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Annual Radiological Environ Operating Rept for 1990
	ML20024G961
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	12/31/1990
From:	Mroczka E; CONNECTICUT YANKEE ATOMIC POWER CO., NORTHEAST UTILITIES
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	B13802, NUDOCS 9105030410
	Download: ML20024G961 (83)
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(203) 665 5000 April 24, 1991 Docket No. 50-213 Ill3M2 Re:

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U.S. Nuclear Regulatory Commission Attention:

Document Control Desk Washington, DC 20555 Gentlemen:

Haddam Neck Plant Annual Radiological Environmental Operatina Report in accordance with the requirements of the Haddam Neck Radiological Effluent Monitoring Manual, an implementing document of the Haddam Neck Technical Specifications

-two (2) copies of the Annual Radiological Environmental Operating Report are herewith submitted.

Copies of this report are being distributed in accordance with 10CFR50.4(b)(1).

Very truly yours, 1

CONNECTICUT YANKEE ATOMIC POWER COMPANY E. J.' ~

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ocz a Senior Vice President cc:

T. T. Martin, Region 1 Administrator

'A. B. Wang, NRC Project-Manager, Haddam Neck Plant J. T. Shediosky, Senior Resident inspector, Haddam Neck Plant 1

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U.S. Nuclear Regulatory Commission I

Attention:

Document Control Desk l

Washington, DC 20555 Gentlemen:

Haddam Neck Plant Annual Radiolooical Environmental Operatina Report n

In accordance wxth the requirements of the Haddam Neck Radiological Effluent I

Monitoring Manual, an implementing document of the Haddam Neck Technical Specifications, wo (2)- copies of the Annual Radiological Environmental Operating Report are herewith submitted.

Copies of this report are being distributed in accordance with 10CfR50.4(b)(1).

Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY

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E. J.'

oczka ' (/

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l Mu Senior Vice President cc:

T. T. Martin, Region 1 Administrator A. B. Wang, NRC Project Manager, Haddam Neck Plant I

J. T. Shedlosky, Senior Resident inspector, Haddam Neck Plant I

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HADDAM NECK STATION RAO!OLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT PERIOD JANUARY 1,1990 - DECEMBER 31,1990 1

I DOCKET NO. 50 213 I

LICENSE NO. DPR-61 I

I PREPARED FOR THE I

CONNECTICUT YANKEE ATOMIC POWER COMPANY H ADDAM, CONNECTICUT BY THE l

NORTHEAST UTILITIES SERVICE COMPANY BERLIN, CONNECTICUT I

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I TABLE OF CONTENTS Pace No.

1.0 S u m m a ry............................

1-1 1

2.0 Program Description 2-1 I

2.1 Sempling Schedule and Locations 2-1 2.2 Samples Collected During Report Period.....................

27 3.0 Radiochemical Results............

3-1 3.1.

Summary Table 31 3.2 Dat a Ta b l es..............................

3-14 4.0 Discussion of Results..........

4-1 I

5.0 Offsite Dose Equivalent Commitments 51 6.0 -

Discussion 61 I

Appendix A - Cow and Goat Census for 1990 A-1 Appendix B - Northeast Utilities QA Program...........................

B1 Appendix C - Summary of EPA Interlaboratory Comparisons................

C-1 I

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SUMMARY

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The radiological environmental monitoring arogram for the Haddam Neck PIant was continued for the period January throuq, ffsite Dose Calculation Manual. This 1 December 1990, in compliance with E

the Radiological Effluent Monitoring and O annual report was prepared for the Connecticut Yankee Atomic Power Company (CYAPCO) by the Radiological Assessment Branch of the Northeast Utilities service Company (NUSCO) Gamma exposure measurements were performed by NUSCO at I

the Production Operations Services Laboratory. All remaining laboratory analyses were performed by Teledyne Isotopes, Inc. Yankee Atomic Environmental La boratory was used to independently check on the primary contractor's laboratory as part of he overall quality assurance program.

Radiological analyses were performed with gamma exposure measuring devices 3

and on samples of air particulates and iodine, milk, broad leaf vegetation, well E

water, fruits, vegetables, river water, bottom sediment, shellfish, and fish. In evaluating the results of these analytes it is necessary to consider the variability of radionuclide uptake in environmental media. This variability is dependent on many

,I factors, including plant release rates, meteoroloc y, number and size of nuclear weapon tests, seasonal variability of fallout, soil claracteristics, farming practices, and feed type. Significant variations in measured levels of radioactivity could be I

caused by any one of these factors. Therefore, these factors need to be considered in order to properly explain any variations.

The predominant radioactivity, indicated by the results, was that from nonplant

.l (not Haddam Neck) sources, such as fallout from nuclear weapons tests and naturally occurring radionuclides. As typical of previous years, plant related radioa:tivity was observed at some of the onsite gamma monitoring locations and I

in several other environmental samples. These include tritium in well water at the on site location, tritium in river water near the East Haddam Bridge, cobalt-60, and cesium 137 in bottom sediment from near the end of the canal, cesium-137 in shellfish downstream of the discharge canal, and cesium-137 in fish.

As usual, cesium-137 and strontium 90 were measured in both cow and goat milk.

These levels are a result of nuclear weapons testing in the 1960's and not the result I

of plant operation. This can be concluded based on the facts that: insufficient quantities (at least 1000 times less) of these isotopes have been released by the plant to account for the measured concentrations, chemically similar and plant related cesium 134 and strontium-89 have not been detected and comparable levels of cesium-137 and strontium-90 were detected prior to initial plant operation.

I During 1990, the Haddam Neck Station was shut down from January through t

August for a refueling outage. In August the unit started up and excluding a few short shutdowns, remained in opvation throughout the rest of the year.

The radiation dose (dose equivalent commitment) to the general public from the plant's discharges has been evaluated by two methods. One method utilizes the measured station's discharges and conservative transport models and the other I

utilizes the measured concentrations of radioactivity in the environmental media.

J The maximum whole body dose (station boundary) that could occur to a member of the general public as a result of the plant's discharges was 0.27 millirem and the I

average dose to a member of the public residing within 50 miles of the plant is 0.00021 millirem. These doses are 1.1 percent and 0.00084 percent of the standards as set by the Environmental Protection Agency on the maximum allowable dose to an individual of the general public. These standards are a small' fraction (le.ss I

than 70 percent) of the 280 mrem per year normal background radiation and are i

1-1 I

I ard to public health and safety. Plant related designed to be inconse uentialin refhe natural background; they are less than 10 doses are even a smaller fraction of percent of the variation in natural background in Connecticut, Therefore, for the I

above stated reasons the plant related doses have insignificant public health consequences.

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B 2.0 PROGRAM DESCRIPTION 2.1 Samplina schedule and Locations The sample locations and the sample types and frequency of analysis are given in Table 21 and 2 2 and Figures 2.1 and 2.2. The program as described here 4

includes both required samples as specified in the Radiological Effluent I

Monitoring and Offsite Dose Calculation Manual and any extra samples.

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21

TABLE 2-1 ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS The following lists the environmental sampling locations and the types of samples obtained at each location.

I Direction & Distance From Number Name Release Point" Sample Typy 1 -l

On site Mouth of Discharge Canal 1.1 Mi, ESE TLD 21 Haddam-Park Rd.

0.8 Mi,5 TLD I

31 Haddam Jail Hill Rd.

0.8 Mi, WSW TLD 41 Haddam Ranger Rd.

1.8 Mi, SW TLD, Air Particulate, lodine g

5-l On site-Injun Hollow Rd.

0.4 Mi, NW TLD, Air Particulate, lodine 6-1 On site-Substation 0.5 Mi, N E TLD, Air Particulate, lodine, Veg 71 Haddam 1.8 Mi, SE TLD, Air Particulate, lodine 8l East Haddam 3.1 Mi, ESE TLD, Air Particulate,lodme 91 Higganum 3.2 Mi, WNW TLD, Air Particulate, lodine I

10-1 Hurd Park Rd.

2.8 Mi, NNW TLD 11-C Middletown 9.0 Mi, NW TLD 12 C Deep River 7.1 Mi, SSE TLD 13-C North Madison 12.5 Mi, SW TLD, Air Particulate, lodine I

14 C Colchester 10.5 Mi, NE TLD 15-1 On site Wells 0.8 Mi, ESE Well Water i

I 16-C Well State Highway Dept. E. Haddam 2.8 Mi, S E WellWater 17-C Fruits & Vegetables Beyond 10 Miles Vegetation 18 l Site Boundary 0.4 Mi, NW Vegetation 19 1 Cow Location #1 5.5 Mi, ENE Milk 3.7 Mi, E Milk I

20-1 Cow location #2 6.0 Mi, NW Milk 21-1 Cow Location #3 4.5 Mi, NE Milk 22-C Cow Location #4 11.0 Mi, E NE Milk 23-C Goat Location # 1 17.0 Mi, NE Milk 24 1 Goat Location #2 4.5 Mi, N Milk 25-l Fruits & Vegetables Within 10 Miles Vegetation 26-1 Conn. River Near intake 1.0 Mi, WNW Fish I

27-C Conn. River Higganum Light 4.0 Mi, WNW Bottom Sediment, Shellfish 28-l Conn. River E. Haddam Bridge 1.8 Mi, SE Bottom Sediment, River Water 28-X Conn. River E. Haddam Bridge 1.8 Mi, SE Snellfish l

29-l Vicinity of Discharge Bottom Sediment, Fish 30-C Conn. River Middletown 7.6 Mi, NW River Water, Fish 31-1 Mouth of Salmon River 0.8 Mi, ESE Shellfish I

40-X Near intake Structure 0.1 Mi, SSW TLD 41-X Picnic Area 0.3 Mi, WNW TLD l

42-X Environmental Trail 0.1 Mi, NW TLD 43-:.

Moodus - Rts 149 & 151 2.5 Mi, ENE TLD 2-2

TABLE 2-1 (Cont'd) g Location Direction & Distance From

.I Number Name Release Point" Sample Types 44-X Shailerville Horton Rd.

1.0 Mi, SE TLD 45 X Old Waste Gas Sphere Fence 0.1 Mi, E TLD j-46 X Discharge Canal Fence 0 2 Mi, SE TLD 47 X Info Center 0.1 Mi, WNW TLD I

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- The release points are the stack for terrestriallocations and the end of the discharge canal for aquatic locations.

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l TABLE 2 2 HADDAM NECK RADIOLOG! CAL ENVIRONMENTAL MONITORING PROGRAM Sampling &

Exposure Pathway Number of Collection and/or Sample t ocations Aeavency Type & Frecuency of Analvsji 1a. Gamma Dose-14 Monthly Gamma Dose Monthly Environmental TLD Ib. Gamma Dose.

27 Quarterly (a)

N/A(a)

Accident TLD 2.

Airborne Particulate

?

Continuous sampler -

Gross Beta - Weekly weekly filterchange Gamma Spectrum - Quarterly on composite (by location), & on individual sample if gross E

beta is greater than 10 times the mean of the weekly control stations gross beta results 3.

Airborne lodine 7

Continuous sampler -

I l 131 Weekly weekly canisterchange 4,

Vegetation 4

One sample near middle Gamma isotopic, Sr 89 and Sr-90on each

& one near end of sample I

growing season 5.

Milk 6

Monthly Gamma Isotopic,1 131, Sr 89 & Sr-90 on each sample 6.

Well Water 2

Quarterly Gross Beta, Gamma Isotopic, & Tritium on each sample 7.

Bottom 5ediment 3

Quarterly Gamma isotopic 8.

River Water 2

Quarterly Sample -

Quarterly - Gross Beta, Gamma isotopic &

'l Indicator is Continuous Tritium E-Composite: Background is composite of Six weekly Grab Samples

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Fish Bullheads 8, 3

Quarterly Gamma Isotopic-Quarterly when available.

Perch or other edible I

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10. Shellfish 2

Quarterly Gamma isotopic - Quarterly I

(a) Accident monitoring TLDs to be dedosed at least quarterly ll 2-4 l

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2.2 Samples Collected Durina Report Period The following table summarizes the number of samples of each type collected during the present reporting period:

Number of Number of Sample Type Required Samples Extra Samples Gamma Exposure (TLD) 168 96 Air Particulates 364 0

Air lodine 364 0

l Dairy Milk 48 1

Goat Milk 23 0

l Well Water 8

0 Fruit & Vegetables 8

0 Broad Leaf Vegetation 4

8 River Water 8

0 Bottom Sediment 12 0

Fish 24 2

Shellfish 12 0

Total AllTypes 1,043 107 I

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2-7

3.0 RADIOCHEMICAL RESULTS 3.1 Summary Table In accordance with the Radiolo ical Effluent Monitoring Manual (REMM)d Section F.7, a summary table of he radiochemical results has been prepare and is presented in Table 3 f.

In the determination of the mean, the data was handled as recommended by the Health and Safety Laboratory, Idaho and NUREG/CR-4007 (Sept.1984): all I

valid data, including negative values and zeros were used in the determina-tion of the mean (see Part 3.2).

A more detailed analysis of the data is given in Section 4.0 where a discussion I

of the variations in the data explains many aspects that are not evident in the Summary Table because of the basic limitation of data summaries.

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I FOOTNOTES A,
For Ge(Li) measurements the MDL's== LLD + 2.33. For all others, MDL = 2 x o background. These MDL's are based on the absence of large amounts of interfering I
activity (excluding naturally occurring radionuclides). Deviations by about factors of 3 to 4 can occur.
I The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with a 5% probability of falsely concluding that a blank observation represents a "real" signal.
l For a particular measurement system (which may include radiochemical separation):
4.66 5b LLD =
E
V
2.22
Y
exp (4 3t) where LLD is the lower limit of detection as defiaed above (as pti per unit mass or volume)
I sb s the standard deviation of the background counting rate or of i
the counting rate of a blank sample as appropriate (as counts per minute)
E is the counting efficiency (as counts per transformation) l V is the sample size (in units of mass or volume) 2.22 is the number of transformation per minute per picocurie Y is the fractional radiochemical yield (when applicable)
A is the radioactive decay constant for the particular radionuclide at is the elapsed time between sample collection (or end of the sample collection period) and time of counting it should be recognized that LLD is defined as a priori (before the fact) limit representi the capabilit of a measurement system and not as a posteriori(after th fact)li t for a particu ar measurement.
Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these a priori LLDs unachievable. In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report.
B.
Analytical results are handled as recommended by HASL (" Reporting of Analytical Results from HASL," letter by Leo B. Higginbotham) and NUREG/CR 4007 (Sept.1984). Negative values were used in the determination of mean.
C, Nonroutine reported measurements (NRM's). These are results of samples that jl exceed the report levels of Table E 2 of the Radiological Effluent Monitoring l n Manual.
l 3-12 l
..=.
. ~. -
l FOOTNOTES (Cont'd)
D.
First number is the number of indicator measurements, the second is the number of I
control measurements.
E.
Assuming 270 m3/ paper F.
Assuming 1080 m3 G.
LLD for leafy vegetables.
H.
Reduce LLD by a factor of two if the fractional beta for the sample exceeds 15 pCi/l.
l 1.
LLD from the end of the sample period.
1 I
I i
I I
I I
I LE
~
I 3-13
I l
3.2 Data Tables The data reported in this section are strictly counting statistics. The reported E
error is two times the standard deviation of the not activity. Unless otherwiso
-5 noted, the overall error (counting, sample size, chemistry, errors, etc ) is estimated to be 2 to 5 times that listed, f
Because of countin statistics, ne ative values, zeros and numbers below the Minimum Detectabfe Level (MDL) are statistically valid pieces of data. For the purposes of this report, in order to indicate any background biases, all the I
valid data are presented. In instances where zeros are listed after significant digits, this is an artifact of the computer data handling program.
Data are given according to sample type as indicated below.
1.
Gamma Exposure Rate 2.
Air Particulates, Gross Beta Radioactivity 3.
Air Particulates, Weekly 1 131 4.
Air Particulates, Quantitative Gamma Spectra I
5.
Air Particulates, Quarterly Strontium
6.
Soit*
7.
Milk Dairy Farms 8.
Milk - Goat Farms 9.
Pasture Grass *
10. Well Water 1
11.
Reservoir Water
I
12. Fruits & Vegetables 13.
Broad Leaf Vegetation 14.
River Water l
15.
Bottom Sediment
16. Shellfish 17.
Fish I
g
This type of sampling or analysis was not performed, therefore there is no table.
3 14
N N
E' N
E E
E O
N M
E E
PAGE 3-15 TA8tE 1 CONNECTICUT VCHKEE 19PO '
MONTHLV GA.9tA EXPOSURE RATE EUR/t*RI LCCATIONS PERIOD 1
2 3
4 5
6 7
8 9
le 11C JAN 90 e.0
.e 6.0
.2 e.8 1
6.1
.2 7.8
.2 7.2
.I 6,6
.8 7.9
.6 e.9
.2 8.0
.1 9.3
.2 FE8 90 6.2
.2 6.5
.2 7.1
.1 0.5
.1 7.9
.e 7.3
.e 6.5 9
e.2
.1 6.7
.2 8.4
.e 9.0
.e MAR 99 6.1
.1 6.4
.e 6.8
.1 6.0
.2 7.9
.2 7.6
.4 6.5
.1 8.0
.2 6.9
.1 8.6
.2 9.3
.3 QPR 4e 6.8 1
6.2
.1 6.6 1
6.3
.2
.6
.0 7.0
.1 6.4
.8 8.0
.3 6.6
.2 8.4
.2 8.9
.8 MAY 99 6.0
.2 6.3
.1 6.8
.2 6.2
.2 7.9
.e 7.7
.2 6.5
.1 8.8
.1 6.9
.2 8.4
.1 8.3
.3 JUN 99 6.4
.9 e.7
.e 7.1
.1 6.7
.2 8.9
.1 7.4
.6 6.3
.1 8.3
.3 6.9
.3 8.1
.1 8.5
.2 JUL 99 6.5
.1 6.8
.9 6.9
.1 6.3
.1 8.3
.e 7.5
.2 6.6
.5 8.e
.1 7.1
.3 8.8
.e 8.5
.1 AUG 90 e.2
.1 6.7
.1 7.0
.1 6.6
.1 8.8
.2 7.5
.e 6.2
.1 8.3 4
6.9
.3 8.2
.8 8.4
.3 SEP 96 6.2
.2 6.8
.2 7.9
.1 6.3
.1 8.3
.3 7.9
.3 6.6
.8 7.7
.2 7.9
.1 8.2
.e 8.6
.2 DCT 98 6.3
.e 6.8
.1 7.3
.1 e.8
.1 8.2
.e 7.7
.1 6.9 9
8.6
.4 7.2
.1 8.e
.2 8.8 4
NOV 99 6.2
.1 6.9
.2 6.9
.1 6.3
.1 8.1
.3 7.8
.2 6.7
.1 8.1
.e 7.2
_e 8.5
.1 8.7
.2 DEC 99 6.1
.1 6.6
.2 7.2
.1 6.e
.3 7.8
.9 7.6
.4 6.3
.1 8.5
.2 7.1
.2 9.8
.e 8.4
.2 PERIOD 12C 13C 14C 4eX 41X 42X 43X 44X 45X 46X 47X JAN 98 e.7 4
e.9
.I 5.1 1
7.2
.6 e.1
.3 49.8 I A 7.6
.6 6.6
_I 18.2
.1 7.8
.2 51.8 9
FE8 99 6.7
.3 6.2
.e 8.1
.2 7.7
.1 5.9
.2 53.3 18 7.7
.9 7.0
.9 18.7
.1 7.9
.3 56.7 1C MAR 99 6.4
.3 6.3
.5 8.4
.1 7.5
.1 5.4
.8 78.4
.5 7.6
.8 6.*
.1 11.4
.2 7.6
.2 57.5 1D APR 90 6.5
.1 6.1
.1 7.9
.1 7.7
.1 5.4
.3 64.5 1E 7.6
.1 7.0
.1 11.2
.2 8.0
.1 75.8 1G MAY 95 6.1
.4 6.5
.2 8.4
.8 7.3
.1 5.9 1
57.6 1F 7.8
.1 6.9
.1 18.8
.3 7.5 2
54.1 1H JUN 99 6.8
.1 e.3
.e 8.5
.e 8.9
.2 6.1
.e 12.2
.3 K 8.1
.1 7.5
.2 11.7
.1 8.1
.e 19.3
.8 K JUL 40 6.7
.4 6.6
.4 5.4
.e J 9.0
.8 8.1 1 I 11.8
.e 8.2
.1 7.4
.e 11.0
.2 7.8
.2 10.5
.1 AUG 99 6.6
.e 6.3
.e 8.4
.1 7.4
.1 5.8
.1 11.8
.8 8.0
.e 7.4
.2 11.2
.5 8.0
.e J 9.1
.3 SEP 90 6.7
.3 7.5
.1 8.6
.1 7.2
.1 6.5
.1 11.5
.8 8.3
.3 7.3
.8 le.7
.1 7.9
.2 8.9
.1 OCT 9e 6.8
.9 6.6
.1 8.7
.2 7.7
.2 5.7
.2 11.3
.1 8.1
.1 7.6
.1 11.2
.e 8.1
.1 9.9
.4 NOV 90 e.5
.4 e.5
.2 8.6
.1 7.7
.6 5.5
.9 11.4
.2 8.0
.9 7.1
.9 10.5
.e 7.5
.1 9.5
.3 DEC 90 6.8
.2 6.4
.1 S.5
.2 7.6
.1 5.7
.1 11.9
.1 7,9
.e 7.4
.1 19.8
.3 8.1
.2 9.7
.e ERRORS LISTED ARE 1 SICMA.
A: ERROR = 1.28.
8: ERROR = 3.27.
C: ERROR = 1.68.
D: ERROR = 6.23.
E: ERROR = 3.83.
F: ERROR = 1.09, G: ERROR =11.91.
H: ERROR = 4.27.
1: E RROR = 2.38.
J: SINGLE TLD RESULT. CO-LOCATED TLD RESULT WAS LOST.
LOCATION (423 WAS MOVED 498 FT, NW AND LOCATION (47) WAS LOVED 608 FT,Soet K:
TO INCREASE THE DISTAMCE FROM THE ONSITE RAD WASTE STORAGE AREA.
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(*/-)
(*/-)
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-2.4 4.0 7.8 1.9 8.s6 9.16
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(PCI/tt l
1 00tLECTION LOLATION DATE SR-89 SR-99 I-131 CS-134 CS-137 BA-140 LA-140 t*/-)
(*/-)
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(*/-3 23C 32/28/*e C e.3 2.1 0.2 c.2 S.le e.11
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-5.5 8.4
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1 A: BA-140 MDL OF 25 WAS 9007 MET D'JE TO A DELAY IN SAMPLE AMALYSIS.
D:
LA-14e MDL OF le WAS NOT MET DUE TO A DELAY IN SAMPLE AMALYSIS.
C: NEITHER MILK 900# PASTUEFE GRASS WERE AVAILABLE AT LOCATION E23Cp IN JAMUAeY.
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CopeeECTICUT Vale (EE 1949 TABLE le PACE 3-28 WELL WATE3 (PCI/L)
COLLECTION LOCATION DATE K-4 s
.....__-51_..___
CR 996-54 00-58 FE-59 CD
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15 03/13/99
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16
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15 96/11/98
-5 25 7
21 2.5 1.8
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-3 34
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29
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_....__-95____._
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15 89/24/99
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28 92/12/99 15 24
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COLLECTION LOCATION DATE ZM-65 ZR 95 NB 5 2U-103 SU-106 1-131
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COLLECTION LOCATION DATE CS-134
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LOCATION DATE H
BETA 1
(*/-)
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28 92/12/*e 31 122 8.74 1.36 28 85/14/99 235 86 1.49 9.72 28 98/14/99 226 lol 3.69 e.81 28 11/12/96 19e 81 2.06 0.71 3DC el/28/94
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il 4.0 DISCUSSION OF RESUL TS This section summarizes the results of the analyses of environmental media g
sampled. NUSCO has carefully examined the data throughout the year and has I
l3 presented in this section all cases where plant related radioactivity could be detected and compared the results with previous environmental surveillance data.
I Naturally occurring nuclides such as Be 7, K-40, Ra 226 and Th-228 were detected in l
numerous samples. Be 7 which is produced by cosmic processes was observed i
predominantly in airborne and vec etation samples. Ra-226 and Th 228 results were variable and are generally at level higher than plant related radionuclides.
l Cs-137 and Sr 90 were observed at levels similar to those of past years. In general, the detectable levels of Cs-137 and Sr 90 were the result of atmospheric nuclear I
weapons testing of years past.
1990 is the first year Teledyne Isotopes, Inc. was used as the primary contractor for i
NUSCO to provide analytical services on environmental media. Generally the quality of data was excellent. In a few instances, the laboratory has had to work j
with the requirements and quality expectations of this environmental program and revise their data analysis and reporting methods accordingly. This resulted in a few I
l problems. One such problem was the occurrence of false positives. A number of occurrences of Nb 95 and Cs-134, and a few occurrences of other nuclide positives were noted. These positives were reported in almost all types of samples. Because they had rarely been reported in the past, special scrutiny and investigations were invested to verify their presence. After thorough investigation of spt:ctral data, Teledyne verified that tqe reported positives were not real in almost every case.
I The occurrences were a result of data sof tware problems. All data was corrected and is reported in the Data Tables in Section 3 of this report.
Another problem with data reporting by Teledyne that can be observed in almost all gamma analysis results is the negative bias of reported 2n 65. Again data software problems are caus,ing these occurrences. 2n 65 has a gamma spectral peak at 1115 kev that is af fected by the naturally occurring Bi 214 peak at 1120 kev. The
_I higher background near the 1115 kev peak causes a larger background subtraction and resulting negative bias. The 2n 65 bias is being investigated on both its effects on 1990 data and for the best possible solution. This problem will be tracked during 1991. Results of the analyses of " spiked samples" containing 2n 65 as part I
of the Quality Assurance program, showed that with the aresence of Zn 65 in a sample, the negative bias had minimal if any effect on t le accuracy of results.
Therefore, there is little reason to believe that the possible undetection of Zn-65 in I
routine environmental samples occurred. 2n 65 has not been observed in any 5
Connecticut Yankee environmental samples since 1983 and based on effluent measurements there is no reason to expect its presence in 1990.
Gamma Exposure Rate (Table 1)
Gamma exposure from all sources including cosmic arid utner natural and ariificial radioactivityis measured over periods of approximatelf ane month using CaF (Mn) 2 thermoluminescent dosimeters (TLDs). These dosimeters are strategically placed at a number of on site locatiuns, as well as at inner and outer off-site locations. Glass bulb type TI.Ds such as these, are subject to inherent self irradiation which has been experimentally measured for each dosimeter. The results, shown in Table 1 have been adjusted for this effect. The range of this correction for field dosimeters is 0.4 uR/hr to 2.0 pR/hr,with a meen of approximately 1 pR/hr.
41
I I
I The data for 1990 exhibits the same trends as that of previous years; ganvna exposure rates did not differ significantly for the off site inner and outer ring loc 6tions. The on site locations at the boren waste storage tank (location 42X) and guardhouse fence (location 47X) were moved in June. The dosimeters were alaced in areas further from where radwaste processing occurs as shown in the ligher exposure rates seen in January May results. The old locations are within the plant's restricted area and, as such, are away from areas where members of the l
general public are usually allowed. Dosimeters located at areas which are accessible to the public, such as the picnic area (location 41X) and the mouth of the dis:harge canal (location 01), do not indicate any change in exposure rate due to the plant at any time.
Air Particulates and lodine (Table 2,3,4 A L and 5)
Il Air is continuousi sampled at six inner rin$ese are collected weekly and an it through glass ifber particulate filters. T and one outer ring location by passing for gross beta radioactivity. Results are shown on Figure 44 and Table 2.
I Gross beta activity rema'.1ed at levels similar to that seen over the last eight years.
Inner and outer ring rionitoring locations showed no significant variation in measured activities. This indicates that any plant contribution is not measurable.
I Charcoal cartridges are included at all of the air particulate locations for the collection of iodine. No detectable levels of 1131 were seen in the 1990 charcoal samples. This is confirmed by the absence of I 131 in any of the milk samples. Milk j
from cows and goats is a much more sensitive indicator of I-131 presence in the environment.
ig The weekly air particulate filters are composited quarterly for gamma spectral
'3 analyses. The results, as shown in Tables 4A 40, indicate the presence of naturally occurring Be 7, which is produced by cosmic processes. Positive results for all the other isotopes are attributable to statistical fluctuations in counting. These i,
analyses indicate the lack of plant effects.
Table 5 in past years was used to report the measurement of Sr-89 and Sr 90 in
.E quarterly composited air particulate filters. These measurements are not required
!E by the Radiological Effluent Monitoring Manual (REMM) and have been discontinued. Previous data has shown the lack of detectable station activity in this media. This fact, and the fact that milk samples are a much more sensitive indicator I
of fission product existence in the environment, prompted the decision for discontinuation, in the event of widespread plant contamination or special event such as the Chernobylincident, these measurements may be made.
Soil (Table 6)
!g Soil samples are special samples not required by the REMM. Previous data has lg shown the lack of detectable stawn activity in this media resulting in discontinuing these samples. In the event of widespread plant contamination or special studies, these sample would be collected.
I il 42
I
_ Cow Milk (Table 7)
I Analysis of milk samples is generally the most sensitive indicator of fission proc [uct existence in the terrestrial environment. This, in combination with the fact that I
consumation of milk is significant, results in this pathway usually being the most critical from the plant release viewpoint. This pathway also shows significant amounts of nuclear weapons testing fallout. Therefore this media needs to be evaluated very carefully when trying to determine if there are any plant ef fects.
St 90 was observed in nearly all samples; the range of results was 0.0 to 7.8 pCill.
Detailed analysis of previous data has concluded that these levels of Sr-90 are from
'E weapons testing and are not plant related (see Section 6.0 for details to this 5
argument). Sr 89 was not detected in any of the samples above its MDL This isotope is usually released from the plant in quantities similar to those of Sr-90, g
indicating that Sr 90 is the result of weapons testing and not from the plant. Sr-89 5
is only detceted in these samples during episodes of fresh fallout from weapons testing.
I Cs-137 usually shows the same tendencies as Sr-90. Results for 1990 are similar to those of the past twelve years. Detailed analysis has concluded that these concentrations are most likely the result of fallout from previous weapons testing (see Section 6.0 for details). Cs 134 was not observed above detectable levels in any I
of the samples, further confirming the absence of plant effects. Although not listed on Table 7, the only other nuclide detected by gamma spectrometry was naturally occurring K 40.
All samples showed a lack of I 131 detectable above the MDL of 0.5 pCi/l. These results are consistent with previous years' results. The only occasions when this I
nuclide has been detected are those irnmediately following atmospheric testing of nuclear weapons and the Chernobyl accident.
Goat Milk (Table 8)
I Depending on the feeding habits, goat milk can be e more sensitive indicator than cow milk of fission products in the environment. This is due to the metabolism of I
these animals. Similar to the results of the cow milk samples, these show significant amounts of nuclear weapons testing fallout.
Sr 90 and Cs 137 were observed in all samples, with values similar at both locations.
I In previous years (1977 1983) the control location had significantly higher values than the indicator location. This difference in results between locations decreased substantially with a change in farms in 1983. The difference in results demonstrate I
the variability in the uptake of fallout levels among various farms. This variability is caused by many factors, including feeding habits (amount of stored feed, etc.), soil characteristics, farming practices (tillage and quality of fertilization and land management), and feec type. For a complete discussion of the problem see I
Section 6.0. As typical of periods lacking fresh fallout, no detectable Sr-89 was seen in these samples. The absence of Sr 89 and Cs 134 confirm that the levels of Sr 90 and Cs 137 are caused by previous weapons fallout.
All samples showed a lack of I 131 detectable above the MDL of 0.5 pCi/l. These results are consistent with previous years' results. The only occasions when this nuclide has been detected are those immediately following atmospheric testing of nuclear weapons and the Chernobyl accident.
I 43
I l
Pasture Grass (Table 9)
When the routine milk samales are unavailable, samples of pasture grass are required as a replacement. T1ese sampks may also be taken to further investigate I
the levels of radioactivity in milk. During January pasture grass was not available as a replacement at goat location #1, hence, no pesture grass samples were taken in 1990. In samples of past years, no plant effects were seen in this media.
I WellWat_e_r (Table 10)
I Ac.tivity in ibis media results from either soluble plant effluents permeating through tiie ground or the leaching of naturally occurring nuclides from the soil and rr,ck. H 3 and Gross Beta were detected in these samples, at levels similar to previtius years. Cs 137 was observed in an indicator sample. Its value is similar to
-I what has been observed in past years in both indicator and control samples and has been shcwn not to be plant related.
I As usual the on site wells (location 75) exhibited plant related H 3 significantly above backaround levels.
This plant effect results from the wells being located within an area influenced by the water in the discharge canal and H 3 having the ability to readily follow the flow of ground water. Off site concentrations are much I
lower. This pathway does not result in any dose consequence since the water from these wells is used only in process streams at the station.
I Also consistent with previous years, some gross beta values for the control location et the State Highway Department (location 16C) were higher than the values for
'he indicator location. This activity is due to the teaching of naturally occurring g
nalides. Variations can be caused by different flow patterns of the ground water, E
variable permeability of the different soil and rock formations, and the usage pattern of the wells. Therefore, the results of this type of analysis are not very indicative of plant effects.
Reservoir Water (Table 11)
I Reservoir water samples are special samples not required by the REMM. Previous data has shown the lack of detectable station activity in this media. This fact and the extremely unlikely possibility of observing routine plant effluents in this media has resulted in discontinuing these samples. In the event of widespread plant I
contamination, these samples would be collected.
Fruits and Veaetables (Table 12)
Sirnitar to past years, this media did not show any plant effects. Concentrations of Sr-90 in these samples existed at levels comparable to past years and is due to fallout. Naturally occurring K-40 was detected in all samples. Since there was no I
fresh f allout, no other nuclides were detected.
Broad Leaf Vegetation (Table 13)
Concentrations of Sr-90 and Cs-137 in these samples are at levels comparable to past years and are due to fallout. In the past, this media has shown early indication of I 131 release from the plant from both uaplanned releases and normal I
operations. Therefore, to enhance program monitoring effectiveness, samples of broadleaf vegetation are collected monthly during the growing season, May -
October, even though requirements are to collect twice a year. No plant related l
activity was detectable during 1990.
44
3 I
River Water (Table 74)
I These samples are collected on a quarterly basis; the sampling procedure is different at the control and indicator locations. Weekly grab samples of the first six weeks of each quarter are composited at the control station (Middletown -
location 30C). Continuous samples are utilized at the indicator station (East I
Haddam Bridge -location 28).
Tritium was observed above background levels at the indicator location at different I-periods throughout the year. These elevated levels are attributable to plant operation. The levels measured are comparable to those seen in years past.
Because this nuclide only emits low energy beta particles and river water is not a I
source of drinking water, the dose consequence resulting from these levels is insignificant. Fish consumption is the only media through which the population encounters dose from H 3 in liquid effluents. The do>e consequence of the H 3, although not routinely measured in fish, is calculated based upon the measured I
effluents and aapropriate dispersion models (NRC approved computer code-LADTAP). In orc er to verify these calculations, a special program of measuring H 3 in fish samples had been performed. The results of these analyses indicated that I
the effluent calculations are conservative. The dose consequences, discussed in Section 5.0, are insignificant.
Gross beta was the only other activity that was consistently seen in these samples.
I The gross beta activities are similar to past data. These results are a gross ty 3e measurement and are not very indicative of plant effects; they are masked ay background activities.
Bottom Sediment (Table 15)
Plant related levels of Co 60 were observed at one indicator location (Area of Plant i
Discharge - Iocation 29). These levels are comparable to those observed in past years. Cs-137 was observed in both the indicator and the control locati ns at levels similar to past years. Even though the Cs-137 levels at the control location are due I
to fallout and are at the same levels as those seen at the indicator locations, a portion of the Cs 137 in the indicator samples could be due to plant operation.
Shellfish (Table 16)
Cs 137 was observed in two samples, one taken at the mouth of the Sannon River (location 31) and the other from the East Haddam Bridge locale (location 28X).
l Even though Cs-134 was not observed, a portion of the Cs-137 in these samples could be due to plant operation. No other activity was observed except for the naturally occurring radionuclides. Because this media is not a source of I
consumption, other media (e.g., fish results) are utilized in the determination of dose consequences.
Fish Bullheads (Table 17A)
Cs-137 was observed in both the indicator and the control locations at levels similar to past years. Even though Cs-134 was not observed, a portion of the Cs 137 in I
these samples could be due to plant operation. Dose consequences were calculated based on concentrations corrected for background (fallout) levels. The results of the calculations are shown in Section 5.0.
h Fish Perch and other Types (Table 178)
These fish samples exhibit the same results as the bullhead samples. Cs 137 was I
detectable at both indicator and control locations. The dose consequence, though very minimal, is discussed in Section 5.0.
l l
45
M M
WM M
M M
M M
M M
M W
M M
M M
M
'M Figure 4-1 f
a CY AIR PARTICULATE a
Gross Beta Radioactivity l4 Q
pCi/m3 l
0.035 i
g.
0 controls O Indicators O.03 1
j
[-
0.025Gt(
i
/G'N j
'C D
'\\
0.02 9
/
9 j
i N
O O'N'O 0.015
'x n
n j
G
'N.
=
0.01 4
0.005 p
O P
Jan
.Feb Mar Apr May Jun Jul Aug Sep Oct N ov Dec g
l 1990
?
Average error of these values is 0.004 4
1
I l
5.0 OFFSITE DOSE EQUIVAl.ENT COMMITMENTS The off site dose consequences (dose equivalent commitments) of the station's
,I radioactive liquid and airborne effluents have been evaluated using two methods.
The first method utilizes the station's measured radioactive discharges as input parameters to conservative models that simulate the transport mechanism through the environment to man. This results in the computation of the maximum doses to
,I individuals and the 0 to 50 mile population dose. The results of these computations have been submitted to the NRC in the Annual Radioactive Effluents Dose Report written in accordance with the Radiological Effluent Monitoring Manual Section I
F. 2.
The second method utilizes the actual results of the concentrations of radioactivity in various environmental media (e.g., milk, fish) and then computes the dose consequences from the consumption of these foods.
'l The first method, which is usually conservative (i.e., computes higher doses than that which actually occur), has the advantage of approximating an upper limit to the dose consequances. This is important in those cases where the actual dose iI cannot be measured because they are so small as to be well below the capabilities of conventional monitoring techniques. The results of both methods are compared in Table S.1. For gaseous releases, no plant related detectable activity was observed in any sampling media. The less than values given for the second method are the I
doses which would be calculated if the annual average activity was equal to the minimum detectable level. Although the lic uid releases are also low, traces of plant related activity were detected !a, fis (caught in the discharge canal),
,g shellfish, bottom sediment, well water and river water samples.
The doses presented in Table 5.7 are the maximum doses to an individual for g
specific pathweys to man. That is, the dose is calculated at the location of 3
maximum effect from the alant effluents for that pathway and for the critical age group. For example, the c ose via the fish pathway is calculated for fish caught in i
the discharge canal and the external gamma dose is calculated at the site boundary I
which has the least meteorolo total doses to an individual of:gical chspersion. The calculations result in maximum 0.27 mrem whole body to an adult, 0.13 mrem to a child's thyroid, and 0,42 mrem to an teen's liver. The calculated doses for all other locations and other age groups will be less than those shown on Table S.1.
The average dose to an individual within 50 miles from the site cannot bc l5 calculated using the second method. However, Method 1 yields the following m
results for the period January December 1990 for the average individual:
t ANNUAL AVERAGE WHOLE BODYDOSE :
DUE TO AIRBORNE EFFLUENTS = 0.00016 miem l
DUE TO LIQUID EFFLUENTS = 0.00005 mrem Thus,it can be seen that the average whole bod dose to an individual is much less l
than the maximum whole body dose to an individual as shown in Table 5.f.
In order to provide perspective on the doses in Table 5.1, the standards for 1990 on the allowable maximum dose to an individual of the oeneral pubhc are given in 40CFR190 as 25 mrem whole body,75 mrem thyroid, ancl 25 m_ am any other organ.
.'g These standards are a fraction of the normal background radiation of 280 mrem per year and are designed to be inconsequential in regard to public health and safety.
Since plant related doses are even a smaller fraction of natural baq, sound, they have insignificant public health consequences. In fact, the plant related doses to jI the maximum individual are less than 10% of the variation in natural background l
in Connecticut.
51 l
m a
y a
m mmmm W
W W
W W
M M
M M
M TABl.E 5A COMPARISON OF DOSE CALCULATION METHODS HADDAM NECK STATION JANUARY-DECEMBER 1990 ANNUAL DOSE (MILLIREM)
METHOD 2(1) 0)
PATHWAY ORGAN METHOD 1 AIRBORNE EFFLUENTS 1.
External Gamma Dose Max. Ind. (2)-Whole Body 0.27 NA (4) 2.
a.
Inhalation Max. Ind. - Thyroid 0.10 NAD 0), <0.6 b.
Vegetables Max. Ind. - Thyroid 0.012 NAD c.
Goat's Milk Max. Ind. - Thyroid 0.013 N AD, < 1.8 LIOUID EFFLUENTS 1.
Fish Max. Ind. -Whole Body 0.29 0.0035 Max. Ind. - Liver 0.42 0.0055 (1) Method 1 uses measured station discharaes and meteorological data as input parameters to conservative transport to man models. Method 2 uses actual measured ~ concentrations in environmental media.
(2) Maximum individual-The maximum individual dose is the dose to the most critical age group (teen for inhalation, infant for milk, and child for vegetables), at the location of maximum concentration of plant related activity. The dose to the average individual is much less than the maximum individual dose. The doses for inhalation and vegetable consumption assume that the individual resides at the point of maximum quarterly dose. Therefore, his residence is subject to variation for conservatism.
l (3) NAD - No activity detected above the minimum detectable level. The less-than value reported is the dose corresponding to the l
MDL (4) NA - Not Available - NoTLDswere within the area of maximum whole body exposure.
I 6.0 DISCUSSION The evaluation of the effects of station operation on the environment requires the I
careful consideration of many factors. Those factors depend upon the media being effected. They include station release rates, effluent dispersion, occurrence of nuclear weapons tests, seasonal variability of fallout, local environment, and locational variability of fallout. Additional factors affecting the uptake of radionuclides in milk include soil conditions (mineral content, pH, etc.), quality of fertilization, quality of land management (e.g., irrigation), pasturing habits of animals, and type of pasturage. Any of these factors could cause significant I
variations in the measured radioactivity. A Wure to consider thcse factors could I
cause erroneous conclusions.
Consider, for example, the problem of deciphering the effect of station releases on I
the radioactivity measured in milk samples. This is an important problem because this product is widely consumed and fission products readily concentrate in this media. Some of these fission products, such as 1-131 and St-89 are relatively short-I lived. Therefore they result from either plant effluents, recent nuclear weapons tests or recent nuclear incidents (e.g. Cheracbyl). Sr-89's hfetime is longer than l-131's, therefore it must be remembered that it will remain around for much longer periods of time. Problems are caused by the long lived fission products, Sr-90 and i
Cs 137. These isotopes are still remaining f rom the high weapons testing era of the 1960's. This results in significant amounts of Sr 90 and Cs-137 appearing in milk samples. Distinguishing between this " background" of fallout activity and plant effects is a dif ficult problem.
In reviewing the Sr-90 and Cs 137 measured in cow and goat milk in the areas g
around the Millstone and Haddam Neck stations, a casual observer could notice g
that in some cases the levels of these isotopes are higher at farms closer to th '
station than at those further away from the stations. The stations effluents might at first appear to be responsible. However, the investigation of the following facts prove this conclusion wrong.
J.
The stations accurately measure many fission products, including Sr-90 and Cs-I 137 in their releases. Based on these measurements and proven models developed by the Nuclear Regulatory Commission, concentrations in the environment can be calculated. These calculations (generally conservative,
.a see Section 5.0) show that insufficient quantities (by more than a factor of g
1000) of Sr 90 and Cs-137 have been released from the stations to yield the measured concentrations in milk.
j 2.
Over the many years of plant operation, Sr-89 has often been released in
.E comparable quantity to Sr-90. Since they are chemically similar, comparable levels should have been detected in milk if the Sr-90 was plant related. No plant related Sr-89 has ever been detected in milk samples.
3.
Similar to Sr-89, Cs-134 can be used as an indication of plant related Cs-137.
Although not as conclusive as Sr-89, the lack of any measurable Cs-134 in any I
of the milk samples suggests that the Cs 137 is not plant related. This is further confirmed by the evaluation of the air particulate data. The only occurrences of detectable Cs 134 in milk resulted from the Chernobylincident.
l 61
i l
4.
Since dairy milk sampling began in the 1960's, years rior to plant operation, J
the immediate station areas have always shown hi her levels of weap'ons fallout related Sr 90 and Cs-137 (see Figures 6 7 and 2). The ratio of activity
]
between the locations has not changed with plant operation. All areas show j
the same significant decrease in radioactivity since the 1964 Nuclear Test Ban i
Treaty.
]
5.
l ocal variability of Sr 90 and Cs 137 in milk is common throughout the United States. Due to the variability in soil conditions, pasturing methods, rainfall, etc.,it is the rule rather than the exception. Therefore, it is not surprising that 3
certain farms have higher levels of radioactivity than other farms. In fact.
5 there are some cases where the farms further from the station have higher St-90 and Cs-137 values than the farms that are closer to the station (e.g., see 1-pre 1984 Haddam Neck Goat Milk data.)
6.
The Millstone goat farm with the highest levels of Sr 90 and Cs 137 has also experienced the highest levels of short-lived activity from the 1976 and 1977 1
Chinese Tests and the 1986 Chernobyl accident. This indicates that for some d
unknown reason this farm has the ability for higher reconcentration. Special studies performed at this and other farms failed to find any link to the plant.
Based on these facts, the observation that the station effluents are responsible is obviously false. The cause must be one or more of the other variables.
-E Northeast Utilities has carefully examined the data throughout the year and has
'A presented in this report all cases where plant related radioactivity can be detected.
1 An analysis of the potential exposure to the population from any plant related activity has been performed and shows that in all cases the exposure is insignificant.
Throughout the year, the Connecticut Department of Environmental Protection performs a parallel environmental program under contract with the Nuclear j
Regulatory Commission. On a regular basis, the results of their analyses are 25 compared to the results from this program's analyses. The comparisons are tracked and used as a cross-reference to verify measured plant activity. During 1990, both programs showed similar results.
As in previous years, this data is being submitted to, and will be reviewed by the appropriate regulatory bodies such as the Nuclear Regulatory Commission, i
Environmental Protection Agency and Connecticut Department of Environmental Protection.
I I
I I
I 6-2
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p STRONTIUVI-90 IN MILK f
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61 63 65 67 69 71 73 75 77 79 81 83 85 87 89 ii i
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lI II I
ilI APPENDIX A g
ll COW AND GOAT CENSUS FOR 1990 s
!lI r,
I 1
)
i 1
(
o l
is 4
l-t
!I lI A1 i
,,,,,,,,%.,<~,-
,-,.w.y.,d.,ey-.
,-e, w g
Dairy Covs Vithin 15 Miles of Connecticut Yankee As of May 1990 I_
Direction Distance Name and Address No. of Covs NNE 14 M.
Robert K. Gasper 80 694 Gilead St.
Hebron, CT 06248 NNE 14 M.
Hills Farm 78 527 Gilead St.
Hebron, CT 06248 NNE 14 M.
Mapleleaf Farm, Inc.
175 750 Gilead St.
I Hebron, CT 06248 NNE 14 M.
Gordon N. Rathburn 42 I
Martin Rd.
Hebron, CT 06248 NNE 14.5 M.
Douglas Porter 132 I
RFD #1 Hebron, CT 06248 I
NE 4.5 M.
Charles & Carol Dill 29 Vaterhole Rd.
Colchester, CT 06415
- East Hampton -
I NE 14 H.
Victor Botticello 25 Levita Rd.
Lebanon, CT 06249 ENE 5.5 H, Grandpa Hill Farm 43 R. S. Cone I
Box 251 East Baddam, CT 06423 I
ENE 8.1 H.
Villiam Smith 48 Town Road Colchester, CT 06415
- East Haddam -
ENE 11 H.
Richard Svider 45 Route 85 Colchester, CT 06415 ENE 14 M.
Robert Avery 32 Rathburn Hill Rd.
I Colchester, CT 06415
- Salem -
I
'I i
Dairy.Covs Vithin 15 Miles of Connecticut Yankee As of May 1990
)
i Direction Distance Name and Address No. of Covs ENE.
14.5 M.
Valter Makarevich 12 Geer Rd.
Lebanon, CT 06249 E
3.7 M.
Susan H. Gelston 2
i Bogle Road j
East Haddam, CT 06423 i
E 11.5 M.
Salem Valley Farms Dairy 42 Eugene Vilczewski
I Darling Rd.
Salem, CT 06415
g E
13 M.
Garry Vaill 36 g
Forsythe Rd.
Salem, CT 0641:,
il E
14 H.
Stuart Gadbois 200
.W Route 82 Salem, CT 06415 i
S 2.9 M Norman C. Hanning 1
530 Plains Road
'Haddam, CT 06438 SE 11 M.
Tiffany Farms 75 Sterling City Rd.
,m Old Lyme, CT 06371 E.
- 'v=*
SE 12 M.
J. Ely Harding 60 ig Ashlavn Farm W
Old Lyme, CT 06371
- Lyme -
l SV 14.5 M.
Sugarloaf Farm 24 l
154 Beaver Head Rd.
North Guilford, CT 06437 VSV 8 M.
Michael Dvyer 43 Route 17 Durham, CT 06492 I
- Vallingford -
VSV 8 M.
Robert Raudat 32 i3 Old Durham Rd.
ig Killingvorth, CT 06417 I -
VSV 11 H.
Raymond Vimler 191 a
Guilford Rd.
Durham, CT 06422 i
I Dairy Covs Within 15 Hiles of Connecticut Yankee As of May 1990 Direction Distance Name and Address No. of Cows
- I VSV 14 H.
Cella Brothers 130 Vhirlvind Hill 2 No. Brandford St.
Vallingford, CT 06492 VSV 15 M.
Co Ag Farm, Inc.
252 Valter Augur 6 George Cooke I
180 Northford Rd.
Vallingford, CT 06492 I
V 4.5 M David Lundgren, Jr.
1 345 Candlevood Hill Road Higganum, CT 06441 i
V 8.5 M.
Richard Rove 30 Box 4, Higganum Rd.
Durham, CT 06422 V
11.5 M.
Friendly Acres Dairy Farm 34 Tony Caltabiano Parmalee Hill Rd.
Durham, CT 06422 V
14 M.
North Farms 24 Valter Verbiski I.
1069 Farms Rd.
Vallingford, CT 06492 I
V 14.5 M.
Charles Greenback 6 Sons, Inc. 130 Box 451 Route 68 Durham, CT 06422 VtN 7 M.
Calvin Harvey 37 55 Tryon St.
Middletown, CT 06457 VNV 8 M.
Richard Brock 28 787 Ridge Rd.
Middletovn, CT 06457 VNV 12 M.
John Kolman 52 Heriden Rd.
Middletovn, CT 06457 VNV 12 M.
Valnut Hill Farm 130 Villiam 6 Thomas Mint::
I Jackson !!ill Rd.
Middlefield, CT 06455 I
I Dairy Covs Vithin 15 Miles of Connecticut Yankee
~
As of May 1990 Direction Distance Name and Address No. of Covs VNV 15 M.
Bilger Brothers 26 Hickory Grove Farm 705 Vestfield Rd.
Meriden, CT 06450 NV 6 M.
Edvard flills 36 Brooks Rd.
I Middletown, CT 06457 NV 13 M.
Higgins Farm, Inc.
78 I
837 Ridgewood Rd.
Middletovn, CT 06457 NV 15 M.
Venceslaus & Jean Backiel 36 I
Riverside Farm RFD #2 Berlin, CT 06037
- Rocky Hill -
NV 15 M.
John V. Meisterling 38 Ro k ikl C'I b67 NNV 14 M.
Roaring Brook Farm 16 I
Ilenry Killam 77 Tryon St.
So. Glastonbury, CT 06073
- Glastonbury -
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PAlRY GOATS WITHIN__20 MILES OF CDNBECJ1 CUT YANKEE AS OF JUNE 1990 I
DIRECTION DISTANCE NAME AND ADDRESS
GOATS I
N 4.5 M Philip Bourdon 8
I 104 Young Street East Hampton, CT 06424 267 4778 N
15 M
Joan & Thomas Kemble 4
581 Thompson Street Glastonbury, CT 06033 633 4503/659 2711 ext. 277 NNE 12 M
. Louise Sage 1
155 Reidy Hill Road I
Hebron, CT 06248 228 3774 NNE 16 M
Joan Bowers I
350 Wall Street Hebron, CT 06248 228 3157
'NNE 16 M
Kathy Waters 15 Burnt Hill Road Hebron, CT 06248
_I.
228 3098 NE 16 M Barbara Nadeau 2
I Clubhouse Road Lebanon, CT 06249 456 2641 NE 17 M Lynn Miller 7
Goshen Hill Road Lebanon, CT 06249 642 6224 NE 8-M Johnathan & Elizabeth Gilman 3
178 Cato Corner Road I-Colchester, CT 06415 537 3884 I
ll DAIRY GOATS WITHIN 20 MILES OF CONNECTICUT YANKEE AS OF JUNE 1990 DIRECTION DISTANCE NAME AND ADDREjj LQQAIS NE 17 M Sharon Stewart J
54 A Kick Hill Road J
Lebanon, CT j
423 8268 j
E 12 M Anne B. Henrici 1
Round Hill Road Salem, CT 06415 859 0871 l
ESE 13 M Dave & Pam Richards 4
285 Grassy Hill Road
I-Lyme, CT 06371 434 5676
g-SE 19.5 M Mrs. John Mingo 3
W 69 Spithead Road Waterford, CT 06385 443-7858 SE 15.8 M George Scacciaferro 338 Boston Post Road East Lyme, CT 06333 739 6739 S
11.5 M Victor Trudeau 7
-I 174 Horse Hill Road Westbrook, CT 06498 399 9583 WSW 3 M William & Lori Kapacziewski 3
598 Guilford Road, Route 77 Durham, CT 06422 349 8885 W
4.8 M Pat Mannetho 3
.l Jacoby Road
.3 Higganum, CT 06441 345 4957 W
14.5 M Robert Pogomore 177 Williams Road Wallingford, CT 06492 l
269 4654 I
QAIRY GOATS WITHIN 2Q MILES OF CONNECTIQ1[T YANKEE AS OF JUNE 1]lS,Q I
QlBEC 00N DISTANCE NAME AND AQPRESS LQOAIE W
15.3 M Jim & Mary Hall Pettack 11 1000 North Farms Road Wallingford, CT 06492 265 4028 WNW 10.5 M Roger Kinderman 721 Wadsworth Road
I_
Middlefield, CT 06082 344-2950 1
I WNW 19 M Daniel Nitkowski i
46 Firch Avenue MeriAn, CT 06450 634 4542 NW 13.2 M Harry & Dilys McIntyre 104 Court Street I
Cromwell, CT 06416 635 6126 NW 13.5 M The LaRoche Family I
South Road Portland, CT 06480 NW
'13.5 M Melvin Granger 140 Coles Road Cromwell, CT 60106 635 3719 NNW 14 M Dorothy Joba 13 171 Ferry Lane S. Glastonbury, CT 06073 633 0894
=
NNW 15 M Donald Reid 14 1654 Main Street Glastonbury, CT 06033 633 7197
UNABLE TO CONTACT AS OF THIS TIME.
t
NOT MILKING AS OF THIS TIME.
'A I
jI I
I APPENDIX B I
NORTH E AST UTILITIES O A PROGRAM I
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I g
B-1
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Northeast Utilities Service Company (NUSCO), acting as the agent for both the North Nuclear Energy Company (NNECO) and the Connecticut Yankee Atomic Power Comp, east any (CYAPCO), maintains a quality assurance (QA) program of its 3rimary contractor of radiological analyses, Teledyne isotopes,Inc. This is accomplished ay the use of the three I-quality control methods that are specified in Radioassay Procedures for Environmental i
- Samples, U.S. Department of Health, Education, and Welfare (January 1967).
j i
J E~
These three quality control methods are:
}
E_
a)
Duplicate analyses of actual surveillance samples with one laboratory. This 1
3 type of quality control allows an evaluation of the contractor's precision or reproducibility of results.
I b)
Cross check analyses of actual surveillance samples with more than one laboratory; e.g., Yankee Atomic Environmental Laboratory.
This intercomparison allows the determination of what agreement the primary j
contractor has with another laboratory, c)
Analyses of " spiked" samples. This type of quality control allows a check on the contractor s accuracy of results.
Additional QA programs are preformed, these include: 1 Teledyne isotopes' internal QA
2) Teledyne isotopes' participation in EPA)s Environmental Ractioactivity
arogram,
- E Laboratory Intercomparison Studies Program, and 3) Nuclear Regulatory Commission -
5 State of Connecticut Independent Verification Program.
l The number and type of QA samples are $e samples as QA samples. The resu iven in Table f. In general, the objective was to obtain between 10 and 20 percent of t satisfy acceptance criteria as defined in Radioassay Procedures for Environmental Samples, U. 5. Department of Health, Education and Welfare (Jan.1967) and the Handbook for
E Analytical Quality Control in Radioanalytical Laboratories, EPA 600/7 77 088 (Aug.1977).
' s Comparisons of the results to the acceptance criteria are tracked on control charts to make apparent radioanalytical trends, biases or other problem areas.
h The NUSCO QA Program indicated that,in general, the Teledyne isotopes' environmental radiological analysis program was adequate This assessment is supported by Teledyne isotopes' results in the EPA Intercompanson Program as shown in Appendix C. Potential t
. weaknesses were identified by some NUSCO QA data in the areas of strontium analyses in milk, gross beta and gamma analyses of air filters, and gamma analyses in water. Because this is Teledyne isotopes first year as the primary contractor, investigations of these potential weaknesses are still in the prelimmary stages. As part of these investigations I
NUSCO is also examining the methodologies of its own QA program in order to identify possible weaknesses.
1
.I 4
1 B2
I TABLE 1 i
NUMBER OF QUALITY CONTROL
SAMPLES
\\
Number of Number of Sample Type QC Samples Routine Samples a,b I
TLDs 135 503 g
Milk 67 142 Well Water (
26 8
Sea Waterc 2
8 i
River Waterc 2
8 Bottom Sediment 8
26 Aquatic Flora 2
6
- I Fish 8
46 1
l Shellfish 3
49
' Lobster / Crab 0
12 Fruits and Vegetables 0
16
' Airparticulate - Gross Beta 15 826
- todine 12 780
- GeLi 10 100 I
An additional program is performed by the contractor I
a - Total for both Millstone and Connecticut Yankee i
g b - Depends on availability c - OC breakdown does notinclude H 3 analysis; total number of tritium QC samples was 21 I
l i
B-3
g I
I APPENDIX C I
l
SUMMARY
OF EPA INTERLABORATORY COMPARISONS I
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C-1
I US EPA INTERLABORATORY COMPARISON PROGRAM 1990 f
(ENVIRONMENTAL)
I Collection Teledyne Date Media Nuclide EPA Result (a)
Isotopes Result (b)
I 10/31/89 lab Perf.
Gr Alpha 49.00 i 12.00 42.33 5.77 Water Ra 226 8.40 i 1.30 9.20 0.46 Sample A Ra-228 4.10 1 0.60 4.00 1 0.50 Sample B Gr Beta 32.00 1 5.00 30.33 0.58 Sr 89 15.00 i 5.00 15.00 3.46 Sr 90 7.00 1 1.50 7.00 0.00 Cs 134 5.00 5.00 5.33 t 1.15 Cs 137 5.00 1 5.00 7.00 1 0.00 i
11/10/89 Water Ra 226 8,70 1 1.30 8.47 0.49 Ra 228 8.57 1.40 8.57 1.46 l
01/12/90 Water Sr-89 25.00 1 5.00 24.00 1,73 Sr 90 20.00 1.50 19.67 t 2.52 01/26/90 Water Gr Alpha 12.0 i 5.0 10.00 1.73 Gr-Beta 12.0 5.0 12.33 1.53 02/09/90 Water Co 60 15.00 1 5.00 15.00 3.46 I
Zn 65 139.00 t 14.00 131.33 9.07 Ru-106 139.00 14.00 113.-67 4.04 (e)
Cs 134 18.00 5.00 15.33 1 2.31 Cs-137 18.00 1 5.00 19.33 1 3.21 Ba 133 74.00 7.00 66.00 3.46 02/23/90 Water H3 4976.00 1 498.00 4900.00 i 100.00 03/09/90 Water Ra 226 4.9 0.7 4.73 0.47 Ra-228 12.7 1.9 13.00 1.00
-03/30/90 Air Filter Gr Alpha 5.0 1 5.0 6.33 1 0.58 Gr-Beta 31.0 5.0 31.67 0.58 I
Sr 90 10.0 1.5 9.33 0.58 Cs 137 10.0 5.0 10.67 i 1.15 I
04/17/90 Water Gr Alpha 90.0i-23.0 79.33 1 2.89 (Lab Perf)
Ra 226 5.0 1 0.8 5.67 i 0,15 Sample A Ra 228 10.2 i 1.5 9.37 1.44 Sample B Gr Beta 52.0 1 5.0 53.33 i 1.53 I
Sr 89 10.0 5.0 10,67 i 1.15 Sr90 10.0 t 1.5 9.67 1 0.58 Cs-134 15.0 1 5.0 12.67 1 1.53 Cs-137 15.0 1 5.0 16.33 i 1.15 Footnotes at end of table.
I
lI US EPA INTERLABORATORY COMPARISON PROGRAM 1990 (cont.)
l (ENVIRONMENTAL)
Collection Teledyne Date Media Nuclide EPA Result (a)
Isotopes Result (b)
I 04/27/90 Milk Sr 89 23.0 1 5.0 24.67 1 1.53 Sr90 23.0 5.0 24.00 1 0.00 I-1 131 99.0 i 10.0 89.67 1 3.21 Cs 137 24.0 1 5.0 27.33 1 2.52 K
1550.0 1 78.0 1483.33 75.06 05/04/90 Water Sr 89 7.0 1 5.0 6,67 1 0.58 Sr90 7.0 1 5.0 6.67 1 0.58 I
05/11/90 Water Gr Alpha 22.0 1 6.0 16.00 1 1.00 Gr-Beta 15.0 1 5.0 17.00 1 1.00 06/08/90 Water Co 60 24.0 1 5.0 25.33 1 2.52 Zn-65 148.0 i 15.0 148.67 1 3.06 Ru 106 210.0 1 21.0 196.00 1 20.66 I
Cs 134 24.0 1 5.0 23.67 2.89 Cs 137 25.0 1 5.0 24.67 1 2,08 Ba 133 99.0 1 10.0 93.00 1 6.08 06/22/90 Water H3 2933.0 1 358.0 2900 100.00 07/13/90 Water Ra-226 12.1 i 1.8 11.37 1 0.60 I
Ra 228 5.1 1.3 4.20 1 0.75 08/10/90 Water I 131 39.0 1 6.0 36.00 1 3.00 08/31/90 Water Gr Alpha 10.0 1 5.0 16.00 i 1,00 (d)
Gr Bela 62.0 1 5.0 63.33 i 1,53
'I Sr90 20.0 1 5.0 18.00 1 1.00 Cs 137 20.0 1 5.0 18.33 1 3.21 I
09/14/90 Water Sr-89 10.0 1 5.0 8.67-0.58 Sr 90 9.0 1 5.0 9.0 t 1.00 09/21/90 Water Gr Alpha 10.0 1 5.0 11.00 1 1.00 Gr-Deta 10.0 1 5.0 11.00 1 1.00 I
I I
I
l US EPA INTERIABORATORY COMPARISON PROGRAM 1990 (cont.)
I (ENVIRONMENTAL)
Collection Teledyne Date Media Nuclide EPA Result (a)
Isotopes Result (b) 09/28/90 Milk Sr 89 16.0 1 5.0 9.0 1 2.65 (d)
Sr90 20.0 i 5.0 15.33 1 0.58 I 131 58.0 i 6.0 54.67 i 1.53 I
Cs 137 20.0 1 5.0 23.00 1 1.73 K
1700.0 1 85.0 1710.00 1 65.51 I
10/15/90 Water Co 60 20.0 1 5.0 21.00 1 1.00 Zn 65 115.0 i 12.0 115.00 i 11.53 Ru 106 151.0 i 15.0 142.00 1 8.66 I
Cs 134 12.0 1 5.0 11.00 1 0.00 Cs 137 12.0 1 5.0 16.33 1 2.52 Ba 133 110.0 i 11.0 94.67 1 5.13 (d) 10/19/90 Water H3 7203.0 i 720.0 7133.33 1 251.66 11/09/90 Water Ra 226 7.4 i 1.1 7.27 i 0.38 Ra 228 7.7 1.9 7.57 1 0.32 I
Footnotes:
(a)
EPA Results Expected laboratory precision (1 sigma). Units are pCl/ liter for water. and milk except K is in mg/ liter. Units are total pCI for air particulate filters.
(b)
Teledyne Results Average i one sigma. Units are pCl/ liter for water and milk except K is in mg/ liter. Units are total pCI for air particulate filters.
I No apparent cause for the low results were found. Three aliquots of the sample were (c) counted oa three separate detectors. The results of all three were similar. The calibrauon curve fit is good (0.997). Ruthenium lO6 will be obtained from the EPA to further investigate the matter and future mixed gamma in water EPA Intercomparisons will be monitored to identify continutng trends.
(d)
An investigation is being conducted and the results will be available shortly.
I I
I 2/1/91 I
-

B13802, Annual Radiological Environ Operating Rept for 1990

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B13802, Annual Radiological Environ Operating Rept for 1990

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