 -

3.3)E 0

(-3.5 -

6.6)E 0 et 0/ 38)e el 0/ 19)*

et 0/19)*

e NDHOUTIE REFERS TO TE NUMBER OF SEPARATE EASLREENTS E!!Di ERE GREATER THAN TEN (10) TIES TE AVERAGE BACK0R0lMD FOR TE PERIOD OF TE REPORT.

- TE FRACTION OF S#PLE ANALYSES YIELDING DETECTABLE EASLREENTS (I.E. >3 STD DEVIATIONS) IS ! $1CATED WITH e(

18.............

E)NIR0 MENTAL MDIOLOGICAL PROGRAM SLfflARY YAREE MJCLEAR POER STATION ROE. MA JAMJARY - DECEleER 1984 EDILM: MILX LMITS: PCI/I(D I EICATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONS

HHet eteHHHH

HeHHtHeHHHHHeH

HHeMeHHeH RADIOMKLIDES EAN LEAN EAN (ND. ANALYSES) EQll! RED RANGE STA. RANGE RAIEE (NDHOUTIE)*

LLD NO. DETECTEDH NO.

M). DETECTED H NO. DETECTEDH ZR-95 ( 57)

( 2.5 1 21.4)E -2 21

( 8.2 1 2.6)E -1 (8.21 2.6)E -1

( 0)

(-2.4 -

3.3)E 0

(-1.2 -

3.5)E 0

(-1.2 -

3.5)E 0 et 0/ 38)*

el 0/ 19)e et 0/ 19)*

RU-103 ( 57)

(-4.6 t 1.3)E -1 11

(-7.9 1 2.3)E -1

(-1.1 i

.2)E 0

( 0)

(-2.2 -

1.9)E 0

(-2.2 -

1.9)E 0

(-2.3 -

.1)E 0

(

0/ 38)e

(

0/ 19)e et 0/ 19)e M1-106 ( 57)

( 7.9 i 12.6)E -1 11

( 1.5 i 1.6)E 0

(-3.6 i 16.4)E -1

( 0)

(-1.3 -'

!.9)E 1

(-9.1 - 16.9)E 0

(-1.1 -

1.0)E 1

(

0/ 38)e et 0/ 19)e

(

0/ 19)e I-131 ( 57) 1.

I 5.5 1 5.3)E -3 21 ( 1.1 i

.6)E -2

( !.1 i

.6)E -2

( 0)

(-4.8 -

9.4)E -2

(-2.2 -

8.2)E-2

(-2.2 -

8.2)E -2 et 0/ 38)*

et 0/ 19)e e( 0/ 19)e CS-134 ( 57) 15.

(-4.0 i 1.1)E -1 11

(-3.4 i 1.1)E-1

(-5.3 1 1.1)E -1

( 0)

(-2.4 -

.8)E 0

(-1.1 -

.6)E 0

(-1.3-

.5)E 0 et 0/ 38)e et 0/ 19)e et 0/ 19)e CS-137 ( 57) 18.

( !.2 i

.2)E 1

!! ( 2.0 t

.1)E 1

( 9.7 1 1.6)E -1

( 19)

( 2.3 - 32.1)E 0

( !.1 -

3.2)E 1

(-2.7 - 27.7)E -1 et 30/ 38)e et 19/ 19)e

(

2/ 19)*

BA-140 ( 57) 15.

(-5.6 t 2.5)E -1 21

(-2.6 1 27.5)E -2

(-2.6 i 27.5)E -2

( 0)

(-4.4 -

4.2)E O

(-2.1 -

2.7)E 0

(-2.1 -

2.7)E O at 0/ 38)e

(

0/ 19)e et 0/ 19)*

E-141 ( 57)

( !.2 t 2.7)E -1 21

( 3.6 1 2.6)E -1

( 3.6 t 2.6)E -1

( 0)

(-4.2 -

2.8)E 0

(-1.4 -

2.2)E 0

(-1.4 -

2.2)E 0

(

0/ 38)e

(

0/ 19)e f( 0/ 19)e CE-144 ( 57)

( 8.9 i 4.01E-1 11

( !.3 i 1.0)E 0

( 4.5 i 85.4)E -2

( 0)

(-5.4 -

9.2)E 0

(-5.4 -

9.2)E 0

(-6.9 -

6.8)E 0 et 0/ 38)e

(

0/ 19)e et 0/ 19)*

TM-232 ( 57)

( !.6 t

.5)E 0 11 ( !.7 i

.6)E 0

( 2.4 1 7.2)E -1

( 0)

(-3.0 -

8.2)E 0

(-2.7 -

7.1)E 0

(-6.0 -

5.7)E 0 et 0/ 38)e et 0/ 19)*

e( 0/ 19)e e NON40JTIE REFERS TO TE MMBER (F SEPARATE EASLREENTS IMICH IDE GREATER THAN TEN (10) TIES TE AVERAGE BACKGROLMD FOR TE PERIOD OF TE flEPORT.

- TE FRACTION 0F SAffLE ANALYSES YIELDING DETECTABLE EASLREENTS (1.E. >3 STD K VIATIONS) !$ INDICATED WITH et

)e.

t D) Food Crop Samples of tomatoes were collected at harvest time and analyzed for ganuna-emitting nuclides. These crops were both sampled from three indicator and one control station. Other than naturally occurring K-40 and Be-7, no radionuclides were detected in the samples.

ENVIR0ffENTAL RADIOLOGICAL PROGRAN SlM1ARY YAREE NUCLEAR POWER STATION. ROE. HA J M ARY - DECEMBER 1984

[

IEDIlM: F000 CROP LMITS: PCI/KG ET k

IEICATOR STATI(NS STATION WITH HIGEST M CONTROL STATIONS l

neneennuenn unnenenenenennee neen n u neees RADIOMI2.! DES M

M M

(10. ANALYSES) EDVIRED RANGE STA. RME RAEE (NDHOUTIEle LLD NO. IETECTEDee NO.

NO.IETECTEDee NO. DETECTEDn E-7

( 4)

(1.41 1.7)E 2 32 ( 4.7 i 1.3)E 2

(-2.4 1 6.7)E 1

( !)

(-7.3 - 46.6)E 1

(

1/ 3)e et 1/ 1)e et 0/ 1)e K-40 ( 4)

( 2.4 i

.1)E 3

!! ( 2.6 i

.2)E 3

( !.7 1

.2)E 3

( 0)

( 2.3 -

2.6)E 3 et 3/ 3)*

(

1/ 11e

(

1/ 1)e f9F54 ( 4)

(-3.6 i 5.5)E 0 11 ( 7.4 1 8.4)E 0

(-5.2 i 9.9)E 0

( 0)

(-9.4 -

7.4)E 0 et 0/ 3)e

( 0/ 1)*

st 0/ lie CO-58 ( 4)

( 7.8 i 6.3)E 0 32 ( !.5 i 1.1)E 1

( !.51 8.5)E 0

( 0)

(-4.7 - 14.8)E 0 et 0/ 3)*

ef 0/ 11e et 0/ 1)*

FE-59 ( 4)

( 5.1 1 14.6)E 0

!! ( 2.0 i 1.5)E 1

(-4.7 1 15.2)E 0

( 0)

(-2.4 -

2.1)E 1 a( 0/ 3)*

(

0/ 11e et 0/ 1)*

CD-60 ( 4)

(-4.7 i 11.4)E 0 11 ( !.6 i 1.0)E 1

( !.31 1.5)E 1

( 0)

(-2.3 -

1.6)E 1

( 0/ 3)e et 0/ 1)e et 0/ 1)e ZN-65 ( 4)

( 5.4 i !!.0)E 0

( 2.1 i 1.5)E 1

( !.6 i 1.8)E 1

( 0)

(-1.6 -

2.1)E 1

. *(

0/ 3)e

(

0/ 11e et 0/ 1)*

ZR-95 ( 4)

( 3.8 k 98.9)E -1 12 ( 2.0 1 1.5)E 1

(-2.2 i 1.7)E 1

( 0)

(-1.1 -

2.0)E 1 et 0/ 3)e et 0/ 1)*

8( 0/ 1)*

RIM 03 ( 4)

( 6.7 i 4.2)E 0 12 ( !.5 i

.9)E 1

( 7.5 1 80.4)E -1

( 0)

( 2.0 - 15.2)E 0 et 0/ 3)e et 0/ 1)*

(

0/ lie

N0H00 TIE REFERS TO TE NLMBER OF SEPARATE EASUREENTS WHICH WERE GREATER JHAN TEN (10) TIES TE AVERAGE BACKGROUND FOR TE PERIOD OF TE REP (RT.

es TE FRACTION OF SAff'LE ANALYSES YIELDING DETECTABLE EASLREENTS (1.E. >3 STD DEVIATIONS) l$ IE!CATED WITH *(

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

ENVIROPfENTAL RADIOLOGICAL PROGRAM SlfMARY YANCEE Mln. EAR POWER STATION. ROE. Im JAMJARY - DECDGER 1984

(

E DIlM FOOD DIOP L911TS: PCI/XG WET L-IM)!CATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONS y

l e******e**********

- - - - eeeeeeee+eseenese sete*****+ee+ese RADIOMKLIDES EAN EAN EAN (ND. ANALYSES) K0UIRED RANE STA. RANGE RANGE

~ (NDH0llTIEle LLD NO. DETECTED H NO.

NO. DETECTEDee NO. DETECTEDee All-106 ( 4)

( l.6 i 3.7)E 1 11 ( 8.3 i 6.8)E 1

(-1.1 i

.9)E 2

( 0)

(-4.7 -

8.3)E 1 et 0/ 3)e e( 0/ 1)e

(

0/ 1)e 1-131 ( 4)

(-2.8 i 2.2)E 1 21

( l.4 i 9.7)E 0

( !.4 i 9.7)E 0

( 0)

(-7.2 -

.3)E 1 el 0/ 3)*

ef 0/ Ile et 0/ 1)*

CS-134 ( 4) 60.

(-2.6 i 9.9)E 0 21 ( 1.7 i 1.0)E 1

( !.7 1 1.0)E 1

( 0)

(-1.5 -

1.7)E 1 et 0/ 3)*

et 0/ 11e et 0/ lie CS-137 ( 4) 80.

(-3.8 i 70.0)E -1 12 ( !.3 i

.8)E I

(-1.4 i 1.1)E 1

( 0)

(-9.0 - 13.5)E 0 a( 0/ 3)e

(

0/ lie et 0/ lie BA-140 ( 4)

(-4.6 i 5.8)E 0 21 ( 1.9 2 1.9)E 1

( !.9 i 1.9)E 1

( 0)

(-1.6 -

.1)E 1 el 0/ 3)e

(

0/ lie et 0/ 1)*

CE-141 ( 4)

(-1.3 i 4439.6)E -3 21 ( l.0 t 1.2)E 1

( l.0 1 1.2)E 1

( 0)

(-7.9 -

7.4)E O et 0/ 3)e

( 0/ 1)e

(

0/ 11e E-144 ( 4)

(-1.4 i 2.5)E 1 21 ( 4.0 i 5.5)E 1

( 4.0 1 5.5)E 1

( 0)

(-6.2 -

2.4)E 1 et 0/ 31s

(

0/ Ile

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

( 2.2 i 2.1)E 1 32 ( 6.3 i 4.6)E 1

(-2.8 i 4.5)E 1

( 0)

(-6.4 - 62.6)E 0 et 0/ 3)e

( 0/ 1)e el 0/ 1)e e N0HORIE REFERS TO TE MMBER OF SEPARATE EASLRDENTS lef!CH lERE CREATER THAN TEN (10) TIES TE AVERAGE BACKGROLND FOR TE PERIOD OF TE REPORT.

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

le.

E) Broad Leaf Vegetation l

The Radiological Ef fluent Technical Specifications require that one

\\-

sample of broad leaf vegetation be sampled at harvest time. In 1984, a Swiss chard sample was collected from Station TV-11 (Monroe Bridge). The required I-131 analysis showed no detectable radioactivity.

ENVIROKNTAL RADIOLOGICAL PROGRAM StifMRY YAREE WCLEAR POER STATION. R0E. MA JANJARY - DECDBER 1984 ED!lM: OREEN LEAFY VEGETABLE LMITS: PCI/KG ET IEICATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONS l

eueeweee++wnee eueeeuwweneewe+eees weneeeuw+we RADIONJCLIIES EAN EAN EAN (NO. ANALYSES) REQllIED RANGE STA. RANGE RANGE (NON-90UTIEle LLD NO. DETECTEDee NO.

NO. I)ETECTEDet NO. DETECTEDee I-131 ( 11 60.

( !.6 i 1.0)E 0 11 ( !.6 i 1.01E 0 NO DATA

( 0) et 0/ lie et 0/ 1)e e NDHOUTIE REFERS TO TE RfBER OF SEPARATE EASLEEENTS IMICH ERE GREATER THAN TEN (10) TIES TE AVERAGE BACKGR0lND FOR TE PERIOD OF TE EPORT.

ee TE FRACTION OF SAfFLE ANALYSES YIELDING DETECTABLE EAStREENTS (I.E. >3 STD DEVIATIONS) IS I E!CATED WITH *(

le.

F' F) Maple Syrup Maple syrup grab samples (not required by Technical Specifications) were collected during April at one indicator and two control locations. In addition to naturally occurring K-40, 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 1984 had a higher Cs-137 level than detected at the indicator station.

~

e I

EWIR0ffENTAL RADIOLOGICAL PROGRAM SIATIARY YAf0(EE filCLEAR P0ER STATION, ROE, im JANUARY - DECEMBER 1984 PEDILM: flAPLE SYlltP (MITS: PCI/KG IEICATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONS MoMeeHHoHMee eHeM*MesesseHH4 hem

HeMeeMeseMe IMDIOM.lCLIDES LEAN PEAN EAN (NO. ANALYSES) E0tlIRED FLANGE STA. RANGE IMNGE (NON-ROUTIEle 1.LD NO. DETECTED **

NO.

NO. DETECTED M NO. IETECTEDee E-7

( 3)

( 2.7 i 7.8)E 0 31 ( 2.7 1 7.8)E 0

(-9.2 i

.0)E 0

( 0)

(-9.2 - -9.2)E 0 et 0/ 13e et 0/ 1)*

a( 0/ 21e K-40 ( 3)

( 2.0 t

.0)E 3 31

( 2.0 k

.0)E 3

( !.9 i

.1)E 3

( 0)

( !.7 -

2.0)E 3

(

1/ 1)e

(

1/ 1)*

( 2/ 2)e 79f-54 ( 3)

( !.1 i

.8)E 0 41 ( !.5 i 1.0)E 0

( 6.2 1 8.7)E -1

( 0)

(-2.6 - 14.9)E -1 et 0/ 1)e et 0/ 1)*

ef 0/ 21e C0-56 ( 3)

(-1.5 t

.9)E 0 41

(-4.8 i 10.2)E -1

(-7.9 i 3.1)E -1

( 0)

(-1.1 -

.5)E 0 et 0/ 1)e f( 0/ 11e et 0/ 2)*

FE-59 ( 3)

( 4.9 1 2.6)E 0 31

( 4.9 i 2.6)E 0

( 3.9 i

.3)E 0

( 0)

( 3.7 -

4.2)E O a( 0/ 1)*

( 0/ 1)e

(

0/ 2)e CD-60 1 3)

( 4.0 i !!.6)E -1 42 ( 5.1 i !!.8)E -1

(-1.1 1 1.6)E 0

( 0)

(-2.7 -

.5)E 0 et 0/ 11e f( 0/ 11e e( 0/ 2)e ZN-65 ( 3)

(-1.3 i 2.7)E 0 41 (5.11 2.5)E 0

( !.5 1 3.6)E O

( 0)

(-2.1 -

5.1)E 0

( 0/ 1)*

(

0/ 11e

(

0/ 21e ZR-95 ( 3)

(-1.1 i 1.6)E 0 42 ( 3.0 i 1.6)E 0

( 2.1 1 1.0)E 0

( 0)

( !.! -

3.0)E 0

(

0/ 11e et 0/ 13e 5( 0/ 2)*

R)-103 ( 3)

(-1.4 i 1.0)E 0 31

(-1.4 i 1.0)E 0

(-2.5 i

.4)E 0

( 0)

(-2.9 - -2.1)E O el 0/ 1)e et 0/ lie et 0/ 2)*

N0N4t0UTIE REFERS TO TE IUlBER OF SEPARATE lEASUREENTS IMICH ERE GREAIER THAN TEN (10) TIES TE AEACE BACXGR0tND FOR TE PERIOD OF TE REPORT.

- TE FRACTION OF SAfFLE ANALYSES YIELDING DETECTABLE tEASLREENTS (1.E. >3 STD DEVIATIONS) IS IE!CATED WITH ef

)*. -.. - -. -

EWIR0 ENTAL RADIOLOGICAL PR00PAff SIMIARY YAM (EE WCLEAR POER STATION. ROE. MA JAPAJARY - DEEl9ER 1984 EDILM: MPLE SYRlP (MITS: PCI/KG IfSICATOR STATIONS STATION WITH HIGEST MAN CONTROL STATIONS seunne+ennen essenununeeeneenee eeeeeee***een RADIOWCLIBES EAN EAff EAN (ND. AMLYSES) flE0VIRED RANGE STA. RANGE RANGE (N0lHIOUTIEle LLD NO. DETECTEDe*

NO.

NO.IIETECTEDu NO. DETECTED *e ALF106 ( 3)

(-3.9 1 8.1)E 0 42 ( 9.4 1 6.0)E 0

( l.3 i 8.1)E 0

( 0)

(-6.7 -

9.4)E 0

(

0/ lie f( 0/ 1)*

( 0/ 2)*

I-131 ( 3)

( 3.2 1 20.3)E -1 31

( 3.2 1 20.3)E-1

(-1.8 i 1.0)E O

( 0)

(-2.8 -

.7)E 0 el 0/ 11e

(

0/ 1)e

(

0/ 21e CS-134 ( 3)

(-1.4 i

.9)E 0 42 ( !.7 t 8.9)E -1

(-1.4 t 1.6)E O

( 0)

(-3.0 -

.2)E 0 j

(

0/ !)*

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

CS-137 ( 3)

( 2.1 i

.1)E 1 41

( 8.9 i

.3)E 1

( 5.8 1 3.1)E I

( 0)

( 2.8 -

8.9)E 1 l

e( 1/ 11e et 1/ 1)e et 2/ 2)*

BA-140 ( 3)

(-9.8 1 14.0)E -1 41

(-1.7 t 15.1)E -1

(-5.9 2 4.2)E -1

( 0)

(-1.0 -

.2)E 0 et 0/ lle e( 0/ 1)*

e( 0/ 2)*

E-141 ( 3)

( l.3 1.6)E O 31

( !.3 i 1.6)E 0

( !.71 2.4)E -1

( 0)

(-7.0 - 41.6)E -2 of 0/ 11e et 0/ 11e

( 0/ 2)e E-144 ( 3)

(-2.3 t 5.7)E O 42 ( 8.8 t 5.5)E 0

( 8.4 i

.4)E 0

( 0)

( 8.1 -

8.8)E 0 et 0/ lie of 0/ 11e

( 0/ 2)*

TH-232 ( 3)

( 4.4 1 2.9)E 0 31

( 4.4 1 2.9)E 0

( !.3 t 21.3)E -1

( 0)

(-2.0 -

2.3)E 0 of 0/ 1)e

(

0/ lie et 0/ 2)*

NON-RillTIE REFERS TO TE IUIBER OF SEPARATE EASUREEKTS lef!CH WERE OREATER THAN TEN (10) TIES TE MRAGE BAC3(GROLND FOR TE PERIOD 0F TE REPORT.

e TE FRACTION OF SAfFLE ANALYSES YIELDING DETECTABLE EASLREENTS (f.E. >3 STD lEVIAil0NS) IS INDICATED WITH *(

le.

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

(Technical Specifications require a quarterly collection.) Each of these samples was analyzed for gross-beta and genuna-omitting radionuclides. Each sample from

. Station WG-11 was analyzed for H-3, and the. monthly samples from Station WG-12 were composited for a quarterly H-3 analysis.,

Tritium (M-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 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 1984 concentration of 1600 pCi/ kilogram, would be approximately 0.06 meem, using USNRC Regulatory Guide 1.109 methodology (Reference 2).

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

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

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

No gamma-emitting radionuclides were detected in the ground water samples.

i i

4 J.____. -__.., _ - _. - _ _____

ENVIROMENTAL MDIOLOGICAL PROGRAM SLMARY

(

YAEEE NUCLEAR POWER STATION, ROE. M J M ARY - DECEMBER 1984 EDILMt OROLND WATER LNITS: PCI/KG IE!CATOR STATIONS STATION WITH HIGEST MAN CONTROL STATIONS HMefHetHHeMe HeftfHeefHeffMfM94H Mf f f fMHfMHf MDIOMJCLIDES EAN PEAN EAN (ND. ANALYSES) EQUIED RME STA. MNGE MNE (NOHOUTIEle LLD NO. DETECTEDef MI.

NO. DETECTED **

NO. DETECTEDH (R-B ( 24) 4.

( 3.8 i

.2)E 0

!! ( 4.4 i

.2)E 0 NO MTA

( 0)

( 2.1 -

5.9)E 0

( 3.5 -

5.9)E 0 e( 24/ 24)e et 12/ 12)e E-7

( 24)

(-1.1 &

!.6)E 0 12 ( 9.7 & 23.6)E -1 NO DATA

( 0)

(-1.4 -

1.7)E 1

(-1.0 -

1.7)E 1 et 0/ 24)e el 0/ 12)e K-40 ( 24)

(-2.6 t 3.2)E 0 12 ( 2.2 t 4.0)E 0 NO MTA

( 0)

(-3.6 -

2.4)E 1

(-1.8 -

2.4)E 1 et 0/ 24)e et 0/ 12)*

19f-54 (24) 15.

(-2.9 t 2.2)E -1

(-2.0 &

3.9)E -1 NO MTA

( 0)

(-1.8 -

2.8)E 0

(-1.8 -

2.8)E 0 et 0/ 24)e el 0/ 12)s CD-58 ( 24) 15.

(-6.0 1 2.3)E-1 12 ( !.8 1 1.7)E -1 NO DATA

( 0)

(-3.2 -

1.2)E 0

(-4.5 - 12.3)E -1 et 0/ 24)e

(

0/ 12)e FE-59 ( 24) 30.

( !.6 i 3.8)E-1 12 ( 4.6 1 6.0)E -1 NO DATA

( 0)

(-4.0 -

4.0)E 0

(-4.0 -

4.0)E 0 et 0/ 24)e e( 0/12)*

CD-60 ( 24) 15.

(-3.2 &

!.7)E-1 12

(-2.9 1 2.4)E -1 NO DATA

( 0)

(-2.0 -

.8)E 0

(-2.0 -

.7)E 0 el 0/ 24)#

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

( 5.1 &

4.4)E -l

( !.! t

.8)E 0 NO DATA

( 0)

(-4.0 -

3.8)E 0

(-4.0 -

3.8)E 0 et 0/ 24)*

(

0/12)e ZR-95 ( 24) 15.

(-6.0 t 3.7)E -l 12

(-6.7 & 41.1)E -2 NO DATA

( 0)

(-4.2 -

3.6)E 0

(-3.8 -

1.6)E 0 of 0/ 24)e of 0/ 12)e e N0HOUTIE RETERS TO M MMBER OF SOAPATE EMREENTS WH!Df UE OREATER THM TEN (10) TIES TE AVERACE BACKGROLND FOR TE PERIOD 0F TE REP (RT.

- TE FRACTION OF SATLE ANALYSES Y!ELDING KTECTABLE EASUPDENTS (1.E. >3 STD DEVIAil0NS) IS lEICATED WITH #(

)*.

EWIROMENTAL RADIOLOGICAL PROGRAM SlMWIRY YAREE MJCLIAR POER STATION. R0E. M JAM)ARY - DECDOER 1984 EDILM: (R0l#8 IMTER tm!TS: PC!/KG IM)lCATOR STATIONS STATION WITH Hl0EST EAN CONTROL STATIONS ee++eHeeeeennu e+HHHHeeHeeHHHeH

HfHHMMMee MDl0MILIDES EAN EAN EAN (NO. ANALYSES) EQUIRED RANGE STA. RANGE RANGE (NON-R0llTIE)#

LLD

18. DETECTED +e NO.

NO. DETECTED +e NO. DETECTED +e Rt)-103 ( 24)

(-7.9 1 1.7)E-1 12

(-5.81 2.8)E -1 NODATA

( 0)

(-2.2 -

1.3)E 0

(-2.1 -

1.3)E 0 of 0/ 24)e et 0/ 12)e Rt)-106 ( 24)

( !.2 i 1.5)E 0 12 ( 2.0 1 2.0)E 0 NO DATA

( 0)

(-1.6 -

1.4)E 1

(-8.1 - 14.2)E 0 et 0/ 24)#

ef 0/12)*

I-131 ( 24) 1.

( 6.5 i 5.6)E -1 12 ( 9.6 1 3.7)E-1 NO DATA

( 0)

(-7.7 -

8.0)E 0

(-1.1 -

2.6)E 0 et 0/ 24)e et 0/ 12)e CS-134 ( 24) 15.

(-2.6 i 1.5)E-1

(-1.9 1 2.1)E-1 NODATA

( 0)

(-2.3 -

.8)E 0

(-1.4 -

.8)E 0

(

0/ 2418 et 0/ 12)e CS-137 ( 24) 18.

(-4.1 1 2.4)E-l 12 ( 3.4 1 1.9)E-1 NODATA

( 0)

(-2.8 -

1.1)E 0

(-6.8 - II.3)E -1 et 0/ 24)*

ef 0/12)*

M -140 ( 24) 15.

(-1.5 1 3.7)E-1

( 6.4 1 4.9)E-1 NO DATA

( 0)

(-4.2 -

3.2)E 0

(-1.7 -

3.2)E 0 et 0/ 2418 el 0/ 12)e CE-141 ( 24)

(-4.22 4.5)E-l

(-3.21 6.6)E-1 NO DATA

( 0)

(-3.4 -

4.6)E 0

(-3.4 -

2.9)E 0 of 0/ 24)*

(

0/12)*

CE-144 ( 24)

(-5.0 i 12.0)E-l

( 6.4 i 206.0)E -2 NODATA

( 0)

(-1.4 -

1.0)E 1

(-1.4 -

1.0)E 1 ef 0/ 24)e et 0/ 12)*

TH-232 ( 24)

(l.61

.6)E 0 12 ( 2.1 i

.9)E 0 NODATA

( 0)

(-4.8 -

8.2)E 0

(-1.3 -

8.2)E 0 et 0/ 2418 et 0/ 12)e H-3

( 21) 2000.

( 9.3 i 1.8)E 2 12 ( !.6 i

.1)E 3 M) DATA

( 12)

(-1.5 - 20.8)E 2

( l.1 -

2.1)E 3 el 12/ 21)e el12/1218 e NON4KUf!E ETERS TO TE Nl#9ER OF EPARATE EASLFIENTS INICH ERE GREATER THAN TEN (10) TIES TK AVERACE BACMROUND FOR TE PERIOD 0F TE EPORT.

H TE FRACTION OF SAMLE ANALYSES YlELDING IETECTABLE EARREENTS (f.E. >3 STD DEVIAfl0NG) IS IM)!CATED WITH *(

le...

H) River Water Composite samplers were used at the two required sampling locations

.and samples from each of these were collected monthly and analysed for gross-beta, gasuna-emitting radionuclides, and I-131.

Quarterly composites were analysed for M-3.

The third quarter composite sample 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 sasyling location, with the average concentration of 390 PCi/ kilogram, it would be shown that the dose would be approximately.009 arem per year, using USNRC Regulatory Guide 1.109 methodology (Reference 2).

Gross beta radioactivity, primarily from naturally occurring radionuclides in river water, was detected in most samples. The mean and range were similar to those measured in previous years.

The control and indicator station mean concentrations were also equal in 1984.

Other than naturally occurring Th-232, no gansna-emitting radionuclides were detected in the 1984 river water samples.

4 i

s ENVIR0Pf D TAL RADIOLOGICAL PROGRAM SUlflARY YAWEE EllEAR POWER STATION. ROE. l%

JAftJARY - DECEMBER 1984 ED!tM: RIS li4TER LMITS: PCI/KG l E!CATOR STAil0NS STATION WITH HIGEST EAN CONTROL STATIONS

- - MMGMeeHGMe MeeeeeHeffe HeeHeG H M

H eMetteMMM RADIOKCLIBES EAN MAN EM (ND. ANALYSES) EQUIRED RANE STA. RANGE RANI (NOPHIOUTIE)*

LLD NO. DETECTEDee M).

NO. DETECTEDH NO. DETECTEDee OR-3 ( 26) 4.

( l.9 i

.1)E 0 21

( !.9 i

.1)E O

(!9i

.1)E 0

( 0)

( 8.7 - 25.1)E -1

( l.2 -

2.7)E 0

( l.2 -

2.7)E 0

( 12/ 13)*

( 13/ 13)*

8( 13/ 13)*

K-40 ( 26)

( 6.2 1 29.0)E -l

!! ( 6.2 1 29.0)E -1

(-3.9 i 4.5)E 0

( 0)

(-1.7 -

1.8)E 1

(-1.7 -

1.8)E 1

(-3.4 -

3.1)E 1

(

0/ 13)*

et 0/ 13)*

(

0/13)e P91-54 ( 26) 15.

(-3.7 i 1.7)E -1

( 6.7 1 2.8)E -1

( 0)

(-1.3 -

.9)E 0

(-1.3 -

.9)E 0

( 2.0 -

1.1)E 0 et 0/ 13)e et 0/ 13)e

! 0/13)e CD-58 ( 26) 15.

( !.0 1 3.0)E-1

!! ( !.01 3.0)E -1

(-2.1k 3.6)E-1

( 0)

(-1.9 -

2.0)E 0

(-1.9 -

2.0)E 0

(-2.2 -

2.4)E 0 e( 0/ 13)*

(

0/ 13)*

8( 0/13)e FE-59 ( 26) 30.

( !.2 i

.5)E 0

!! ( 1.2 i

.5)E 0

( 7.8 i 6.6)E -1

( 0)

(-3.2 -

3.4)E 0

(-3.2-3.4)E 0

(-2.8 -

4.5)E 0 et 0/ 13)*

et 0/ 13)*

of 0/ 13)*

CD-60 ( 26) 15.

( 2,5 1 2.7)E -1 11 ( 2.5 1 2.7)E-1

( !.9 1 3.7)E -1

( 0)

(-7.4 - 19.1)E-1

(-7.4 - 19.1)E -1

(-2.3 -

2.5)E 0 et 0/ 13)e e( 0/ 13)*

(

0/ 13)*

ZN-65 ( 26) 30.

(-5.7 i 4.3)E -1 11

(-5.7 1 4.3)E -1

(-6.1 1 5.9)E -1

( 0)

(-3.5 -

1.3)E 0

(-3.5 -

1.3)E 0

(-3.7 -

4.5)E 0 et 0/ 13)e et 0/ 1316

(

0/13)*

ZR-95 ( 26) 15.

(-1.1 1 4.5)E -l

(-1.1 1 4.5)E-1

(-2.0 1 4.4)E -1

( 0)

(-2.3-3.1)E 0

(-2.3 -

3.1)E 0

(-2.7 -

2.9)E 0 of 0/ 13)*

st 0/ 13)*

(

0/ 13)e 1U 103 ( 26)

(-9.1 1 3.5)E -1 21

(-5.5 1 2.9)F"!

(-5.5 1 2.9)E -1

( 0)

(-3.1-1.1)E 0

(-2.1 -

1.3L 0

(-2.1 -

1.3)E 0 ei 0/ 13)#

(

0/13)#

(

0/ 1318 e NOPHt0L' TIE REIDtS TO TE lotER OF SEPARATE EA$lREENTS IMIDI DE GEAD TH4N D (10) TIES TE AVERAE BACG0tND F(ft TE PERIOD OF TE REP 0lT.

et TE FRACil0N OF SAfftE ANALYSES Y!ELDING DETECTABLE EASURDOTS (1.E. >3 STD D IAfl0NS) l$ I E!CATED WITH et le.

EWIR0lfENTAL RADIOLOGICAL PR00 FAN SLMARY YAf0EE 10 CLEAR POWER STATION, ROE. M4 JAf0ARY - ECD 9ER 1984 ED!tMr RIVER WATER LMITS: PC1/KG I E!CATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONS eeeeen m n+++en nee ++neenenneennes e+nneeeenene RADIO 10CLIES MAN EAN EAN (ND. ANALYSES) K0UIRED RANGE STA. RANGE RANGE (N0HOLITIEle LLD NO. DETECTED **

NO.

NO. DETECTED **

10-106 ( 26)

( 9.6 1 216.6)E -2 11 ( 9.6 i 216.6)E -2

(-7.0 1 22.7)E -1

( 0)

(-1.5 -

1.9)E 1 1-1.5 -

1.9)E 1

(-1.4 -

1.0)E 1 et 0/ 13)e et 0/ 13)e et 0/ 13)e I-131 ( 24)

( 2.2 i 1.1)E -2

( 2.2 1 1.1)E-2

( 6.7 i 8.0)E -3

( 0)

(-3.1 - 12.3)E -2

(-3.1-12.3)E -2

(-5.8 -

3.8)E -2 e( 0/ 13)e

(

0/ 13)e et 0/ 13)e CS-134 ( 26) 15.

(-6.9 i 2.2)E -1

(-6.9 1 2.2)E -1

(-1.2 i

.2)E 0

( 0)

(-2.6 -

.3)E 0

(-2.6 -

.3)E 0

(-2.5 -

.1)E 0 et 0/ 13)e el 0/ 13)e et 0/13)e CS-137 ( 26) 18.

(-2.0 1 1.4)E -1 11

(-2.0 t 1.4)E -1

(-4.5 1 2.2)E -1

( 0)

(-1.1 -

.5)E 0

(-1.1 -

.5)E 0

(-2.0 -

.8)E 0 et 0/ 13)e et 0/ 13)e

(

0/13)e 94-140 ( 26) 15.

(-3.6i 5.5)E -1

(-3.6 1 5.5)E-1

(-1.0 i

.5)E 0

( 0)

(-3.5 -

4.2)E 0

(-3.5 -

4.2)E 0

(-6.0 -

.6)E 0

(

0/ 13)e et 0/ 13)e et 0/13)*

E-141 ( 26)

( 7.9 i 4.2)E -1 21 ( 9.4 1 4.8)E -1

( 9.4 1 4.8)E -1

( 0)

(-2.5 -

3.1)E 0

(-1.8 -

4.0)E 0

(-1.8 -

4.0)E 0 et 0/ 13)e et 0/13)e et 0/13)e E-144 ( 26)

(-8.4 1 18.3)E -1 21

( 2.5 i 1.6)E 0

( 0)

(-1.1 -

1.4)E I

(-6.7-12.9)E 0

(-6.7 - 12.9)E 0 et 0/ 13)*

el 0/ 13)e

(

0/ 13)*

Tit-232 ( 26)

( 2.4 i 1.3)E 0 11

( 2.4 i 1.3)E 0

( 2.8 i 9.2)E -1

( !)

(-7.4 - !!.4)E 0

(-5.7 -

5.2)E 0 of 1/ 13)e

(

1/13)e et 0/ 13)e H-3

( 8) 2000.

( 2.4 i 1.2)E 2 11

( 2.4 1 1.2)E 2

(-1.21 15.1)E 1

( !)

( 9.6 - 58.4)E 1

( 9.6 - 58.4)E i

(-3.9 -

3.5)E 2 et 1/ 4)e et 1/ 4)e et 0/ 4)e e NON-ROLITIE RETERS TO M IOEER OF SEPARATE EASUREENTS WHICH ERE GEATER TIMN TEN (10) TIES M AVERAGE BACER0lND FOR TE PERIOD OF M EPORT.

- M FRACf!0N OF SAfftf ANALYSES YlELDING KTECTABLE EASURDOTS (f.E. >3 STD K V!Afl0NS) IS !!OICATED WITH a(

le. -.. _

1) Sediment Sediment cores were collected semiannually from two locations.

Rach core was separated into 5 cm segments, which were analyzed for sama-emitting radionuclides. Cesium-137 was detected in most 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.

Station SE-21 at Harriman Reservoir (control) has in the past had.

levels of Cs-137 that'are comparable to those at station SE-11 on the Deerfield River. During 1984, however, several cores were taken in May and then again in August at Harriman Reservoir, but at a location a short distance away from the traditional one at the Whitingham boat launch.

(Cores were also collected at the traditional location during August and October.) The cores at the new location showed a much higher level of Cs-137 (up to 4609 pCi/kg in the 5-10 cm segment), consequently elevating the annual mean as compared to previous years. The higher levels are apparently due to the very high organic matter content in the soil, which was collected from near the high water mark under a stand of trees.

Other than naturally occurring K-40 and Th-232, no other gama-emitting radionuclides were detected in 1984 sediment samples.

t.. - -

E)NIR0lfENTAL RADIOLOGICAL PROGRAM SUHRY YAREE 10 CLEAR POER STATION, ROE. MA JA WARY - DECEMBER 1994 EDIT #f: SEDIENT IAi!TS: PCI/KG DRY Ile!CATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONS

H44He***MeeMe etHMHffHfffMffeffHe eHeeHeHeMets RADIOEC.! DES EAN EAN EAN (NO. MALYSES) IGUIRED MNGE STA. RANE RANE (NON-ROUTIEle LLD NO. ETECTEDee 10.

NO. DETECTED **

ND. DETECTEDee EE-7 ( 21)

( 6.5 1 6.5)E 1

( 3.9 i 6.4)E I

(-1.5 -

4.1)E 2

(-1.5 -

4.1)E 2

(-2.7 -

7.3)E 2

( 0) e( 0/ 7)e et 0/ 7)e

(

1/ 14)*

K-40 ( 21)

( !.5 i

.1)E 4 11 ( !.5 i

.1)E 4

( !.3 i

.1)E 4

( 0)

( !.0.-

1.8)E 4

( 1.0 -

1.8)E 4

( !.0 -

1.8)E 4 et 7/ 7)*

st 7/ 7)*

( 14/ 14)*

191-54 ( 21)

(-1.2t

.4)E 1 11

(-1.2 i

.4)E 1

(-1.3 i

.3)E 1

( 0)

(-2.0 -

1.1)E 1

(-2.0 -

1.1)E 1

(-3.2 -

.6)E 1 a( 0/ 7)e

( 0/ 7)*

(

0/ 14)e CD-58 ( 21)

(-1.6 &

.5)E 1 21

(-6.4 1 2.3)E 0

(-6.4 i 2.3)E O

(-3.8 -

.2)E 1

(-1.9 -

1.2)E 1

(-1.9 -

1.2)E 1

( 0) e( 0/ 7)#

et 0/ 14)e el 0/ 14)e FE-59 ( 21)

(-1.7 t 1.9)E 1 21

(-7.3 t 10.7)E 0

(-7.3 1 10.7)E O

( 0)

(-9.5 -

4.4)E 1

(-8.8 -

8.3)E 1

(-8.8 -

8.3)E 1 et 0/ 7)*

(

0/ 14}e et 0/ 14)e CO-60 ( 21)

(-2.3 t 55.4)E-1

(-2.3 k 55.4)E -1

(-3.5 t 2.4)E 0

( 0)

(-1.7 -

2.0)E 1

(-1.7 -

2.0)E 1

(-2.0 -

.8)E 1 et 0/ 7)e

( 0/ 7)e

(

0/ 14)e IN-65 ( 21)

( 7.1 i 9.7)E O 11

( 7.1 t 9.7)E 0

(-5.4 t 11.4)E 0

( 0)

(-2.7 -

5.7)E 1

(-2.7 -

5.7)E 1

(-6.2 - 10.0)E 1 et 0/ 7)e et 0/ 7)e af 0/ 14)*

( !.6 i 1.0)E 1 11

( !.6 t 1.0)E 1

( !.2 &

.5)E 1 ZR-95 ( 21)

^

(-1.1 -

6.2)E I

(-1.1 -

6.2)E 1

(-1.4 -

5.5)E 1

( 0) el 0/ 7)e et 0/ 7)*

st 0/ 14)*

1U-103 ( 21)

(-4.6 1 5.8)E 0 21

(-1.4 1 4.0)E 0

( 0) N

(-3.7 -

.7)E 1

(-2.6 -

2.4)E I

(-2.6 -

2.4)E 1 el 0/ 7)e et 0/ 14)e

(

0/ 14)*

NON-ROUTIE REFERS TO TE NLPEOt 0F SEPARATE EASLFIENTS IMICH ERE CREATER THAN TEN (10) TIES TE AVERAGE BACKGROUND FCR TE PERIOD OF TE REPORT.

- TE FRACTION OF S#FLE ANALYSES YIELDING KTECTAPl EASUREENTS (1.E. 23 STD KVIATIONS) IS INDICATED WITH *(

le.,

,-------n-

P' l

DNIROMOTAL RADIOLOGICAL PROGRAM SLM%RY YN#IE WCLEAR POER STATION ROE 1%

JMIARY - DECEMBER 1984 4

EDILM SEDIENT (MITSIPCI/KGDRY I

IWICATOR STATI(NS STATION WITH HIGEST EAN CONTROL STATIONS sese m ne m esese emenemmmneessu emumsseme RADIONJCI.! DES EAN EAN EAN (NO. # % LYSES) IGL)! RED RANGE STA. RANGE MNE (N0HOUTIEle LLD NO. DETECTEDes NO.

NO. DETECTEDes NO. DETECTEDee Mll-106 ( 21)

( 2.7 i 3.8)E 1

!! ( 2.7 &

3.8)E 1 1-3.1 1 2.2)E 1

( 0)

(-1.1 -

2.2)E 2

(-1.1 -

2.2)E 2

(-1.7 -

1.3)E 2 et 0/ 7)e et 0/ 7)e

(

0/14)e 5

CS-134 ( 21) 150.

(-4.1 i 6.0)E 0 21

(-3.4 1 2.4)E 0

(-3.4 k 2.4)E 0

( 0)

(-3.3 -

1.8)E I

(-2.3 -

1.5)E 1

(-2.3 -

1.5)E 1 f

el 0/ 7)#

et 0/ 14)#

(

0/ 14)s CS-137 ( 21) 180.

( 3.2 i

.5)E 2 21 ( !.4 &

.4)E 3

( !.4 i

.4)E 3 i

( 0)

( 2.2 -

5.7)E 2

( 7.6 - 4610.0)E 0

( 7.6 - 4610.0)E 0 t

et 7/ 7)e of 13/ 14)e of 13/ 14)e b

E BA-140 ( 21)

(-1.1 i

.7)E 2 21

(-9.9 1 3.1)E 1

(-9.9 t 3.1)E 1 gg '

L

( 0)

(-4.2 -

.6)E 2

(-4.0 -

.3)E 2

(-4.0 -

.3)E 2

'M b

et 0/ 7)e et 0/ 14)e et 0/ 14)e F

[

E-141 ( 21)

( l.3 i 1.2)E 1 21

( !.7 i

.5)E I

( !.7 i

.5)E 1

[

( 0)

(-1.3-7.5)E 1

(-2.5 -

5.2)E 1

(-2.5 -

5.2)E 1 et 0/ 7)e et 0/ 14)e

(

0/ 14)e f

E-144 ( 21)

(-3.7 t 2.9)E I 11

(-3.7 1 2.9)E I

(-3.8

1.4)E 1

( 0)

(-1.6 -

.5)E 2

(-1.6 -

.5)E 2

(-1.2 -

.4)E 2 et 0/ 7)e el 0/ 7)*

(

0/14)e TH-232 ( 21)

( 8.8 t

.3)E 2 11 ( 8.8 i

.3)E 2

( 4.3 i

.2)E 2

( 0)

( 7.5 - 10.5)E 2

( 2.7 -

5.8)E 2 el 7/ 7)*

el 7/ 7)e e( 14/ 14)e e NDH0llTIE REFERS TO TE NLNG OF SEPARATE EASLEDDTS IMICH WERE CREATER THAN TEN (10) TIES TE AVEKAGE BACK0R0lND FOR TE PERIOD OF TE REPORT.

es TE FRACTION OF SMFLE NHLYSES YlELDING DETECTABLE EASLREENTS g-(1.E. >3 STD DEVIATIONS) IS I E !CATED WITH et le.

i 1

I.

h

J) Finfish Fish samples were collected semiannually from two locations. Each was analyzed for gamma-emitting radionuclides.

Cesium-137 was detected in all samples. Over the past several years, the levels have been comparable between Station FH-11 and Station FH-21, fish. The measured levels have also decreased slightly over the past three years at both stations. Consequently, we can conclude that the detected Cs-137 is due to nuclear weapons testing fallout.

Other than Cs-137 and naturally occurring K-40, no gamma-emitting radionuclides were detected in 1984 fish samples.

E)WIROPfENTAL RADIOLOGIrAL PROGRAM SuttARY YAEEE MJCLEAR POER STATION, R0WE. MA JAMJARY - DECEMBER 1984 EDIttt: FINFISH LMITS: PCI/KG ET IE!CATOR STATIONS STATION WITH HIGEST EAN CONTROL STATIONS eteH Hf HeeH H H ef f HHeMillif ff f Heath

- - f *Me* ** H He i

RADIONJC1.IMS EAN EAN EAN (ND. ANALYSES) EQUIRED RANGE STA. RANGE RAEE (NON-ROUTIEle LLD NO. DETECTEDet NO.

NO. DETECTEDee NO. DETECTED **

E-7

( 4)

( 2.3 2 7.1)E 1 21

( 2.6 t 9.1)E 1

( 0)

(-4.8 -

9.4)E 1

(-6.5 - 11.7)E 1

(-6.5 - 11.7)E 1 et 0/ 2)*

et 0/ 2)e et 0/ 2)*

K-40 ( 4)

( 2.9 t

.1)E 3 11

( 2.9 i

.1)E 3

( 2.7 i

.1)E 3

( 0)

( 2.8 -

3.0)E 3

( 2.8 -

3.0)E 3

( 2.6 -

2.8)E 3 et 2/ 2)e et 2/ 2)e e( 2/ 2)e 19f-54 ( 4) 130.

( 4.5 t 3.8)E 0 21

( 1.9 i

.7)E 1

( 1.9 i

.7)E 1

( 0)

( 7.1 - 82.3)E -1

( 1.2 -

2.6)E I

( !.2 -

2.6)E 1 et 0/ 2)e

(

0/ 2)e

( 0/ 2)e F

C0-58 ( 4) 130.

(-1.2 2 83.8)E -1 21

( 4.1 t 2.2)E o

( 4.1 t 2.2)E 0

( 0)

(-8,5 -

8.3)E 0

( 1.9 -

6.2)E 0

( !.9 -

6.2)E 0 et 0/ 2)e et 0/ 2)e et 0/ 2)*

FE-59 ( 4) 260.

( 4.3 1 9.4)E -1 11

( 4.3 t 9.4)E -1

(-3.6 i 1.0)E 1

( 0)

(-5.2 - 13.7)E -1

(-4.6 -

-2.6)E 1 et 0/ 2}e et 0/ 2),

e( 0/ 2)e CD-60 ( 4) 130.

( 3.0 1 6.9)E 0

(-3.7 i 6.8)E 0 l

t 0)

(-3.9 -

9.9)E 0

(-3.9 -

9.9)E 0

(-1.0 -

.3)E 1 e( 0/ 2)e et 0/ 2)e et 0/ 2)*

ZN-65 ( 4) 260.

( 7.9 1 1.6)E 0 11

( 7.9 1 1.6)E 0

(-1.7 t 2.3)E 1

( 0)

( 6.3 -

9.5)E 0

( 6.3 -

9.5)E 0

(-4.0 -

.6)E 1 et 0/ 2)e et 0/ 2)e et 0/ 2)*

2R-95 ( 4)

(-2.2 & 40.1)E -1 11

(-2.2 t 40.1)E -1

(-3.0 t

.2)E 1 l

( 0)

(-4.2 -

3.8)E 0

(-4.2 -

3.0)E 0

(-3.2 -

-2.7)E 1 et 0/ 2)e el 0/ 2)e

( 0/ 2)*

i RU-103 ( 4)

(-8.0 1 3.0)E 0

(-8.0 t 3.0)E 0

(-1.3 i

.3)E I

( 0)

(-1.1 -

.5)E 1

(-1.1 -

.5)E I

(-1.5 - -1.0)E 1 et 0/ 2)e et 0/ 2)e et 0/ 2)e NONWtJTIE REFERS TO TE NLftBER OF SEPARATE EASUREENTS WHICH ERE CREATER e

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

- TE FRACTION OF SAff'LE AMLYSES YIELDING DETECTA!LE EASLEEENTS II.E. >3 STD DEVIATIONS) IS INDICATED WITH *(

le.

=.

m--.

M

[-

2 p

ENVIR0 MENTAL RADIOLOGICAL PROGRM SLffMRY j

l YAEEE NJCLEAR POWER SIATION R0WE. IM i

JAMJARY - DECEMBER 1984 I

EDILM: FIFISH LNITS: PCI/KO ET

-5 4

i m

(

IM)!CATOR STATIONS STATION WITH HIGEST M CONTROL STATIONS mmemumm ennunnummuun mmumam 9

R.

RADIOMJCLIDES M

M EAN Y

j

( W. ANALYSES) REQllIRED RANGE STA. RANGE RANGE

[

(N]N-AOLITIEle LLD NO. DETECTEDee NO.

NO. DETECTED **

NO. DETECTEDee it

(;

I RU-106 ( 4)

( 2.2 A

.0)E 1 21

( 4.9 t 5.9)E 1

( 4.9 t 5.9)E 1 Z

l

( 0)

( 2.2 -

2.2)E 1

(-1.1 - 10.8)E 1

(-1.1 - 10.8)E 1 et 0/ 2)*

( 0/ 2)e

( 0/ 2)e 1

I-131 ( 4)

(-1.6 t 1.5)E 2 21

(-5.1 i

.4)E 1

(-5.1 A

.4)E 1

( 0)

(-3.1 -

.1)E 2

(-5.6 - -4.7)E 1

(-5.6 -

-4.7)E 1

(

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

1 a

h CS-134 ( 4) 130.

(-2.9 1 14.9)E 0 11

(-2.9 t 14.9)E 0

(-3.6 1 13.2)E 0 f

( 0)

(-1.8 -

1.2)E 1

(-1.8 -

1.2)E 1

(-1.7 -

1.0)E 1 el 0/ 2)e et 0/ 2)*

a( 0/ 2)*

CS-137 ( 4) 150.

I 5.1 *

.1)E 1 11 ( 5.1 i

.1)E 1

( 4.3 i 1.7)E 1

( 0)

( 4.9 -

5.2)E 1

( 4.9 -

5.2)E 1

( 2.6 -

6.1)E 1

_d a( 2/ 2)*

st 2/ 2)e el 2/ 2)*

v BA-140 ( 4)

(-1.4 i 2.3)E 1 21 ( 3.3 i 8.1)E 1

( 3.3 A 8.1)E 1

( 0)

(-3.7 -

.9)E 1

(-4.9 - 11.4)E 1

(-4.9 - 11.4)E 1 e( 0/ 2)e et 0/ 2)e

( 0/ 2)*

i E-141 ( 4)

( 1.8

1.2)E 1 11 ( !.8 t 1.2)E 1

(-1.9 1 1.7)E 1 g

( 0)

( 6.3 - 29.3)E 0

(-3.7 -

.2)E 1 E

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

I

[

E-144 ( 4)

(-1.6 t 1.8)E 1 II

(-1.6 g 1.8)E I

(-1.6 i 3.2)E 1 E

( 0)

(-3.4 -

.2)E 1

(-3.4 -

.2)E 1

(-4.8 -

1.7)E 1

)

et 0/ 2)e et 0/ 2)*

( 0/ 2)e i

l TM-232 ( 4)

( 2.6 i

.4)E 1 11 ( 2.6 i

.4)E 1

( 2.5 *

.5)E 1

( 0)

( 2.3 -

3.0)E 1

( 2.3 -

3.0)E I

( 2.0 -

3.0)E 1 5

et 0/ 2)s et 0/ 2)*

( 0/ 2)*

y

]

a p

m e NON-ROL! TIE REFERS TO TE N.MBER OF SEPARATE EASUREENTS WHICH ERE GREATER THAN TEN (10) TIES TE AVERAGE BACK(ROLND FOR TE PERIOD OF TE REPORT.

r'

- TE FRACTION 0F SA&LE AMLYSES YIELDING DETECTABLE EASLREENTS I'

(i.E. >3 STD DEVIATIONS) IS INDICATED WITH a(

le.

I I

I r

K) Direct Radiation Direct gamma radiation exposure was determined from the use of thermoluminescent dosimeters (TLDs). One CaSO :Dy TLD dosimeter 4

was placed at each of the monitoring stations.

(Each dosimeter has four readout areas.) A total of thirty-eight stations is required by the Radiological Effluent Technical Specifications. TLDs from twenty-two must be read out quarterly, while those from the remaining sixteen incident response (outer ring) stations need only be de-dosed quarterly, unless a gaseous release LCO was exceeded during the period. During 1984, all TLDs were routinely readout on a quarterly schedule. Table 3.1 provides a summary of the results.

The results for 1984 are similar to those from 1983 indicating no significant change in direct radiation levels. As in 1983, the mean of the indicator stations is slightly below that of the control stations.

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

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

performed in October of 1984 (see Table 3.2).

4

Environmental Radiological Program Summary Yankee Nuclear Power Station Rowe, Massachusetts January - December 1984 Medium: Direct Radiation Measurements (TLD)

Units: Micro-R per Hour Indicator Restricted Control Stations Area Fence Stations Mean Mean Mean Range Range Range (No. Meas.)*

(No. Meas.)*

7.9 17.8 8.4 5.7 - 10.6 12.4 - 28.1 7.1 - 9.4 (52)

(36)

(8)

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

Table 3.1 Yankee Atomic Summary of Direct Radiation Measurements. 1984 Micro-R Micro-R Station Per Hour

Station Per Hour

1 8.1 13 18.6 2

7.9 14 12.9 3

6.6 15 14.0 4

7.0 16 15.4 5

10.0 17 15.3 6

7.7 18 24.0 7

7.3 19 22.7 8

7.9 20 17.9 9

7.7**

21 19.5 10 6.6 22 8.0 11 8.3 23 8.8 12 9.3 40 8.2

Annual average

- Fourth quarter TLD stolen. Annual average based on data from first three quarters only.

O L) Soil-Q During October 1984, soil at seven locations was analyzed for gamma emitting radionuclides using in situ measurements involving both a

-j

-n high purity germanium (HPGe) detector and a high pressure 4

ionization chamber (PIC). Core samples were taken at one of the W.

sites for analysis at the Environmental Laboratory for comparison with the in situ results. The only man-made radionuclide detected in the soil analyzed was Cs-137, which is associated with fallout h

from atmospheric weapons testing and was detected at levels 3

_si consistent with well documented environmental levels. The results y

of these analyses are summarized in Tables 3.2 and 3.3.

(.

1 b

Soil analysis is not required by the Radiological Effluent Technical Specifications.

]

_.-ess r

ik b$

S

=

8E m

3

-i.

g 4

2 3 3 5

8 a

2_

7

=

9)

=m M

A Table 3.2

=T Yankee Nuclear Power Station. Rowe MA Summary of In Situ Soil Analyses S

October 1984

=

m Exposure Rate (Micro-R Per Hour) 5 aM Location Cs-137 K-40 Th-232 U-238 Total

g 3

01 Furlon House 0.23 1 0.01 2.2 1 0.05 1.6 i 0.10 1.0 1 0.05 8.4 0.12 L

4 1

02 Monroe Bridge 0.25 i 0.01 2.7 i 0.06 2.5 i 0.09 1.6 1 0.06 10.7 1 0.13 6

Y 03 Observation Stand 0.27 1 0.01 2.7 i 0.06 1.9 i 0.08 1.2 1 0.05 9.4 i 0.11 s

04 Williamstown 0.15 _+ 0.01 2.7 _+ 0.06. 2.4 _+ 0.09 1.2 _+ 0.05 10.1 _+ 0.12 C

05 Heartwellville 0.24 i 0.01 2.2 1 0.04 2.5 0.09 1.0 0.05 9.5 i 0.11

]

06 Harriman Station 0.19 + 0.01' 2.9 + 0.06 2.5 + 0.10 1.2 + 0.05 10.4 + 0.13

_,m

_=

=

07 Rowe School 0.17 1 0.01 2.1 1 0.05 1.9 0.08 0.93 1 0.05 8.7 1 0.11 9

m

_==

Includes 3.6 uR/hr cosmic component.

2 2

O

=

q A

1 i

4

=

5

]

=

4

- ]

=

s b

a

==1 a

Table 3.3 S

Yankee Nuclear Power Station. Rowe. MA 5

Summary of In Situ Soil Analyses October 1984 7

i Concentration (pCi Per Kilotram)

G Location Cs-137 K-40 Th-232 U-238

_g 01 Furlon House 430 i 19 12100 1 300 590 i 87 550 1 26 H

02 Monroe Bridge 460 1 20 15000 1 340 900 1 33 890 1 33 i'

03 Observation Stand 490 1 22 15000 1 340 670 1 28 660 1 29 04 Wiliiamstown 270 18 15000 340 850 i 31 650 1 28 i

05 Hear?wellville 440 i 19 12000 1 300 900 1 31 540 1 26 h=

06 Harriman Station 340 1 19 16000 1 350 890 1 36 670 1 27 07 Rowe School 320 1 16 12000 1 300 680 28 510 1 25 53 Z

5 5

3

--a Mui M

75.a

=

"iii E

Y Y

i i

i M

=

N,. -

E 3

m:

L f

4.0 QUALITY ASSURANCE PROGRAM I

z Three separate Quality Assurance programs were performed during 1984 to

[

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

YAEL participates in the EPA Interlaboratory Comparison (cross-check) j program for those species and matrices routinely analyzed by the laboratory.

k 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.

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 l

program are reviewed by the responsible cognizant individual, and corrective h

measures are taken whenever applicable.

5 A blind duplicate / replicate program is maintained in which samples are prepared from split or 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.

EPA Interlaboratory and Intralaboratory 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 1984 for EPA 1

samples, intralaboratory analyses, and interlaboratory cross-check analyses.

?

For accuracy, 55.2 and 84.4 percent of the results were within 5 and 10 percent of the known values, respectively, with 96.4 percent of all results falling within the laboratory criteria of 15 percent. Fce precision, 82.2 and 97.2 percent of the results were within 5 and 10 percent of the mean, respectivply, with 100 percent of all results meeting the laboratory criteria of 15 percent.

pp g

~54-64i

+:

'\\_

Table 4.1 EPA Interlaboratory and Intralaboratory Results - 1984 Accuracy Total Number 0 to 5%

0 to 10%

0 to 15%*

of Samples 868 479 733 837 (55.2%)

(84.4%)

(96.4%)

Precision Total Number 0 to 5%

0 to 10%

0 to 15%*

of Samples 850 699 826 850 (82.2%)

(97.2%)

(100%)

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

The results of the EPA Interlaboratory Comparison program, when considered apart from the remainder of the Quality Assurance program, were satisfactory with respect to accuracy and precision in 1984. One-hundred seventeen samples were analyzed (air particulate filters, food, milk, and I

water). A total of 294 analyses were performed (beta, Sr-89, Sr-90, I-131 Ba-140, K. Cs-137, Cr-51, Co-60, 2n-65, Ru-106, Cs-134, Ra-226, Ra-228, and H-3).

Of the 294 analyses, 3 (1.0 percent) did not meet the EPA acceptance criteria for accuracy. The first two of these were beta analyses of air filters. The use of an artificially prepared matrix by EPA, for which no reference nuclide has been quoted and no background air filters have been supplied, has caused the YAEL to question the EPA's results. The problem has been well documented in the past (Reference 3).

The third of these was a Sr-90 analysis of a milk sample. After reprocessing of the originally-analyzed precipitate, the results were acceptable. All of the analyses met the EPA acceptance criteria for precision. Details on all of the above cases may be found in References 4 and 5.

1

Blind Duplicate-Replicate Proaram A total of 57 paired samples were submitted by the five participating plants for analysis during 1984. The data base used for the duplicate-replicate analysis consisted of paired measurements of 26 gamma-emitting nuclides. H-3, Sr-89, Sr-90, low level I-131 and gross beta. A dual level criteria for agreement was established. If the paired measurements fall within i 15 percent of their average value, then agreement between the measurements has been met. If the value falls outside of the i 15 percent, then a two standard deviation range (95 percent confidence level) for duplicates and a three standard deviation range (99 percent confidence level) for replicates is established for each of the analyses. If the ranges overlap, agreement is obtained. One thousand four hundred and fif ty-tAne paired duplicate and replicate measurements were analyzed for 1984. A total of 99.5 percent of all measurements fell within the established criteria discussed above. The seven measurements that did not meet the criteria were measurements of Tel-132 in river water, Fe-59 in milk, cc-51 in ground water, Cr-51 in mussel bodies, Ce-141 in milk, co-58 in seawater, and I-131 in seawater. Each was a single measurement in a 26-radionuclide gamma spectrometry analysis. The seven duplicate measurements represent 0.5 percent of all the blind duplicate-replicate measurements made during 1984. In all the above cases, the radionuclide in question was not present at a detectable level in the sample, and three-standard deviation acceptance criteria was met. No trend was evident with respect to repeated failings of measurements for the above radionuclides.

/

5.0 LAND 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 vesetables in each of the sixteen meteorological sectors within a distance of five miles. The 1984 census was completed on August 8.

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

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

Table 5.1 1984 Land Use Census Results Nearest Nearest Nearest Residence Milk Animal Garden Sector (km)

(km)

N 2.4 6.3 3.5 NME 4.5 7.4 4.8 NE 3.7 3.7 3.7

'ENE 3.1 7.7 E

3.1 6.0 3.1 ESE 3.4 6.0 3.4 2.3 SE 2.3 SSE 2.1 2.1 S

2.3 2.3 SSW SW 1.3 1.3 WSW 1.3 1.3 W

1.9 1.9 WNW 1.9 1.9 1.9 NW 0.45 0.45 NNW 2.9 3.9 3.9

/

6.0

SUMMARY

During 1984, as in 1983, samples collected as part of the' radiological environmental monitoring program at Yankee Atomic showed detectable levels of man-made radionuclides in cow milk, ground water, river water, sediment, soil, l

i finfish, and maple syrup. The H-3 detected in ground water (sta. WG-12, Sherman Spring) and river water (Station WR-11, Bear Swamp Lower Reservoir) l were the only radionuclides possibly related to plant operations. Since water from the spring or the Deerfield River is not consumed by man, there would be no impact on man from the low levels detected. The dose to an imaginary person who consumed large 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 ground waters), the dose to man was negligible when compared to natural background radiation and its yearly fluctuations.

The Cs-137 detected in cow milk, sediment, soil, finfish, and maple

~~

syrup, as well as the Sr-90 detected in cow milk, originated from atmospheric nuclear weapons testing fallout and not from plant operations.

G

REFERENCES 1.

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

2.

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.

l 3.

YAEL Quarterly Status Report, October-December 1983 Environmental Laboratory Group, Yankee Atomic Electric Company.

4.

YAEL Quarterly Status Report, April-June 1984. Environmental Laboratory Group, Yankee Atomic Electric Company.

5.

YAEL Quarterly Status Report, October-December 1984. Environmental Laboratory Group, Yankee Atomic Electric Company.

O l

YANKEE ATOMIC ELECTRIC COMPANT "'

Te'epho"e (6") 8' -*'oo TWX 710 380 7619 2.C.2.1

(,

's 1671 Worcester Road, Framingham, Massachusetts 01701 yyg 85-50 C

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k May 1, 1985 y

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'I United States Nuclear Regulatory Comission I

Region I li 631 Park Avenue King of Prussia, PA 19406

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Attention:

Dr. Thomas E. Murley, Regional Administrator

Reference:

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

I

Subject:

Annual Radiclogical Environmental Report

Dear Sir:

+

Enclosed herewith please find three (3) copies of the Annual Radiological 1

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 1984, and is submitted as required by Technical Specification 6.9.5(a),

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Please contact us if you have any questions in regard to this material.

L L

h-Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY I

GK E

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. A. Kay Senior Project Engineer - Licensing

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ML20128D106

Contents

Text

1.0 INTRODUCTION

SUMMARY

SUMMARY

1.0 INTRODUCTION

SUMMARY

SUMMARY

Reference:

Subject:

Dear Sir:

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ML20128D106

Text

1.0 INTRODUCTION

SUMMARY

SUMMARY

1.0 INTRODUCTION

SUMMARY

SUMMARY

Reference:

Subject:

Dear Sir:

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