B11502, Radiological Environ Monitoring Program,Annual Environ Operating Rept for 1984
| ML20138M752 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 12/31/1984 |
| From: | Counsil W CONNECTICUT YANKEE ATOMIC POWER CO., NORTHEAST UTILITIES SERVICE CO. |
| To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| B11502, NUDOCS 8511040308 | |
| Download: ML20138M752 (98) | |
Text
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HADDAM NECK STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL ENVIRONMENTAL OPERATING REPORT PART B PERIOD JANUARY 1, 1984 - DECEMBER 31, 1984 DOCKET NO. 50-213 LICENSE NO. DPR-61 PREPARED FOR TIE CONNECTICUT YANKEE ATOMIC POWER COMPAh7 i HADDAM, CONNECTICUT BY TIE NORTilEAST UTILITIES SERVICE COMPANY BERLIN, CONNECTICUT
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HADDAM NECK STATION RADIOLOGICAL EhTIRONMENTAL MONITORING PROGRAM ANNUAL EhTIRONMENTAL OPERATING REPORT PART B PERIOD JANUARY 1, 1984 - DECEMBER 31, 1984 DOCKET NO. 50-213 LICENSE NO. DPR-61 PREPARED FOR THE CONNECTICUT YANKEE ATOMIC POWER COMPAhT HADDAM, CONNECTICUT BY THE NORTHEAST UTILITIES SERVICE COMPAhT BERLIN, CONNECTICUT
TABLE OF CONTENTS Page No.
1.0 Summary 1-1 2.0 Program Description 2-1 2.1 Sampling Schedule and Locations 2-1 2.2 Samples Collected During Report Period 2-9 3-1 3.0 Radiochemical Results 3.1 Summary Table 3-1 3.2 Data Tables 3-15 4.0 Discussion of Results 4-1 5.0 Offsite Dose Consequences 5-1 6.0 Discussion 6-1 Appendix A - Cow and Goat Census for 1984 A-1 Appendix B - QA Program B-1
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1 mental media. 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 a.6 millirem and the average dose to a member of the public residing within 50 miles of the plant.is 0.0023 millires. These doses are 10.4 percent and 0.0092 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 (20 percent) of the 125 mrem per year normal background radiation and are designed to be incon-sequential in regard to public health and safety. Plant related doses are even a smaller fraction of the natural background; they are less than 10 percent of the variation in natural background in Connecticut. Therefore, for the above stated reasons the plant related doses have insignificant public health consequences.
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1.0
SUMMARY
The radiological environmental monitoring program for the Haddam I Neck Plant was continued for the period January through December 1984, in compliance with the Environmental Technical Specifications, Section 3.2. This 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 and tritium analyses were performed by Teledyne Isotopes, Inc. All the remaining analyses were performed by Chemical Waste Management of Massachusetts, Inc.
Yankee Atomic Electric Company was used to independently check on the primary contractors' laboratories as part of the overall quality assurance program.
Radiological analyses were performed with gamma exposure measuring devices and on samples of air particulates and iodine, soil, milk, pasture grass, well water, fruits, vegetables, river water, bottom sediment, shellfish, and fish. In evaluating the results of these analyses it is necessary to consider the variability of radionuclide uptake in environmental media. This variability is dependent on many factors, including plant release rates, meteorology, number and size of nuclear weapon tests, seasonal variability of fallout, locational variability of fallout, soil characteristics, farming practices, and feed type. Significant variations in measured levels of radioactivity could be 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 sources, such as fallout from nuclear weapons tests and from naturally occurring radionuclides. Plant related radioactivity was observed at some of the onsite gamma monitoring locations and in several other environmental samples. These include tritium in well water at the onsite location, tritium in river water collected in the vicinity of the mouth of the discharge canal and near the East ;
Haddam Bridge, and cesium-137 and cesium-134 in bottom sedirent collected from the vicinity of the mouth of the discharge canal.
As usual, cesium-137 and strontium-90 were measured in both cow and l goat milk. These levels are a result of nuclear weapons testing in the 1960's and not the result of plant operation. This can be l
l concluded based on the facts that: insufficient quantities (at l
1 east 2000 times less) of these isotopes have been released by the [
plant to account for the measured concentrations, chemically similar cesium-134 and (plant related) strontium-89 which are released in about equal or larger quantities from the plant can not be detected and comparable levels of cesium-137 and strontium-90 were detected L prior to initial plant operation.
The radiation dose 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 utilizes the measured concentrations of radioactivity in the environ-1-1
! _~ __ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
2.0 PROGRAM DESCRIPTION 2.1 Sampling Schedule and Locations The sample locations and the sample types and frequency of analysis are given in Table 2-1 and 2-2 and Figures 2.1, 2.2 and 2.3. The program as described here is that which is required by Environmental Technical Specification 3.2.
4 2-3
w Table 2-1 CONNECTICUT YANKEE RADIOLOGICAL ENVIRONMENTAL MONITORING PRO Sample Type, Frequency (b) and Analysis (c)
Distance Camma Air Vegetation Water Milk (d)
Particulate (f) Soil
& Direction (a) Dose Location Terrestrial Stations _ .
- 1. On site fence near boron waste 0.1 miles,W M --
storage tanks --
- 2. On site fence near waste gas 0.1 miles,E M surge sphere -
On site fence near discharge 3.
0.2 miles,SE M - --
canal 0.1 miles,WW M -
A2,5 --
- 4. On site fence near guard house 0.4 miles W M W1-M2-Q5(e) -
A2,5 --
- 5. On site-Injun Hollow Road 0.5 miles,NE M W1-M2-Q5(c)
A2,5 --
- 6. On site-Substation 1.8 miles.SE M W1-M2-Q5(e) --
A2,5
- 7. Haddam M W1-M2-Q5 --
3.1 miles.ESE A2,5 --
- 8. East Haddam 3.2 miles.WNW M W1-M2-Q5 --
Higganum 2.8 miles,FNW M W1-M2-Q5 A2.5 - --
- 9. A2,5 --
Y 10. Hurd Park Road--East Hampton *10.0 miles,NW M Wi-M2-Q5 A2,5 --
" 11. Middletown *8.0 miles,SSE M W1-M2-Q5 -- --
A2,5 --
- 12. Deep River *12.0 miles,SW M W1-M2-Q5(e)
A2,5 --
- 13. North Madison *10.0 miles,NE M W1-M2-Q5
- 14. Colchester -- -- MI,2,4,5 0.8 miles,SE
- 15. On Site-Wells -- -- Q1,2,4,5 -
- 16. Well-State Highway Dept. *3.0 mile,S -- --
-- -- Q1,2,4,5 -
East Haddam 1.0 mile,NW -- --
-- -- Q1,2,4,5 -
- 17. Well-Injun Hollow Road 1.0 mile,S --
-- M3
- 18. Well-Haddam -- --
1.5 miles,NNW -- --
- M3
- 19. Cow Location #1 2.2 miles,ESE - --
-- M3
- 20. Cow Location #2 --
M3 4.5 miles,NE -- --
- 21. Cow Location #3 *11.0 miles,ENE -- --
-- M3(g) -- --
- 22. Cow Location #4 *16.0 miles, NE --
-- M3(g) - --
- 23. Goat Location #1 1.5 miles,W -- --
-- A2(h)
- 24. coat Location #2 --
- 25. Fruits & Vegetables
Table 2-1 (continued)
Sample Type, Frequency (b) and Analysis (c)
Distance & Bottom Direction (a) Sediment Water Fish (1) Shellfish Location Aquatic Stations
-- Q2,5 --
- 26. Conn. River - Vicinity of intake 1.0 miles,WNW Q2,5 -- -- Q2,5
- 27. Conn. River - Higganum Light *4 niles,WNW Conn. River - E. Haddam Bridge *1.8 miles,SE Q2,5 -- --
28.
Q2,5 Q1,2,4,5 Q2,5(i) --
- 29. Plant Discharge Canal Conn. River - Middletown *7.6 miles,NW -- Q1,2,4,5 Q2,5(i) .-
30.
0.8 miles,ESE -- -- --
Q2,5
- 31. Mouth of the Salmon River Y
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- Control Stations (a) Distance to nearest half mile (b) W-Weekly, M-Monthly, Q-Quarterly, SA-Semi-Annual, A-Annual (c) 1-Gross Beta, 2-Ganana Spectrum, 3-I-131, Sr-89, Sr-90, 4-H-3; 5-Sr-89, Sr-90 (d) During the period April through October and once in February .
(e) Includes a charcoal filter that is to be analyzed weekly for I-131 (f) . Analyses are done on the monthly and quarterly composites (g) A similar analysis will be done on milk instead of grass if the former is available (h) During the harvest season, when available from conunercial farms (i) Bu11 heads and when available perch
- - - - - _ _ _ . _s TABLE 2-2 MINIIGJM DETECTABLE 1.EVEl.S IN ENVIRONMENTAL SAMLES AND RESULTING DOSM Minimum Detectable Annual Dose L evels' Associated (MDL) with 21,' (eren) Critical Orsan Annual Intake Sample Type Anaivete Seele Sise Crose beta 1 liter 1 pCi/1 - -
Well and River Water 20 pC1/1' - - -
Ca me spectrum 3 liter 2.0 pC1/1 0.2' bone 440 1 Sr-89 2 liter 1.0' bone 440 1 Sr-90 2 liter 1.0 PC1/1 6.0 pC1/1 0.078' whole body 440 1 Co-137 2 liter 60 pC1/1 0.005' body tissue 440 1 5-3 2 liter Cama spectrum I kg 0.05 pct /g' 8' - -
totton Sediment and Soil 1 kg 0.072 pC1/g - - -
y Sr-89 - -
- Sr-90 1 kg 0.036 pC1/3 -
Co-137 1 kg 0.064 pC1/g c- spectrum I kg 0.05 pC1/g' -
18.3 kg Fista and Shellfish 100 g 0.018 pC1/g 0.08 bone St-89 0.4 bone 18.3 k.a Sr-90 100 3 0.000 pC1/g 0.056 pC1/g 0.031 whole body 18.3 kg Co-137 100 g whole body 12 month T13 1 month 1 aren -
exposure Cam e Dooe esposure 1.6 Child's thyroid 183 1 1-131 4 liter 0.5 pct /1 Milk 2.0 pC1/1 0.08 bone 183 1 Sr-89 1 liter 0.40 bone 183 1 Sr-90 1 liter 1.0 pC1/1 0.036 whole body 183 1 Co-137 1 liter 6.0 pC1/1
~ _- . s TABLF. 2-2 (Cont'd) Minimum Detectable Annual Dose I.evels' Associated with MDL' (aren) Critical Organ Annual Intake Analyste Sample Stre (MDL)
Sample Type 0.04 pC1/m3 0.5 ' Child's thyroid 1100 m3 I-131 270m3 Filtered Air Cross Beta 270m 3 0.01 pC1/m 3' ~
210m3 0.045 pC1/m3 * -
Cross Camma - -
Camma Spectrum 1.0Som3 0.02 pC1/m3 8 -
Camma Spectria 1 kg 0.05 pct /g 8 -
Vegetation I-131 1 kg 0.05 pC1/g 7.5' ' Child's thyroid -
Sr-89 1 kg 0.018 pC1/g Sr-90 1 kg 0.009 pC1/g Cs-137 1 kg 0.034 pC1/g
' Based on a calibration with Cs-137 of 1.5 pCi=1 cosme per minute a For Co-137 assuming no interference from etter nuclides
' Ca-137 used as a reference source They apply to the activity at the
- These are sintama practical detectat.e levels (MDL) as opposed to theoretical detection limits.
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& time of sample collection. MDL = 2 o background.
- Based on the Teletal Radiation Council reports on Radiation Frotection Cuides and associated dose.
- Applies to drinking water only' Dose to a child's thyroid through the air-grass-cow-milk-man food chain for an annual milk intake of 183 1.
- From WASH-1258 (July 1973)
' From WASH-1258 Table 68-4 "pC1/g per grc:a - vet weight
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\ p/r Particulate Sampli Ai Stations 12 DFF f;tR.R Radius: 10 miles N. s SW -
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...i.,,i scale of miles D Well Water Sampling Stations ,l e Aquatic Sampling Stations FIGURE 2.3 Aquatic and Well Water Sampling Stations Haddam Neck Plant 2-8
l 2.2 Samples Collected Durine. Aeport Period l The following table summarizes the number of required samples of each type collected during the present reporting period:
Sample Type Number of Samples Gamma Exposure (TLD) 367 Air Particulates 529 212 Air Iodine 10 Soil Dairy Milk 32 16 Goat Milk 0
Pasture Grass ,
Well Water 24 Fruit and Vegetables 8 8
I River Water i 12 Bottom Sediment 23 Fish 8
Shellfish iotalAllTypes 1,049 i
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3.0 RADI0 CHEMICAL RESULTS 3.1 Summary Table In accordance with Environmental Technical Specification 5.6.la., Table 5.6-1, a summary table of the radiochemical results has been prepared and is presented in Table 3-1.
In the determination of the mean the data was handled as recommended by Health and Safety Laboratory, Idaho: all valid data, including negative values and zeroes were used in the determination of the meat. (see part 3.2).
A more detailed analysis of the data is given in section 4.0 where a discussion of the variations in the data brings to light many aspects that are not evident in the summary table because of the basic limitation of such an approach.
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FOOTNOTES
- a. For Ge(Li) measurements the MDL's ~ 2 x /2B where B = background.
For all others, MDL = 2 x o background. These MDL's are based on the absence of large amounts of interfering activity (excluding naturally occurring radionuclides). Deviations by about factors of 3 to 4 can occur, excluding Technical Specification Items.
- b. Analytical results are handled as recommended by HASL (" Reporting of Analytical Results from HASL," letter by Leo B. Higginbotham).
Negative values were used in the determination of the mean.
- c. Nonroutine reported measurements (# of NRMs) are defined in Section 5.6.2b of the Technical Specifications.
- d. First number is the number of indicator measurements, the second is the number of control measurements.
- e. Assuming 270 m8 / paper.
- f. Assuming 1080 m8 .
- g. Quarterly composites.
- h. N/A--Not Applicable.
3-13
3.2 Data Tables The data reported in this section are strictly counting statis-tics. The reported error is two times the standard deviation of the net activity. Unless otherwise noted, the overall error is estimated to be 2 to 5 times that listed.
Because of counting statistics, negative values, zeroes and numbers below the Minimum Detectable Level (MDL) are statis-tically valid pieces of data. For the purposes of this report, in order to indicate any background biases, all the valid data are presented. In instances where zeroes 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 I-131
- 4. Air Particulates, Monthly Quantitative Gamma Spectra
- 6. Soil **
- 7. Milk - Dairy Farms
- 8. Milk - Goat Farms
- 9. Pasture Grass *
- 10. Well Water
- 11. Reservoir Water
- 12. Fruits & Vegetables *
- 13. Meat, Poultry and Eggs *
- 14. River Water
- 15. Bottom Sediment **
- 16. Shellfish *
- 17. Fish
- There was no commercially available meat, poultry, or eggs for which the feed was grown within 10 miles of the site.
- For these sample types, the results are reported as pCi/g wet weight.
- For these, the results are reported as pCi/g dry weight.
3-14
LOCATION KEY FOR DATA TABLES CONNECTICUT YANKEE 1 Boron Waste Storage Tanks Fence - NW, 0.1 miles 2 Waste Gas Surge Sphere Fence - E, 0.1 miles 3 Discharge Canal Fence - SE, 0.2 miles 4 Guard House Fence - WNW, 0.1 miles 5 Injun Hollow Road - NW, 0.4 miles 6 Substation - NE, 0.5 miles 7 Haddam - SE, 1.8 miles 8 East Haddam - ESE, 3.1 miles 9 Higganum - WNW, 3.2 miles 10 Hurd Park Road - NNW, 2.8 miles 11A Middletown - NW, 10 miles 12A Deep River - SSE, 8 miles 13A North Madison - SW, 12 miles 14A Colchester - NE, 10 miles 15A On Site Wells 1 & 2 - SE, 0.8 miles 16A State Highway Dept. - E. Haddam - S, 3 miles 17 Vell - Injun Hollow Road - NW, 1 mile 18 Well - Haddam - S, 1 mile 19 Cow Location #1 - NNW, 1.5 miles 20 Cow Location #2 - ESE, 2.2 miles 21 Cow Location #3 - NE, 4.5 miles 22 Cow Location #4 - ENE, 11 miles 23A Goat Location #1 - NE, 16 miles 24 Goat Location #2 - NW, 1.5 miles 25 Within 10 miles of plant 35A Beyond 10 miles of plant 26 Conn. River - Intake Vicinity - WNW,1.0 miles 27A Conn. River - Higganum Light - WNW, 4 miles 28A Conn. River - E. Haddam Bridge - SE, 1.8 miles 29 Vicinity of Discharge 30A Conn. River - Middletown - NW, 7.6 miles 31 Mouth of Salmon River - ESE, 0.8 miles 40B Near Intake Structure - SSW, 0.1 miles 41B Picnic Area - NW, .5 miles 4?B Mouth of Discharge Canal - ESE, 1.1 miles 43B Moodus - ENE, 2.5 miles 44B Shailerville (Horton Road) - SE 1.0 miles 45B Haddam Jail (Jail House Road) - WSW, 1.0 miles 46B Ranger Headquarters (on Ranger Road) - SW, 1.8 miles SIB . Conn. Valley Hospital - NW, 7.5 miles
$2B Mt. Higby - WNW,12.5 miles A - Control Stations B - Site not required by ETS
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0 Cot #JEC7ICtJT YUREE TABLE 14 ft0tnHLY cat 914 EXPOSURE RATEf UR/HRI PEDIOD tOCATIOHS 09 10 11A 04 05 06 07 08 Et:DitM 01 02 03 ...._ _=.........................
_.--__ -_=..............__ __ _ ___
.. _ .__.=__ _ ___
7.0 6.7 6.0 7.2 6.7 7.3 9.0 9.1 6.7 1/31/84(a)-___ 9.9(b) 6.8 7.7 8.0 7.5 6.3 8.0 6.9 8.4 9.4 2/28/84 10.8 10.3 7.8 7.5 8.0 9.9 10.3 7.8 7.3 7.7 7.8 6.7 8.1 3/31/84 10.7 7.9 6.5 8.8 7.3 8.7 9.7 10.8 8.2 7.8 8.6 ;
4/30/84 11.2 7.4 7.3 7.3 7.1 T.1 9.4 10.5 9.7 6.9 6.6 7.1 10.1 l 5/31/84 7.9 8.5 8.0 6.8 8.6 7.6 8.6 1 6/30/84 12.2 10.9 8.0 8.0 6.4 7.9 7.1 7.6 9.3 10.5 7.8 7.8 7.9 9.8 7/31/84 13.6 7.4 6.8 8.1 7.4 8.0 8.5 9.6 8.2 8/31/84 23.9(c) 11.9 8.5 8.4 8.1 6.8 8.2 7.4 7.6 9.7 9/30/84 17.3 11.6 8.7 7.2 8.8 8.0 8.6 10.4 17.1 13.2 10.2 9.0 9.1 8.1 10.5 10/31/84 7.9 8.1 8.3 6.8 8.2 7.8 0.0 11/30/84 13.6 12.7 9.4 7.7 6.9 8.6 7.2 9.0 10.0 12/31/84 13.6 12.3 9.6 8.1 8.5 428 438 44B 45B 46B 134 14A ACB 418 12A .......................................
=____................__--. - .........==__ _ _ - - _ _ _ = - - - _
6.1 5.7 7.0 6.3 5.9 5.9 7.7 6.3 5.4 1/31/84 5.9 7.3 6.4 6.5 7.9 7.1 7.0 6.6 2/28/84 6.3 6.3 8.2 7.3 7.1 6.4 7.1 5.9 6.6 8.0 3/31/84 6.5 6.5 8.5 7.5 7.3 6.8 7.8 6.1 6.8 8.5 4/30/84 6.7 6.7 8.9 6.8 6.2 5.2 6.2 7.4 7.1 5.9 7.9 6.4 7.0 5/31/84 6.3 6.1 6.8 8.5 7.9 7.6 6.6 8.9 7.7 6/30/84 7.0 8.4 7.5 5.9 4.4 8.1 7.1 6.8 6.1 7/31/84 6.3 6.4 8.1 7.9 7.5 6.9 8.4 8.5 7.0 6.6 8/31/84 6.7 6.3 8.5 7.5 7.2 6.4 8.7 8.5 6.1 6.8 9/30/84 6.5 6.6 8.6 8.6 8.0 7.4 9.1 6.6 6.9 10/31/84 7.4 7.1 8.9 8.3 7.8 7.6 6.9 8.9 8.8 6.2 6.6 11/30/R4 6.8 6.7 8.3 8.0 7.6 7.1 7.2 8.6 8.8 6.5 6.7 12/31/84 7.1 TABLE IB set 11 At#RJ A'.
CAtit1A EXPO 5UPE D ATEtUp/HRI PEpIDO L0CA7 IONS 08 09 10 llA 03 04 05 06 07 EPOItG 01 02 ....-__ ==.- =.................................................
8.0 9.6 7.5 6.6 8.0 7.2 10.2 7.6 7.3 7.8 6/30/84 10.9 8.4 7.9 6.8 8.3 7.5 6.8 9.9 16.5 12.0 9.0 8.5 12/31/84 428 43B 44B 458 468 134 14A 40B 418 124 ...................................==__
=.-_ _ _=.............
.......-_ - =._=____ - --_ _
6.4 7.9 7.2 7.0 6.5 6.4 6.3 8.3 7.1 5.8 7.4 6.8 6/30/84 6.4 6.7 8.* 7.8 12/31/84 6.8 6.7 8.6 8.5 (a) Not actual dates. TLD's are changed near the end of the month.
(b) Results are +/- 10%.
(c) High result caused by temporary storage of radioactive waste in area.
. 1027 Y . 3278 0125 50878 C .39858 1435 1 201 11 1 1 121 10 131 1 32231 2212 0000 00000 0000 8 . 00000 0000 0000 6 0000 0000 00000 0000 4 .00000 0000
. 1120 01 11 15423 0874
.89425 5435 1211 1 1 1 1 1 1 1 1 1 1211 1 212
.22222 A . 00000 0000 0000 0000 00000 0.C.0 0 4 . 0000 00000 0000 1 . 00000 0000 0000 I . 3792
. 351 6 1236 42636 E . 85971 8536 1 21 1 11 1 1 1 2101 1 312
. 22232 1 21 2 00000 0000 G 0000 0000 0000 A A . 00000 P 3 . 0000 00000 0000 0000 0000 1 -- 00000 9206 39575 3577
. 00941 9243 3484 1 1 1 1 1 1 31 1 1 21 2 1 201 01 1 1 0000
. 33242 0000 0000 00000 A . 00000 0000 2 . 0000 00000 0000 1 . 00000 0000 0000 3765 0313 26572 1247
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TABLE 3-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
CONNECTICUT YANKEE ATOMIC POWER COMPANY, HADDAM NECK PLANT DOCKET 50-213 JANUARY - DECEMBER 1984 LOCATION WITH HIGHEST ANNUAL MEAN CONTROL LOCATIONS ANALYSIS AND MIMIMUM ALL INDICATOR # OF LOCATIONS - (b) NRMs MEDIUM OR TOTAL NUMBER DETECTABLE (b) NAME, DISTANCE (b)
PATHWAY OF ANALYSES LEVELS AND DIRECTION Mean (Range) Mean (Range) (c).
(MDL's)(a) Mean (Range)
SAMPLED PERFORMED N/A 0 0 0 N/A Ir-95 25 230 (140 - 400) 0 Vicinity of 1400 (160 - 3300)
Tritium 4,4 60 1400 (160 - 3300)
Plant Discharge H-3 3.9 (1.6 - 7.9) 0 4,4 2.2 (1.9 - 2.8) Middletown 3.9 (1.6 - 7.9)
Beta 1 7.6 Miles NW 8
E. Haddam Bridge 0.001 (-0.008 - 0.012) -0.004 (-0.017 - 0.012) 0 Botton Sediment Sr 4,8 0.072 -0.002 (-0.012 - 0.011) 1.8 Miles SE (pC1/g] Sr-69 E. Haddam Bridge 0.013 (0.009 - 0.019) 0.013 (0.009 - 0.019) 0 Sr-90 0.036 0.010 (0.008 - 0.015) 1.8 Miles SE 0.11 (0.00 - 0.25) 0 0.12 (0.06 - 0.20) E. Haddam Bridge 0.15 (0.10 - 0.25)
Ge(L1) 4,8 0.064 1.8 Miles SE Cs-137 0.0 0 N/A N/A l-131 0.2 0.0 Vicinity of 0.04 (0.0 - 0.08) 0.00 (0.00 - 0.02) O Cs-134 0.06 0.04 (0.0 - 0.08) Plant Discharge .
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TABLE 3-1 ENVIRO % MENTAL RADIOLOGICAL MOMITORIMG PPOGRAM SL* MART CONMECTICUT TAMKEE ATOMIC POWER COMPAMT. HADDAM NECK PLANT ON KET 50-213 JANUARf - CECEMBER 1994 LOCATiOM WITH HIGHEST AMi4AL ME AM CONTROL LOCAT1045 ANALv515 Am3 MINimLM ALL tmDICAIGA f 0F TOTAL Nt36ER CETECTABLE LOCATIOMS MEDILM OR (b) NAME. DISTANCE (b) (b) MRMs PETHidAf # AMALYSES LEVELS Mean (Range) (c)
AMD OIRECTION Mean (Ran<fe)
SAPPLED PE8r0RmED (MOL's)(a) Mean (Ran<1e)
Onsite Fence - Boron (5.9 - 10,5) 0 Waste Storage Tanks 13.7 (9.9 - 23.9) 7.9 Gassia Dose AU.+e(3) 1.5 8.7 (6.0 - 23.9) 0.1 elles Ed (uRfhr) 0.021 (0.008 - 0.043) Injun Hollow Road. 0.022 (0.010 - 0.037) 0.021 (0.008 - 0.044) O Air Particulate Beta 317.212 0.01(e) Haidae,and North 0.022 (0.010 - 0.043) and fodine Mailson - 0.4 Miles 0.022 (0.011 - 0.037)
(pC1/e3) NW. 1.8 Miles SE,and 12 Miles SW 0.016 (-0.04 - 0.05) North Madison 0.024 (-0.03 - 0.06) 0.024 (-0.03 - 0.06) 0 Mal 159.53 0.04 1-131 12.0 Miles SW (0.00 - 0.001) North Madtson 0.0003 (0.00 - 0.003) 0.0001 (0.000 - 0.003) O Ge(L1) 72.48 0.025(f) 0.0000 Cs-137 12.0 Miles SW N/A 0.000 0 Cs-134 0.02(f) 0.000 N/A(h) 0.0001 (0.000 - 0.003) Hurd Park Road 0.0005 (0.000 - 0.003) 0.0001 (0.000 - 0.004) 0 Ra-103 -
2.8 Miles MMW 0.0001 (0.000 - 0.004) North Madison 0.0005 (0.000 - 0.006) 0.0001 (0.000 - 0.C06) 0 2r-95 -
12 Miles SW 0.000 0 NS-95 - 0.0000 (0.000 - 0.003) East Haddam 0.0002 (0.000 - 0.003) 3.1 Miles ESE Cs 28,16 0.001(9) 0.00012 (0.0000 - 0.0003) Haddam 0.00015 (0.0001 - 0.0002) 0.00009 (0.0000 - 0.0002) 0 Cs 1.8 Miles SE
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TABLE 3-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SIMtARY CONNECTICtIT YANKEE ATOMIC POWER COMPANY. HADOAM MECK PLANT DOCKET 50-213 JANUART - DECEMBER 1984 CONTROL LOCATION 5 LOCAll0N WITH HIGHEST ANNUAL MEAN ANALYSIS AND MINIMUM ALL INDICATOR f 0F LOCATIONS (b) NRMS MEDI C OR TOTAL NUMBER DETECTABLE (b) NAME. DISTANCE (b)
PATHWAf 0F ANALYSES LEVELS Mean (Range) Mean (Range) (c)
(MOL's)(a) Mean (Range) AND DIRECTION
$NIPLED PERFOR9t3 0.92 N/A 0.66 (0.46 - 0.92) 0 0.43 (0.30 - 0.87) Colchester Th-228 -
10 Miles NE 6.4 (4.0 - 8.5) 0 6.0 (5.5 - 7.0) Colchester 8.5 N/A K 40 --
10 Miles NE 0.58 (0.44 - 0.86) 0 Colchester 0.86 N/A Ra-226 -- 0.52 (0.33 - 0.79) 10 Miles NE 0.17 (0.0 - 0.4) 0 0.13 (0.0 - 0.3) Dairy Fare f4 0.17 (0.0 - 0.4)
Milk (Dalry) fadine 36.12 0.5 11 Miles ENE (pC1/1) 1-131 0.35 (-0.7 - 1.2) 0 2 0.30 (-1.0 - 1.6) Dairy Fars #2 0.37 (-0.5 - 1.3)
Sr 36.12 2.2 Miles ESE Sr-89 4.1 (2.9 - 6.7) 0 5.6 (3.2 - 10.3) Dairy Fare #1 7.1 (5.3 - 10.3)
Sr-90 1 1.5 Miles lumi Dalry Farm il 9.2 (5 - 12) 3.3 (1 - 7) O Ge(Lt) 36.12 6 5.8 ( 15) 1.5 Miles NNW cs-137 0.17 (0.0 - 0.4) 0 0.17 (0.0 - 0.4) ' Goat Location #2 0.17 (0.0 - 0.4)
Goat Milk Todine 12.9 0.5 1.5 Miles NW (pC1/1) 1-131 0.23 (-3.0 - 3.0) 0 0.56 (-0.8 - 2.2) Goat Location #2 0.56 (-0.8 - 2.2)
Sr 12.9 2 1.5 Miles NW 5r-C9
i 1
1 l
I 1
' TABLE 3-1 ,
ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SLNMARY j
CONNECTICUT YANKEE AT3MIC POWER COMPANY. HADDAM NECK PLANT j DOCKET 50-213 JANUARY - DECEMBER 1964 LOCATION WITH HIGHEST ANNUAL MEAN CONTROL LOCATIONS ANALYSIS MD MINIMUM ALL INDICATOR f 0F DETECTABLE LOCATIONS NRMs MEDIUM OR TOTAL NUMBER lb) NAME. DISTANCE (b) (b)
PATHWAY OF ANALYSES LEVELS (Range) AND DIRECTION Mean (Range) Mean (Range) (c)
PERFORMED (MDL's)(a) Mean SAMPLED 7.2 (3.2 - 14.0) 7.2 (3.2 - 14.0) 0 5.6 (2.5 - 11.6) Goat Location #1 1
Sr-90 1 16 Miles ME 4
i 20.2 (11 - 35) 20.2 (11 - 35) 0 Ge(L1) 12.9 6 7 (2 - 19) Goat Location fl i 16 Miles NE
! Cs-137 6.7 (3.8 - 9.0) 0 I
1.7 (0.8 - 4.2) State Highway Dept. 6.7 (3.8 - 9.0) i Groundwater Beta 20.4 1 East Haddam 3 Miles $ i
?
(PCf/l) l -0.3 (-0.8 - 0.5) 0 Sr 20.4 2 0.0 (-0.6 - 0.4) Onsite Wells 0.0 (-0.6 - 0.4) ,
Sr-59 0.8 Miles SE I.
0.4 (0.2 - 0.5) 0 I 0.4 (0.1 - 0.7) Onstte Wells 0.4 (0.2 - 0.7)
Sr-90 1 1
0.8 Miles SE lI 1
0 0 0 N/A N/A
- Ge(Lt) 20.4 6 3 Cs-137 i
0 0
! N/A N/A I-131 30** O l
0 0 N/A N/A Cs-134 6 0 1
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TABLE 3-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SIM ARY CONNECTICUT YANKEE ATOMIC POWER COMPANY. HADDAM MECK PLANT DOCKET 50-213 JANUARY - DECEMBER 1984 LOCATION WITH HIGHEST ANNUAL MEAN CONTROL LOCATIONS ANALYSIS AND MINIMUM ALL INDICATOR LOCATIONS
- OF MEDitM OR TOTAL NUMBER DETECTABLE OF ANALYSES LEVELS lb) NAME, DISTANCE (b) (b) MRMs PATHWAY (Range) AND DIRECTION Mean (Range) Mean (Range) (c)
SAMPLE 0 PERFORMED (MDL's)(a) Mean N/A N/A 0.00 0 Co-60 0.05 0.00 N/A N/A 0.00 0 Zr-95 -- 0.00 N/A N/A 0.00 0
, Mb-95 -- 0.00 Mouth of Salmon River 0.18 (0.0 - 0.4) 0.08 (0.0 - 0.3) 0 K-40 -- 0.18 (0.0 - 0.4) 1.8 Miles SE 7.4 0.018 0.007 (0.000 - 0.013) Intake Vietntty 0.009 (0.005 - 0.013) 0.000 (-0.002 - 0.003) 0 Fish - Bu11 heads Sr (pC1/g) 5r-59 1 Mlle WNW Sr-90 0.009 0.038 (0.009 - 0.059) Intake Vietntty 0.044 (0.031 - 0.055) 0.042 (0.023 - 0.085) 0 1 Mlle WNW 0.056 0.013 (0.00 - 0.04) Plant Discharge 0.015 (0.00 - 0.04) 0.006 (0.00 - 0.03) O Ge(L1) 7.4 Cs-137 Canal N/A 0.00 0 I-131 -- 0.00 N/A N/A 0.00 0 Cs-134 0.05 0.00 N/A N/A 0.00 0 Mn-54 0.05 0.00 N/A
TABLE 3-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SUPMARY CONNECTICUT YANKEE ATOMIC POWER COMPANY. HADDAM NECK PLANT 00CKET 50-213 JANUARY - DECEMBER 1984 CONTROL LOCATIONS ALL INDICATOR LOCATION WITH HIGHEST ANNUAL MEAM f 0F ANALYSIS AND MINIMUM LOCATIONS (b) NRMs MEDitM OR TOTAL NUMBER DETECTABLE NAME. DISTANCE (b)
OF ANALYSES LEVELS (b) Mean (Range) Mean (Range) (c)
PATP4N Mean (Range) AND DIRECTION PERFORMED (MDL's)(a)
SAMP'fQ 0.00 0 N/A N/A Co-58 0.05 0.00 0.00 0 N/A N/A Co-60 0.05 0.00 0.00 0 0.007 (0.00 - 0.05) Intake Vicinity 0.017 (0.00 - 0.05)
Zr-95 --
1 Mlle WNW _
0.00 0 0.007 (0.00 - 0.05) Plant Discharge 0.012 (0.00 - 0.05)
Mb-95 --
Canal j
2.5 (1.9 - 2.9) 0 I 2.2 (1.3 - 2.8) Middletown 2.5 (1.9 - 2.9)
K-40 --
7.6 Miles NW Middletown 0.001 (-0.005 - 0.008) 0.001 (-0.005 - 0.008) 0 Fish - Other Sr 8,4 0.018 -0.002 (-0.016 - 0.009) 7.6 Miles NW (pC1/g) Sr-89 Intake vicinity 0.082 (0.065 - 0.108) 0.051 (0.032 - 0.098) 0 Sr-90 0.009 0.078 (0.040 - 0.108) 1 Mlle WNW Plant Discharge 0.03 (0.00 - 0.05) 0.008 (0.00 - 0.03) O Ge(L1) 8,4 0.056 0.028 (0.00 - 0.05)
Canal Cs-137 4
0.00 0 Plant Discharge 0.01 (0.00 - 0.07)
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TA8LE le PAGE 2 CY WELL WATER IPCI/LI PUtpHI-106 CR-51 R-40 COLLECTION FE-59 ZN-65 IR-95 .............. ..............
LOCATION DATE CO-60 .............. ..............
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15 3/13/84 0. 3. O.
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15 4/ 2/84 O. 6.
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- 30. O. 30. O. 30.
15 5/ 7/84 0.
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15 6/12/84 0.
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15 7/16/84 0. 3. O. 6. O. 30. O. 40.
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15 8/16/84 0.
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15 9/10/84 0. 3. 9.
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15 10/ 9/84 8. O. 5. O. 30.
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15 11/13/84 7. O. 6. O. 5.
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I TABLE 11 CY PAGE 1 l RESERVOIR WATER 4PCI/L)
COLLECTIDH 7-131 CS-134 194-5 4 CO-58 LOCATION DATE SR-89 S#-90 C5 137
(+/ ) (+/.i (4/-) (+/.)
(+/.I (+/.I (+/.)
ZW-95 RUtPHl.106 CR-51 K-40 CD-60 FE-59 ZH-65
. ........... .............. (+/-I
(+/.I
(+/.)
(+/.3 t+/.) .... ........
(+/.)
(+/-)
BE.7 NB-95 H.3 GROSS BETA RA-226 TH-228 .............. ........... .
(+/.) (+/.I (+/.I
(+/.) (+/.) (+/.)
These samples are not required.
p e
M
. 0466 0076 Y . ) 1576 9076 .I. 9465 0000 0000 2065 . I. 1 000 1200 0000 C - 1 000 0200 -
6 - /0000 0200 . / 0000 r 0000 = +
./0000 + 0 +
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. ( 0000 0000 1 5 _ f
- 9 _
4 . I _
5 . B d M
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_ 0000 0000 e 0000 0000 t 0000 d M u _
0000 0000 e p 0000 0000 .
0000 0000 _
. e
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. 0610 3020 . l 0000
. - 8455 0000 8465 e
.l 2577 1076 1200 . I. 201 1 1311
. / 0000 0100
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7.
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0000 0000 M
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. l 3690 0013 - l 0153
- 3111 0002 2421 . - 3122
/ 0000 3421 0000 p m
T.
. - 1001 2211 / 0000 0000
. /0000 0000 + 8 . ( 0000
+
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0000 0000 . cr
. . . ne e
0004 . ) 0921 0030 s9
. ) 0576 9075 . ) 0103 - - 201 1 2311 e8
. - 3121 2421 0000
. - 1000 0000
. / 0000 0000 _ / 0000 r -
. / 0000 0000 . +
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EE/
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. =
. on ti B C . l0000 0000 A8P . l 3676 1086 0003 T . ) 2771 21 12
. - 1 000 1 200 . - 0004 ed I
. - 0000 0000 . /2121 2521 ue S . / 0000 0000 . / 0000 0000 . +
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R 0 6 4 .
0000 0000 t u F 9 . - - .
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(( 9575 . l 0000 0000 sl 4004 5666 . l 1466 . - 0455 7255
. l . - 1 000 01 00 01 00 ab
. /0000 0260 0000 0000 . / 0000
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+
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1 - 8 p 9 . 5 - 5 1 8 . - y R .
2002 0240 0010 0000 243 000 O C
0000 0000 R
C
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s
= f i
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ome S S th S S S E
S E E E I
nc e
E E I I I I REES I
REES REES REES RCCE my REES REES RCGE RCCE pCGE EUAL EUUL eb E RCGE RCCE EUAL EUUL BTTP r P EUAL EUUL BTBP STTP BTBP WTTP Y BTBP BTTP WTDP WTTP WTBP AEEA id T WTDP AEAA WTTP AEEA AEAA AEEA RLL aEAA RLC RLL ue qs RLL RLC T T RLC T T T T S S S eu S S S racn .
4444 4444 L o N 4444 4444 4444 4444 8888 8888 8888 Dd s O 8888 8888 //// //// 0189 Ml ee a I 8888 //// ////0189 0189 TE //// ////0189 0189 2111 2211 CT 0189 221 1 2111 2211 //// //// .i r EA LD L
2111
//// ////6699 6799
//// ////6699 6799 6799 6699 S. y s O
C T. oh wi N
ELt O
I A444 ))
T A A444 44A4 5555 5555 5555 ab
((
5555 5555 5555 3333 2222 3333 C 3333 2222
_ O 2222
_ L 1 !
TABLE 13 CT 11 EAT. FOULTRY 8 EGGS (a) trCI/G)
COLLECTION 1 131 CS-134 994-54 SR-90 CS-137 LOCATION DATE TYPE SR-89
(+/-l
.............. t+/-l
(+/-l
(+/-l 1+/-) (+/-)
ZN-65 ZR-95 RUtRHi-106 CO-58 CO-60 FE-59 .............. ..............
.............. (+/.I 1+/-l (+/-l t+/-)
t+/-l to/-)
TH-228 BE-7 NB-95 CR-51 K-40 RA-226
.............. t+/-l (+/-)
(+/-l t+/-) (+/-l
(+/-)
4 1
i (a) Commercial samples for which feed was grown within 10 miles of the station were not available in 198
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I TABLE 17A CY FISH BULLHEADS PAGE I trCI/GI COLLECTION I-131 CS-134 NH-54 Cd-56 OATE SR-89 SR-90 CS-137 LOCATION
.....__....... ...__._...__.. _......_______ ___..______... _________..... (+/.I
(+/-)
(+/.)
(+/-) (+/-) (+/-)
f*/.)
0.0 0.030 0.0 0.030 0.0 0.030 0.0 0.020 26(8) 4/29/64 0.0090 .0060 0.0470 .0020 0.030 0.030 0.030 0.0 0.030 0.0550 0020 0.0 0.0 30 0.0 0.040 0.0 0.040 0.0 26 7/23/84 0.0130 .0090 0.030 0.0 0.040 0.0 0.030 0.0 0.030 0.0 0.030 26 10/16/84 0.0050 .0080 0.0310 0020 0.0 0.150 0.0 0.030 0.0 0.020 0.0 0.030 2d 4/10/84 0.0030 .0040 0.0240 .0020 0.030 0.020 0.0 0.030 0.020 0.0 0.020 i 0.0290 .0030 0.0 0.030 0.0 0.050 0.0 0.0 teB 7/17/84 0.0040 .0090 0.020 0.040 0.0 0.030 0.0 0.030 0.0 0.020 20B 10/16/84 0.0010 .0130 0.0670 .0040 0.0 0.0 0.030 0.0 0.030 0.0 0.020 0.0 0.020 29 1/ 4/84 0.0 .0040 0.0180 0020 0.040 0.030 0.0 0.030 0.040 0.030 0.200 0.0 0.030 0.0 0.0 29 4/ 9/84 0.0040 .0060 0.0490 .0020 0.0 0.0 0.0 0.020 0.0 0.020 0.0 0.020 0.020 0.020 0.0 0.030 29 7/18/84 0.0100 .0080 0.0590 .0020 0.020 0.020 0.0 0.020 0.0 0.015 0.0 0.020 29 10/17/84 0.0100 .0200 0.0090 0080 0.0 0.0 0.040 0.030 0.0 0.030 0.0 0.020 304 2/ 9/84 0.0020 0060 0.0360 .0020 0.030 0.020 0.0 0.0 0.030 0.030 0.030 0.0 0.200 0.0 0.030 0.0 0.0 304 4/10/84 0.0010 0060 0.0230 .0020 0.0 0.030 0.0 0.030 0.0 0.040 0.0230 .0020 0.0 0.030 0.0 0.050 0.0 304 7/16/84 0.0030 .0070 0.030 0.0 0.030 0.0 0.020 0.0 0.020 10/13/84 0.0 .0090 0.0050 .0020 0.0 0.020 0.0 30A (a) Samples were unavailable during the first quarter.
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TABLE 178 CY FISH-0THER PAGE 1 (PCI/G)
COLLECTION 1-131 CS-134 DN-54 SR-89 SR-90 CS-137 LOCATION DATE TYPE
.............. .............. I'/*3 I'/~I I'/~I I'/~I ..............
I'/~I I'/*I 0.0 0.020 0.0 0.020 0.0 0.020 4/30/84(a) PERCH 0.0060 0.0090 0.0740 0.0030 0.030 0.020 0.030 0.020 26 0.1080 0.0050 0.040 0.030 0.0 0.030 0.0 0.0 26 7/26/84 OTHER (c) -0.0160 0.0180 0.030 0.0 0.020 0.0 0.020 0.0 0.0090 0.0650 0.0020 0.0 0.020 0.0 26 10/10/84 PERCH 0.060 0.0 0.040 0.0 0.030 OTHER(d) 0.0080 0.0140 0.1530 0.0040 0.070 0.040 0.0 0.030 0.030 28B 7/16/84 0.0570 0.0030 0.0 0.030 0.0 0.300 0.0 0.0 28B 10/19/84 PERCH (e) -0.0030 0.0100 0.040 0.0 0.030 0.0 0.0'30
-0.0090 0.0110 0.1040 0.0030 0.050 0.030 0.0 0.030 0.030 29 1/ 5/84 PERCH 0.0400 0.0020 0.0 0.020 0.0 0.200 0.0 0.0 29 4/10/84 PERCH 0.0090 0.0050 0.0 0.020 0.020 0.020 7/17/84 -0.0030 0.0090 0.0750 0.0020 0.030 0.020 0.070 0.040 0.020 0.0 0.020 29 OTHER 0.0750 0.0020 0.030 0.020 0.0 0.040 0.0 29 10/ 9/84 PERCH -0.0030 0.0090 0.030 0.0 0.020 0.0 0.020 0.0 0.0090 0.08'60 0.0020 0.040 0.020 0.0 29 10/16/84* PERCH 0.0 0.020 0.0 0.040 0.0 0.020 0.0 0.020 PERCH 0.0020 0.0070 0.0400 0.0020 0.030 0.0 0.020 0.0 0.020 304 2/ 7/84 0.0386 0.0015 0.0 0.020 0.0 304 4/25/84 PERCH -0.0050 0.0040 0.030 0.0 0.050 0.0 0.030 0.0 3.030 7/17/84 PERCH (g) 0.0080 0.0070 0.0340 0.0020 0.0 0.020 0.0 0.020 304 0.0980 0.0030 0.030 0.020 0.0 0.030 0.0 30A 10/12/84 PERCH (g) 0.0 0.0100 (a) Samples were unavailable during the first quarter. '
i (b) Samples were unavailable during the first and second quarter.
(c) Northern pike.
(d) Sunfish.
(e) Perch and bluegill.
(f) Catfish.
(g) Perch and bass.
- Extra sample was taken.
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4.0 DISCUSSION OF RESULTS Gamma Exposure Rate (Table 1)
Gamma exposure from all sources including cosmic and other natural and artificial radioactivity is measured over periods of approximately one month using CaF2 (Ma) thermoluminescent dosimeters (TLDs).
These dosimeters are strategically placed at a number of on-site 1er.clons, as well as at inner and outer off-site locations. Glass bulb type TLoc such as these, are subject to inherent self-irradiation which has been e.<perimentally measured for each dosimeter. The results, shown in Table 1 have been adjusted for this effect. The range of this correction is 0.3 pR/hr to 1.7 pR/hr, with
- nean of approximately 1 pR/hr.
The data for 1984 exhibits the same trends as that of previous years; gamma exposure rates did not differ significantly for the off-site inner and outer ring locations. The on-site locations at the boron waste storage tank (location 01), the waste gas surge sphere (location 02), and discharge canal fence (location 03) were the only locations showing any plant effects. Increases from 1 to 14 pR/hr due to direct radiation f rom the plant are observed.
Location 01 during August shows the effect of temporary storage of radioactive material in the area. These locations are within the plant's restricted area and, as such, are away from areas where members of the general public are usually allowed. Dosimeters located at areas which are accessible to the public, such as the picnic area (location 41B) and the mouth of the discharge canal (location 42B), did not indicate any increase in exposure rate due to the plant.
Further evaluation of the monthly data reveals a decrease in background during January of 1984, most likely caused by the extraordinary large snowfall during this month and its resultant shielding effect.
Increased exposure rate levels occurred during the 4th quarter of 1984. These increases are caused by the use of a new TLD reader to measure the exposure of the TLD bulbs. Over the last five years, a trend of decreased exposure rates have been observed (see Figure 4-1) due to photomultiplier tube aging. In October, the new TLD reader was placed into service and measured exposure rates have increased to the magnitude of rates of past years.
Air Particulates and Iodine (Table 2, 3, 4A-L and 5)
Air is continuously sampled at seven inner ring and four outer ring locations by passing it through glass fiber particulate filters.
These are collected weekly and analyzed for gross beta radioactivity.
Results are shown on Figure 4-2 and Table 2. Gross beta activity remained at levels similar to that seen in 1982-1983 samples. As in 1979 and 1980, the data for the last three years has failed to show an increase in the spring and summer such as that seen in 1981 and other previous rea rs . This is due to the absence of recent atmospheric nuclear testing in the northern hemisphere. Inner and outer ring monitoring loca tions showed no significant variation in measured 4-1 l
t
activities. This indicates that any plant contribution is not measurable.
Charcoal cartridges are included at five of the air particulate locations for the selective collection of iodine. Analysis of these cartridges (see Table 3) shows that eleven of the samples have 1-131 slightly above its minimum detectable level (MDL). The positive values are attributable to statistical fluctuations in counting, rather than actual I-131. This premise is confirmed by the absence of I-131 in any of the milk samples. Milk from cows and goats are much more sensitive indicators of I-131 presence in the environment.
The weekly air particulate filters are composited monthly for gamma spectral analyses. The results, as shown in Tables 4A-4L, indicate the presence of naturally occurring Be-7, which is produced by cosmic processes. All other positive results are attributsble to statistical fluctuations in counting. These analyses indicate the lack of any plant effects.
The weekly air particulate filters are also composited quarterly for the measurement of strontium and total cesium. These analyses involve the performance of radiochemical separation and appropriate counting techniques. The results presented in Table 5 are much more sensitive indicators of environmental radioactivity than gamma spectrometry, due to the greater sensitivity caused by compositing for a longer period of time and higher efficiency of beta counting.
However this higher sensitivity suffers from the drawback that it Therefore, does not allow the separation of Cs-137 and Cs-134.
analytical results presented in Table 5 include total cesium along with Sr-89 and Sr-90. The total cesium results, as usual, followed the same trend as the gross beta results. Indicator (inner ring) and control (outer ring) locations had comparable results, thus indicating that the total cesium is a result of fallout from weapons testing. The Sr-90 results show the same trend as the gross beta and total cesium analyses. Levels continued to remain at the faily constant low values as observed Because in 1982-83. There of the was no detectable occurrence of comparable Sr-89 in any of these samples.
results at both indicator and control locations and the lack of Sr-89, it can be concluded that there are no indications of plant effects.
Soil (Table 6)
Soil samples are collected annually at ten of the air particulate monitoring stations. They are analyzed for stror. tium and gamma emitting radionuclides. The results of these analyses indicate that the only detectable radionuclides at levels above the respective MDL's consisted of Sr-90, Cs-137, the naturally occurring radionuclides, K-40, Ra-226 and Th-228, and cosmic produced Be-7. Due to the absence of Sr-89 and Cs-134, the presence of Sr-90 and Cs-137 is It attributable to fallout from previous nuclear weapons testing.
was also noted that the levels of these two radionuclides did not significantly vary between indicator and control locations and these j
results were similar to those observed for the past nine years.
l l
4-2 l
i t
i Cow Milk (Table 7) ,
j Analysis of milk samples is generally the most sensitive indicator i of fission product existence in the terrestrial environment.
Airborne releases will usually be detected first in this media. t This, in combination with the fact that consumption of milk is significant, results in this pathway usually being the most critical i
i i
from the plant release viewpoint. ibis pathway also shows significant !
amounts of nuclear weapons testing fallout. Therefore this media r l
4 needs to be evaluated very carefully when trying to decipher if k i
there are any plant effects. >
Sr-90 was observed in all samples; all results were below 11 pCi/A.
Data was similar to previous years. All three indicator locations
- exhibited higher values than the control location. This trend has Detailed analysis of 1
usually been the case for these samples.
l J previous data has concluded that these levels of Sr-90 are from weapons testing and are not plant related (see Section 6.0 for details to this argument). Sr-89 was not detected in any of the j
samples above its MDL. This isotope is released in greater quantities from the plant, indicating that the Sr-90 is the result of weapons !
l testing and not from the plant. Sr-89 is only detected in these samples during episodes of fresh fallout from weapons testing.
1 1 Cs-137 usually shows the same tendencies as Sr-90, but at higher l
levels. Results for 1984 are similar to those of the past seven years. All three indicator locations showed Cs-137 activity above i
j the control location. This trend has been observed in past data.
i However detailed analysis has concluded that these concentrations l are most likely the result of fallout from previous weapons testing (see Section 6.0 for details). Cs-134 was not observed above 4
detectable levels in any of the samples, further confirming the
]
i absence of plant effects. Prior to 1982, the values for Cs-137 in this table were representative of total cesium as determined by l chemistry. For the past few years these values were confirmed by -
l Cesium chemistry allows a higher j gamma spectrometry to be Cs-137.
degree of sensitivity but suffers the problem of possible interferences 4
from other nuclides, specifically Cs-134. In order to maintain
" state of the art" analysis techniques, the gamma spectrometry has been improved and cesium chemistry discontinued. Although not i listed on Table 7, the only other nuclide detected by gamma spectometry i
I was naturally occurring X-40.
4 j All samples showed a lack of I-131 detectable above the MDL of 5 0.5-pCi/1. These results are consistent with previous years' results. The only occasions when this nuclide has been detected are 4 those immediately following atmospheric testing of nuclear weapons.
I Goat Milk (Table 8)
Depending on tia feeding habits, goat milk can be a more sensitive l indicator than cow milk of fission products in the environment.
Similar to the This is due to the metabolism of these animals.
' results of the cow milk samples, these show significant amounts of i
i 4-3
'1 l
I . - - - - - . - -, ,, , . - ._ - - _ . - - . . --- - - _. - . .. - _ _ .. - - ..~. - - _ .- -
i nuclear weapons testing fallout. Sr-90 was observed in all samples, with values similar at both locations. In previous years (1977-1983) l the control location had significantly higher values than the indicator location or any of the cow locations. This difference in results between locations decreased substantially with a change in l farms in 1983 (necessitated by the original control farm going out i
of business). The pre-1984 results demonstrate the variability in l
the uptake of fallout levels among various farms. This variability j is caused by many factors, including feeding habits (amount of i
stored feed, etc.), soil characteristics, farming practices (tillage and quality of fertilization and land management), and feed type.
For a complete discussion of the problem, see Section 6.0. As typical of periods lacking fresh fallout, no detectable Sr-89 was seen in these samples. The Cs-137 results also show a decrease in j the difference between locations, however, the control location still exhibits values higher than the indicator location. This further demonstrates the variability of the uptake of fallout-related t l
nuclides and indicates the lack of plant effects. The absence of l Sr-89 and Cs-134 confirm that the levels of Sr-90 and Cs-137 are i caused by previous weapons fallout.
There were no detectable levels of I-131 seen in any of the samples.
This is also typical of previous years except for periods immediately l following fallout from nuclear weapons testing, when I-131 may be detected.
{ '
i Pasture Grass (Table 9) i Samples of pasture grass are required by the Environmental Technical l
Specifications when samples of milk are unobtainable. They may also be taken to verify the milk pathway measurements. This sample was l
' not available in February when goat milk was not available at the control location. In June and September, samples of broad leaf l
' vegetation were collected and analyzed as part of a new program and ,
are listed in this table. The presence of Sr-90 and Cs-137 in these l
samples is consistent with values seen in pasture grass samples of past years and is most probably due to fallout. The absence of j Co-60 appears in one sample Sr-89 and Cs-134 confirms this premise.
i but is believed to be caused by statistical fluctuations.
l Well Water (Table 10)
Activity in this media results from either soluble plant effluents permeating through the ground or the leaching of naturally occurring nuclides from the soil and rock (past which the groundwater flows).
Bi-214, H-3, and Gross Beta were detected in these samples, at levels similar to previous years. Sr-90 and Nb-95 were also seen in ;
a couple samples, but these were barely above MDLs and were observed in both indicator and control locations and therefore are probably due to counting statistics and are not real.
Bi-214 is a daughter product of naturally occurring Ra-226. In well water supplies it may not necessarily be in equilibrium with its l
l 4-4 1
i
. _ . _ , _ _ , _ , _ _ . _ . . . _ _ _ - _ _ _ _ _ . _ _ _ . ~ . _ . _ . _ . _ _ _ _ _ _ . . _ _ _ _
long lived precursor. Therefore it is not indicative of the Ra-226 concentrations. This effect has been discussed in previous reports.
As usual the on-site wells (location 15) exhibited plant related I:-3 significantly above background levels. This plant effect results from the wells being located in the path of ground water flow between the discharge canal and the Connecticut River and H-3 having the ability to readily follow the flow of ground water. These wells are on-site, therefore these tritium levels are not required to be reported as Anomolous Measurements. This pathway results in no dose consequence since the water from these wells is used only in process streams at the station. Offsite concentrations are much lower than these values (see River Water). The other wells exhibit typical background levels of H-3.
Also consistent with previous years, the gross beta values for the control location at the State Highway Department (location 16A) were higher than the values for the indicator locations. This activity is due to the leaching of naturally occurring nuclides. Variations can be caused by different flow patterns of the ground water, variable permeability of the dif ferent 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)
These samples are not required by the Environmental Technical Specifications. Previous data has never shown any detectable plant activity in this media. This fact and the extremely unlikely possibility of observing any routine plant effluents has caused the discontinuance of these samples. In the event of widespread plant contamination, these samples would be analyzed.
Fruits and Vegetables (Table 12)
Similar to past years, this media did not show any plant effects.
Concentrations of Sr-90 and Cs-137 in these samples existed at levels comparable to past years and is due to fallout. Naturally occurring K-40 was also detected in all samples. Cosmic-produced Be-7 was seen on some of the broad leaf samples. Since there was no fresh fallout, no other nuclides were detected.
l Heat, Poultry, and Eggs (Table 13)
If these samples are available and their feed is grown within 10 l miles of the station, then the Environmental Technical Specifications require that these samples be obtained. However, no samples were obtained because none were available.
l River Water (Table 14)
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 4-5 l
composited at the control station (Middletown - location 30A).
Continuous samples are utilized at the indicator station (area of plant discharge - location 29) and at an extra location (non Environmental Technical Specification location - East Haddam Bridge - location 28B).
l Both the indicator and extra locations show tritium (H-3) con-cenrations above the background levels seen at the control location.
i These elevated levels are attributable to plant operation. They
' show the effect of plant releases being diluted by the Connecticut River. Because this nuclide only emits low energy beta particles l and river water is not a 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 dose consequence of the H-3, although not routinely measured in fish, is calculated based upon the measured effluents and appropriate dispersion models (NRC approved computer i
code - LADIAP). Preliminary results of H-3 analyses in fish samples indicate that the calculations are conservative. The dose consequences, discussed in Section 5.0, are insignificant.
Grcss beta and Sr-90 were the only other activities that were consistently seen in these samples. For most of the samples, the i
gross beta was similar to past data. These results are a gross type measurement and are, therefore, not very indicative of plant effects; they are masked by background activities. Sr-90 was also observed at levels similar to other years, however in most cases at positive levels below the MDL.
i Bottom Sediment (Table 15) 1 The naturally occurring radionuclides, K-40, Ra-226, and Th-228 were j
present in all samples. Cosmic produced Be-7 was measured in a few j samples, at levels near the MDL. The only other nuclides detected were Sr-90, Cs-137, and traces of Cs-134.
l The levels of Sr-90 are similar to those observed in the past; indicator and control locations had comparable values. Therefore these levels are indications of fallout concentrations. Cs-137 was l
measured in all samples, at levels consistent among locations.
j Levels were similar to those seen in 1981-83 samples. The occurence i
of trace quantities of Cs-134 at the indicator location may indicate that a small portion of Cs-137 observed is plant related. The-majority of the Cs-137 is due to fallout activity. Cs-134 levels
' are similar to those for the last three years. With the decrease in discharges since 1980, plant releases have become almost undetectable in th'is media.
Shellfish (Table 16)
\
The only detectable activity observed in this media consisted of l Sr-90 and the naturally occurring radionuclides, Ra-226 and Th-228.
l Many of the samples also showed traces of K-40. This media has j
i always shown low concentrations of this nuclide. One positive value l of Sr-89 was indicated at an extra location (non Environmental l
4-6
!_. - ~_ . -. ___ . _ _ __ - _ _ _ _ _ _ _ __- _ _ _ . _ . _ -
Technical Specification location - East Haddam Bridge - location This value, though 28A) located 1.8 miles downrTver of the plant.
an isolated occurrence, may be plant related. The dose consequence of this value is snsignificant compared to those discussed in Section 5.0.
Sr-90 was detected in all samples, at similar concentrations among locations. Levels are consistent with what has been seen for the past eight years. For these reasons the Sr-90 is most probably due to fallout activity.
4 Fish-Bu11 heads (Table 17A)
As usual, the majority of the activity in these bottom feeding Other aquatic samples consisted of naturally occurring K-40.
nuclides that were observed include Sr-90 and possible traces of Cs-137. Sr-90 showed levels consistent with past data and was similar among locations. This and the absence of Sr-89 indicates that the Sr-90 is generic to fallout. The levels of Cs-137 are somewhat higher in samples taken from the plant discharge canal (location 29). This effect has been more noticeable in past years.
Even though Cs-134 was not observed, partTo of the Cs-137 in these be conservative, dose-samples could be due to plant operation.
consequences were calculated assuming there concentrations resulted from plant effluents. The results of the calculations are shown in Section 5.0.
Fish-Perch and other Types (Table 17B)
These fish samples exhibit the same results as the bullhead samples.
The predominant activity was naturally occurring K-40. Sr-90 levels were consistent at all sampling locations and Sr-89 was not detectable.
Therefore, the Sr-90 observed in these samples is due to fallout.
As in the bullhead samples, Cs-137 was again detectable at higher levels in samples from the discharge canal and from the plant l
intake. This effect is somewhat more noticeable in these fish samples. In addition to this possible plant effect, there was one sample that had traces of I-131 activity, at levels near the MDL.
These elevated levels may be plant related and as such, the dose - -
consequence, though very minimal, is discussed in Section 5.0.
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M O P-4-9
i 5.0 0FFSITE DOSE CONSEQUENCES The off-site dose consequences of the station's radioactive liquid The and airborne effluents have been evaluated using two methods.
first method utilizes the station's measured radioactive discharges as input parameters to conse -vative models thatThis simulate the in results trans-the port mechanism through the environment to man.
computation of the maximum doses to individuals and the O to 50 mile population dose. The results of these computations have been submitted to the NRC in the Semiannual Radioactive Effluent Release Reports written in accordance with Environmental Technical Specification 5.6.lb. 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.
The first method, which is usually conservative (i.e., computes higher doses than that which actually occur), has the advantage This is of approximating an upper limit to the dose consequences.
important in those cases where the actual dose 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 5.1. For gaseous releases, no plant related detectable activity was observed in any sampling media. The less 1
than values given for the second method are the doses which would be calculated if the annual average activity was equal to the minimum detectable level. Although the liquid releases are also low, traces of plant related activity were detected in, fish (caught in the discharge canal), bottom sediment, shellfish and river water samples.
The doses presented in Table 5.1 are the maximum doses to an individual for specific pathways to man. That is, the dose is calculated at the location of maximum effect from the plant effluents for that For example, the dose via pathway and for the critical age group.
the fish pathway is calculated for fish caught in the discharge canal and the external gamma dose is calculated at the site boundary which has the least meteorological dispersion. The calculations 2.6 mres whole result in maximum total doses to an individual of:
body to an adult, 0.40 mrem to a child's thyroid, and 1.5 arem to an adult's liver. The calculated doses for all other locations and other age groups will be less than those shown on Table 5.1.
The average dose to an individual within 50 miles from the site cannot be calculated using the second method. However, Method 1 yields the following results for the period January-December 1984 for the average individual:
0.00073 arem ANNUAL WHOLE BODY DOSE DUE TO AIRBORNE EFFLUENTS =
= 0.00152 arem ANNUAL WHOLE BODY DOSE DUE TO LIQUID EFFLUENTS 1
Thus, it can be seen that the average whole body dose to an individual is much less than the maximum whole body dose to an individual as shown in Table 5.1.
5-1
In order to provide perspective on the doses in Table 5.1, the standards for 1984 on the allowable maximum dose to an individual of the general public are given in 40CFR190 as 25 mrem whole body, 75 arem thyroid, and 25 mrem any other organ. These standards are a fraction of the normal background radiation of 125 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 background, they have insignificant public health consequences.
In fact, the plant related doses to the maximum individual are less than 10% of the variation in natural background in Connecticut.
l l
5-2
i i
TABLE 5.1 COMPARISON OF DOSE CALCULATION METHODS e
HADDAM NECK STATION I
JANUARY-DECEMBER 1984 l >
4 METHOD 1
} METHOD 2(1)
ORGAN I PATHWAY ,
l ND( }
I AIRBORNE EFFLUENTS Max. Ind.( -Wole Body 1.5 >
- 1. External Gamma Dose ) , <0.6
] NAD i r
Max. Ind.-Thyroid 0.13 !
- 2. a. Inhalation Max. Ind.-Thyroid 0.28 NAD Vegetables NAD, <2.3 b.
Max. Ind.-Thyroid 0.18 a
- c. Goat's Milk 0.023 ,
LIQUID EFFLUENTS 1.10
- 1. Fish Max. Ind.-Woleggdy 1.49 0.035 Max. Ind.-Liver (1)
Method 1 uses measured station discharges 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 the related activity.
The dose to the average individual is much less than the maximum individual dose.
doses for inhalation and vegetable consumption assume that the individual resides at the point of maxim quarterly dose. Therefore, his residence is subject to variation for conservatism.
(3) The plant effects were so small that they could not beThe distinguished less than valuefrom reportedfluctuations is the dosein natural (4) NAD - No activity detected above the minimum dectable level.
' corresponding to the MDL.
(5) For adult.
4 i
i
[
l 4
6.0 DISCUSSION The evaluation of the effects of station operation on the environment requires the 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 variations in the measured radioactivity. A failure to consider these factors could cause erroneous conclusions.
Consider, for example, the problem of deciphering the effect of station releases on 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 I-131 and Sr-89 are relatively short-lived. Therefore they result from either plant effluents or from recent nuclear weapons tests. Sr-89's lifetime is longer than I-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 Cs-137. These isotopes are still remaining from 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 difficult problem.
In reviewing the Sr-90 and Cs-137 measured in cow and goat milk in the areas around the Millstone and Haddam Neck stations, a casual observer could notice that in some cases the levels of these isotopes are higher at farms closer to the 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.
- 1. The stations accurately measure many fission products, including Sr-90 and Cs-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, see Section 5.0) show that insufficient quantities (by more than a factor of 1000) of Sr-90 and Cs-137 have been released from the stations to yield the measured concentrations in milk.
- 2. Based on the ratio of Sr-89 to Sr-90 in the measured releases from the stations and on the similar chemical properties of the two nuclides, plant-related Sr-90 cannot be detected in milk without also detecting plant related Sr-89. During 1981 (and a few other occassions), Sr-89 has been detected in many of the milk samples. To investigate the source of Sr-89, air particulate data has been evaluated. Evaluation shows that airborne Sr-89 6-1
i is generally uniform at all the indicator and control locations for both the Millstone and Haddam Neck stations. Therefore it can be concluded that the Sr-89 seen in milk is from recent fallout. Similarly, the levels of airborne Sr-90 (and total Cesium) are also generally uniform at all the air sampling locations. However, with the longer half lives of these isotopes, the same conclusion cannot be made. But, plant related Sr-89 has never been detected in milk, therefore levels i
of Sr-90 observed must be attributable to nuclear weapon's l
testing.
i
- 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 of the milk samples suggests that the Cs-137 is not plant related. This is further confirmed l by the evaluation of the air particulate data.
l ,
- 4. Since dairy milk sampling began in the 1960's, years prior to plant operation, the immediate station areas have always shown higher levels of weapons fallout related Sr-90 and Cs-137 (see Figures 6-1 and 6-2). The ratio of activity between the i
! locations has not changed with plant operation. All areas show the same significant decrease in radioactivity since the 1964 Nuclear Test Ban Treaty.
l
- 5. Local variability of Sr-90 and Cs-137 in milk is cosunon through-out the United States. Due to the variability in soil con-ditions, pasturing methods, rainfall, etc., it is the rule rather than the exception. Therefore, it is not surprising that certain farms have higher levels of radioactivity than other farms. In fact, there are some cases where the farms further from the station have higher Sr-90 and Cs-137 values than the farms that are closer to the station (e.g., see Haddam Neck Goat Milk data.)
- 6. The goat farm with the highest levels of Sr-90 and Cs-137 has f also experienced the highest levels of short-lived activity l
from the 1976 and 1977 Chinese Tests. This indicates that for j
some 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.
l I Based on these facts, the observation that the station effluents are responsible is obviously false. The cause must be one or more of l
the 0ther variables.
7 l
I Northeast Utilities has carefully examined the data throughout the i
year and has presented in this report all cases where plant related l
radioactivity can be detected. An analysis of the potential exposure I to the population from any plant related activity has been performed and shows that in all cases the exposure is insignificant.
6-2
i 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, Environmental Protection Agency and Connecticut Department of Environmental Protection.
4 r
I 6-3 i
i
(
APPENDIX A Cow and Goat Census for 1984 A-1 i
DAIRY COWS WITHIN 15 MILES OF CONNECTICUT YANKEE AS OF APRIL 1984 NAME AND ADDRESS NO. OF COWS DIRECTION DISTANCE William Bailey 27 N 15 M.
79 Cand1ewood Rd.
Marlborough, CT 06447 Foot Hills Farm 35 N 15 M.
Edward Fotte RFD #2 Hebron, CT 06248 Kristoff Brothers 138 N 15 M.
Hyland Farm 183 Bailey St.
Glastonbury, CT 06033 Rankt Farm-Theo Rankt 134 NNE 8 M.
South Road Marlborough, CT 06447 Robert K. Gasper 54 NNE 14 M.
694 Gilead St.
Hebron, CT 06248 Hills Farm 85 NNE 14 M.
527 GIIcad St.
Hebron, CT 06248 Mapleleaf Farm, Inc. 150 NNE 14 M.
750 Gilead St.
Hebron, CT 06248 Douglas Porter 160 NNE 14.5 M.
RFD #1 Hebron, CT 06248 14.5 M. Jonas Valys 134 NNE Hardy Road Hebron, CT 06248 John Dill 24 NE 4.5 M.
Waterhold Rd.
i Colechester, CT 06415 j - East Hampton -
John Mohrlein 60 NE 8.5 M.
Route 16 Colchester, CT 06145 Marvin Maynard 20 NE 10 M.
RFD #2 Colchester, CT 06415
I I
DAIRY COWS WITHIN 15 MILES OF CONNECTICUT YANKEE l AS OF APRIL 1984 DIRECTION DISTANCE NAME AND ADDRESS NO. OF C0WS NE 14 M. Victor Botticello 28 Levita Rd.
Lebanon, CT 06249 14 M. Grabber Brothers 45 NE RFD #1 Lebanon, CT 06249 ENE 6 M. William Dill 70 Beebe Rd.
East Haddam, CT 06423 ENE 6.5 M. Grandpa Hill Farm 61 l
R.S. Cone Box 251 East Haddam, CT 06423 ENE 8.1 M. William Smith 43 Town Road Colchester, CT 06415
- East Haddam -
ENE 11 M. Walter Swider 47 Route 85 Colchester, CT 06415 ENE 14 M. Burton Avery 50 Rathburn Hill Rd.
Colchester, CT 06415
- Salem -
ENE 14.5 M. Walter Makarevich 17 Geer Road Lebanon, CT 06249 E 11.5 M. Valley View Farm 24 Eugene Wiczewski Da'rling Rd.
Colchester, CT 06415 12 M. Robin & William Houser 24 E
Salem 4 Corners Salem, CT 06415 E 13 M. Anne B. Henrici 15 Catawampus Darry Round Hill Road Salem, CT 06415
DAIRY COWS WITHIN 15 MILES OF CONNECTICUT YANKEE AS OF APRIL 1984 DIRECTION DISTANCE NAME AND ADDRESS NO. OF COWS E 13 M. Garry Vall) 34 Forsythe Rd.
Colchester, CT 06415
- Salem -
E 14 M. .
Stuart Gadbols 225 Route 85 s Route 356 Colchester, CT 06415
- Salem -
ESE 2.5 M. Mortimer Geiston 45 Maple Ridge Farm Maple Avenue East Haddam, CT 06423 ESE 14.5 M. Raymond Muschinsky 27 Grassy Hill Road East Lyme, CT 05333 SE 11 M. John Tiffany 70 Sterling City Rd.
Old Lyme, CT 06371
- Lyme -
SE 12 M. J. Ely Harding 60 Ashlawn Farm Old Lyme, CT 06371
- Lyme -
SW 13 H. Thomas Haggarty 43 Hoophole Rd.
Gullford, CT 06437 WSW 8 M. Michael Dwyer 7 Route 17 Durham, CT 06492
,allingford W -
WSW - 8 M. Robert Raudat 33 Old Durhem Rd.
Killingworth, CT 06417 WSW 11 M. Raymond Wimler 180 Guilford Rd.
Durham, CT 06422 WSW 14 M. Cella Brothers 125 Whirlwind Hill 2, No. Brandford St.
Wallingford, CT 06492
DAIRY COVS WITHIN 15 MILES OF CONNECTICUT YANKEE AS OF APRIL 1984 DISTANCE NAME AND ADDRESS NO. OF C0WS DIRECTION John Kranyak 48 WSW 14 M.
1349 Whirlwind Rd.
Wallingford, CT 06492 Alfred Anderson 23 WSW 15 M.
216 Northford Rd.
Wallingford, CT 06492 Co Ag Farm, Inc. 187 WSW 15 M.
Walter Augur s George Cooke 180 Northford Rd.
Wallingford, CT 06492 Richard Rowe 30 W 8.5 M.
^
Box 4, Higganum Rd.
Durham, CT 06422 V 11.5 M. Friendly Acres Dairy Farm 37 l Tony Caltabiano Parmalee Hill Rd.
Durham, CT 06422 W 12.2 M. Powder Hill Dairy Farm 170 Henry Bugal Powder Hill Rd.
Durham, CT 06422 W 12 5 M. Linus Sanstrom, Jr. 30 Strickland Rd.
Middlefleid, CT 06455 Thomas Wall 48 W 14 M.
963 Northrop Rd.
Wallingford, CT 06492 North Farms 22 W 14 M.
Alex Werbiski 1069 Farms Rd.
Wallingford, CT 06492 14.5 M.
Charles Greenbacker s Sons, Inc. 131 W
743 Murdock Avenue Meriden, CT 06450 Robert Self 91
! W 14.5 M.
Fieldstone Farm 63 Grieb Rd.
Wallingford, CT 06492
DAIRY C0WS WITHIN 15 MILES OF CONNECTICUT YANKEE AS OF APRIL 1984 DIRECTION DISTANCE NAME AND ADDRESS NO. OF C0WS W David Cella 18 15 M.
899 Old Rock Hill Rd.
Wallingford, CT 06492 W 15 M. Fairlawn Dairy Farm 68 Harold Gehrke, Sr.
178 Grieb Rd.
Wallingford, CT 06492 WNW 7 M. Wilbur Harris 31 174 Wilcox Rd.
Middletown, CT 06457 WNW 7 M. Willie Harvey 59 Lee Street Middletown, CT 06457 l
8 M. E. Leroy Brock 66 WNV 796 Ridge Rd.
Middletown, CT 06457 WNV 8 M. George Seifert 30 j
Kelsey St.
Middletown, CT 06457 WNW 12 H. John Kolman 55 Meriden Rd.
Middletown, CT 06457 WNW 12 M. Walnut Hill Farm 100 William f, Thomas Mintz Jackson Hill Road Middlefleid, CT 06455 WNW 12.5 M. Far View Farm 40 Gustave Schmaltz Ja.ckson Hill Road Middlefield, CT 06455 WNW 13 5 M. Richard Westfort 62 543 Allen Avenue Meriden, CT 06450 WNW 15 M. Bilger Brothers 32 Hickory Grove Farm 705 Westfield Rd.
Meriden, CT 06450 L
DAIRY C0WS WITHIN IS MILES OF CONNECTICUT YANKEE AS OF APRIL 1984 DISTANCE NAME AND ADDRESS NO. OF COWS DIRECTION John Hanson 17 WNW 15 M.
506 Spruce Brook Rd.
Berlin, CT 06037 6 M. Edward Hills 36 NW Brooks Rd.
Middletown, CT 06457 Daniel Anderson 79 NW 9.5 M.
Blague Dairy Farm 56 Strong Avenue Portland, CT 06480 NW 13 M. Higgins Farm, Inc. 49 837 Ridgewood Rd.
Middletown, CT 06457 Leland Gilbert 28 NW 15 M.
730 Elm St.
Rocky H111, CT 06067 John Kruger 14 NNW 1.5 M.
Quarry Hill Rd.
Haddam, CT 06438 2.5 M. Halls Pride Farm 25 NNW John Hall Haddam Neck Rd.
East Hampton, CT 06424
- Haddam -
NNW 13 M. Charles Matway, Est. 17 Brook St.
Rocky Hill, CT 06067 NNW 14 M. Roaring Brook Farm 25 Henry K111am 77 Tryon St.
So. Glastonbury, CT 06073
- Glastonbury -
l l
l l
DAIRY C0ATS WITHIN 20 MILES OF CONNECTICUT YANKEE AS OF MAY 1984 DIRECTION DISTANCE NAME AND ADDRESS NO. OF G0ATS N 4.5 M. Philip Bourdon 9 164 Young St.
East Hampton, CT 06424 I
N 6 M. Jackle Reardon 5 So. Main St.
East Hampton, CT 06424 N 12.5 M. Allan Armando 1 New London Tkpe.
Glastonbury, CT 06033 M. v. Branco 4 N 18.5 M.
School Rd.
Bolton, CT 06040 12 M. Louise Sage 4 NNE 155 Reidy Hill Rd.
Hebron, CT 06248 NNE 16 M. Joan Bowers 3 350 Wall St.
- Hebron, CT 06248 16 M. Elaine Phillips 8 NNE Burnt Hill Rd.
Hebron, CT 06248 NNE 16 M. Kathy Waters 9 Burnt Hill Rd.
Hebron, CT 06248 228-3098 NNE 18 M. Cira Petersons 1
! Route 87
' Columbia, CT 06237 r
NNE 18.5 M. Carolyn Bellows 1 Route 87 Columbia, CT 06237
DAIRY GOATS WITHIN 20 MILES OF CONNECTICUT YANKEE AS OF MAY 1984 4
DIRECTION DISTANCE NAME AND ADDRESS NO. OF GOATS 20 M. Ted Beebe 5 NNE Route 6 Columbia, CT 06237 NNE 20 M. Arthur Cobb 1
, 128 Lake Rd.
i Columbia, CT 06237 Barbara Nadeau 3 NE 16 M.
Clubhouse Rd.
Lebanon, CT 06249 Lynn Miller 8 NE 17 M.
Goshen Hill Rd.
Lebanon, CT 06249 l
1
. ENE 11 M. Lawrence Brown
! West Rd.
Colchester, CT 06415 Henry Rianhard I ENE 17 M.
' Scott Hill Rd.
Borrah, CT 06334 i
E 14.5 M. Joseph Devito 5 1494 Old Colchester Rd.
Oakdale, CT 06370 ESE 3*I M- MaryAnn Halpin 3 Town St.
East Haddam, CT 06423
\
Burton Tucker 2 ESE 7 2 M.
A.P. Gates Rd.
l East Haddam, CT 06423 Tina Korineck 6 ESE 15 M.
233 Upper Pattagansett Rd.
East Lyme, CT 06333
. _ . _ , _ . _ _ . . _ . . _ , - _ _ __ __ s. _. - _
DAIRY COATS WITHIN 20 MILES OF CONNECTICUT YANKEE AS OF MAY 1984 NAME AND ADDRESS NO. OF GOATS DIRECTION DISTANCE 6
ESE 16 M. Ron Birchall 339 Boston Post Rd.
East Lyme, CT 06333 I
5 8.5 M. David Recchla RFD #1 Deep River, CT 06417 Victor Trudeau 5 5 11.5 M.
174 Horse Hill Rd.
Westbrook, CT 06498
'l 2
SSW 6.8 H. Chris Harris 218 Reservoir Rd.
Killingworth, CT 06417 2
SSW 8.5 M. Vickl Fonteneau 312 Old Deep River Tkpe.
Killingworth, CT 06417 Barbara Prisitera I SW 20 M.
94 Mill Plain Rd.
Branford, CT 06405 i
4 W 4.8 M.
- Pat Mannetho Jacoby Rd.
Higganum, CT 06441 Brian Hogan I W 12 M.
Route 157 Middlefield, CT 06082 i
Robert Pogomore 2 W 14.5 M.
177 Williams Rd.
Wallingford, CT 06492 Roger Kinderman 3 WNW 10.5 M.
721 Wadsworth Rd.
Middlefield, CT 06082 I
f DAIRY GOATS WITHIN 20 MILES OF CONNECTICUT YANKEE AS OF MAY 1984 NAME AND ADDRESS NO. OF G0ATS DIRECTION DISTANCE Nancy Hanson 4 WNW 15 M. "
506 Spruce Brook Rd.
1 Berlin, CT 06037 Daniel Nitkowski I WNW 19 M.
46 Firch Ave.
Meriden, CT 06450 Donald Donofrio 7 NW 1.5 M.
injun Hollow Rd.
Haddam, CT 06441 Ronald Marchinkoski 2 NW 13 5 M.
122 Coles Rd.
Cromwell, CT 06106 NW 13 5 M. Melvin Granger - 3 140 Coles Rd.
Cromwell, CT 06106 NNW 3 5 M. Francis McAuliffe 2 Route 151 Middle Haddam, CT 06456 Dorothy Joba 6 NNW 14 ft.
171 Ferry Lane S. Glastonbury, CT 06073 i
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APPENDIX B Quality Control
! B-1 l
Introduction 3
Northeast Utilities Service Company (NUSCO), acting as the agent for both the Northeast Nuclear Energy Company (NNECO) and the Connecticut Yankee Atomic Power Company (CYAPCO), maintains a quality assurance (QA) program of its primary contractor of radiological analyses, Chemical Waste Management of Massachusetts, Inc. , (Teledyne for H-3 in water sample s).
This is accomplished by the use of the three quality control methods that are specified in Radioassay Procedures for Environmental Samples, U.S.
Department of Health, Education, and Welfare (January 1967).
These three quality control methods are:
a) Duplicate analyses of actual surveillance samples with one laboratory. This type of quality control allows an evaluation of the contractor's precision or reproducibility of results.
b) Cross-check analyses of actual surveillance samples with more than one laboratory. This intercomparison allows the determination af what agreement the primary 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 performed, these include: 1) Chemical Waste Management's internal QA program, 2) Chemical Waste Management's participation in EPA's Environmental Radioactivity Laboratory Intercomparison Studies Program, and 3) Nuclear Regulatory Commission -
State of Connecticut Independent Verification Program.
Method The number and type of QA samples are given in Table 1. In general, the objective was to obtain between 10 and 20 percent of the samples as QA samples. The results of the program are shown in Tables 2, 3, and 4.
These three tables correspond to the above methods of quality control.
For I-131 spikes in milk, the acceptance criteria is based on the requirement that the measured value be within 30 percent of the spike.
' The acceptance criteria for the remaining QA samples is based on the standard deviation in counting statistics (1 sigma, c) only. The standard deviation is divided into the difference between the two measurements (A). The result then should satisfy the acceptance criteria i
as developed from the above-mentioned U.S. Department of Health, '
' Education'.and Welfare document. For all GeLi analyses the acceptance criteria is that A/o be less than or equal to 3. For chemistry and beta counting, where the overall error is expected to be higher than the calculated error based on counting statistics only, the acceptance criteria is that A/o be less than or equal to 4.
Results For Precision (Table 2), the requirement is that the unacceptable results be less than 10 percent of the number of measurements for that type of B-2
measurement as shown for the totals.
General statistics indicate that this value should be approximately 2.5 percent for counting statistics, ,
but other non-counting statistical errors exist such as sample volume, a sampling, etc. Hence, 10 percent has been found to be reasonable From the totals at the bottom of Table 2 this requirement is criteria. However, 11.1 percent of the satisfied for Ge(Li) and H-3 analyses.All four sets of unacceptable Sr-90 analyses were unacceptable.
measurements were compared with the results of the secondary contractor.
Comparison indicated that the primary contractor's first analysis was correct, and three of the four unacceptable measurements were conservative.
For Interlaboratory Comparisons (Table 3) the requirement is less stringent than both Precision and Accuracy, that is the unacceptable results be less than 20 percent of the number of measurements for that As indicated by the totals on the bottom of type of measurement.
Table 3, the results are acceptable.
For the case of Accuracy, only the primary contractor need satisfy the acceptance criteria. The secondary contractor receives only a small number of samples thus making the evaluation of the secondary contractor difficult.
The requirement that need be satisfied by the primary contractor here is the same as that for Precision, that the unacceptable results be less than 10 percent of the number of measurements for that type of measurement. From the totals at the bottom of Table 4 This this requirement is satisfied for H-3 and I-131 (in air) analyses.
requirement is just exceeded for Sr-89 and Ge(Li) analyses (14 and 13 percent, respectively).
Investigations were performed for the other analyses that did not meet the acceptance criteria. For the I-131 in milk analyses, problems of The switch from CuI to PdI carrier has previous years have remained.Of the 6 unacceptable results, 5 occurred for low improved spikes. the results.All five of these yielded conservative results, therefore, it can be concluded that the data presented in this rep nt for this type of The increased spiked I-131 in milk program analysis, is conservative.
will continue.
For the Sr-90 and Sr-89 spikes in milk, the only unacceptable results occurred in the same sample. The first Sr-90~result was ~ low.
36 percent 55 percent The first low. Reanalysis indicated a value that was Sr-89 result was high (by ~ 300 percent), indicating interference fromFor the th Sr-90. Reanalysis for Sr-89 was acceptable.
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Sr-90 and two unacceptable Sr-89 results in water, five samples wereThe origina j involved. Four of these were reanalyzed. Reanalyses indicated acceptable res l were three ~samples.
30 percent low.The original Sr-89 results were only ' 20 percent low.
Resnalysis of one of these indicated acceptable results.
One sample was Two fish spikes had Sr-90 results that were unacceptable.This media often reanalyzed; the Sr-90, however, remained unacceptable.
presents a problem because of calcium interferences and Fornonuniformi l
spikes. Therefore, no further investigation was deemed necessary.
the two unacceptable Sr-90 results in air particulates, results were B-3
l ' 60 percent low. Reanalysis of this media is not possible since the
- whole sample is destructively analyzed.
- Air particulate Cs (chemistry) spikes had only two of eight spikes meeting the acceptance criteria. However, all of these were within j ' 30 percent, except for one which was 80 percent low.
For the GeLi results, the calibration factors were at fault and these have been corrected.
The gross beta results, although only 3 of 13 results were acceptable, has no analysis problem. The problem is related to the geometry of spiking the filter paper. Corrective actions are being taken.
j Conclusion i
Based on the results discussed above, it is concluded that the results of the routine measurements presented in the report are valid. The results
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l B-4 i -' . - - - - , . _ _ _ _ _ _ _
4 i
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i Table 1 Number of Quality Contro1* Samples Number of Number of Routine a,b QC Samples Required Samples Sample Type 51 112 i Milk 17 28
! Well Water
- 2 16
! Sea Water
- 1
]
7 8 River Water
- 3 16 i Soil 4 26 Bottom Sediment 4 12
! Aquatic Flora 12 40 Fish i
4 52 Shellfish 0 12 Lobster l 16 Fruits and Vegetables 0 l
i 1113 Air Particulate - Gross Beta 13 11 424
- Iodine 24 252
- Geli 8 84
- Chemistry l
1
)
(
- An additional program is performed by the contractor l
i a - Total for both Millstone and Connecticut Yankee
! I - !tpends on availability l
c e QC breakdown does not include H-3 analysis; total nimber of tri-tium QQ samples was 31.
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1
+
B-S ,
i
.. _- .- . ~.
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Table 2 i
' Precision 4
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Acceptance Number of Measurements j Acceptable Unacceptable a Media Analysis Criteria 90 25 3 Milk Sr A/o$ 4*
E9 27 1 l Sr A/05 4 Cs137 (Geli) A/05 3 27 1 l
A/05 4 8 0 Water H-3 l 0 Soil & A/oS 3 3 Gegg's 2
- Bottom Sr A/of 4 1 i Sediment A/of 3 5 0 l Aquatic Ge}f's 0 i Life Sr A/oS 4 5 90 32 4 Total Sr A/05 4 ,
j Geli A/os 3 35 1 A/os 4 8 0
1
- A = difference between the two values a = standard deviation i
t 1
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i B-6 1
i
Table 3 Interlaboratory Comparisons Acceptance Number of Measurements Media Analysis Criteria Acceptable Unacceptable 90 0 Milk Sr 89 A/oS 4* 11 Sr A/oS 4 11 0 Cs137 (Geli) A/of 3 11 0 90 0 Water Sr A/of 4 7 H-3 A/c5 4 11 1 Soil & A/of 3 4 0 Gegg's 0 Bottom Sr A/oS 4 4 Sediment Aquatic A/oS 3 10 0 Gejf's 9 Life Sr A/oS 4 1 90 33 Total Sr 3fgg 4 3 H-3 A/of 4 11 1 Geli A/oS 3 25 0
- A = difference between the two values a = standard deviation i
, B-7 i
Table 4 Accuracy (Results of Spikes)
Number of Measurements Acceptable Unacceptable Acceptance Pr inia ry Secondary Primary Secondary Media Analysis Criteria Contractor Contractor Contractor Contractor I
Milk I A 5 30% IS 6 6 0 Sr 89 A/o 5 4 7 4 1 0 Sr A/o 5 4 7 4 1 0 Cs A/o 5 3 8 4 0 0 Cs A/c 5 3 7 4 1 0 Water Gegg A/o 5 3 11 6 1 0 Sr gg A/o 5 4 9 6 3 0 Sr A/o 5 4 10 6 2 0 E-3 A/o 5 4 8 4 0 0 Aquatic Geff A/c 5 3 0 1 2 1 Food and Sr A/ 5 4 0 2 2 0 89 Flora Sr A/o 5 4 2 2 0 0 Air Gross S A/o 5 4 3 -
10 -
Particulate Geli A/o 5 3 21 -
3 -
Csfchemistry) g A/o 5 4 2 -
6 -
Sy37 A/o 5 4 6 - 2 -
I 4/o 5 4 II -
0 -
3 Total I 9
(milk) A 5 30% 18 6 6 0 Sr A/o 4 22 12 8 0 89 Sr A/o 5 4 19 12 3 0 Cs (chemistry) A/o 5 4 2 -
6 -
Geli A/o 5 3 40 11 6 1 A/o 5 4 8 4 0 0 Hyjg(air)
I 4/o 5 4 11 -
0 -
Gross S (air) A/o 5 4 3 -
10 -
- A = difference between the two values a = standard deviation i
i B-8 1
CONNECTICUT YANKEE AT O M IC POWER COMPANY B E R L I N, CO N N E CTICU T P O BOX 270 HARTFORD. CONNECTICUT 06141-0270 TELEPHONE 203-666-6911 March 27, 1985 Docket No. 50-213 B11502 Dr. T. E. Murley Regional Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406
Dear Dr. Murley:
HADDAM NECK STATION ANNUAL ENVIRONMENTAL OPERATING REPORT, PART B: RADIOLOGICAL In accordance with the requirements of Appendix B to the operating license, Environmental Technical Specifications, 5.6.1.a., two (2) copies of the Annual Environmental Operating Report, Part B: Radiological, are herewith submitted. Copies of this report are being distributed in accordance with Ragulatory Gufde 10.1.
Very truly yours, CONNECTICUT YANKEE ATGMIC POWER COMPANY d
W. G. 'Counsil Nf Senior Vice President c: J. A. Zwolinski S
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