ML20138M510
| ML20138M510 | |
| 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. |
| To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| B11502, NUDOCS 8511040043 | |
| Download: ML20138M510 (100) | |
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S HADDAM NECK STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL ENVIRONMENTAL OPERATING REPORT PART B PERIOD JANUARY 1, 1984 - D"CEMBER 31, 1984 DOCKET NO. 50-213 LICENSE NO. DPR-61 PREPARED FOR TIE CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM, CONNECTICUT BY THE NORTIIEAST UTILITIES SERVICE COMPANY BERLIN, CONNECTICUT i i
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l l HADDAM NECK STATION $ RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l t ANNUAL ENVIRONMENTAL OPERATING REPORT ^ PART B PERIOD JANUARY 1, 1984 - DECEMBER 31, 1984 f ! DOCKET No. 50-213 LICENSE NO. DPR-61 i PREPARED FOR THE ! CONNECTICUT YANKEE ATOMIC POWER COMPANY l HADDAM, CONNECTICUT i i BY THE ) NORTilEAST UTILITIES SERVICE COMPANY BERLIN, CONNECTICIIT l l I i r.., . , - _ _ .. , _ . . _ . _ . _ - _ . , . - _ _ _ , . , _ _ . ~ __ . _ . . . _
i i TABl.E OF CONTENTS Page No. 1.0 Summary 1-1 2.0 Program Description 2-1 2.1 Sarrpling Schedule and Locations 2-1 2.2 Samples Collected During Report Period 2-9 3.0 Radiochemical Results 3-1 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
- = _. - - - - - _. _ - .- . _ . ~ . . _ =. . -
4 i 1.0
SUMMARY
The radiological environmental monitoring program for the Haddam , 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 4 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 l devices and on samples of air particulates and iodine, soil, milk, ! I 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 i 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 sediment
- collected from the vicinity of the mouth of the discharge canal.
i 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 of plant operation. This can be i concluded based on the facts that: insufficient quantities (at least 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. t i 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
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 2.6 miilirem and the average dose to a
- l member of the public residing within 50 miles of the plant is 0.0023
! millirem. These doses are 10.4 percent and 0.00<>2 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. 4 l 4 I I l-2
1 l l 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. i 2-1
Table 2-1 CONNECTICUT YANKEE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sample Type. Frequency (b) and Analysis (c) Distance Gamma Air Location & Direction (a) Dose Particulate (f) Soil Vegetation Water Milk (d) Terrestrial Stations
- 1. On site fence near boron waste storage tanks 0.1 miles,NW M -- -- -- -- --
- 2. On site fence near waste gas surge sphere 0.1 miles,E M -- -- -- -- --
- 3. On site fence near discharge canal 0.2 miles,SI: M -- -- -- -- --
- 4. On site fence near guard house 0.1 miles,WNW M -- -- -- -- --
- 5. On site-Injun Hollow Road 0.4 miles,NW M Wl-M2-Q5(e) A2,5 -- -- --
- 6. On site-Substation 0.5 miles,NE M Wl-M2-Q5(e) A2,5 -- -- --
- 7. Haddam I .C miles,SE M Wl-M2-Q5(e) A2,5 -- -- --
- 8. East Haddam 3.1 miles,ESE M Wl-M2-Q5 A2,5 -- -- --
- 9. Higganum 3.2 miles,WNW M W1-M2-Q5 A2,5 -- -- --
7 10. Hurd Park Road--East Hampton 2.8 miles,FNW M Wl-M2-QS A2,5 -- -- --
" 11. Middictown *10.0 miles,NW M Wi-M2-Q5 A2,5 -- -- --
- 12. Deep River *8.0 miles,SSE M Wl-M2-QS A2,5 -- -- --
- 13. North Madison *12.0 miles,SW M Wl-M2-Q5(e) A2,5 -- -- --
- 14. Colchester *10.0 miles,NE M W1-M2-Q5 A2,5 -- -- --
- 15. On Site-Wells 0.8 miles,SE -- -- -- --
M1,2,4,5 --
- 16. Well-State Highway Dept.
East Haddam *3.0 mile,S -- -- -- -- Ql.2,4,5 --
- 17. Well-Injun Hollow Road 1.0 mile,NW -- -- -- --
Ql.2,4,5 --
- 18. Well-Haddam 1.0 mile,S -- -- -- --
Ql,2,4,5 --
- 19. Cow Location #1 1.5 miles,NNW -- -- -- -- --
M3
- 20. Cow Location #2 2.2 miles ESE -- -- -- -- --
M3
- 21. Cow Location #3 4.5 miles,NE -- -- -- -- --
M3
- 22. Cow Location #4 *11.0 miles,ENE -- -- -- -- --
M3
- 23. Goat Location #1 *16.0 miles, NE -- -- --
M3(g) -- -- i 24. Goat Location #2 1.5 miles,NW -- -- -- M3(g) -- --
- 25. Fruits & Vegetables -- -- -- --
A2(h) -- --
Table 2-1 (continued) Sample Type, Frequency (b) and Analysis (c) Distance & Bottom Location Direction (a) Sediment Water Fish (i) Shellfisil Aquatic Stations
! 26. Conn. River - Vicinity of intake 1.0 miles,WNW -- --
Q2,5 -- l 27. Conn. River - liigganum Light *4 niles,Lna; Q2,5 -- -- Q2,5
- 28. Conn. River - E. Haddam Bridge *1.8 miles,SE Q2,5 -- -- --
- 29. Plant Discharge Canal ------ Q2,5 Ql.2,4,5 Q2,5(1) --
- 30. Conn. River - Middletown *7. 6 miles,NW -- Ql,2,4,5 Q2,5(i) --
- 31. Mouth of the Salmon River 0.8 miles,ESE -- -- --
Q2,5 Y w 4
- 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-Gamma Spectrum, 3-I-131, Sr-89, Sr-90, 4-11-3; 5-Sr-89, Sr-90 (d) During the period April through October and once in February (c) 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 seacon, when available from commercial farms i'
(i) Bullheads and when available perch i
M P TABLE 2-2 l MINIMUM DETECTABLE LEVELS IN ENVIRONMBTAL SAMPLES AND RESULTING DOSES Minimum Detectable Annual Dose
- L evels" Associated Sample Type Analysis Sample Size (MDL) with MDL' (mrem) Critical Organ Annual Intake Well and River Water Gross beta 1 liter 1 pC1/1 - - --
Camma spectrum 3 liter 20 pC1/la _ _ Sr-89 2 liter 2.0 pC1/1 0.2' bone 440 1 t Sr-90 2 liter 1.0 pC1/1 1.0' bone 440 1 Cs-137 2 liter 6.0 pC1/1 0.078' whole body 440 1 H-3 2 liter 60 pCi/1 0.005' body tissue 440 1 I Bottom Sediment and Soil camma spectrum 1 kg 0.05 pC1/g' " -- -- -- y Sr-89 1 kg 0.072 pC1/g -- - -
- Sr-90 1 kg 0.036 pC1/g - - -
Cs-131 1 kg 0.064 pC1/g -- - Fish acd Shellfish Gamma spectrum 1 kg 0.05 pC1/g' -- - - St-69 100 g 0.018 pCi/g 0.08 bone 18.3 kg br-90 100 g 0.00) pCi/g 0.4 bone 18.3 kg Cs-137 100 g 0.056 pC1/g 0.031 whole body 18.3 kg I Gamma Dose TLD 1 month 1 mrem -- whole body 12 month exposure exposure i Milk I-131 4 liter 0.5 pC1/1 1.6 Child's thyroid 183 1 Sr-80 1 liter 2.0 pC1/1 0.08 bone 183 1 Sr-90 1 liter 1.0 pC1/1 0.40 bone 183 1 Cs-137 1 liter 6.0 pC1/1 0.036 whole body 183 1 i
'I
4 TABLE 2-2 (Cont'd) Minimum Detectable Annual Dose Levels" Associated Sample Type Analysis Sample Stre LMDL) with MDL' (mreml Critical Organ Annual intake Filtered Air I-131 270m3' O.04 pC1/m3 0. 5 ' child's thyroid 1100 m3 Cross Beta 270m3 0.01 pC1/m 33 - Cross cannna 270m3 0.045 pC1/m3 ' -- -- -- Camma Spectrum 1,080m3 0.02 pC1/m3 _ __ __ Vegetation Gamma Spectrum 1 kg 0.05 pC1/g' -- -- -- i 1-131 1 kg 0.05 pCi/g 7.5' ' Child's thyroid - Sr-89 1 kg 0.018 pCi/g ) q Sr-90 1 kg 0.009 pC1/g Cs-137 1 kg 0.034 pC1/g t
' Based on a calibration with Cs-137 of 1.5 pCi=1 count per minute a For Cs-137 assuming no interference from other nuclides
' Cs-137 used as a reference source u ' These are minimum practical detectable levels (MDL) as opposed to theoretical detection limits. They apply to the activity at the
& time of sample collection. MDL = 2 o background.
5 Based on the Federal Radistion Council reports on Radiation Protection Guides 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 1831.
s ' From WASH-1258 (July 1973)
' From WASH-1258 Table 6B-4
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- East Haddom i,,,i,,,i scale of miles O tiell Water Sampling Stations e Aquatic Sampling Stations FIGURE 2.3 Aquatic and Well Water Sampling Stations Haddam fleck Plant 2-8
l 2.2 Samples Collected During Report Period 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 (TIS) 167 Air Particulates 529 Air Iodine 212 Soil 10 Dairy Milk 32 Goat Milk 16 Pasture Grass 0 Well Water 24 Fruit and Vegetables 8 River Water 8 Bottom Sediment 12 Fish 23 Shellfish 8 Total All Types 1,049 2-9 1 1
__ _ _ = - - ._ 3.0 RADIOCHEMICAL _ljESul.TS 3.1 Summary Table In accordance with Environmental Technic.il 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 cata was handled as recommended by llealth and Safety Laboratory, Idaho: all valid data, including negative values and zeroes were used in the determination of the mean (see part 3.2). A more detailed analysis of the data is given in section 4.') 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. i Y I i J l 4 i i 1 1 3-1
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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 l, ANALYSIS AND MINIMUM ALL INDICATOR LOCATION WITH HIGHEST ANNUAL MEAN CONTROL LOCATIONS MEDIUM OR TOTAL NUMBER DETECTABLE LOCATIONS PATHWAY OF ANALYSES f 0F LEVELS (b) NAME. DISTANCE (b) (Range) (b) NRMs SAMPLED PERFORMED (MDL's)(a) Mean AND DIRECTION Mean (Range) Mean (Range) (c) Sr 24,16- 0.002(9) 0.00006 (-0.0003 - 0.0006) Higganum 0.00013 (0.000 - 0.0002) Sr-89 -0.00013 (-0.0014 - 0.0004) 0 3.2 Miles WNW Sr-90 0.001(9) 0.00020 (-0.000 - 0.0008) East Haddam 0.00030 (0.0001 - 0.0008) 0.00011 (-0.002 - 0.0004) 0 3.1 Miles ESE
- Soil Sr 6,4 0.072 0.001 (-0.008 - 0.013) Haddam 0.013 -0.003 (pC1/g) Sr-89 1.8 Miles SE N/A (-0.03 - 0.006) 0 I
Sr-90 0.036 0.058 (0.033 - 0.089) Colchester 0.110 0.078 , 10 Miles NE N/A (0.008 - 0.110) 0 a Ge(Lf) 6,4 0.064 0.29 (0.12 - 0.47) North Madison 0.93 N/A 0.46 4 Cs-137 (0.00 - 0.93) 0 12 Miles SW l i Cs-134 0.06 0.00 N/A N/A 0.00 0 i Mn-54 -- 0.00 N/A N/A 0.00 0 Co-58 -- 0.00 N/A N/A 0.00 0 i Co-60 -- 0.00 N/A N/A 0.00 0 I . Nb-95 -- 0.023 (0.00 - 0.06) Hurd Park Road 0.06 4 N/A 0.017 (0.00 - 0.04) 0 2.8 Miles NNW l i 1
! i 1 i i
1 TABLE 3-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
j CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT j DOCKET 50-213 i JANUARY - DECEMBER 1984 ANALYSIS AND MINIMUM ALL INDICATOR LOCATION WITH HIGHEST ANNUAL MEAN CONTROL LOCATIONS 1 MEDIUM OR TOTAL NUMBER DETECTABLE LOCATIONS f 0F PATHWAY OF ANALYSES LEVELS (b) NAME, DISTANCE (b) (b) NRMs SAMPLED PERFORMED (MDL's)(a) Mean (Range) AND DIRECTION Mean (Range) Mean (Range) (c) l Th-228 -- 0.48 (0.30 - 0.87) Colchester 0.92 N/A 0.66 (0.46 - 0.92) 0 10 Miles NE K-40 6.0 (5.5 - 7.0) Colchester 8.5 6.4 (4.0 - 8.5) N/A 0 10 Miles NE Ra-226 -- 0.52 (0.33 - 0.79) Colchester 0.86 0.58 N/A (0.44 - 0.85) 0 J 10 Miles NE 4 Milk (Dairy) lodine 36,12 0.5 0.13 (0.0 - 0.3) Dairy Farm f4 0.17 (0.0 - 0.4) 0.17 (0.0 - 0.4) 0 (pC1/1) 1-131 11 Miles ENE Sr 36,12 2 0.30 (-1.0 - 1.6) Dairy Farm #2 0.37 Sr-89 (-0.5 - 1.3) 0.35 (-0.7 - 1.2) 0 2.2 Miles ESE Sr-90 5.6 (3.2 - 10.3) Dairy Farm #1 7.1 (5.3 - 10.3) 4.1 1 (2.9 - 6.7) 0 1.5 Miles NNW i Ge(Li) 36,12 6 5.8 (-l - 15) Dairy Farm #1 9.2 (5 - 12) 3.3 Cs-137 (1 - 7) O 1.5 Miles NNW Goat Milk Iodine 12,9 0.5 0.17 (0.0 - 0.4) Goat Location #2 0.17 (0.0 - 0.4) 0.17 (pCi/1) 1-131 (0.0 - 0.4) 0 1.5 Miles NW ' .j Sr 12,9 2 0.56 (-0.8 - 2.2) Coat Location #2 0.56 (-0.8 - 2.2) 0.23 (-3.0 - 3.0) 0 5r-89 1.5 Miles NW I l J J
_ -. - __ = - .- -- - . = - _ _ _ . _ - TABLE 3-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
CONNECTICUT YANKEE ATOMIC POWER COMPANY, HADDAM NECK PLANT DOCKET 50-213 JANUARY - DECEMBER 1984 ANALYSIS AND MINIMUM ALL INDICATOR LOCATION WITH HIGHEST ANNUAL MEAN CONTROL LOCATIONS MEDIUM OR TOTAL NUMBER DETECTABLE LOCATIONS f 0F PATHUAY OF ANALYSES LEVELS (b) NAME, DISTANCE (b) (b) HRMs SAMPLED PERFORMED (MDL's)(a) Mean (Range) AND DIRECTION Mean (Range) Mean (Range) (c) , Sr-90 1 5.6 (2.5 - 11.6) Goat Location il 7.2 (3.2 - 14.0) 7.2 (3.2 - 14.0) 0 16 Miles NE Ge(L1) 12,9 6 7 (2 - 19) Goat Location #1 20.2 (11 - 35) 20.2 (11 - 35) 0 Cs-137 16 Miles NE Groundwater Beta 20,4 1.7 (0.8 - 4.2) State Highway Dept. 6.7 (3.8 - 9.0) 6.7 (pCf/1) 1 (3.8 - 9.0) 0 East Haddam 3 Miles S j Sr 20,4 2 0.0 (-0.6 - 0.4) Onsite Wells 0.0 Sr-89 (-0.6 - 0.4) -0.3 (-0.8 - 0.5) 0 0.8 Miles SE Sr-90 1 0.4 (0.1 - 0.7) Onsite Wells 0.4 (0.2 - 0.7) 0.4 (0.2 - 0.5) 0 0.8 Miles SE Ge(Li) 20,4 6 0 N/A 0 N/A 0 Cs-137 I-131 30** O N/A N/A 0 0 Cs-134 6 0 N/A N/A 0 0 Co-58 6 0 N/A N/A 0 0 i
**at time of counting l
i
i l i TABLE 3-1 4 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT DOCKET 50-213 JANUARY - DECEMBER 1984 ANALYSIS AND MINIMUM ALL INDICATOR LOCATION WITH HIGHEST ANNUAL MEAN CONTROL LOCATIONS MEDIUM OR TOTAL NUMBER DETECTABLE LOCATIONS PATHUAY i 0F OF ANALYSES LEVELS (b) NAME, DISTANCE (b) (b) NRMs __ SAMPLED PERFORMED (MDL's)(a) Mean (Range) ANO DIRECTION Mean (Range) Mean (Range) (c) Co-60 6 0.2 (0.0 - 3.0) Onsite Wells 0.3 (0.0 - 3.0) 0 0 0.8 Miles SE 4 i Mn-54 6 0 N/A N/A 0 0 Tritium 20,4 60 3900 (150 - 9900) Onsite Wells 6350 (4680 - 9900) 190 (0 - 430) 0 H-3 0.8 miles SE 1 Fruits and Sr 4,4 0.018 0.04 (-0.002 - 0.14) Within 10 Miles 0.04 (-0.002 - 0,14) 0.002 ! Vegetables S r-89 (0.000 - 0.004) 0 1 (pCi/g) I Sr-90 0.009 0.052 (0.006 - 0.15) Within 10 Miles 0.052 (0.006 - 0.15) 0.016 (0.005 - 0.030) 0 l. Ge(L1) 4,4 0.034 0.002 (0.000 - 0.006) Beyond 10 Miles 0.005 (0.00 - 0.02) 0.005 Cs-137 (0.000 - 0.020) O l ) I-131 0.05 0.00 N/A N/A 0.00 0 i
\
- Cs-134 0.025 0.00 N/A N/A 0.00 0 i
Mn-54 -- 0.00 N/A N/A 0.00 0 l Co-58 -- 0.00 N/A N/A 0.00 0 Co-60 -- 0.00 N/A N/A 0.00 i 0 I 1 I
l TABLE 3-1 ENVIRONMENTAL RAD 10 LOGICAL MONITORING PROGRAM
SUMMARY
CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT DOCKET 50-213 JANUARY - DECEMBER 1984 ANALYSIS AND MINIMUM ALL INDICATOR LOCATION Wi1H HIGHEST ANNUAL MEAN CONTROL LOCATIONS MEDIUM OR TOTAL NUMBER DETECTABLE '~' LOCATIONS f 0F PATHWAY OF ANALYSES LEVELS (b) NAME, DISTANCE (b) (b) NRMs SAMPLED PERFORMED (MDL's)(a) Mean (Range) AND DIRECTION Mean (Range) Mean (Range) (c) K-40 1.8 (1.0 - 3.3) 7eyond 10 Miles 2.3 (0.8 - 3.9) 2.3 (0.8 - 3.9) 0 Ra-226 -- 0.003 (0.00 - 0.013) Within 10 Miles 0.003 7 (0.00 - 0.013) 0.00 0 l Th-228 -- 0.00 N/A N/A 0.00 0 River Water Sr 4,4 2 0.0 (-0.4 - 0.4) Vicinity of 0.0 (-0.4 - 0.4) -0.1 (pCi/1) Sr-89 (-0.2 - 0.2) 0 Plant Discharge Sr-90 1 0.7 (0.5 - 1.2) Vicinity of 0.7 (0.5 - 1.2) 0.5 (0.4 - 0.9) 0 Plant Discharge Ge(L1) 4,4 6 0 N/A N/A 0 0 Cs-137 I-131 -- 0 N/A N/A 0 0 i Cs-134 13 0 N/A N/A 0 0 Mn-54 13 0 N/A N/A 0 0 i Co-58 13 0 N/A N/A 0 0 Co-60 13 0 N/A P:/A 0 0 I
. .- - .- - ~ . - _ _ - - . - - - - .. ._ . _ _ . . _ - . - . _ _ . - - -
TABLE 3-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
CONNECTICUT YANKEE ATOMIC POWER COMPANY. HADDAM NECK PLANT DOCKET 50-213 JAWJARY - DECEMBER 1984 ANALYSIS AND MINIMUM ALL INDICATOR LOCATION WITH HIGHEST ANNilAL MEAN CONTROL LOCATIONS MEDIUM OR TOTAL NUMBER DETECTABLE LOCATIONS i 0F PATHUAY OF ANALYSES LEVELS (b) NAME DISTANCE (b) (b) NRMs SAMPLED PERFORMED (MDL's)(a) Mean (Range) AND O!RECTION Mean (Range) Mean (Range) (c) Zr-95 25 0 N/A N/A 0 0 Tritium 4,4 60 1400 (160 - 3300) Vicinity of 1400 (160 - 3300) 230 (140 - 400) 0 H-3 Plant Discharge Beta 4,4 1 2.2 (1.9 - 2.8) Middletown 3.9 (1.6 - 7.9) 3.9 (1.6 - 7.9) 0 B 7.6 Miles NW bottom Sediment Sr 4,8 0.072 -0.002 (-0.012 - 0.011) E. Haddam Bridge 0.001 (-0.008 - 0.012) -0.004 (-0.017 - 0.012) 0 (pC1/g) Sr-89 1.8 Miles SE Sr-90 0.036 0.010 (0.008 - 0.015) E. Haddam Bridge 0.013 (0.009 - 0.019) 0.013 (0.009 - 0.019) 0 1.8 Miles SE
. Ge(Li) 4,8 0.064 0.12 (0.06 - 0.20) E. Haddam Bridge 0.15 (0.10 - 0.25) 0.11 (0.00 - 0.25) O Cs-137 1.8 Miles SE l
l I-131 0.2 0.0 N/A N/t 0.0 0 Cs-134 0.06 0.04 (0.0 - 0.08) Vicinity of 0.04 (0.0 - 0.08) 0.00 (0.00 - 0.02) 0
- Plant Discharge l
Mn-54 -- 0.00 N/A N/A 0.00 0 Co-58 -- 0.00 N/A N'A 0.00 0 l i
i i TABLE 3-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
CONNECTICUT YANKEE ATOMIC POWER COMPANY, HADDAM NECK PLANT DOCKET 50-213 I JANUARY - DECEMBER 1984 ANALYSIS ANO MINIMUM ALL INDICATOR LOCATION WITH HIGHEST ANNUAL MEAN CONTROL LOCATIONS MEDIUM OR TOTAL NUMBER DETECTABLE LOCATIONS f 0F PATHWAY OF ANALYSES LEVELS (b) NAME. DISTANCE (b) (b) NRMs SAMPLED PERFORMED (MDL's)(a) Mean (Range) AND DIRECTION Mean (Range) Mean (Range) (c) Co-60 -- 0.00 N/A N/A 0.00 0 , } 4
! Zn-65 --
0.00 N/A N/A 0.00 0 Nb-95 -- 0.01 (0.00 - 0.03) Higganum Light 0.01 (0.00 - 0.04) 0.00 (0.00 - 0.04) 0 j 4 Miles WNW
! K-40 --
6.6 (5.8 - 7.8) Higganum Light 8.8 (7.7 - 9.9) 8.0 (6.9 - 9.9) 0 4 Miles WNW Shell fish Sr 4,4 0.018 0.020 (0.018 - 0.02) Higganum Light 0.022 (0.00 - 0.07) 0.022 (0.00 - 0.07) 0 i (pCi/g) Sr-89 4 Miles WNW 4 Sr-90 0.009 0.28 (0.19 - 0.36) Mouth of Salmon River 0.28 (0.19 - 0.36) 0.20 (0.13 ".24) 0 1.8 Miles SE l Ge(Li) 4,4 0.056 0.00 N/A N/A 0.00 0 , Cs-137
- l-131 --
0.00 N/A N/A 0.00 0 1 i j Cs-134 0.05 0.00 N/A N/A 0.00 0 Mn-54 0.05 0.00 N/A N/A 0.00 0 Co-58 0.05 0.00 N/A !./ A 0.00 0 i l
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__ - - - _. -. . _ _ . - -- . - -_ _ _ _ _ _ _ . - _ _ - - - . . . . - . _ _ - ~ _ - _ . I l TABLE 3-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
CONNECTICUT YANKEE ATOMIC POWER COMPANY,ItADDAM NCCK PLANT l DOCKET 50-213 JANUARY - DECEMBER 1984 , l ANA YSIS AND MINIMUM AlL INDICATOR LOCATION WITH HIGHEST ANNUAL MEAN CONTROL LOCATIONS MEDIUM OR TOTAL NUMBER DETECTABLE LOCATIONS f 0F , PRTHWAY OF ANALYSES LEVELS (b) NAME, DISTANCE (b) (b) NRMs l SAMPLED PERFORMED (MDL's)(a) Mean (Range) AND DIRECTION Mean (Range) Mean (Range) (c) Co-58 0.05 0.00 N/A N/A 0.00 0
, Co-60 0.05 0.00 N/A N/A 0.00 0 1
j Zr-95 -- 0.007 (0.00 - 0.05) Intake vicinity 0.017 (0.00 - 0.05) 0.00 0 1 Mile WNW 1 ! Nb-95 -- 0.007 (0.00 - 0.05) Plant Discharge 0.012 (0.00 - 0.05) 0.00 0 l Canal
! K-40 --
2.2 (1.3 - 2.8) Middletown 2.5 (1.9 - 2.9) 2.5 (1.9 - 2.9) 0 j 7.6 Miles NW i Fish - Other Sr 8,4 0.018 -0.002 (-0.016 - 0.009) Middletown 0.001 (-0.005 - 0.008) 0.001 (-0.005 - 0.008) 0
, (pC1/g) Sr-89 7.6 Miles NW Sr-90 0.009 0.078 (0.040 - 0.108) Intake Vicinity 0.082 (0.065 - 0.108) 0.051 (0.032 - 0.098) 0 I Mlle WNW
- Ge(Li) 8,4 0.056 0.028 (0.00 - 0.05) Plant Discharge 0.03 (0.00 - 0.05) 0.008 (0.00 - 0.03) 0 ,
Cs-137 Canal , j I-131 -- 0.01 (0.00 - 0.07) Plant Discharge 0.01 (0.00 - 0.07) 0.00 0 , j Canal i l i I
i i I ,
! TABLE 3-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
CONNECTICUT YANKEE ATOMIC POWER COMPANY, HADDAM NECK PLANT DOCKET 50-213 JANUARY - DECEMBER 1984 ANALYSIS AND MINIMUM ALL INDICATOR LOCATION WITH HIGHEST ANNUAL MEAN CONTROL LOCATIONS MEDIUM OR TOTAL NUMBER DETECTABLE LOCATIONS f 0F PATHUAY OF ANALYSES LEVELS (b) NAME DISTANCE (b) (b) NRMs SAMPLED PERFORMED (MDL's)(a) Mean (Range) AND DIRECTION Mean (Range) Mean (Range) (c) Cs-134 0.05 0.00 N/A N/A 0.00 0 ! Mn-54 0.05 0.002 (0.00 - 0.02) Plant Discharge 0.004 (0.00 - 0.02) 0.00 0 Canal i Co-58 0.05 0.00 N/A N/A 0.00 0 1 j Co-60 0.05 ') . 00 N/A N/A 0.00 0 1
, Zr-95 --
0.00 N/A N/A 0.00 0 1 Nb-95 -- 0.00 N/A N/A 0.00 0 K-40 2.5 (1.2 - 3.6) Plant Discharge 2.7 (1.2 - 3.3) 2.3 (1.6 - 4.1) O Canal i i I i I i b l
5 FOOTNOTES
- a. For Ge(Li) measurements the MDL's ~ 2 x /Es 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).
i Negative values were used in the determination of the mean.
- c. Nonroutine reported measurements (# of NRMs) are defined in dection 5.6.2b i
of the Technical Specifications.
- d. First number is the number of indicator measurements, the -second is the number of control measurements.
- e. Assuming 270 m3 / paper.
- f. Assuming 1080 m3 .
- g. Quarterly composites.
a
- h. N/A--Not Applicable.
l 4 i 1 1 l l I ! 3-13
l 1 1 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. 1 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
- 5. Air Particulates, Quarterly Strontium and Cesium
- 6. Soil **
- 7. Milk - Dairy Farms
- 8. Milk - Goat Farms
- 10. Well W t r
- 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.
t l } l 3-14 l
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 Well - 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 42B 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 52B Mt. Higby - WNW, 12.5 miles A - Control Stations B - Site not required by ETS 1 s
COMECTICUT YAtCCEE TABLE 1A MotHHL) GAMMA EXPOSURE RATEIUR/HR) FERIOD L0 CATIONS EtDIllG 01 02 03 04 05 06 07 08 09 10 11A 6.7 9.0 1/31/84(a) 9.9(b) 9.1 6.8 6.7 7.0 6.7 6.0 7.2 7.3 8.4 9.4 2/20/84 10.8 10.3 7.8 7.7 8.0 7.5 6.3 8.0 6.9 3/31/84 10.7 10.3 7.8 7.3 7.7 7.8 6.7 8.1 7.5 8.0 9.9 4/30/84 11.2 10.8 8.2 7.8 8.6 7.9 6.5 8.8 7.3 8.7 9.7 5/31/84 10.5 9.7 6.9 6.6 7.1 7.4 7.3 7.3 7.1 7.1 9.4 6/30/S4 12.2 10.9 8.0 7.9 8.5 8.0 6.8 8.6 7.6 8.6 10.1 7/31/84 13.6 10.5 7.8 7.8 7.9 8.0 6.4 7.9 7.1 7.6 9.3 8.5 9.6 8.2 7.4 6.8 8.1 7.4 8.0 9.8 8/31/84 23.9(c) 11.9 8.7 8.5 8.4 8.1 6.8 8.2 7.4 7.6 9.7 9/30/04 17.3 II.6 10/31/64 17.1 13.2 10.2 9.0 9.1 8.1 7.2 8.8 8.0 8.6 10.4 11/30/84 13.6 12.7 9.4 7.9 8.1 8.3 6.8 8.2 7.8 0.0 10.5 12/31/84 13.6 12.3 9.6 8.1 8.5 7.7 6.9 8.6 7.2 9.0 10.0 12A 13A 14A 40B 41B 42B 43B 44B 45B 46B t/31/84 5.9 5.9 7.7 6.3 5.4 5.7 7.0 6.3 6.1 5.9 2/28/84 6.3 6.3 8.2 7.3 6.4 6.5 7.9 7.1 7.0 6.6 3/31/84 6.5 6.5 8.5 7.1 5.9 6.6 8.0 7.3 7.1 6.4 4/30/84 6.7 6.7 8.9 7.8 6.1 6.8 8.5 7.5 7.3 6.8 5/31/84 6.3 5.9 7.9 6.4 5.2 6.2 7.4 7.1 6.8 6.2 6/30/84 7.0 6.6 8.9 7.7 6.1 6.8 8.5 7.9 7.6 7.0 7/31/84 6.3 6.4 8.4 7.5 5.9 6.4 8.1 7.1 6.8 6.1 8/31/84 6.7 6.3 8.4 8.5 7.0 6.6 8.1 7.9 7.5 6.9 9/30/84 6.5 6.6 8.7 8.5 6.1 6.8 8.5 7.5 7.2 6.4 10/31/84 7.4 7.1 8.9 9.1 6.6 6.9 8.6 8.6 8.0 7.4 11/30/84 6.8 6.7 8.9 8.8 6.2 6.6 8.3 7.8 7.6 6.9 12/31/84 7.1 7.2 8.6 8.8 6.5 6.7 8.3 8.0 7.6 7.1 TABLE IB SEMIAfDIUAL GAMMA EXF05UPE MATEIUR/HR1 PEPIOD L0 CATIONS El.'DItG 01 02 03 04 05 06 07 08 09 10 11A 6/30/84 10.9 10.2 7.6 7.3 7.8 7.5 6.6 8.0 7.2 8.0 9.6 12/31/84 16.5 12.0 9.0 8.5 8.4 7.9 6.8 8.3 7.5 6.8 9.9 12A 13A 14A 400 41B 42B 430 44B 45B 468 6/30/84 6.4 6.3 8.3 7.1 5.8 6.4 7.9 7.2 7.0 6.5 12/31/84 6.8 6.7 8.6 8.5 6.4 6.7 8.3 7.8 7.4 6.8
~
(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. O ____ _ _ _ _ _ _ _ _ _ _ _ _ _
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TABLE 4A AIR PARTICULATES CY GAMMA SFECTRA - JAN (PCI/M3) ANALYSES CS-137 CS-134 RU-103 ZR-95 RU(RH)-106 K-40 TH-228 DE-7 US-95 LOCATION ! (+/-) (+/-) (+/-) (+/.) (+/-) (+/-) (+/-) (+/-) (+/-) 0.002 0.003 0.0 0.005 0.0 0.005 0.0 0.000 0.0 0.030 0.0 0.006 0.000 0.040 0.0 0.004 5 0.0 0.0 6 0.0 0.002 0.0 0.003 0.0 0.004 0.0 0.006 0.0 0.030 0.0 0.040 0.0 0.007 0.100 0.040 0.0 0.004 0.003 0.0 0.003 0.0 0.004 0.0 0.005 0.0 0.030 0.0 0.000 0.0 0.008 0.080 0.030 0.0 0.004 7 0.0 8 0.001 0.001 0.0 0.002 0.0 0.003 0.0 0.004 0.0 0.014 0.0 0.013 0.0 0.004 0.100 0.0?0 0.003 0.003 9 0.0 0.002 0.0 0.002 0.0 0.003 0.0 0.004 0.0 0.000 0.0 0.000 0.0 0.005 0.070 0.030 0.0 0.C03 10 0.0 0.002 0.0 0.002 0.0 0.003 0.0 0.004 0.0 0.000 0.0 0.000 0.004 0.004 0.070 0.030 0.0 0.003 IIA 0.0 0.000 0.0 0.002 0.0 0.003 0.0 0.004 0.0 0.000 0.0 0.030 0.0 0.005 0.093 0.030 0.0 0.003 ! 10A 0.0 0.002 0.0 0.002 0.0 0.004 0.0 0.005 0.0 0.020 0.0 0.000 0.0 0.005 0.110 0.030 0.0 0.005 13A 0.0 0.003 0.0 0.003 0.0 0.005 0.0 0.007 0.0 0.000 0.0 0.030 0.0 0.007 0.C?0 0.030 0.0 b.006 14A 0.0 0.002 0.0 0.002 0.0 0.003 0.0 0.004 0.0 0.000 0.050 0.030 0.0 0.004 0.C.0 0.020 0.0 0.003 46B 0.0 0.003 0.0 0.004 0.0 0.007 0.0 0.009 0.0 0.030 0.0 0.040 0.0 0.007 0.070 0.040 0.0 0.006 TABLE 4B AIR PARTICULATES ) GAMMA SPECTRA - FEB ( PCI/M3 ) ANALYSES } LOCATIDH CS-137 CS-134 RU-103 ZR-95 RU(RHI-106 K-40 TH-228 DE-7 NB-95 (+/-) (+/-) (+/-) (+/-) (+/-) (+/-) (+/-) (+/-) (+/-) 3 5 0.0 0.003 0.0 0.004 0.0 0.005 0.0 0.008 0.0 0.030 0.0 0.030 0.0 0.008 0.090 0.c40 0.0 0.005 6 0.0 0.003 0.0 0.003 0.0 0.006 0.0 0.007 0.0 0.030 0.0 0.030 0.0 0.003 0.050 0.030 0.0 0.006 7 0.0 0.003 0.0 0.004 0.0 0.006 0.0 0.008 0.0 0.030 0.0 0.040 0.0 0.003 0.070 0.040 0.0 0.006 8 0.0 0.002 0.0 0.002 0.0 0.003 0.0 0.004 0.0 0.000 0.0 0.000 0.0 0.C05 0.050 0.020 0.0 0.003 6 9 0.0 0.000 0.0 0.002 0.0 0.003 0.0 0.004 0.0 0.000 0.0 0.000 0.005 0.005 0.100 0.030 0.0 0.002 10 0.0 0.002 0.0 0.003 0.0 0.003 0.0 0.004 0.0 0.000 0.0 0.000 0.0 0.005 0.090 0.030 0.0 0.003 11A 0.0 0.002 0.0 0.002 0.0 0.003 0.0 0.004 0.0 0.C00 0.0 0.000 0.0 0.004 0.060 0.000 0.0 0.003 12A 0.0 0.C03 0.0 0.003 0.0 0 . 0 0 '+ 0.0 0.005 0.0 0.000 0.0 0.030 0.0 0.005 0.080 0.030 0.0 0.004 0 13A 0.0 0.003 0.0 0.004 0.0 0.006 0.0 0.006 0.0 0.030 0.0 0.040 0.0 0.00S 0.090 0.040 0.0 0.005 14A 0.0 0.002 0.0 0.002 0.0 0.003 0.0 0.004 0.0 0.000 0.050 0.040 0.0 0.004 0.090 0.000 0.0 0.003 46B 0.0 0.004 0.0 0.004 0.0 0.006 0.0 0.008 0.0 0.030 0.0 0.040 0.0 0.009 0.100 0.040 0.0 0.C05 ( t ( W f
TABLE 4C ) AIR PARTICULATES C7 G W!!A SPECTRA - MAR (PCI/M3) A AHALYSES CS-134 RU-103 2R-95 PU(RH)-106 K-40 TH-208 DE-7 US 05 LCCATIDH CS-137 (+/-) (+/-) (+/-) (+/-) (+/-) (+/-) (+/-l (+/ ) (+/-) 0.030 0.0 0.040 0.0 0.007 0.080 0.040 0.0 0.005 5 0.0 0.003 0.0 0.003 0.0 0.005 0.0 0.006 0.0 0.0 0.006 0.0 0.007 0.0 0.030 0.0 0.020 0.0 0,008 0.050 0.040 0.0 0.006 6 0.0 0.003 0.0 0.003 7 0.0 0.003 0.0 0.004 0.0 0.006 0.0 0.008 0.0 0.030 0.0 0.040 0.0 0.009 0.100 0.050 0.0 0.007 g 0.000 0.0 0.000 0.0 0.006 0.090 0.030 0.0 0.003 8 0.0 0.002 0.0 0.002 0.0 0.004 0.0 0.004 0.0 9 0.0 0.002 0.0 0.002 0.0 0.003 0.0 0.004 0.0 0.020 0.0 0.030 0.0 0.005 0.070 0.030 0.0 0.003 0.005 0.0 0.000 0.0 0.000 0.0 0.005 0.090 0.030 0.0 0.004 10 0.0 0.002 0.0 0.002 0.0 0.004 0.0 0.004 IIA 0.0 0.002 0.0 0.002 0.0 0.004 0.0 0.005 0.0 0.020 0.0 0.000 0.0 0.004 0.110 0.030 0.0 I 0.002 0.003 0.004 0.0 0.000 0.0 0.000 0.0 0.005 0.090 0.030 0.0 0.004 104 0.0 0.002 0.0 0.0 0.0 0.005 13A 0.003 0.003 0.0 0.003 0.0 0.006 0.0 0.007 0.0 0.000 0.0 0.C40 0.0 0.007 0.100 0.040 0.0 0.002 0.004 0.005 0.0 0.000 0.0 0.000 0.0 0.005 0.090 0.030 0.0 0.003 14A 0.0 0.002 0.0 0.0 0.0 46B 0.0 0.003 0.0 0.003 0.0 0.006 0.0 0.009 0.0 0.030 0.0 0.030 0.0 0.009 0.110 0.040 0.0 0.006 y TABLE 4D AIR PARTICULATES I GAMMA SPECTRA - APR (PCI/M3) ANALYSES CS.134 RU-103 ZR-95 RU(RH)-106 K-40 TH-228 BE-7 US-95 LOCATION CS-137 (+/-) (+/-) (+/-) (+/-) (+/-) (+/-) (+/-) (+/.) (+/-l
' 5 0.0 0.003 0.0 0.003 0.0 0.003 0.0 0.005 0.0 0.020 0.0 0.030 0.0 0.007 0.030 0.030 0.0 0.003 6 0.0 0.002 0.0 0.003 0.0 0.004 0.0 0.006 0.0 0.030 0.0 0.030 0.0 0.007 0.030 0.030 0.0 0.004 0.003 0.0 0.005 0.0 0.007 0.0 0.0!O 0.0 0.030 0.0 0.007 0.050 0.030 0.0 0.005 7 0.0 0.003 0.0 0.001 0.001 0.0 0.002 0.0 0.003 0.0 0.013 0.0 0.012 0.0 0.003 0.040 0.000 0.0 0.000 8 0.0 0.0
' 0.002 0.003 0.0 0.015 0.0 0.000 0.0 0.005 0.060 0.000 0.0 0.003 9 0.0 0.002 0.0 0.002 0.0 0.0 0.0 0.001 0.0 0.001 0.0 0.000 0.0 0.003 0.0 0.012 0.0 0.000 0.0 0.003 0.060 0.000 0.0 0.002 to 0.012 0.0 0.000 0.0 0.003 0.050 0.000 0.0 0.000 IIA 0.0 0.001 0.0 0.001 0.0 0.002 0.0 0.003 0.0 0.0 0.001 0.0 0.002 0.0 0.000 0.0 0.003 0.0 0.015 0.0 0.014 0.0 0.004 0.C60 0.000 0.0 0.000 10A 0.003 0.0 0.005 0.006 0.006 0.0 0.030 0.0 0.030 0.0 0.007 0.030 0.030 0.0 0.004 134 0.0 0.003 0.0 0.002 0.0 0.002 0.0 0.002 0.0 0.003 0.0 0.015 0.0 0.014 0.0 0.003 0.030 0.000 0.0 0.000 14A 0.0 0.003 0.006 0.0 0.030 0.0 0.030 0.0 0.008 0.060 0.030 0.0 0 C04 468 0.0 0.003 0.0 0.0 0.005 0.0 i
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,,- - -- - . =_ _ - . . . - . --. TABLE 4E AIR PARTICULATES CY GAf5A SPECTRA - MAY (FCI/M3) AHALYSES LOCATION CS-137 CS-134 RU-103 ZR-95 PUtkH3-106 K-40 TH-228 BE-7 HS-95 (+/-l (+/-) (+/-) (+/-) (+/-) (+/-) (+/-) (+/-) (+/-) 5 0.0 0.003 0.0 0.004 0.0 0.004 0.0 0.006 0.0 0.020 0.0 0.020 0.0 0.009 0.100 0.030 0.0 0.005 6 0.0 0.003 0.0 0.003 0.0 0.004 0.0 0.005 0.0 0.030 0.0 0.040 0.0 0.006 0.120 0.040 0.0 0.004 7 0.0 0.004 0.0 0.004 0.0 0.005 0.0 0.006 0.0 0.030 0.0 0.040 0.0 0.008 0.!!0 0.040 0.0 0.005 8 0.0 0.002 0.0 0.C02 0.0 0.003 0.0 0.003 0.0 0.000 0.0 0.000 0.0 0.005 0.070 0.000 0.0 0.002 9 0.0 0.002 0.0 0.002 0.0 0.003 0.0 0.004 0.0 0.000 0.0 0.020 0.0 0.005 0.080 0.020 0.0 0.003 10 0.0 0.002 0.0 0.002 0.0 0.003 0.0 0.003 0.0 0.020 0.0 0.014 0.0 0.005 0.000 0.020 0.0 0.002 11A 0.0 0.002 0.0 0.002 0.0 0.003 0.0 0.004 0.0 0.000 0.0 0.020 0.0 0.004 0.050 0.020 0.0 0.002 12A 0.0 0.000 0.0 0.002 0.0 0.003 0.0 0.004 0.0 0.000 0.0 0.020 0.0 0.004 0.120 0.030 0.0 9.003 13A 0.0 0.003 0.0 0.003 0.0 0.005 0.0 0.007 0.0 0.020 0.0 0.030 0.0 0.008 0.0v0 0.0'+0 0.0 0.005 14A 0.0 0.002 0.0 0.002 0.0 0.002 0.0 0.004 0.0 0.015 0.0 0.013 0.0 0.004 0.080 0.020 0.0 0.003 46B 0.0 0.003 0.0 0.004 0.0 0.006 0.0 0.006 0.0 0.040 0.0 0.030 0.0 0.011 0.100 0.040 0.0 0.005 TABLE 4F AIR PARTICULATES GAMMA SPECTRA .;UH IFCI/M3) ANALYSES LOCATION CS-137 CS-134 R'8-103 ZR-95 RU(RH)-106 K-40 TH-228 BE-7 ND-95 (+/-) (+/-) (+/-l (+/-) I+/-) (+/-) (+/-) (+/-) (+/.) 5 0.0 0.003 0.0 0.004 0.0 0.006 0.0 0.003 0.0 0.030 0.0 0.030 0.0 0.006 0.150 0.050 0.0 0.006 6 0.0 0.004 0.0 0.003 0.0 0.006 0.0 0.008 0.0 0.030 0.0 0.030 0.0 0.008 0.130 0.040 0.0 0.005 7 0.0 0.004 0.0 0.004 0.0 0.006 0.0 0.009 0.0 0.040 0.070 0.070 0.0 0.009 0.130 0.050 0.0 0.c07 8 0.0 0.002 0.0 0.002 0.0 0.004 0.0 0.005 0.0 0.020 0.0 0.030 0.0 0.005 0.160 0.030 0.0 0.004 9 0.0 0.002 0.0 0.002 0.0 0.003 0.0 0.005 0.0 0.000 0.0 0.000 0.0 0.005 0.140 0.0'+e 0.0 0.003 10 0.0 0.002 0.0 0.002 0.0 0.003 0.0 0.005 0.0 0.020 0.0 0.000 0.0 0.005 0.140 0.035 0.0 0.004
!!A 0.0 0.002 0.0 0.002 0.0 0.004 0.0 0.004 0.0 0.000 0.0 0.000 0.0 0.005 0.160 0.030 0.0 0.004 12A 0.0 0.000 0.0 0.002 0.0 0.004 0.0 0.006 0.0 0.000 0.0 0.020 0.0 0.005 0.140 0.030 0.0 0.004 13A 0.0 0.004 0.0 0.004 0.0 0.007 0.0 0.009 0.0 0.040 0.0 0.040 0.0 0.010 0.140 0.050 0.0 0.007 14A 0.0 0.002 0.0 0.002 0.0 0.004 0.0 0.004 0.0 0.020 0.0 0.030 0.0 0.005 0.130 0.030 0.0 0.003 468 0.0 0.004 0.0 0.004 0.0 0.006 0.0 0.010 0.0 0.040 0.0 0.C50 0.0 0.011 0.150 0.050 0.0 0.008 WW W
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TABLE 4G 7 CY AIR PARTICULaTES GAMMA SPECTRA - JUL (FCI/H3) AHALYSES LCCATION CS-137 CS-134 RU-103 2R-95 RUI RH )-106 K-40 TH-228 BE.7 HD-95 1 .---...--__. ...........- ........__.. ............ ........_--_ ............ .....-.---.. -- -_... .._____..--- I (+/-) (+/.) (+/-) (+/-) (+/.) (+/-) (+/.) (+/-) (+/-) 5 0.0 0.003 0.0 0.003 0.0 0.004 0.0 0.006 0.0 0.020 0.0 0.030 0.0 0.006 0.060 0.030 0.0 0.005 6 0.0 0.002 0.0 0.003 0.0 0.005 0.0 0.007 0.0 0.020 0.0 0.030 0.0 0.006 0.040 0.030 0.0 0.004 7 0.0 0.003 0.0 0.003 0.0 0.005 0.0 0.007 0.0 0.020 0.0 0.030 0.0 0.007 0.040 0.030 0.0 0.005 8 0.0 0.001 0.0 0.001 0.0 0.002 0.003 0.003 0.0 0.000 0.0 0.014 0.0 0.003 0.060 0.020 0.0 0.003 9 0.0 0.002 0.0 0.002 0.0 0.003 0.0 0.004 0.0 0.000 0.0 0.000 0.0 0.004 0.060 0.020 0.0 0.003 10 0.0 0.001 0.0 0.011 0.003 0.003 0.0 0.004 0.0 0.011 0.0 0.000 0.0 0.004 0.060 0.000 0.0 0.003 IIA 0.002 0.000 0.0 0.002 0.0 0.003 0.0 0.004 0.0 0.024 0.040 0.030 0.0 0.004 0.060 0.030 0.0 0.C03 12A 0.0 0.002 0.0 0.002 0.0 0.003 0.0 0.00'+ 0.0 0.014 0.0 0.020 0.0 0.004 0.030 0.030 0.0 0.003 13A 0.0 0.003 0.0 0.003 0.0 0.006 0.0 0.007 0.0 0.030 0.0 0.030 0.0 0.007 0.000 0.040 0.0 0.005 14A 0.0 0.001 0.0 0.002 0.0 0.003 0.0 0.004 0.0 0.01C 0.0 0.020 0.0 0.C04 0.060 0.020 0.0 0.003 468 0.0 0.003 0.0 0.004 0.0 0.006 0.0 0.007 0.0 0.030 0.0 0.040 0.0 0.008 0.080 0.040 0.0 0.006 TABLE 4H AIR PARTICULATES 3 GAMMA SPECTRA - AUG (PCI/N3) ANALYSES LCCATICH CS-137 CS-134 RU-103 ZR-95 RU(RH)-106 K-40 TH-228 BE-7 N3-95 (+/-) (+/-) (+/.) (+/-) (+/-) (+/-) (+/-) (+/-) (+/-) 3 5 0.0 0.003 0.0 0.003 0.0 0.005 0.0 0.006 0.0 0.030 0.0 0.030 0.0 0.007 0.0C0 0.040 0.0 0.C05 6 0.0 0.003 0.0 0.003 0.0 0.005 0.0 0.007 0.0 0.030 0.0 0.030 0.0 0.006 0.110 0.040 0.0 0.005 7 0.0 0.003 0.0 0.004 0.0 0.005 0.0 0.007 0.0 0.030 0.0 0.050 0.0 0.00S 0.110 0.040 0.0 0.006 8 0.0 0.002 0.0 0.002 0.0 0.003 0.0 0.004 0.0 0.000 0.0 0.000 0.0 0.005 0.070 0.020 0.0 0.003 9 0.0 0.000 0.0 0.002 0.0 0.003 0.0 0.005 0.0 0.000 0.0 0.020 0.0 0.006 0.!!0 0.030 0.0 0 . 0 0 ** 10 0.0 0.000 0.0 0.002 0.0 0.003 0.0 0.004 0.0 0.000 0.0 0.000 0.0 0.004 0.000 0.030 0.0 0.003 IIA 0.0 0.002 0.0 0.002 0.0 0.003 0.0 0.004 0.0 0.000 0.0 0.015 0.0 0.005 0.070 0.020 0.0 0.C03 12A 0.0 0.002 0.0 0.003 0.0 0.0C4 0.0 0.006 0.0 0.000 0.0 0.030 0.0 0.007 0.!!0 0.043 0.0 0.C04 134 0.0 0.004 0.0 0.004 0.0 0.C06 0.0 0.008 0.0 0.000 0.0 0.030 0.0 0.011 0.110 0.050 0.0 0.005 14A 0.0 0.000 0.0 0.002 0.0 0.003 0.0 0.005 0.0 0.000 0.0 0.014 0.0 0.005 0.090 0.030 0.0 0.003 4tB 0.0 0.005 0.0 0.004 0.0 0.006 0.0 0.009 0.0 0.040 0.0 0.030 0.0 0.011 0.110 0.040 0.0 0.006 l
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Y TABLE 11 ( PAGE 1 CY RES!9VOIR WATER (FCI/L)
, COLLECTICf4 LCCATIC'8 DATE SR-89 5R-93 Cs-137 I-131 CS-134 ??4- 54 CO-5S
(+/-) (+/-) (+/-l (+/.) (+/.) (+/ ) (+/-) f CO-60 FE-59 ZN-65 ZR-95 RUtRHI-Ic6 CR-51 K-40 (+/-) (+/-) I+/-) (+/-) (+/-) (+/.) (+/-) RA-226 TM-228 BE-7 t:!3-95 H-3 GROSS CETA (+/-) (+/-) (+/.) (+/-) (+/-) (+/-) ( ( These samples are not required. ( t summ. k 6 e i e I _-
l i l D. u 3 O ^ .* th N 4 1 E 4
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. f w oooo oooo 6 woooo ooao O
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M t mI b i
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o n o m. @ 'O c.e s N. o. o. o.o. o. o. o. o. e 6 N
+ o. o. o. o. o. o. o. o. e N. e4. . ed.
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- TABLE 13 WE AT. FCULTRY s EGGS (a) CY (FCI/GI COLLECTION LCCATI0tl DATE TYPE 59-89 SR-90 CS-137 I-131 C5-134 PM-54
(+/-) (+/-l (+/-) (+/-l i+/-l i+/-l CO-55 CO-60 FE-59 ZH-6 5 ZR-95 PU(PHI-!C6 i+/-I (+/-) (+/-) (+/-l l+/-l (+/-l CR-51 K-40 RA-226 TH-228 EE-7 IS-95 1+/.I (+/-) (+/-l (+/-) (+/-) t+/.I (a) Commercial samples for which feed was grown within 10 miles of the station were not available in 1984 M 1
. .- - - -- - . - - , = - = _ . =
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l 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 (Mn) thermoluminescent dosimeters (TLDs). These dosimeters are strategically placed at a number of on-site locations, as well as at inner and outer off-site locations. Glass bulb type TLDs such as these, are subject to inherent self-irradiation which has been experimentally measured for each dosimeter. The results, shown in Table I have been adjusted for this effect. The range of this correction is 0.3 pR/hr to 1.7 pR/hr, with a mean 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 from 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 l remained at levels similar to that seen in 1982-1983 samples. As in l 1979 and 1980, the data for the last three years has failed to show l an increase in the spring and summer such as that seen in 1981 and i other previous years. This is due to the absence of recent atmospheric nuclear testing in the northern hemisphere. Inner and outer ring monitoring locations showed no significant variation in measured 4-1
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 I-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 1-131 presence in the environment. The weekly air particulate filters are composited monthly for gamma spectral analyses. The results, as shown in Tables 4A-4L, indic-te the presence of naturally occurring Be-7, which is produced by cosmic processes. All other positive results are attributable to statistical fluctuations in enunting. These analyses indicate the lack of any plant ef fects. 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 environtwntal 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 does not allow the separation of Cs-137 and Cs-134. Therefore, 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 in 1982-83. There was no detectable Sr-89 in any of these samples. Because of the occur rence of comparable results at both indicator and control locations and the lack of Sr-89, it can be concludeo 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 strontium 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 tha absence of Sr-89 and Cs-134, the presence of Sr-90 and Cs-137 is attributable to fallout from previous nuclear weapons testing. It was also noted that the levels of these two radionuclides did not significantly vary between indicator and control locations and these results were similar to those observed for the past nine years. l 4-2
_ ._ . - ~ _ _- -- - - .- __ . Cow Milk (Table 7) Analysis of milk samples is generally the most sensitive indicator of fission product existence in the terrestrial environment. Airborne releases will usually be detected first in this media. This, in combination with the fact that consumption 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 nueds to be evaluated very carefully when trying to decipher if there are any plant effects. i Sr-90 was observed in all samples; all results were below 11 pCi/2. Data was similar to previous years. All three indicator locatior, exhibited higher values than the control location. This trend has usually been the case for these samples. Detailed analysis of 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 samples above its MDL. This isotope is released in greater quantities from the plant, indicating that the Sr-90 is the result of weapons testing and not from the plant. Sr-89 is only detected in these samples during episodes of fresh fallout from weapons testing. Cs-137 usually shows the same tendencies as Sr-90, but at higher levels. Results for 1984 are similar to those of the past seven years. All three indicator locations showed Cs-137 activity above the control location. This trend has been observed in past data. However 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 of the samples, further confirming the absence of plant effects. Prior to 1982, the values for Cs-137 in this table were representati re of total cesium as determined by chemistry. For the past few years these values were confirmed by gamma spectrometry to be Cs 137. Cesium chemistry allows a higher degree of sensitivity but wuffers the problem of possible interferences 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 listed on Table 7, the only other nuclide detected by gamma spectometry was naturally occurring K-40.
All samples showed a lack of I-131 detectable above the MDL of 0.5 pCi/1. 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. Goat Milk (fable 8) Depending on the feeding habits, goat milk can be a more sensitive indicator than cow milk of fission products in the environment. This is due to the metabolism of these animals. Similar to the results of the cow milk samples, these show significant amounts of j 4-3
nuclear weapons testing fallout. Sr-90 was observed in all samples, with values similar at both locations. In previous years (1977-1983) 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 farms in 1983 (necessitated by the original control farm going cut of business). The pre-1984 results demonstrate 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 feed type. For a complete discussion of the problem, see Section 6.0. As t typical of periods lackinr f resh fallout, no detectable Sr-89 was seen in these samples. The Cs-137 results also show a decrease f, 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 nuclides and indicates the lack of plant effects. The absence of Sr-89 and Cs-134 confirm that the levels of Sr-90 and Cs-137 are 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 following fallout from nuclear weapons testing, when I-131 may be detected. Pasture Grass (Table 9) Samples of pasture grass are required by the Environmental Technical
- Specifications when samples of milk are unobtainable. They may also be taken to verify the milk pathway measurements. This sample was not available in February when goat milk was not available at the control location. In June and September, samples of broad leaf 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 Sr-89 and Cs-134 confirms this premise. Co-60 appears in one sample but is believed to be caused by statistical fluctuations. 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 4-4
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 H-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 grosr. 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 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) These samples are not required by the Environmental Technical Specificctions. 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. Freits 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. Meat, Poultry, and Egge (Table 13) i If these samples are available and their feed is grown within 10 i miles of the station, then the Environmental Technical Specifications ( require that these samples be obtained. However, no samples were obtained because none were available. 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
. __ _ __ _ _ _ . _ _m _ _ _ . _.
composited at the control station (Middletown - locatson 30A). Continuous samples are utilined at the indicator station (area of plant discharge - location 29) and at an extra location (non Envircnunental Technical Specification location - East lladdam Bridge - location 28B). Both the indicator and extra locations show tritium (11-3) con-cenrations above the background levels seen at the control locatioa. These elevet.ed 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 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 code - LADTAP). Preliminary results of 11-3 analyses in fish samples indicate that the calculations are conservative. The dose consequences, discussed in Section 5.0, are insignificant. Gross beta and Sr-90 were the only other activities that were consistently seen in these samples. /or most of the samples, the 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. Bottom Sediment (Table 15) The naturally occurring radionuclides, K-40, Ra-226, and Th-228 were i present in all samples. Cosmic produced Be-7 was measured in a few samples, at levels near the MDL. The only other nuclides detected were Sr-90, Cs-137, and traces of Cs-134. 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 measured in all samples, at levels consistent among locations. Levels were similar to those seen in 1981-83 samples. The occurence of trace quantities of Cs-134 at the indicator location may indicate that a small portion of Cs-137 observed is plant relate!. 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 this, media. Shellfish (Table 16) The only detectable activity observed in this media consisted of Sr-90 and the naturally occurring radionuclides, Ra-226 and Th-228. Many of the samples also showed traces of K-40. This media has ' always shown low concentrations of this nuclide. One positive value of Sr-89 was indicated at an extra location (non Environmental 4-6 i __, . _ _ _ = _ _ . . , _
Technical Specification location - East fladdam Bridge - location 28A) located 1.8 miles downriver of the plant. This valee, though an isolated occurrence, may be plant related. The dose consequence of this value is insignificant compared to those discussed in j Section 5.0. I Sr-90 was detected in all samples, at similar concentrations among l 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. Fish-Bullheads (Table 17A)
)
! As usual, the majority of the activity in these bottom feeding aquatic samples consisted of naturally occurring K-40. Other 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, part of the Cs-137 in these samples could be due to plant operation. To be conservative, dose ; consequences were calculated assuming these 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 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. 4-7 _ , . .__._. _.._. _ _. ~ _ . _ . . . _ . . - - _ . _ _ . . _ _ _ _ . . . . . . _ _ _ _ , _ . _ ,
FIGURE 4-1 CONNECTICUT YANKEE AVERAGE TLD EXPOSURE RATE PER MONTH (UR/HR) i 8.75-o , 8.51-0 o o o o o 8.254 o o o oo 0 o o , ,
# o 0
G A 8.00i #o O M o o M o o A o o 0 a o o 0 0 o
& E 7.75-P o 0 0 o o
- 5 o o 0
U 7.502 ~ o R E o o o O R . o o A 7.25- ' T E o o o I 7.00- 0 1 6.75i o 6.502 , , , , , i 1983 1984 1965 1980 1981 1982 YEAR NEW READER WAS PLACEO INTO SERVICE ON OCTOBER 198'4 GRMMA EXPOSURE RATES ARE AN AVERRGE OF ALL CONTROL LOCATION EXPOSURES PER MONTH
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l 5.0 0FFSITE DOSE CONSEQUENCES The off-site dose consequences of the station's 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 trans-port mechanism through the environment to man. This results in the 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 of approximating an upper limit to the dose consequences. This is 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 l detectable activity was observed in any sampling media. The less 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 pathway and for the critical age group. For example, the dose via 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 result in maximum total doses to an individual of: 2.6 mrem whole body to an adult, 0.40 mrem to a child's thyroid, and 1.5 mrem 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: ANNUAL WHOLE BODY DOSE DUE TO AIRBORNE EFFLUENTS = 0.00073 mrem ANNUAL WHOLE BODY DOSE DUE TO LIQUID EFFLUENTS = 0.00152 mrem Thus, it can be seen that the average whole bc.y 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 mrem 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 f raction of natural background, they have insignificant public health consequencea. In fact, the plant related doses to the maximum individual are less I than 10% of the variation in natural background in Connecticut. l l 5-2
TABLE 5.1 COMPARISON OF DOSE CALCULATION METHODS HADDAM NECK STATION JANUARY-DECEMBER 1984 ORGAN METHOD 1( METHOD 2(I} PATHWAY AIRBORNE EFFLUENTS ND( }
- 1. External Gamma Dose Max. Ind.(2) Whole Body
- 1.5 Max. Ind.-Thyroid 0.13 NAD( ), <0.6
- 2. a. Inhalation NAD
- b. Vegetables Max. Ind.-Thyroid 0.28 Max. Ind.-Thyroid 0.18 NAD, <2.3
- c. Goat's Milk LIQUID EFFLUENTS 0.023
- 1. F i = 5- Max. Ind.-Wholeggdy 1.10 Max. Ind.-Liver 1.49 0.035 (1) Method I uses measured station discharges and meteorological data as input parameters to conservative transport to man models. Method 2 uses actuel 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 vegatables), 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. (3) The plant ef fects were so small that they could not be distinguished from fluctuations in natural background. (4) NAD - No activity detected above the minimum dectable level. The less than value reported is the dose corresponding to the MDL. (5) For adult. 1
)
1
l l 6.0 DISCUSSION The evaluation of the effects of station operation on the environment requires the careful consideration of many factars. Those factors depend upon the media being effected. Th e.r 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. f Any of these factors could cause significant variations in the measured radioactivity. A failure to consider these factors could cause erroneous cone.lusions. Consider, for example, the problem of deciphering the effect of l 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 l 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
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 of Sr-90 observed must be attributable to nuclear weapon's testing.
- 3. Similar to Sr-89, Cs-134 can be used as an indication of plant related Cs-137. Althoegh not as conclusive as Sr-89, the lack of any measurable Cs-134 in any of the milk samples suggest -
that the Cs-137 is not plant related. This is further confirmed by the evaluation of the air particulate data.
- 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 locations has not changed with plant operation. All areas show the same significant decrease in radioactivity since the 1964 Nuclear Test Ban Treaty.
- 5. Local variability of Sr-90 and Cs-137 in mi..k is common through-out the United States. Due to the variabil tty 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 f a rms . 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.)
'. The 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 Chinese Tests. This indicates that for some unknown reason this farm has the ability for higher reconcentration. Special studies performed at this and other f a rms failed to find any link to the plant.
1 Based on these facts, the observation that the station effluents are respc.sible is obviously false. The cause must be one or more of the other variables. Northeast Utilities has carefully examined the data throughout the year and has presented in this report all cases where plant related radioactivity can be detected. 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. 6-2
1 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. I l 1 I i 6-3
/
CT Start-up M1 start -up N2 Skart-up 1 0 'I , FIGURE 6-1 STRONTIUM-90 IN MILK C 22.5' 20.0- c =
- 17. 5-.
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- 15. 0-- i l
P c C I , / 12.5-L = =
- c. I a =
T c e " E . R 10. 0-- c = .
= .
C M M M M W W
-O E N H 7.54 w 1 . e a ,
M S C W N H M 5.02 e e c C C C C C e 2.5
- y. .,. .,. .,. .,. .,. .,. .,. .,. .g. .,. ,,. .y. .y. .g. .g. ,,, ,,. ,,, .,. .,. , .,.
G1 32 G3 64 G5 66 67 68 69 70 71 72 73 74 75 76 77 78 79 80 81 82 63 04 YEAR C = CENTRAL CONN. AREA--SAMPLES OF POOLED MILK--YEARLY AVERAGE OF MONTHLY DATA ti = HADDAM NECK AREA- AVERRGE OF INDIVIDUAL FARM SAMPLES SOURCE--1965 - IE,3 r0NNECTICUT STATE DEPARIMENT OF HEALTH
.374 - 1984 NORTHEAST UTILITIES DATA M = MILLSTONE AREA--RVERAGE OF INDIVIDUAL FARM SAMPLES SOURCE--1966 - 1973 CONNECTICUT STATE DEPARTMENT OF HEALTH 1974 - 1984 NORTHEAST UTILITIES DATA
e c CY Start-up M1 start-up M2 S t a r t -u p (143)(135) FIGURE G-2 CESIUM-137 IN MILK 70-c 60-50-P 402 a C I cn / L c . T 30- ~ E . R M M N 20- =
" E c w l w e M
. e c c 10- -
c c u e c = e C 0,, ,,, ,,, , , ,,, .,. ,,, ,,, ,,, ,,, ,,. ,,, ,,, ,,, ,,, ,,, ,,, ,,, ,,, ,,, ,,, ,, m ,,,,,,, 61 62 63 64 SS 66 67 68 69 70 71 72 73 74 75 76 77 76 79 80 81 82 83 84 YEAR C CENTRAL CONN. AREA--SAMPLES OF POOLED MILK--YEARLY AVERAGE OF NONTHL7 DATA H = HADDAM NECK AREA--AVERAGE OF INDIVIDUAL FARM SAMPLES SOURCE--1956 - 1973 CONNECTICUT STATE DEPARTMENT OF HEALTH 1974 - 1984 NORTHEAST UTILITIES DATA M = MILLSTONE AREA--AVERAGE OF INDIVIDUAL FARM SAMPLES SOURCE--1966 - 1973 CONNECTICUT STATE DEPARTMENT OF HEALTH 1974 - 1984 NORTMERST UTILITIES DRTA
APPENDIX A Cow and Goat Census for 1984 A-1
DAIRY COWS WITHIN 15 MILES OF CONNECTICUT YANKEE AS OF APRIL 1984 DIRECTION DISTANCE NAME AND ADDRESS NO. OF COWS N 15 M. William Bailey 27 79 Candlewood Rd. Marlborough, CT 06447 N 15 M. Foot Hills Farm 35 Edward Fotte RFD #2 Hebron, CT 06248 N 15 M. Kristoff Brothers 138 Hyland Farm 183 Bailey St. Glastonbury, CT 06033 NNE 8 M. Ranki Farm-Theo Rankl 134 South Road Marlborough, CT 06447 NNE 14 M. Robert K. Gasper 54 694 Gilead St. Hebron, CT 06248 NNE 14 H. Hills Farm 85 527 Glicad St. Hebron, CT 06248 NNE 14 M. Mapleleaf Farm, Inc. 150 750 Gilead St. Hebron, CT 06248 NNE 14.5 M. Douglas Porter 160 RF0 #1 Hebron, CT 06248 NNE 14.5 M. Jonas Valys 134 Hardy Road Hebron, CT 06248 NE 4.5 M. John Dill 24 Waterhold Rd. Colechester, CT 06415
- East Hampton -
NE 8.5 M. John Hohrlein 60 Route 16 Colchester, CT 06145 NE 10 H. Marvin Maynard 20 RFD #2 Colchester, CT 06415 l
DAIRY COWS WITHIN 15 MILES OF CONNECTICUT YANKEE AS OF APRIL 1984 4
. DIRECTION DISTANCE NAME AND ADDRESS NO. OF COWS NE 14 M. Victor Botticello 28 Levita Rd.
Lebanon, CT 06249 NE 14 M. Grabber Brothers 45 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 R.S. Cone Box 251 East Haddam, CT 06423 ENE 8.1 M. William Smith 43 Town Road Colchester, CT 06415 l
- 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 E 12 M. Robin & William Houser 24 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 H. Garry Vaill 34 Forsythe Rd. Colchester, CT 06415
- Salem -
E 14 M. . Stuart Gadbois 225 Route 85 & Route 356 Colchester, CT 06415
. - Salem -
ESE 2.5 M. Mortimer Gelston 45 Maple Ridge Farm Maple Avenue East Haddam, CT 06423 { ESE 14.5 M. Raymond Muschinsky 27 Grassy Hill Road East Lyme, CT 06333 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 l
- Lyme -
SW 13 M. Thomas Haggarty 43 Hoophole Rd. Guilford, CT 06437 WSW 8 M. Michael Dwyer 7 Route 17 Durham, CT 06492
- Wallingford -
WSW 8 M. Robert Raudat 33 Old Durham 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
DAtRY COWS WITHIN 15 MILES OF CONNECTICUT YANKEE AS OF APRIL 1984 DIRECTION DISTANCE NAME AND ADDRESS NO. OF COWS WSW 14 M. John Kranyak 48 1349 Whirlwind Rd. Wal1ingford, CT 06492 WSW 15 M. Alfred Anderson 23 216 Northford Rd. Wallingford, CT 06492 WSW 15 M. Co Ag Farm, Inc. 187 Walter Augur & George Cooke 180 Northford Rd. Wallingford, CT 06492 W 8.5 M. Richard Rowe 30 Box 4, Higganum Rd. Durham, CT 06422 W 11.5 M. Friendly Acres Dairy Farm l 37 l Tony Caltabiano Parmalee Hill Rd. Durham, CT 06422 W 12.2 M. Powder Hill Dairy Farm ' 170 Henry Bugai Powder Hill Rd. l Durham, CT 06422 l l W 12.5 M. Linus Sanstrom, Jr. 30 Strickland Rd. Middlefield, CT 06455 W 14 M. Thomas Wall 48 963 Northrop Rd. Wallingford, CT 06492 W 14 M. North Farms 22 Alex Werbiski 1069 Farms Rd. Wallingford, CT 06492 W 14.5 M. Charles Greenbacker & Sons, Inc. 131 743 Murdock Avenue Meriden, CT 06450 W 14.5 M. Robert 5 elf 91 Fieldstone Farm 63 Grieb Rd. Wallingford, CT 06492
l 4 DAIRY C0WS WITHIN 15 MILES OF CONNECTICUT YANKEE AS OF APRIL 1984 DIRECTION DISTANCE NAME AND ADDRESS NO. OF COWS W 15 M. David Cella 18 899 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 WNW 8 M. E. Leroy Brock 66 796 Ridge Rd.
- Middletown, CT 06457 WNW 8 M. George Seifert 30 Kelsey St.
Middletown, CT 06457 WNW 12 M. John Kolman 55 Meriden Rd. Middletown, CT 06457 WNW 12 M. Walnut Hill Farm 100 William & Thomas Mintz Jackson Hill Road Middlefield, CT 06455 WNW 12.5 M. Far View Farm 40 Gustave Schmaltz Jackson Hill Road
~
i Middlefield, CT 06455 WNW 13 5 M. Richard,Westfort 62 543 Allen Avenue Meriden, CT 06450 4 + WNW 15 M. Bilger Brothers 32 Hickory Grove Farm 705 Westfield Rd. Meriden, CT 06450 s
i DAIRY COWS WITHIN 15 MILES OF CONNECTICUT YANKEE AS OF APRIL 1984 DIRECTION DISTANCE RAME AND ADDRESS NO. OF COWS WNW 15 M. John Hanson 17 506 Spruce Brook Rd. Berlin, CT 06037 l NW 6 M. Edward Hills 36 Brooks Rd. Middletown, CT 06457 : NW 9.5 M. Daniel Anderson 79 Blague Dairy Farm 56 Strong Avenue Portland, CT 06480 NW 13 M. Higgins Farm, Inc. 49 837 Ridgewood Rd. Middletown, CT 06457 NW 15 M. Leland Gilbert 28 730 Elm St. Rocky Hill, CT 06067 NNW l.5 M. John Kruger 14 Quarry Hill Rd. Haddam, CT 06438 NNW 2.5 M. Halls Pride Farm 25 John Hall Haddam Neck Rd. East Hampton, CT 06424
- Haddam -
NNW 13 M. Charles Matway, Est. 17 Brook St. Rocky Hill, CT 06067 i NNW 14 M. Roaring Brook Farm 25 l Henry Killam 77 Tryon St. . So. Glastonbury, CT 06073
- Glastonbury -
l l i DAIRY GOATS WITHIN 20 MILES OF CONNECTICUT YANKEE AS OF MAY 1984 DIRECTION DISTANCE NAME AND ADDRESS, NO. OF GOATS N 4.5 M. Philip Bourdon 9 164 Young St. East Hampton, CT 06424
'l N 6 M. Jackie Reardon 5 So. Main St.
East Hampton, CT 06424 N 12.5 M. Allan Armando 1 New London Tkpe. Glastonbury, CT 06033 N 18.5 M. M. v. Branco 4 School Rd. Bolton, CT 06040 NNE 12 M. Louise Sage 4 155 Reidy Hill Rd. Hebron, CT 06248 NNE 16 M. Joan Bowers 3 350 Wall St. Hebron, CT 06248 NNE 16 M. Elaine Phillips 8 Burnt Hill Rd. Hebron, CT 06248 NNE 16 M. Kathy Waters 9 Burnt Hill Rd. Hebron, CT 0/'48 228-3098 NNE 18 M. Cira Petersons 1 Route 87 Columbia, CT 06237 NNE 18.5 M. Carolyn Bellows 1 Route 87 Columbia, CT 06237
1 I 4 4 DAIRY GOATS WITHIN 20 MILES OF CONNECTICUT YANKEE , AS OF MAY 1984 i
- DIRECTION DISTANCE NAME AND ADDRESS NO. OF GOATS
! NNE 20 M. Ted Beebe 5 Route 6 Columbia, CT 06237 NNE 20 M. Arthur Cobb I 128 Lake Rd. 4 Columbia, CT 06237 4
- NE 16 M. Barbara Nadeau 3 Clubhouse Rd.
Lebanon, CT 06249 i 1 NE 17 H. Lynn Miller 8
- Goshen Hill Rd.
Lebanon, CT 06249 ENE 11 M. Lawrence Brown 1 West Rd. Colchester, CT 06415 , ENE 17 M. Henry Rianhard 1 l Scott Hill Rd. Bozrah, CT 06334 l E 14.5 M. Joseph Devito 5 1494 Old Colchester Rd. Oakdale, CT 06370 ESE 3.1 M. MaryAnn Halpin 3 i Town St. East Haddam, CT 06423 i , ESE 7.2 M. Burton Tucker 2 A.P. Gates Rd. East Haddam, CT 06423 , ESE 15 M. Tina Korineck 6 l 233 Upper Pattagansett Rd. !. East Lyme, CT 06333 i
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9 I DAIRY GOATS WITHIN 20 MILES OF CONNECTICUT YANKEE AS OF MAY 1984 DIRECTION DISTANCE NAME AND ADDRESS NO. OF GOATS ESE 16 M. Ron Birchall 6 339 Boston Post Rd. East Lyme, CT 06333 5 8.5 M. David Recchia 1 i RFD #1 l Deep River, CT 06417 1 j S 11.5 M. Victor Trudeau 5
! 174 Horse Hill Rd.
Westbrook, CT 06498 SSW 6.8 M. Chris Harris 2 218 Reservoir Rd. Killingworth, CT 06417 SSW 8.5 M. Vicki Fonteneau 2 312 Old Deep River Tkpe. Killingworth, CT 06417 SW 20 M. Barbara Prisitera ~ 1 94 Mill Plain Rd. Branford, CT 06405 i W 4.8 M.
- Pat Mannetho 4 Jacoby Rd.
Higganum, CT 06441 W 12 M. Brian Hogan 1 Route 157
+ Middlefield, CT 06082 W 14.5 M. Robert Pogomore 2 177 Williams Rd.
i Wallingford, CT 06492 WNW 10.5 M. Roger Kinderman 3 721 Wadsworth Rd. Middlefield, CT 06082 i .
DAIRY GOATS WITHIN 20 MILES OF CONNECTICUT YANKEE AS OF MAY 1984 DIRECTION DISTANCE _N_AME AND ADDRESS NO. OF G0ATS WNW 15 M. Nancy Hanson 4 506 Spruce Brook Rd. Berlin, CT 06037 WNW 19 M. Daniel Nitkowski 1 46 Firch Ave. Meriden, CT 06450 NW l.5 M. Donald Donofrio 7 injun Hollow Rd. Haddam, CT 06441 NW 13.5 M. Ronald Marchinkoski I g 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 NNW 14 M. Dorothy Joba 6 171 Ferry Lane S. Glastonbury, CT 06073
l l APPENDIX B Quality Control i
]
1 B-1
Introduction 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 samples). 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 of what agreement the primary contractor has with another laboratory. I 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. 1 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, a) only. The standard deviation is divided into the difference between the two measurements (A). The result then should satisfy the acceptance criteria 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 i 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, sampling, etc. Hence, 10 percent has been found to be reasonable criteria. From the totals at the bottom of Table 2 this requirement is satisfied for Ge(Li) and H-3 analyses. However, 11.1 percent of the Sr-9u analyses were unacceptable. All four sets of 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 type of measurement. As indicated by the totals on the bottom of 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 requirement is satisfied for H-3 and I-131 (in air) analyses. This 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 previous years have remained. The switch from CuI to Pdl carrier has improved the results. Of the 6 unacceptable results, 5 occurred for low spikes. All five of these yielded conservative results, therefore, it can be concluded that the data presented in this report for this type of analysis, is conservative. The increased spiked I-131 in milk program will continue. f 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 ~ 55 percent low. Reanalysis indicated a value that was ~ 36 percent low. The first Sr-89 result was high (by ~ 300 percent), indicating interference from Sr-90. Reandtysis for Sr-89 was acceptable. For the three unacceptable Sr-90 and two unacceptable Sr-89 results in water, five samples were involved. Four of these were reanalyzed. The original Sr-90 results were ~ 30 percent low. Reanalyses indicated acceptable results for these three samples. The original Sr-89 results were only ~ 20 percent low. Reanalysis of one of these indicated acceptable results. ! Two fish spikes had Sr-90 results that were unacceptable. One sample was reanalyzed; the Sr-90, however, remained unacceptable. This media often presents a problem because of calcium interferences and nonuniformity of spikes. Therefore, no further investigation was deemed necessary. For the two unacceptable Sr-90 results in air particulates, results were B-3
- - . . _, , e , -
,_ - , , _ . _ . . - ~ . . . _ , - . _ _ _ - - - - -. _ . - -_ _~___
~ 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
~ 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, t has no analysis problem. The problem is related to the geometry of . spiking the filter paper. Corrective actions are being taken. C,oncOdsion . Based on the results discussed above, it is concluded that the results of the routine measurements presented in the report are valid. The results of primary contractor's participation in the EPA QA program confirms this i Conclusion. 1 4 4 i 4 1 1 1 I i I B-4 i
Table 1
- Number of Quality Controlf- Samples Number of Number of Routine Sample Type QC Samples Required Samples a'b Milk 51 112 Well Water' 17 28 C
Sea Water 2 16 River Water' 7 8 Soil 3 16 Bottom Sediment 4 26 Aquatic Flc.ra 4 12 Fish 12 40 Shellfish 4 52 Lobster 0 12 , Fruits and Vegetables 0 16 Air Particulate - Gross Beta 13 1113 Iodine 11 424
- Geli 24 252
- Chemistry 8 84
- An additional program is performed by the contractor a - Total for both Millstone and Connecticut Yankee b - Depends on availability c - QC breakdown does not include H-3 analysis; total number of tri-tium QC samples was 31.
B-5
Table 2 Precision i Acceptance Number of Measurements Media Analysis Criteria Acceptable Unacceptable 90 Milk Sr /05 4* 25 3 Sr A/o$ 4 27 1 Cs 37 (Geli) A/of 3 27 1 Water H-3 A/o$ 4 8 0 Soil & Gegg's A/of 3 3 0 Bottom Sr A/of 4 2 1 Sedi:nent Aquatic Geff's A/o$ 3 5 0 Life Sr A/o$ 4 5 0 90 Total Sr A/o$ 4 32 4 Geli A/05 3 35 1 H-3 A/oS 4 8 0
*a = difference between the two values o = standard deviation B-6
Table 3 Interlaboratory Comparisons Acceptance Number of Measurements Media Analysis Criteria Acceptable Unacceptable Milk Sr A/of 4* 11 0 09 Sr A/o5 4 11 0 Cs l37 (Geli) A/05 3 11 0 0 Water Sr A/0$ 4 7 0 H-3 A/c5 4 11 1 Soil & Gegg's A/o$ 3 4 0 Bottom Sr A/05 4 4 0 Sediment Aquatic A/c5 3 10 0 Life Geff's Sr A/c5 4 9 1 0 Total Sr A/a5 4 31 1 H-3 A/o$ 4 11 1 Geli A/of 3 25 0
*A = difference between the two values a = standard deviation
, B-7 i i
. = . - . - - _. - -
Table 4 Accuracy (Results of Spikes)
- Number of Measurements Acceptable Unacceptable Acceptance Primary Secondary Primary Secondary Media Analysis Criteria Contractor Contractor Contractor Contractor i Milk
~ ~
I a 5 30% 18 6 C 0 Sr A/o 5 4 7 4 1 0 89 Sr A/o 5 4 7 4 1 0 37 Cs A/o 5 3 8 4 0 0 134 Cs A/o 5 3 7 4 1 0 Water A/o 5 3 11 6 0 Geff Sr 1 89 A/o 4 9 6 3 0 Sr A/o 5 4 10 6 2 0 H-3 A/o 5 4 8 4 0 0 Aquatic Gegg A/o 5 3 0 1 2 1 l Food and Sr 89 A/o 5 4 0 2 2 0 ! Flora Sr 4'5 4 2 2 0 0
, Air Gross af o 5 4 3 -
10 -
, Particulate Geli A/c 5 3 21 -
3 - Csfchemistry) g A/o 5 4 2 - 6 - l S f31 a 5 6 - 2 - i I A/o 5 4 11 - 0 - 1 Total I (milk) a 5 30% 18 6 6 0 Sr A/o 5 4 22 12 8 0 Sr A/o 5 4 19 12 3 0 i 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 Hgy(air) I A/o 5 4 11 - 0 - I Gross Q (air) A/o 5 4 3 - 10 - l 1
- A = difference between the two values a = standard deviation i
! B-8 1
CONNECTICUT Y AN K EE AT O M IC POWER COMPANY B E R L I N. CONNECTICUT PO DOX 2 70 H ART F OHD LOY.E CTICUT %141-C2'O TE LFHGNE 2GM664911 March 27, 1985 Docket No. 50-213 B11502 Dr. T. E. Murley Regional Administrator Pegion I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 Deat Dr. Murley: HADDAM NECK STATION ANNUAL ENVIRONMENTAL OPERATING REPORT, PART B: RADIOLOGICAL In accordance with the requirements of Appendix B to the operating two (2) copies license, Environmental Technical Specifications, 5.6.1.a., Radiological, are of the Annual Environmental Operating Report, Part B: herewith submitted. Copies of this report are being distributed in accordance with Regulatory Guide 10.I. Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY jl . ., 01Db W.'G. Counsil Senior Vice President c: J. A. Zwolinski
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