B11501, Point Site,Radiological Environ Monitoring Program Annual Environ Operating Rept,Part B,1984
| ML20138M546 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 12/31/1984 |
| From: | Counsil W NORTHEAST UTILITIES SERVICE CO. |
| To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| B11501, NUDOCS 8511040093 | |
| Download: ML20138M546 (100) | |
Text
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MILLST0h1 POINT SITE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL EhTIRONMENTAL OPERATING REPORT PART B PERIOD JANUARY 1, 1984 - DECEMBER 31, 1984 MILLSTONE UNIT 1, DOCKET No. 50-245 MILLSTONE UNIT 2, DOCKET No. 50-336 PREPARED FOR THE NORTHEAST NUCLEAR ENERGY COMPAhT HARTFORD, CONNECTICUT BY THE NORTIEAST UTILITIES SERVICE COMPANY BERLIN, CONNECTICUT v,/
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k MILLSTONE POINT SITE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL ENVIRONMENTAL OPERATING REPORT PART B PERIOD JANUARY I, 1984 - DECEMBER 31, 1984 3
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d MILLSTONE UNIT 1, DOCKET NO. 50-245 MILLSTONE UNIT 2, DOCKET NO. 50-336 i
PREPARED FOR THE
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. NORTHEAST NUCLEAR ENERGY CO'.1PAhT HARTFORD, CONNECTICUT BY THE i
NORTHEAST UTILITIES SEP.VICE COMPANY
, BERLIN, CONNECTICUT l
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TABLE OF CONTENTS t
- Page No.
l 1.0 Summary 1-1
- 2.0 Program Description 2-1 2.1 Sampling Schedule and Locations 2-1 1
! 2.2 Samples Collected During Report Period 2-7 f
- 3.0 Radiochemical Results 3-1 3.1 Summary Table 3-1 3.2 Data Tables 3-18 4.0 Discussion of Re
- ults 4-1 5.0 Offsite Dose Consequences 5-1 6.0 Discussion 6-1 i
i Appendix A - Cow and Goat Census for 1984 A-1 Appendix B - QA Program B-1 Appendix C - 1983 Report Errata C-1 l I
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1.0
SUMMARY
The radiological environmental monitoring program for the Millstone Nuclear Power Station was continued for the period January through December 1984, in compliance with the Environmental Technical Specification, Section 3.2. This annual report was prepared for the Northeast Nuclear Energy Company (NNECO) 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 as an independent check on the primary contractors' laboratories as part of the overall quality assurance program.
Sampling and radiological analyses were performed with gamma exposure measuring devices and on air particulates and iodine, soil, milk, pasture grass, well water, fruits, vegetables, seawater, bottom sediment, aquatic flora, finfish, mussels, oysters, clams, scallops, lobsters, and crabs. 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, 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 from nonplant sources such as fallout from nuclear weapons tests and from naturally occurring radionuclides. In the case of the terrestrial media, plant related radioactivity above the minimum detectable levels, was observed in gamma exposure measurements at some of the onsite locations and in some of the goat milk samples. The gamma exposure measurements indicate an effect from Unit I via the direct dose pathway (i.e., scattered radiation, "skyshine", from nitrogen-16 in the turbine building; unique to Boiling Water Reactors). This effect is seen by the decrease in the thenmoluminescent dosimeter (TLD) values for the months of May and June, the period when Unit I was shut down for refueling. This direct dose pathway decreases rapidly with distance, to levels that are undetectable at the offsite locations. The gaseous releases have been reduced such that they are no longer detectable by TLD's at any onsite or offsite location. Gaseous releases of iodine, however, are still detectable in milk at the nearest offsite goat location.
Monitoring of the aquatic environment in the area of the discharge indicated the presence of the following plant related radionuclides:
cobalt-58 and cobalt-60 in aquatic flora; cesium-134, cesium-137, and cobalt-60 f a eels; cobalt-60, zinc-65, and silver-110m in oysters; cobalt-60 in clams; cobalt-60 and silver-110m in crabs; and cobalt-60 and silver-110m in lobsters. Except for cobalt-60 in l
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l aquatic flora, the levels of these radionuclides were similar to the levels observed for the last five years. Increased levels of Co-60 in aquatic flora have been observed for the past two years. All activity levels were below those of the higher discharge period of 1974-1975 (before the augumented liquid radwaste treatment system).
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 a result of plant operation. This can be concluded based on the facts that: insufficient gaantities (at least 1000 times less) of these isotopes have been released by the plant to account for the measured concentrations, plant related strontium-89 which is chemically similar to Sr-90 and released in about equal or larger quantities from the plants can not be detected and comparable levels of cesium-137 and strontium-90 were detected prior to initial station operation.
2 The radiation dose to the general public from the station'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 environmental media. The maximum whole body dose (at the station boundary) that could occur to a member of the general public as a result of the station operation was 1.5 millirem. This includes a contribution of 1.3 millirem from "skyshine" and 0.2 millirem from station effluents. The average whole body dose to an individual residing within 50 miles of the station was 0.00086 millirem. These doses are 6.0 percent and 0.0034 percent of the standards as set by the U.S. 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 inconse-quential 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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r 2.0 PROGRAM DESCRIPTION 2.1 Sampling Schedule and Locations
- The sample locations and the sample types and frequency of j analysis are given in Table 2-1 and 2-2 and Figures 2.1, 2.2 i and 2.3. The program as described here is that which is required by Environmental Technical Specification 3.2.
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Table 2-1 Millstone Radiological Environmental Monitoring Frogram-Terrestrial Stations Sample TypeO) and Analysis ICI Distance Camma Air Locations and DirectionI *) Dose FarticulateI *)II) Soil
- 1. Onsite--Old Millstone Road 0.6 miles NNW M W1 - M2 - QS --
- 2. Onsite-Weather Shack 0.3 miles S M W1 - M2 - Q5 --
- 3. Onsite--Bird Sanctuary 0.3 miles NE M W1 - M2 - Q5(f) A2,5
- 4. Onsite-Albacore Drive 1.0 miles N M W1 - M2 - Q5(f) A2,5
- 5. Onsite-Navy Laboratory 0.2 miles SSE M -- -
- 6. ,0nsite-Quarry Discharge Canal Fence 0.3 miles SSE M - -
- 7. Onsite-Fox Island 0.3 miles SE M -- -
- 8. Onsite--Millstone Environmental Lab. 0.3 miles SE M - -
- 9. Onsite-Bay Point Beach (Information Center) 0,2 miles W M - -
- 10. Fleasure Beach 1.2 miles E M W1 - M2 - Q5 A2,5
- 11. New London Country Club 1.6 miles ENE M W1 - M2 - Q5(f) A2,5
- 12. Fisher's Island, New York
- 8.7 miles ESE M W1 - M2 - Q5 --
w 13. Mystic, Connecticut
- 11.5 miles ENE M WI - M2 - QS --
- 14. Ledyard, Connecticut
- 11.5 miles NE M W1 - M2 - Q5If) A2,5
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- 15. Montville, Connecticut
- 14.0 miles N M W1 - M2 - Q5
- 16. Old Lyme, Connecticut
- 9.0 miles W M W1 - M2 - QS --
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- 8) Croundwater Fruit Venetables
- 17. Well No. 1 1.5 miles - SA1,2,4,5 - -
- 18. Well No. 2 1.0 miles - SA1,2,4,5 - -
, 19. Dairy Fara No. 1 6.0 miles N M3,5 - - -
- 20. Dairy Fara No. 2 9.5 miles WNW M3.5 - - -
- 21. Dairy Fare No. 3 11.0 miles NE M3,5 - - -
'22. Dairy Fara No. 4 a 15.0 miles NNW M3,5 - - -
- 23. Coat Tara No. 1 2.0 miles EFE TM3-M5 (composite) - - -
- 24. Coat Fara No. 2
- 14.0 miles NE 1M3-H5 (composite) - -- -
2?. Fruit and Vegetables -- - - SA2,5(h) SA2,5(h)
- a. From Millstone (Init 1 (stack) to nearest half mile
- b. W = weekly TM = twice a month, M= monthly, Q = quarterly, SA = semiannual, A = annual
- d. During the period April through October and once in February.
- e. Analyses are done on monthly and quarterly composites of the weekly air particulate samples collected at each station.
- f. Includes a charcoal filter to be analyzed weekly for 1-131 at inhalation dose levels.
- g. Crass is substituted if milk is not available,
- h. To be collected at the middle and end of the harvest season when available from representative commercial f arms.
1 Comparisons between inner stations (within 1.5 miles) and outer stations (greater than 1.5 miles) will be made instead of using a control staaion concept.
- Control Station
~L Table 2-2 Hillstone Radiological Environmental Monitoring Program--Aquatic Stations Type. Frequency (b) and AnalysisICI Distance Botton
- 4) Mussels Oystery*yr Locations and Direction Sediment Flora Class Lobster (e) Fin Fish (d*e) k* ster
- 1. Golden Spur
- 4.7 miles NNW SA2.3 -* Q2,3,5 Q2,3,5 -- -- ~~
- 2. Nientic Shoals $1.8 miles NW SA2,3 SA2,3- Q2,3,5 Q2,3,5 - ~~ ~~
- 3. Within 500 Feet of Discharge Canal ---
SA2,3 SA2,3 Q2,3,5 Q2.3.5 Q2.3,5 Q2.3.5 Q1,2,3,4
- 4. Seaside Point 1.6 miles ESE SA2,3 SA2.3 -- -- -- -- Q1,2,3,4
- 5. Thames River (Yacht Club) 4.0 miles ENE SA2,3 SA2,3 -- Q2,3,5 -- -- --
- 6. Niantic Bay 0.3 miles WNW -- -- --
Q2,3,5 Q2,3,5 Q1.2.3.4
- 7. Black Point 2.6 miles WSW SA2,3 SA2.3 -- Q2,3,5 -- -- --
- 8. Giants Neck
- 3.5 miles W SA2,3 SA2,3 -- Q2,3,5 Q2,3,5 -- Q1,2,3,4
- 9. Commercial Shellfish -- -- -- Q2,3,5 -- -- --
Bed #316 0.1 miles S Y 10. Waterford Shell fish Bed #1 0.5 miles WNW -- -- - Q2,3,5 -- -- ~~
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- c. From Dischstge Quarry to nearest half mile.
- b. Q = quarterly SA = sent-annual
- d. Flounder and one other type of edible fin fish.
- e. Sampling of crustacea, mollusk and fin fish to be staggered for each month of the quarter.
- Control Stations 4
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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 (TLD) 192 Air Particulates 576 Air Iodine 211 Soil 6 Dairy Milk 32 Goat Milk 28 j
Well Water 4 Fruit and Vegetables 8 Sea Water 16
, Bottom Sediment 14 Aquatic Flora 12 d
Fish 16 Mussels 12 Oysters / Clams 27 Lobster 12 r Total All Types 1,166 4
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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 l
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 4 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 4.0 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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ENVIRONMENTAL RADIOLOGICAL PONITORING PROGRAM
SUMMARY
MILLSTONE NUCLEAR POWER STATION, UNITS I and 2 DOCKET 50-245 and 50-336 JANUARY - DECEMBER 1984 ANALYSIS AND MINIMUM ALL INDICATOR LOCATION WITH HIGHEST ANNUAL ME AN ~ CONTROL LOCATIONS MEDIUM OR TOTAL NUMBER DETECTABLE LOCATIONS # OF PATHWAY OF ANALYSES LEVELS (b) NAME, DISTANCE (b) (b) NRMs SAMPLED PERFORMED (MDL's)(a) Mean (Range) AND DIRECTION Mean (Range) Mean (Range) (c)
- Gamma Dose 132,60(d) 1.5 9.6 (5.8 - 14.2) Weather Shack 13.4 (12.5 - 14.2) 9.1 (7.3 - 12.0) 0 (uR/hr) 0.3 Miles S Air Particulate 316,260 New London and Iodine Beta 0.01(e) 0.021 (0.008 - 0.042) Country Club 0.021 (0.008 - 0.042) 0.019 (0.006 - 0.056) 0 (pci/m3) 1.6 Miles ENE Mai 158,53 0.04 0.013 (-0.03 - 0.05) Albacore Drive 0.018 (-0.02 - 0.04) 0.017 (-0.04 - 0.06) 0 I-131 1.0 Miles N i
Ge(L1) 72,60 0.025(f) 0.000 (0.000 - 0.004) New London Country 0.0003 (0.000 - 0.004) 0.000 0 j Cs-137 Club - 1.6 Miles ENE Cs-134 0.02(f) 0.000 N/A(h) N/A 0.000 0 Ru-103 --
0.0001 (0.000 - 0.005) Bird Sanctuary 0.0004 (0.000 - 0.005) 0.0001 (0.000 - 0.004) 0 0.3 Miles NE i Zr-95 --
0.000 (0.000 - 0.008) Bird Sanctuary 0.0007 (0.000 - 0.008) 0.000 0 0.3 Miles NE i New London Country i Nb-95 --
0.0001 (0.000 - 0.005) Club and Montville 0.0004 (0.000 - 0.005) 0.0001 (0.000 - 0.004) 0 1 1.6 Miles ENE 0.0004 (0.000 - 0.004) 1 and 14 Miles N i
Cs 24,20 0.001(e)(9) 0.00018 (0.00001 - 0.0006) New London Country 0.00033 (0.00013 - 0.0006) 0.00014 (0.0000 - 0.00069) 0 Cs Club - 1.6 Miles ENE
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_ l i L P1 B0 L1 L1 L1 O AE EK U I N D LCA A CO R UD J
) )
N 2 6 L 0 0
_ A E 0 0 T N 0 ) ) )
N O )) 0 3 8 1 E T be 0 0 3 8 M S R (g -
N L O n - 0 0 0 O L TS a 7
_ I R AN R 0 0 - - -
. I M CO ( 0 0 V II 0 0 0 9 2 N DT 0 0 0 2 E NA 0 IC - 0 0 0 0 O ( ( ( ( (
LL L
A 3 6 n 1 1 a 0 0 2 0 0 0 e 0 0 1 1 9 0 0 M 0 0 0 2 5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0
) )
E ) 9 9 L a ( (
)
MBS( )
UAL) e (
e MTEs (
0 0
7 0
3 0
7 0
6 0
IME D M
( 0 0 0 0 0 0 DR
_ NES ABED 0 2, 2,
_ MSE 2, 4 4 SUYM 4 9
7 3
I NLR 2 9 S AO 8 8 )1 4
8 0 5 YLNF - 0 - 0 1 3 4 LAAR r 9 r 9 L s 1 5 5 6 9 AT E S - S - (C - - - - -
_ NOFP r r r r e s n o o r ATO S S S S G C M C C Z
_. R OYD )
AE g MWL UHP /
ITM lf DAA i C op
_ EPS M S(
i1 4 : ;) I!1 ' ;' , ' ! j . ;
il'
. _ _ . - _ . . . _ .. _ _ . _ . . . _ - _ _ _ . . _ _ _ _ . . ~ _ . . _ __ . .. . . -
I J
i i
, TABLE 3-1
! ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SUMARY MILLSTONE NUCLEAR POWER STATION. UNITS I and 2 j DOCKET 50-245 and 50-336
! JANUARY - DECEMBER 1984
! ANALYSIS AND MINIMUM ALL INDICATOR LOCATION WITH HIGHEST ANNUAL MEAN CONTROL L6CA110NS j MEDIUM OR TOTAL NUMBER DETECTABLE LOCATIONS f 0F
! PATHWAY OF ANALYSES LEVELS (b) MAME. DISTANCE (b) (b) NRMs SAMPLED PERFORMED (MDL's)(a) Mean (Range) AND DIRECTION Mean (Range) Mean (Range) (c)
Sr-90 1 19.4 (8.0 - 30.8) Goat Farm #1 19.4 (8.0 - 30.8) 4.6 (2.7 - 7.0) 0 2 Miles ENE
! Ge(L1) 19.17 6 103 (31 - 181) Goat Farm #1 103 (31 - 181) 4.7 (2 - 9) 0 j Cs-137 2 Miles ENE Cs-134 6 0 N/A N/A 0 0 4
Groundwater Sr 4 2 0.22 (-0.2 - 0.5) Well #1 0.35 (0.2 - 0.5) N/A 0 1 -(pC1/1) Sr-89 1.5 Miles NME i
i
] Sr-90 1 0.46 (0.3 - 0.8) Well f2 0.52 (0.3 - 0.8) N/A 0 i l.0 Miles NNE f Ge(L1) 4 6 0 N/A N/A N/A 0
] Cs-137 I-131 30** O N/A N/A N/A 0 i
Cs-134 6 0 N/A N/A N/A 0 t
, Co-58 6- 0 N/A N/A N/A 0 ..
[:
1 Co-60 6 0 N/A N/A N/A 0
! Mn-54 6 0 N/A N/A N/A 0 l
- at time of counting
_ _ . . . - - . ~ . - _ - . . _~ . .- - - -
1 1
TABLE 3-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
MILLS 10NE NUCLEAR POWER STATION, UNITS I and 2 DOCKET 50-245 and 50-336 JANUARY - DECEMBER 1984 ANALYSIS AND MINIMUM ALL INDICATOR LOCAil0N WITH HIGHEST ANNUAL MEAN CONTROL LOCA110NS MEDiltM 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)
Ledyard and Nb-95 -- 0.00 Montville - 11.5 0.04 N/A 0.04 (0.00 - 0.04) 0
- Miles NE and 14 Miles N K-40 -- 6.2 (4.1 - 9.8) Pleasure Beach 9.8 N/A 5.2 (5.1 - 5.2) 0 1.2 Miles E 1
Ra-226 -- 0.49 (0.30 - 0.74) Pleasure Beach 0.74 N/A 0.48 (0.48 - 0.48) 0
- 1.2 Miles E I
Milk (Dairy) lodine 36,12 0.5 0.13 (0.0 - 0.3) Dairy Farm #1 0.15 (0.0 - 0.2) 0.11 (0.0 - 0.2) 0 (pCi/1) 1 131 6 Miles N 4
i Sr 36.12 2 0.19 (-2.0 - 2.0) Dairy Farm #1 0.52 (-1.3 - 1.4) 0.13 (-1.0 - 1.1) 0 Sr-89 6 Miles N Sr-90 1 6.3 (2.8 - 13.7) Dairy Farm #3 8.7 (5.4 - 13.7) 4.2 (2.6 - 5.4) 0 11 Miles NE Ge(L1) 36,12 6 11.3 (1 - 41) - Dairy Farm #1 15.6 (9 - 33) 4.2 (0 - 8) 0 1 Cs-137 6 Miles N Cs-134 6 0 N/A N/A 0 0 Goot Milk lodine 19,17 0.5 0.28 (0.0 - 1.2) Goat Farm #1 0.28 (0.0 - 1.2) 0.22 (0.0 - 0.7) 0
.(pC1/1) 1-131 2 Miles ENE 1
Sr 19,17 2 0.52 (-3.0 - 3.0) Goat Farm #1 0.52 (-3.0 - 3.0) 0.23 (-0.6 - 1.3) 0 4
Sr-89 2 Miles ENE
- _ . . ~ . - . _ . . _ -
I l.
- TABLE 3-1 ,
- ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
i MILLSTONE NUCLEAR POWER STATION, UNITS I and 2 y
DOCKET 50-245 and 50-336
^
JANUARY - DECEMBER 1984 i
ANALYSIS AND MINIMUM ALL INDICATOR LOCATION WITH HIGHEST ANNUAL MEAN CONTROL LOCATIONS
, MEDIUM OR TOTAL NUMBER DETECTABLE LOCATIONS i 0F PATHWAY OF ANALYSES LEVELS (b) NAME. O! STANCE (b) (b) NRMs I SAMPLED PERFORMED (MDL's)(a) Mean (Range) AND DIRECTION Mean (Range) Mean (Range) (c)
Tritium 4 60 128 (0 - 210) Well #2 190 (170 - 210) N/A 0 H-3 1 Mile NNE i Beta 4 1 4.2 (1.1 - 7.0) Well #1 5.4 (3.7 - 7.0) N/A 0 B 1.5 Miles NME
]
i Fruits and j VIgetables Sr 4.4 0.018 0.004 '(0.000 - 0.008) Within 10 Miles 0.004 (0.000 - 0.008) -0.002 (-0.016 - 0.007) 0 j (pC1/g) Sr-89 Sr-90 0.009 0.015 (0.004 - 0.031) Beyond 10 Miles 0.029 (0.012 - 0.038) 0.029 (0.012 - 0.038) 0
! Ge(L1) 4,4 0.034 0.00 N/A N/A 0.00 0 j Cs-137 y
I j I-131 0.05 0.00 N/A N/A 0.00 0
, 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
! Co-58 -- 0.00 N/A N/A 0.00 0
! Co-60 -- 0.00 N/A N/A 0.00 0 ,
s 1
- . . _ , - . - - - - . - - _ _ . . - - - . - . _ _ . - - _ . _ . _ . _ ~ - _ . - . - .- .
l 1
t I
TABLE 3-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SUM ARY
! MILLSTGNE NUCLEAR POWER STATION. UNITS I and 2 DOCKET 50-245 and 50-336 i i JANUARY - DECEMBER 1984 ANALYSIS AND MINIMUM ALL INDICATOR LOCATION WITH HIGHEST ANNUAL MEAh CONTROL LOCATIJNS -
I MEDIUM OR TOTAL NUMBER DETECTABLE LOCATIONS f 0F !
PATHWAY OF ANALYSES LEVELS (b) NAME, DISTANCE (b) (b) NRMs j
SAMPLED PERFORMED (MDL's)(a) Mean (Range) AND DIRECTION Mean (Range) Mean (Range) (c)
K-40 -- 3.0 (1.1 - 5.5) Within 10 Miles 3.0 (1.1 - 5.5) 2.3 (0.9 - 4.5) 0 i Ra-226 -- 0.00 N/A N/A 0.00 0
' t j
} Th-228 -- 0.03 (0.00 - 0.09) Within 10 Miles 0.03 (0.00 - 0.09) 0.00 0 i
a Seawater Sr 12.4 2 -0.12 (-0.7 - 0.5) Seaside Point 0.05 (-0.6 - 0.5) -0.10 (-0.7 - 0.6) 0 <
j (pC1/1) Sr-89 1.6 Miles ESE I Sr-90 1 0.5 (0.3 - 0.9) Within 500 feet 0.5 (0.3 - 0.9) 0.4 (0.1 - 0.7) 0 1 of Discharge and 0.5 (0.3 - 0.7)
- Miantic Bay j 0.3 Miles WNW i
4 Ge(Li) 12.4 6 0 N/A N/A 0 0 Cs-137 j I-131 -- 0 N/A N/A 0 0 Cs-134 13 0 N/A N/A 0 0 4 ,
i Mn-54 13 0 N/A N/A 0 0 l
Co-58 13 0.3 (0 - 3) Within 500 feet 1 (0 - 3) 0 0 of Discharge Co-60 13 0 N/A N/A 0 0
. - -. _. _-..- - . .._. .-- -. - - .. .-- ~ . .
. . _ _ . ~ _ . . _ . - -- - -..._..,- .- -. ..
TABLE 3-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SUPWARY ;
MILLSTONE NUCLEAR POWER STATION, UNITS I and 2 DOCKET 50-245 and 50-336 '
JANUARY - DECEMBER 1984 ANALYSIS AND MINIMUM ALL INDICATOR LOCATION WITH HIDiEST ANNUAL MEAN CONTROL LOCATIONS MEDIUM OR TOTAL NUMBER DETECTABLE LOCATIONS f 0F PATHWAY OF ANALYSES LEVELS (b) NAME, DISTANCE (b) (b) NRMS SAMPLED PERFORMED (MOL's)(a) Mean (Range) AND DIRECTION Mean (Range) Mean (Range) (c)
Tritium 12.4 60 68 (0 - 210) Niantic Bay 93 (0 - 190) 28 - (0 - 110) 0 H-3 0.3 Miles WNW Mb-95 13 0 N/A N/A 0 0 P
K-40 -- 290 (200 - 410) Seaside Point 313 (240 - 410) 288 (150 - 380) 0 1.6 Miles ESE ,
Beta 12.4 1.7 0.02 (-0.2 - 0.4) Within 500 feet 0.07 (-0.1 - 0.2) 0.03 (-0.2 - 0.3) 0 Fraction I of Discharge Beta 1.7 3.0 (1.1 - 7.6) Within 500 feet 3.4 (1.2 - 7.6) 3.3 (1.8 - 5.4) 0 Fraction 11 of Discharge Beta 1.7 0.52 (0.2 - 0.9) Giant's Neck 1.07 (0.3 - 2.7) 1.07 (0.3 - 2.7) O c Fraction !!! 3.5 Miles W Beta 1.7 6.5 (3.5 - 11.9) Niantic Bay 7.8 (5.2 - 11.1) 5.3 (3.1 - 7.2) 0 Fraction ly 0.3 Miles WNW Botton Sediment Sr 10.4 0.072 0.001 (-0.004 - 0.01) Golden Spur , 0.02 (-0.002 - 0.04) 0.01 (-0.002 - 0.04) 0 (pC1/g) Sr-89 4.7 Miles NNW Sr-90 0.036 0.005 (0.00 - 0.002) Thames River 0.013 (0.011 - 0.014) 0.004 (0.003 - 0.006) 0 Yacht Club 4.0 Miles ENE i
TABLE 3-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
MILLSTONE NUCLEAR POWER STATION, UNITS I and 2 DOCKET 50-245 and 50-336 JANUARY - DECEMBER 1984 ANALYSIS AND MINIMUM ALL INDICATOR LOCATION WITH HIGHESI annuat no n.. '
CONTROL LOCATIONS MEDIUM OR TOTAL NUMBER DETECTABLE LOCATIONS f 0F PATHWAY OF ANALYSES LEVELS (b) NAME, DISTANCE (b) (b) NRMs SAMPLED PERFORMfD (MDL's)(a) Mean (Range) AND DIRECTION Mean (Range) Mean (Range) (c)
Ge(Lf) 10.4 0.064 0.03 (0.00 - 0.22) Niantic Shoals 0.11 (0.00 - 0.22) 0.01 (0.00 - 0.06) O Cs-137 1.8 Miles NW I-131 --
0.00 N/A N/A 0.00 0 Cs-134 0.06 0.00 N/A N/A 0.00 0 Mn-54 --
0.00 N/A N/A 0.00 0 Co-58 --
0.00 N/A N/A 0.00 0 Co-60 --
0.00 N/A N/A 0.00 0 Zr-95 --
0.00 Golden Spur 0.02 (0.00 - 0.05) 0.01 (0.00 - 0.05) 0 4.7 Miles NNW Nb-95 --
0.00 N/A N/A 0.00 0 Thames River K-40 --
11.1 (7.7 - 14.6) Yacht Club 13.6 (12.5 - 14.6) 11.9 (10.5 - 13.5) 0 4 Miles ENE Aquatic Flora Sr 10,2 0.01 0.00 (-0.08 - 0.03) Niantic Shoals 0.013 (0.004 - 0.022) 0.00 (-0.002 - 0.00) 0 (pCi/g) Sr-89 1.8 Miles NW
i TABLE 3-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
MILLSTONE NUCLEAR POWER STATION. UNITS 1 and 2 00CKET 53-245 and 50-336 JANUARY - DECEMBER 1984 ANALYSIS AND MINIMUM ALL INDICATQR LOCATION WITH HIGHEST ANNUAL MEAN CONTROL LOCATIONS MEDIUM OR TOTAL NUMBER DETECTABLE LOCATIONS f 0F PATHWAY OF AMALYSES LEVELS (b) NAME DISTANCE (b) (b) NRMs (Range) AND DIRECTION Mean (Range) Mean (Range) (c)
SAMPLED PERFORMED (MDL's)(a) Mean Sr-90 0.009 0.01 (0.004 - 0.04) tC b 0.025 (0.010 - 0.04) 0.01 (0.003 - 0.012) 0 4 Miles ENE Ge(L1) 10,2 0.034 0.00 N/A N/A 0.00 0 Cs-137 I-131 0.05 0.00 N/A N/A 0.00 0 Cs-134 0.025 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 0.01 (0.00 - 0.07) Within 500 feet 0.03 (0.00 - 0.07) 0.00 0 of Otscharge Co-60 0.05 0.09 (0.00 - 0.65) Within 500 feet 0.40 (0.16 - 0.65) 0.00 1 of Discharge N/A 0.00 0 Ir-95 --
0.00 N/A Nb-95 -- 0.00 N/A N/A 0.00 0 3
TABLE 3-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
MILLSTONE NUCLEAR POWER STATION, UNITS I and 2 DOCKET 50-245 and 50-336 JANUARY - DECEMBER 1984 ANALYSIS AND 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)
Ag-110m -- 0.00 N/A N/A 0.00 0 Fish-Flounder Sr
- 0.018 0.002 (0.00 - 0.005) Within 500 feet 0.003 (0.001 - 0.005) N/A 0 (pC1/g) Sr-89 of Olscharge Sr-90 0.009 0.004 (0.001 - 0.012) Niantic Bay 0.005 (0.002 - 0.012) N/A 0 0.3 Miles WNW Ge(L1) 8 0.056 0.01 (0.00 - 0.03) Within 500 feet 0.01 (0.00 - 0.02) N/A 0 Cs-IS/ of Discharge I-131 -- 0.00 N/A N/A N/A 0 Cs-134 0.05 0.00 N/A N/A N/A 0 Mn-54 0.05 0.00 N/A N/A N/A 0 Co-58 0.05 0.00 N/A N/A N/A 0 Co-60 0.05 0.00 N/A N/A N/A 0 Zr-95 --
0.00 N/A N/A ?/A 0 Nb-95 -- 0.00 N/A N/A N/A 0
i l
i 1
I i
I TABLE 3-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SUfetARY 4 MILLSTONE NUCLEAR POWER STATION, UNITS I and 2 I DOCKET 50-245 and 50-336
! JANUARY - DECEMBER 1984 I
ALL INDICATOR LOCATION WITH HIGHEST ANNUAL MEAN CONTROL LOCATIONS ANALYSIS AND MINIMUM TOTAL NUMBER DETECTABLE LOCATIONS f 0F l MEDI O OR (b) (b) NRMs
- PATHWAY OF ANALYSES LEVELS (b) NAME. DISTANCE SAMPLED PERFORMED (NDL's)(a) Mean (Range) AND DIRECTION Mean (Range) Mean (Range) (c)
{
i 0 j K-40 -- 3.2 (2.4 - 5.0) Within 500 feet 3.4 (2.5 - 5.0) N/A of Discharge i
) Within 500 feet 0.002 (0.000 - 0.003) N/A 0
! Fish-Other Sr S 0.018 0.001 (-0.005 - 0.003) l (pC1/g) Sr-89 of Discharge I
Within 500 feet 0.004 (0.000 - 0.008) N/A 0
- Sr-90 0.009 0.004 (0.000 - 0.008) of Discharge J
0.00 N/A N/A N/A 0 Ge(L1) 8 0.056 l Cs-137 N/A N/A N/A 0
~
I-131 -- 0.00 N/A N/A N/7 0 J Cs-134 0.05 0.00 N/A N/A N/A 0 Mn-54 0.05 0.00 1
N/A N/A 0
) Co-58 0.05 0.00 N/A s
N/A N/A 0 Co-60 0.05 0.00 N/A N/A N/A 0 Zr-95 -- 0.00 N/A I
N/A N/A 0 Mb-95 -- 0.00 N/A
]
. _ . _ - _ _ _ _ _ . _ _ _ . _ _ . _ _ _ _-~. -._-_.__ _ .__ _ .-_.._-_ _ _ _ _ _ .- _ _..._ -..- ____ _ . _ .-_ _ _._ _ -._ _ _ - -- - - - . .
i T
l
! t I
i i .
I 1
TABLE 3-1 4 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SUp9tARY j MILLSTONE NUCLEAR POWER STATION. UNITS I and 2 i DOCKET 50-245 and 50-336 l l JANUARY - DECEMBER 1984 1
} ANALYSIS AND MINIM 3M ALL IN0!CATOR LOCATION WITH HIGHEST ANNUAL MEAN CONTROL LOCATIONS I
MEDIta OR TOTAL NUMBER DETECTABLE LOCATIONS f 0F PATHWAY CF ANALYSES LEVELS (b) NAME, DISTANCE (b) (b) NRMs SAMPLED PERFORMED (99L's)(a) Mean (Range) AND DIRECTION Mean (Range) Mean (Range) (c)
} K-40 -- 2.6 (1.7 - 3.3) Within 500 feet 2.7 (2.1 - 3.3) N/A 0
] of Discharge .
l r,
[ Itassals Sr 8.4 0.018 0.001 (-0.004 - 0.007) Golden Spur 0.003 (-0.002 - 0.010) 0.003 (-0.002 - 0.010)- 0 (pC1/g) 5r-89 4.7 Miles NNW 4 !
Sr-90 0.009 0.003 (0.002 - 0.005) Golden Spur 0.004 (0.003 - 0.007) 0.004 (0.003 - 0.007) 0 1 4.7 Miles NNW i
i Ge(LI) 8,4 0.056 0.00 N/A N/A 0.00 0 !
'f Cs-137 6 5 I-131 0.00 N/A 0.00 N/A 0 l
8 Cs-134 0.05 0.00 N/A N/A 0.00 0 i
i Mn-54 0.05 0.00 N/A N/A 0.00 0 i .
I Co-SS 0.05 0.00 N/A N/A 0.00 0 Co-60 0.05 0.00 N/A N/A 0.00 0 i >
j Zr-95 -- 0.00 N/A N/A 0.00 0 I
1 I
I'
i i
I J
l j
i l -
TABLE 3-1 i ENVIRONMENTAL RADIOLOGICAL PONITORING PROGRAM Sum ARY i MILLSTONE NUCLEAR POWER STATION. UNITS 1 and 2 1 DOCKET 50-245 and 50-336 3
JANUARY - DECEMBER 1984 l i
L ANALYSIS AND MINIMUM ALL INDICATOR LOCATION WITH HIGHEST ANNUAL MEAM CONTROL LOCATIONS
! MEDIt'M OR TOTAL NUMBER DETECTA8LE LOCATIONS f 0F l PATHWAY OF ANALYSES LEVELS (b) NAME. DISTANCE (b) (b) NRMs ,
i SAMPLED PERFORMED (MDL's)(a) Mean (Range) AND DIRECTION Mean (Range) Mean (Range) (c) '
} Mb-95 -- 0.00 Golden Spur 0.005 (0.00 - 0.022) 0.005 (0.00 - 0.022) 0
- 4.7 Miles NNW i i (1.0 - 1.6) Within 500 feet K-40 -- 1.4 1.5 (1.3 - 1.6) 1.0 (0.7 - 1.3) 0 i of Discharge b
i
, Oysters /Claes Sr 19.8 0.018 0.000 (-0.005 - 0.008) Giant's Neck 0.005 (-0.001 - 0.011) 0.00 (-0.005 - 0.011) 0 (pCi/g) 5r-89 3.5 Miles W l
Golden Spur #1 ,
Sr-90 0.009 0.003 (-0.002 - 0.011) 4.7 Miles NNW 0.006 (0.004 - 0.012) 0.006 (0.002 - 0.012) 0 ;
I 1 i i Ge(L1) 19.8 0.056 0.00 N/A N/A 0.00 0 I i Cs-137 !
t t i I-131 -- 0.00 N/A N/A 0.00 0 !
J ;
Mn-54 0.05 0.00 N/A N/A 0.00 0 !
I 4
I Co-58 0.05 0.00 N/A N/A 0.00 0 a
0 -
f Co-60 0.05 0.02 (0.00 - 0.23) Within 500 feet 0.10 (0.00 - 0.23) 0.00 0 i of Discharge I
i TABLE 3-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
MILLSTONE NUCLEAR POWER STATION, UNITS 1 and 2 DOCKET 50-245 and 50-336 JANUARY - DECEMBER 1984 ANALYSIS AND 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 SAPPLED PERFORMED (MDL's)(a) Mean (Range) AND DIRECTION Mean (Range) Mean (Range) (c)
In-65 0.11 0.00 N/A N/A 0.00 0 Zr-95 -- 0.00 (0.00 - 0.04) Within 500 feet 0.01 (0.00 - 0.04) 0.00 0 of Discharge Ag-110m -- 0.03 (0.00 - 0.25) Within 500 feet 0.12 (0.00 - 0.25) 0.00 1 of Discharge Thames River K-40 -- 1.3 (0.9 - 2.6) Yacht Club 1.6 (1.0 - 2.6) 1.1 (0.6 - 1.4) 0 4 Miles ENE Lobsters Sr 8.4 0.018 0.00 (-0.002 - 0.01) Within 500 feet 0.004 (0.00 - 0.01) 0.00 (-0.01 - 0.001) 0 (pCl/g) Sr-89 of Discharge Sr-90 0.009 0.008 (0.003 -0.015) Giant's Neck 0.011 (0.006 - 0.015) 0.01 (0.004 - 0.020) 0 3.5 Miles W Ge(L1) 8.4 0.056 0.00 N/A N/A 0.00 0 Cs-137 I-131 -- 0.C0 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 N/A 0.00 0
TABLE 3-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
MILLSTONE NUCLEAR POWER STATION, UNITS I and 2 DOCKET 50-245 and 50-336 JANUARY - DECEMBER 1984 MINIMUM ALL INDICATOR LOCATION WITH HIGHEST ANNUAL MEAN CONTROL LOCATIONS ANALYSIS AND TOTAL NUMBER DETECTABLE LOCATIONS i 0F MEDIEJ OR PATHWAY OF ANALYSES LEVELS (b) NAME, O! STANCE (b) (b) NRMs Mean (Range) AND O! RECT 10N Mean (Range) Mean (Range) (c)
SAMPLED PERFORMED (MDL's)(a)
Co-58 0.05 0.00 N/A N/A 0.00 0 0.05 0.01 (0.00 - 0.07) Within 500 feet 0.03 (0.00 - 0.07) 0.00 0 Co-60 of Discharge Ir-95 -- 0.00 N/A N/A 0.00 0 Mb-95 -- 0.00 N/A N/A 0.00 0 0.01 (0.00 - 0.04) 0.00 0 Ag-110s -- 0.005 (0.00 - 0.04) Niantic Bay 0.3 Miles WNW
FOOTNOTES
- a. For Ge(Li) measurements the MDL's E 2 x d2iiwhere 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. Anlytical 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 mean.
- c. Nonroutine reported measurements (NRM's) are defined in Section 5.6.2b of the Technical Specifications. These occur when a measurement is ten times the value for the control location (s)
(actually this turns out to be ten times the statistical error in determining the background since the background level is often zero). This results in reports when low levels of radioactivity are detected in the environment since background is measured with such a high degree of accuracy. The dose consequences are insignificant; see Section 5.0 for the discussion of these consequences.
- 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.
- h. N/A--Not Applicable.
3-17 I
3.2 Data Tables The data reported in this section are strictly counting statistics. The reported error is two times the standard deviation of the net activity. Unless otherwise noted, the overall error (counting, sample size, chemistry, errors, etc.)
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. Soi1**
- 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. Seawater
- 15. Bottom Sediment **
- 16. Aquatic Flora *
- 17. Fin Fish *
- 18. Mussels *
- 19. Oysters *
- 20. Clams *
- 21. Scallop (and crabs)*
- 22. Lobster (and crabs)*
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.
3-18
- - . - - . . =- - - . . . . _ - - _. .-
i.
k LOCATION KEY FOR DATA TABLES Data Table Section 2.0 Location # Location #
i 01 Old Millstone Rd. - NNW, 0.6 miles 1
! 02 Weather Shack - S, 0.3 miles 2 i 03 Bird Sanctuary - NE, 0.3 miles 3
- 04 Albacore Drive - N, 1 mile 4 l 05 Navy Laboratory - SSE, 0.2 miles 5 06 Quarry Discharge Canal Fence - SSE, 0.3 miles 6 07 Fox Island - SE, 0.3 miles 7 j
08 Millstone Environmental Lab - SE, 0.3 miles 8 l
09 Bay Point Beach - W, 0.2 miles 9
! 10 Plea;ure Beach - E, 1.2 mile 10
- 11 New London Country Club - ENE, 1.6 miles 11 12A,B Fisher's Island, New York - ESE, 8.7 miles 12 13A Mystic, Conn. - ENE, 11.5 miles 13 14A Ledyard, Conn. - NE, 11.5 miles 14 4 ISA Montville, Conn. - N, 14 miles 15 i 16A Old Lyme, Conn. W, 9 miles 16 j 17 Well #1 - NNE, 1.5 miles 17 i 18 Well #2 - NNE, 1 mile 18 I 19 Dairy Farm #1 - N, 6 miles 19 20 Dairy Farm #2 - WNW, 9.5 miles 20 21 Dairy Farm #3 - NE,11 miles 21 22A Dairy Farm #4 - NNW, 15 miles 22 23 Goat Farm #1 - ENE, 2 miles 23 i 24 Goat Farm #2 - NE,14 miles 24 25 Within 10 miles of Plant -
- 26A Beyond 10 miles of Plant -
l 30A Golden Spur - NNW, 4.7 miles 1 i
! 31 Niantic Shoals - NW, 1.8 miles 2 i 32 Within 500' of Discharge 3
! 33 Seaside Point - ESE, 1.6 miles 4 i 34 Thames River Yacht Club - ENE, 4.0 miles 5
! 35 Niantic Bay - WNW, 0.3 mile 6 l 36 Black Point - WSW, 2.6 miles 7 j 37A Giant's Neck - W, 3.5 miles 8
! 38 Waterford Shellfish Bed #1 - WNW, 0.5 miles 10 39B Jordan Cove - NNE, 0.2 miles -
40B Discharge Quarry -
r j SOB Myrock Avenue - ENE, 3.2 miles -
l SIB Groton Reservoir - ENE, 7.5 miles -
l' 52B Lake Konomoc - NNW, 7.5 miles -
53B Niantic (CL&P) - WNW, 1.7 miles -
, 54B Billow Road - WSW, 2.4 miles -
SSB Black Point - SW, 2.6 miles -
l i
A - Control Stations l B - Site not required by ETS i
Pf!LLSTONE POINT TABLE 14 710f4THLY SAtMA EXPOSURE RATE (UR/HR)
PERIOD LOCATIONS ENDItG 01 02 03 04 05 06 07 08 09 le !!
. ..... .................... .._ _ _ _ - _ _ _ _...............- _==...................._........
1/31/84(a) 7.9 (b) 12.5 7.7 7.9 7.2 8.2 9.9 9.8 10.1 8.2 7.5 2/28/84 8.7 13.5 8.4 8.8 7.6 9.3 10.9 10.7 10.8 8.6 7.6 3/31/84 8.9 13.6 8.4 8.9 7.7 8.9 10.9 11.1 !!.4 8.9 8.1 4/30/84 9.1 13.7 8.5 9.2 6.8 9.3 10.8 10.9 11.1 9.0 8.1 5/31/84 8.4 12.6 8.0 8.3 5.8 8.2 9.7 9.4 9.8 8.4 7.8 6/30/84 9.2 13.5 8.6 8.9 6.6 9.2 10.6 10.6 10.6 8.8 8.0 7/31/84 8.4 13.0 7.9 8.2 7.1 8.5 10.3 10.1 10.8 8.2 7.8 8/31/84 9.3 13.5 8.7 9.2 7.8 9.4 11.2 11.2 11.4 8.9 8.4 9/30/84 8.7 13.1 8.2 8.6 7.5 8.6 10.5 10.7 11.2 8.9 8.3 10/31/84 9.7 14.2 9.2 9.5 8.6 9.9 11.9 !!.8 12.1 9.6 9.0 11/30/84 9.5 14.0 8.8 9.2 8.1 9.2 11.3 11.2 11.4 8.9 8.8 12/31/84 9.5 13.8 9.1 9.2 8.0 9.8 11.4 !!.2 11.5 9.1 8.7 124 134 144 15A 164 503 538 548 558
___ __.__ _ _ _ . . . = _
1/31/94 7.9 7.9 10.1 7.8 7.3 7.5 7.5 7.8 6.9 2/28/84 8.1 9.3 11.2 8.9 8.0 8.9 8.7 9.0 7.5 3/31/84 8.6 9.1 11.3 8.6 8.3 8.4 8.3 8.8 7.8 4/30/84 7.9 9.7 11.6 9.5 8.4 9.2 9.0 9.2 8.1 5/31/84 8.6 8.1 10.4 7.8 7.8 8.0 7.7 8.2 7.4 6/30/84 7.5 9.7 11.5 9.4 8.3 9.0 8.9 9.1 8.0 7/31/84 8.1 8.6 11.0 8.3 7.8 8.1 7.6 8.1 7.2 8/31/84 8.0 9.4 10.9 9.1 8.3 9.0 8.8 9.3 8.0 9/30/84 8.5 9.1 11.5 8.8 7.9 8.2 8.0 8.5 7.6 10/31/84 8.6 10.2 12.0 9.8 8.7 9.4 9.3 10.1 8.2 11/30/84 8.7 9.0 11.5 8.9 8.4 8.8 8.7 9.1 8.2 12/31/84 8.7 9.8 11.5 9.4 8.3 8.9 9.2 9.7 8.2 TABLE IB set 1IAt#fJAL GAttfA EXPOSURE RATE (LE/HR)
PERIOD L0 CATIONS EtcIts 01 02 03 04 05 06 07 08 09 10 11 6/30'84 8.7 13.2 8.3 8.7 6.9 8.8 10.5 10.4 10.6 8.6 7.8 12/31/84 9.2 13.6 8.6 9.0 7.8 9.2 11.1 11.0 11.4 8.9 8.5 12A 134 144 154 16A SOS 538 548 558 6/30/84 8.1 9.0 11, 8.7 8.0 8.5 8.3 8.7 7.6 12/31/84 8.4 9.3 11.4 9.0 8.2 8.7 8.6 9.1 7.9 (a) Not actual dates. TLD's are changed near the end of each month.
(b) Results are +/- 10%.
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TABLE 4A AIR PARTICULATES MP GAMMA SPECTR A - JAN IFCI/MS)
ANALYSES CS-137 CS-134 RU-103 ZR-95 RUERHI-106 K-40 TH-228 BE-7 H5-95 LOCATION .... ..........
-- ..____- --- ....___ =-= ............ _____ - .... ....________ ==--
(+/-l (+/-) (+/-) (+/-) (+/-) (+/-) (+/-l (+/.) (+/.)
1 0.0 0.002 0.0 0.002 0.0 0.003 0.0 0.005 0.0 0.020 0.0 0.020 0.0 0.004 0.100 0.030 0.0 0.004 2 0.0 0.002 0,0 0.002 0.0 0.003 0.0 0.003 0.0 0.012 0.0 0.014 0.0 0.004 0.070 0.000 0.0 0.003 3 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 0.006 0.090 0.040 0.0 0.006 4 0.0 0.002 0.0 0.002 0.0 0.004 0.0 0.005 0.0 0.000 0.0 0.030 0.0 0.005 0.100 0.030 0.0 0.004 10 0.0 0.002 0.0 0.002 0.0 0.004 0.0 0.005 0.0 0.000 0.0 0.000 0.0 0.005 0.110 0.030 0.0 0.005 11 0.0 0.003 0.0 0.004 0.0 0.006 0.0 0.005 0.0 0.030 0.0 0.040 0.0 0.006 0.090 0.040 0.0 0.006 0.001 0.0 0.002 0.0 0.002 0.0 0.003 0.0 0.010 0.030 0.030 0.0 0.003 0.000 0.020 0.0 0.002 12A 0.0 134 3.0 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.C05 0.070 0.030 0.0 0.004 14A 0.0 0.003 0.0 0.003 0.0 0.006 0.0 0.007 0.0 0.000 0.0 0.030 0.0 0.006 0.080 0.040 0.0 0.006 ISA 0.0 0.002 0.0 0.003 0.0 0.004 0.0 0.006 0.0 0.000 0.0 0.030 0.0 0.006 0.100 0.030 0.0 0.005 16A 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 0.0!O 0.030 0.0 0.004 53B 0.0 0.002 0.0 0.003 0.0 0.005 0.0 0.00$ 0.0 0.000 0.0 0.030 0.006 0.006 0.090 0.040 0.0 0.006 TABLE 4B AIR PARTICULATES GAMMA SPECTRA - FEB (FCI/N3)
ANALYSES CS-134 RU-103 ZR-95 RUtPH3-106 K-40 TM-228 BE-7 NS-95 LOCATION CS-137 .. . ._ - .... .
1+/-) (+/-) (+/-) (+/-l (+/-) (+/-l (+/-l (+/.I (+/ I 1 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 0.004 0.050 6.320 0.0 0.003 2 0.0 0.002 0.0 0.002 0.0 0.003 0.0 0.004 0.0 0.014 0.0 0.002 0.0 0.005 0.090 0.000 0.0 0.003 3 0.0 0.003 0.0 0.004 0.0 0.006 0.0 0.009 0.0 0.030 0.0 0.040 0.0 0.009 0.100 0.040 0.0 0.006 4 0.0 0.003 0.0 0.003 0.0 0.004 0.0 0.006 0.0 0.000 0.060 0.050 0.0 0.008 0.080 0.030 0.0 0.004 10 0.0 0.002 0.0 0.002 0.0 0.004 0.0 0.005 0.0 0.000 0.0 0.000 0.0 0.005 0.090 0.030 0.0 0.003 11 0.0 0.003 0.0 0.004 0.0 0.006 0.0 0.00$ 0.0 0.030 0.0 0.040 0.0 0.010 0.100 0.040 0.0 0.005 12A 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 0.090 0.030 0.0 0.003 13A 0.0 0.002 0.0 0.002 0.0 0.004 0.0 0.004 0.0 0.000 0.0 0.020 0.0 0.005 0.090 0.035 0.003 0.003 14A 0.0 0.003 0.0 0.003 0.0 0.005 0.0 0.008 0.0 0.030 0.0 0.030 0.0 0.008 0.0!0 0.040 0.0 0.006 0.004 0.0 0.004 0.0 0.006 0.0 0.009 0.0 0.030 0.0 0.040 0.0 0.009 0.140 0.040 0.0 0.005 ISA 0.0 164 0.0 0.002 0.0 0.002 0.0 0.003 0.0 0.005 0.0 0.000 0.0 0.030 0.0 0.004 0.0$0 0.000 0.0 0.003 538 0.0 0.003 0.0 0.002 0.0 0.004 0.0 0.005 0.0 0.000 0.0 0.030 0.0 0.006 0.060 0.030 0.0 0.003
, i
TABLE 4C AIR PARTICULATES MP GAMMA SPECTRA - PAR (PCI/H3)
ANALYSES RU-103 ZR-95 RUtRHI-106 K-40 TH-228 BE-7 NB-95 ,
LOCATION CS-137 CS-134 ............ j
--- =---___ _=-=-_=== _..... ..... ..____ ..... _ . ..._........ _
(+/-l t+/-l t+/-l (+/-l (+/.I (+/-)
(+/-l (+/-l t+/-l 0.002 0.003 0.005 0.0 0.020 0.0 0.000 0.0 0.005 0.090 0.030 0.0 0.003 1 0.0 0.002 0.0 0.0 0.0 0.003 2 0.0 0.002 0.0 0.002 0.0 0.003 0.004 0.003 0.0 0.020 0.0 0.000 0.0 0.004 0.090 0.020 0.0 3 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 0.070 0.040 0.0 0.006 4 0.0 0.003 0.0 0.003 0.0 0.005 0.0 0.006 0.0 0.030 0.0 0.040 0.0 0.007 0.060 0.030 0.0 0.004 0.002 0.005 0.0 0.020 0.0 0.000 0.0 0.006 0.I00 0.030 0.0 0.003 10 0.0 0.002 0.0 0.0 0.003 0.0 0.006 0.0 0.003 0.0 0.003 0.0 0.006 0.0 0.008 0.0 0.040 0.0 0.030 0.0 0.007 0.100 0.040 0.0 11 0.003 0.002 0.0 0.002 0.0 0.002 0.0 0.003 0.0 0.014 0.0 0.000 0.0 0.004 0.050 0.000 0.0 12A 0.0 0.004 134 0.J 0.002 0.0 0.002 0.0 0.004 0.0 0.005 0.0 0.020 0.0 0.030 0.0 0.006 0.I00 0.030 0.0 0.003 0.005 0.007 0.0 0.030 0.0 0.030 0.0 0.007 0.020 0.040 0.0 0.005 144 0.0 0.003 0.0 0.0 0.0 0.004 0.003 0.0 0.003 0.0 0.004 0.0 0.006 0.0 0.020 0.0 0.030 0.0 0.008 0.060 0.030 0.0 15A 0.0 0.003 16A 0.0 0.002 0.0 0.002 0.0 0.003 0.0 0.004 0.0 0.020 0.0 0.000 0.0 0.004 0.080 0.030 0.0 0.002 0.0 0.004 0.0 0.006 0.0 0.020 0.0 0.000 0.0 0.006 0.040 0.030 0.0 0.004 538 0.0 0.002 0.0 TABLE 40 AIR PARTICULATES GAMMA SPECTRA - APR (PCI/N3) e ANALYSES CS-134 20-103 ZR-95 RU(RH1-106 K-40 TH-228 EE-7 HB-95 LDCATIDH CS-137 =. ___ _=--- __ __... ............ ....--......
............ _ _ _ _ - _ __=-- ____ . - - - ....____ -- . __
(+/-l (+/-l (+/-l t+/-l (+/-) (+/-) (+/-l
(+/-l (+/-l 0.002 0.0 0.002 0.0 0.003 0.0 0.004 0.0 0.000 0.0 0.020 0.0 0.003 0.040 0.020 0.0 0.003 1 0.0 0.002 0.0 0.002 0.0 0.002 0.0 0.004 0.0 0.013 0.0 0.015 0.0 0.004 04060 0.000 0.0 0.003 2 0.0 0.006 0.0 0.000 0.0 0.030 0.0 0.006 0.030 0.030 0.0 0.004 3 0.0 0.003 0.0 0.003 0.0 0.005 0.0 0.004 4 0.0 0.003 0.0 0.002 0.0 0.004 0.0 0.006 0.0 0.000 0.0 0.000 0.0 0.006 0.050 0.030 0.0 0.002 0.0 0.003 0.0 0.004 0.0 0.020 0.0 0.000 0.0 0.004 0.060 0.000 0.0 0.004 IO 0.0 0.002 0.0 0.004 11 0.0 0.002 0.0 0.003 0.0 0.004 0.0 0.005 0.0 0.000 0.0 0.030 0.0 0.005 0.060 0.030 0.0 i 0.001 0.003 0.003 0.0 0.012 0.0 0.009 0.0 0.003 0.040 0.000 0.0 0.002 12A 0.0 0.002 0.0 0.0 0.0 0.002 0.0 0.002 0.0 0.002 0.0 0.003 0.0 0.003 0.0 0.015 0.0 0.020 0.0 0.004 0.070 0.000 0.0 13A 0.004 0.003 0.0 0.003 0.0 0.004 0.0 0.006 0.0 0.020 0.0 0.030 0.0 0.007 0.000 0.030 0.0 14A 0.0 0.003 0.002 0.0 0.002 0.0 0.003 0.0 0.004 0.0 0.000 0.040 0.040 0.0 0.005 0.060 0.020 0.0 ISA 0.0 0.003 0.002 0.0 0.002 0.0 0.003 0.0 0.003 0.0 0.015 0.0 0.020 0.0 0.004 0.040 0.020 0.0 16A 0.0 0.004 0.002 0.0 0.002 0.0 0.003 0.0 0.004 0.0 0.020 0.0 0.000 0.0 0.015 0.030 0.020 0.0 53S 0.0
_ - _ _ . - . - - - _ - . . . -. _ _- . _,.. _ - - ~ - - _ - .-
TABLE 4E MP AIR PARTICULATES GAMMA SPECTRA - MAY
( PCI/M3 9 ANALYSES NB-95 j
9U-103 ZR-95 RUtRHI-106 K-40 TM-228 BE-7
' LOCATION CS-137 CS-134 ............ _ - _ - - - - ............
(+/-l t+/-) (+/-) (+/-l t+/-l
(+/-) (+/-l I+/-) (+/-l 0.004 0.0 0.020 0.0 0.020 0.0 0.005 0.100 0.030 0.0 0.003 0.0 0.002 0.0 0.002 0.0 0.003 0.0 0.0 0.003 1
0.002 0.005 0.0 0.020 0.0 0.020 0.0 0.005 0.110 0.030
+ 2 0.0 0.002 0.0 0.0 0.003 0.0 0.030 0.000 0.100 0.040 0.0 0.004 0.003 0.0 '0.003 0.0 0.005 0.0 0.006 0.0 0.030 0.0 0.0 3 0.0 0.006 0.0 0.000 0.0 0.030 0.010 0.007 0.110 0.030 0.0 0.005 4 0.0 0.003 0.0 0.003 0.0 0.004 0.0 0.020 0.030 0.003 0.002 0.0 0.004 0.0 0.020 0.0 0.002 0.0 0.005 0.0 10 0.0 0.002 0.0 0.0 0.003 0.030 0.009 0.110 0.040 0.0 0.005 l
0.003 0.0 0.003 0.0 0.005 0.0 0.007 0.0 0.030 0.0 0.0
] 11 0.0 0.004 0.015 0.0 0.015 0.0 0.004 0.060 0.020 0.0 0.003 12A 0.0 0.002 0.0 0.002 0.0 0.003 0.0 0.0 0.0 0.003 l
0.002 0.002 0.004 0.0 0.020 0.0 0.020 0.0 0.004 U.080 0.020 134 0.0 0.002 0.0 0.0 0.0 0.030 0.007 0.090 0.040 0.0 0.005 l
0.0 0.003 0.0 0.004 0.0 0.005 0.0 0.008 0.0 0.030 0.0 0.0
! 14A 0.004 0.0 0.005 0.0 0.020 0.0 0.020 0.0 0.006 0.110 0.030 0.0 0.004 15A 0.0 0.002 0.0 0.002 0.0 0.004 0.003 0.002 0.003 0.0 0.004 0.0 0.000 0.0 0.020 0.0 0.110 0.030 0.0 l 16A 0.0 0.002 0.0 0.0 0.004 0.0 0.009 0.070 0.040 0.0 0.005 5 38 0.0 0.003 0.0 0.004 0.0 0.006 0.0 0.006 0.0 0.030 0.0 .
i S
- TABLE 4F t
I AIR PARTICULATES GAMNA SPECTRA - JUN i (PCI/N31 i
1 ANALYSES ZR-95 RUIRHI-106 K-40 TM-228 BE-7 NB-95 4 LOCATION CS-137 CS-134 RU-103 -.
? - ... _ -____- ..._
(+/-) (+/-) (+/-) (+/-) (+/.I
(+/-l (+/-) (+/-) (+/-)
0.003 0.0 0.005 0.0 0.020 0.0 0.020 0.0 0.005 0.100 0.030 0.0 0.004 ;
I 0.0 0.002 0.0 0.002 0.0 0.150 0.030 0.003 0.002 0.0 0.003 0.0 0.004 0.0 0.020 0.0 0.020 0.0 0.005 0.0 i 2. 0.0 0.002 0.0 0.030 0.009 0.120 0.040 0.0 0.005 0.0 0.003 0.0 0.004 0.0 0.005 0.008 0.007 0.0 0.030 0.0 0.0 3
0.006 0.0 0.030 0.090 0.050 0.0 0.006 0.120 0.040 0.0 0.004 t 4 0.3 0.003 0.0 '0.003 0.0 0.005 0.0 0.030 0.005 0.110 0.030 0.0 0.004 0.002 0.0 0.002 0.0 0.004 0.0 0.006 0.0 0.020 0.0 0.0 10 0.0 0.033 0.008 0.1E0 0.050 0.0 0.006 0.0 0.003 0.0 0.004 0.0 0.006 0.0 0.006 0.0 0.030 0.0 0.0 i j 11 0.0 0.004 0.020 0.0 0.020 0.0 0.005 0.090 0.030 0.0 0.003 12A 0.0 0.002 0.0 0.002 0.0 0.003 0.0 0.002 0.0 0.003 0.005 0.0 0.000 0.040 0.040 0.0 0.005 0.150 0.030 0.0 0.003 ;
13A 0.0 0.002 0.0 0.0 0.040 0.160 0.050 0.0 0.005 J
0.003 0.0 0.004 0.0 0.005 0.0 0.007 0.0 0.030 0.0 0.010 0.008 t 144 0.0 0.140 0.040 0.0 0.004 154 0.0 0.003 0.0 0.003 0.0 0.004 0.0 0.006 0.0 0.030 0.0 0.040 0.0 0.007 0.005 0.020 0.0 0.030 0.0 0.006 0.120 0.030 0.0 0.004 .
16A 0.0 0.002 0.0 0.003 0.004 0.004 0.0 0.0 0.140 0.050 0.005 0.004 0.006 0.007 0.0 0.0 30 0.0 0.005 0.0 0.009 0.0
. 538 0.0 0.004 0.0 0.0 0.0 i
+
i 1
I I
I i
n-_-______--__--____ _ --- -.
TABLE 4G AIR PARTICULATES MP GAMMA SPECTPA . JUL (PCI/H3)
ANALYSES LOCATION CS-137 CS-134 RU-103 ZR-95 RUIRH)-106 K-40 TM-228 BE-7 H5-95
............ ...=- __-- ............ ............ ............ ............ ............ ............ ............
(+/.I (+/-) (+/-) (+/-) (+/-) (+/.I (+/-l to/-) (+/-l 1 0.0 0.002 0.0 0.002 0.0 0.004 0.0 0.004 0.0 0.014 0.030 0.030 0.0 0.005 0.060 0.020 0.0 0.004 2 0.0 0.002 0.0 0.002 0.0 0.003 0.0 0.004 0.0 0.014 0.0 0.013 0.0 0.004 0.090 0.030 0.0 0.003 3 0.0 0.002 0.0 '0.003 0.005 0.004 0.0 0.006 0.0 0.030 0.060 0.050 0.0 0.007 0.050 0.030 0.0 0.005 4 0.0 0.003 0.0 0.003 0.0 0.004 0.0 0.004 0.0 0.020 0.0 0.020 0.0 0.006 0.060 0.030 0.0 0.004 10 0.0 0.002 0.0 0.002 0.0 0.004 0.0 0.005 0.0 0.000 0.0 0.020 0.0 0.005 0.060 0.030 0.0 0.003 11 0.0 0.003 0.0 0.003 0.0 0.005 0.0 0.005 0.0 0.030 0.0 0.030 0.0 0.006 0.090 0.040 0.005 0.005 12A 0.0 0.001 0.0 0.001 0.0 0.003 0.0 0.004 0.0 0.014 0.0 0.0*0 0.0 0.003 0.040 0.020 0.0 0.003 13A 0.0 0.002 0.0 0.001 0.0 0.003 0.0 0.003 0.0 0.012 0.0 0.020 0.0 0.003 0.070 0.020 0.0 0.003 144 0.0 0.003 0.0 0.003 0.0 0.005 0.0 0.006 0.0 0.000 0.0 0.030 0.006 0.006 0.070 0.030 0.0 0.006 ISA O.0 0.002 0.0 0.002 0.0 0.004 0.0 0.005 0.0 0.000 0.0 0.002 0.0 0.005 0.100 0.030 0.004 0.004 16A 0.0 0.001 0.0 0.002 0.0 0.004 0.0 0.004 0.0 0.020 0.0 0.000 0.0 0.005 0.060 0.030 0.0 0.003 538 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 0.000 0.030 0.0 0.005 TABLE 4H AIR PARTICULATES GAMMA SPECTRA - AUG (PCI/H3)
ANALYSES LOCATION CS-137 CS-134 RU-103 ZR-95 FUtRH)-106 K-40 TH-228 EE-7 IS-95
............ _ _===.. _-__ -- ..._ ___-- ....-------- ....---..... .-----...... ............ ___ _._
(+/.) (+/-) (+/-) (+/-) (+/.) (+/-) (+/.) (+/.) (+/.)
1 0.002 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 0.070 0.0:0 0.0 0.003 2 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 0.006 0.110 0.030 0.0 0.004 3 0.0 0.003 0.0 0.004 0.0 0.004 0.0 0.003 0.0 0.030 0.0 0.030 0.0 0.00S 0.090 0.040 0.0 0.005 4 0.0 0.003 0.0 0.003 0.0 0.005 0.0 0.007 0.0 0.000 0.0 0.040 0.0 0.007 0.130 0.040 0.0 0.005 10 0.0 0.002 0.0 0.003 0.0 0.003 0.0 0.005 0.0 0.000 0.0 0.030 0.0 0.006 0.090 0.030 0.0 0.004 11 0.0 0.004 0.0 0.004 0.0 0.006 0.0 0.006 0.0 0.030 0.0 0.030 0.0 0.009 0.090 0.040 0.0 0.006 12A 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 0.0 0.020 0.0 0.004 134 0.0 0.002 0.0 0.003 0.0 0.004 0.0 0.006 0.0 0.000 0.0 0.030 0.0 0.006 0.0$0 0.030 0.0 0.004 14A 0.0 0.003 0.0 0.004 0.0 0.005 0.0 0.007 0.0 0.030 0.0 0.040 0.0 0.006 0.080 0.040 0.0 0.006 154 0.0 0.003 0.0 0.003 0.0 0.004 0.0 0.005 0.0 0.000 0.0 0.030 0.0 0.004 0.110 0.030 0.0 0.004 16A 0.0 0.002 0.0 0.002 0.0 0.003 0.0 0.005 0.0 0.000 0.0 0.020 0.0 0.006 0.0S0 0.030 0.0 0.004 535 0.0 0.003 0.0 0.004 0.0 0.006 0.0 0.009 0.0 0.030 0.0 0.040 0.0 0.007 0.090 0.040 0.0 0.006
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TABLE 4K AIR PADTICULATES MP GAMMA SrtCTRA - H0Y IPCI/N31 ANALYSES ZR-95 RUtRHi-106 K-40 TH-228 BE-7 HS-95 LOCATIDH CS-137 CS-134 PU-103 -
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ANALYSES ZR-95 PU(RHI-106 K-40 TH-228 EE-7 HB-95 LOCATIDH CS-137 CS-134 RU-103 _-- __ . -_ -____
(+/-l t+/-l (+/-l (+/-) (+/-l (+/.I
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TABLE 10 WELL WATER f1P tFCI/L)
COLLECTION LOCATION DATE SR-89 SR-90 CS-137 I-131 CS-134 t94-54 CO-58
(+/-) (+/.) (+/ ) (+/-) (+/-) (+/-) (+/.)
17 6/12/84 0.5 0.4 0.5 0.1 0.0 3.0 C. 6. O. 4 O. 3. O. 3.
17 9/19/84 0.2 0.4 0.3 0.2 0.0 3.0 0. 9. O. 4. O. 3. O. 3.
18 6/12/84 0.4 0.4 0.3 0.1 0.0 3.0 0. 6. O. 3. O. 3. O. 3.
18 9/19/84 -0.2 0.6 0.8 0.2 0.0 3.0 0. 8. O. 3. O. 3. O. 3.
CO-60 FE-59 ZN-65 ZR-95 RutRH3-106 CR-51 K-40
(+/.) (+/-) (+/-) (+/-) (+/-) (+/-) (+/ )
17 6/12/84 0. 3. O. 7. O. 8. O. 5. O. 30. O. 30. O. 30.
17 9/19/84 0. 3. O. 8. O. 8. O. 6. O. 30. O. 30. O. 30.
18 6/12/84 0. 3. O. 7. O. 7. O. 5. O. 30. O. 30. O. 30.
18 9/19/84 0. 3. O. 8. O. 7. O. 6. O. 30. O. 30. O. 30.
t 4
RA-226 TH-228 BE.7 NB-95 H-3 GDOSS EETA
_ _ _ _ _ = = = _ _ _ ___ --_-__==- ...._--_ __ ...... .__ ...--......... ..............
(+/-) (+/-) (+/-) (+/.) (+/-) (+/.)
17 6/12/84 52. 7. O. 8. O. O. O. 3. 130. 100. 3.7 0.6 17 9/19/84 86. 6. O. 9. O. O. O. 3. O. 60. 7.0 0.8 18 6/12/84 17. 6. O. 8. O. O. O. 3. 170. 120. 1.1 0.4 18 9/19/84 0. 6. O. 8. O. O. O. 3. 210. 60. 5.0 0.6 m
k h
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TABLE 11 RESERVOIR WATER PAGE 1 MP (FCI/L)
COLLECTION CO-58 SR-89 SR-90 CS-137 1 131 CS-134 (14-54 LOCATION DATE
(+/.) (+/.) (+/-) (+/-) (+/.)
(+/-) (+/.)
l FE-59 ZH-65 ZR-95 RUIPHI-106 CR-51 K-40 CO-60 ...... .............. ,
(+/.) (+/-) (+/-) (+/.) (+/.)
(+/-) (+/.)
1 RA-226 TH-228 BE-7 NB-95 H-3 GROSS BETA
(+/-) (+/-) (+/-) (+/-) (+/-)
(+/-)
i t
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tas 4 N N mie =e
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1 TABLE 13 MEAT, POULTRY & EGGS (a) MP (PCI/Gl a
COLLECTION tie-54 j LOCATION DATE TYPE SR-89 SR-90 CS-137 I-131 CS-134
(+/-) (+/-) (+/-) (+/-) (+/-)
(+/-)
CO-58 CO-60 FE-59 ZH-65 ZR-95 PUERHi-106
.............. .._ =....... .............. .--- __--___-_ .............. ...-_
(+/-l (+/-) (+/-) (+/-) (+/-l
' (+/-)
CR-51 K-40 RA-226 TH-228 BE-7 NB-95
. . . . = - - _ _ _ _
(+/-I (+/-) (+/-l (+/-) (+/-l (+/-)
i 1
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(a) Commercial samples for which feed was grown within 10 miles of the station were not available in 1984.
4 i
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& d44M 4444 .
0 0000 0000 0000 E 4 ettfM dtdM \ b @ t= @ b b f* @ f* b t* @ b @ f* @
9 \ +
O + O iw 8w C 9 6 C 5 g e e . e e e e . . . . . . e e o e e * * . e e e me e . . . e e e e OOOO C000 0000 0000 0000 0000 ea DOOM 0000 mO@P @@md WNmm Mm@@
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4.0 DISCUSSION OF RADIOCHEMICAL RESULTS j Gamma Exposure Rate (Table 1)
The gamma exposure rate is determined from the integrated exposure '
measured over a time period of approximately one month using CaF 2(Mn) thermoluminescent dosimeters. These glass bulb dosimeters are subject- to inherent self-irradiation which has been experimentally l measured for each dosimeter. Consequently, the results shown in Table 1 have been adjusted for self-irradiation effects. The range of this correction is 0.3 uR/hr to 1.7 uR/hr with a mean of approximately i
1 uR/hr. !
The exposure rate measurements demonstrate the general variations in natural background radiation between the various on-site and off-site locations. These measurements exhibit the same trends as those j since 1978 and include gamma exposure from all sources including i cosmic, terrestrial, and artificial radioactivity. In particular, the Weather Shack (location 02) experiences higher exposure rates due to its proximity to granite beds while the Ledyard location (location 14A) experiences relatively higher background exposure rates than the other control locations at Mystic, Montville, and Old j Lyme (locations 13A, 15A, and 16A).
4 Further evaluation of the monthly data reveals a decrease in background during January of 1984, most probably caused by the extraordinary large snowfall during this month and its resultant shielding effect. Another decrease at some of the on-site locations only, is noted during the months of May and June. .The data during this time j frame indicates exposure levels slightly lower at some of the J on-site locations (Weather Shack (02), Navy Laboratory (05), Fox
- Island (07), Millstone Environmental Laboratory (08), and Bay Point 4
Beach (09)). This effect is attributable to Unit I being shutdown for refueling and is consistent with data of past years. During 4 Unit 1 operation, a small increase in exposure rates is caused by the direct exposure pathway of "skyshine" (i.e., scattered radiation l
from nitrogen-16 decay in the turbine; this pathway is unique to j boiling water reactors). This direct exposure pathway decreases rapidly with distance from the turbine building, to levels that are i virtually undetectable at the off-site locations. Special surveys performed during 1980 with a high pressure ion chamber support this i premise. The maximum off-site direct exposure due to Unit I was determined to be 0.2 uR/hr. The dose consequence attributable to
{ the direct dose is discussed in Section 5.0.
Increased exposure rate levels occurred during the 4th quarter of 1984. The 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 i was placed into service and measured exposure rates have increased I
to the magnitude of rates of years past.
With the installation of the augmented off-gas treatment system in May of 1978, the plant effluents have decreased significantly to 4-1
. - _. _ _ _ _ _ _. -_ _ _ _ . . - _ , . _ _ . - _ . _ . _ . , - . _ _ _ _ _ . . _ - _ . _ . ~ . _ _ . . _ _ _ . .
i levels that are essentially undetectable by TLD's, even at the onsite monitoring stations. The only appreciable effect, aside from that of skyshine, seen in the TLD data is that attributable to the variation in the background radiation which has been noted as being consistent with previous years.
i Air Particulates and Iodine (Tables 2, 3, 4A-L and 5) 1 Air is continuously sampled at seven inner ring and five outer ring locations by passing it through glass fiber particulate filters.
i The filters are collected weekly and analyzed for gross beta activity.
l Results are shown in Figure 4-2 and Table 2. Gross beta activity remained at levels similar to those seen in 1982-1983. It failed to
- show the typical increase in gross beta activity in the spring and summer due to atmospheric nuclear testing in the northern hemisphere as seen in 1981 and years prior to 1979 when above ground weapons testing had taken place. Also noted in Figure 4-2, there was only j a slight variation between the activity measured at the inner and outer monitoring stations and as such, it is concluded that the 4 plant contribution is negligible.
I 1 Charcoal cartridges are included at six of the air particulate i stations for the selective coIIection of atmospheric iodine. These cartridges are analyzed on a weekly basis for I-131. Data in
] Table 3 shows seven samples where I-131 was detected above its HDL y
and many other numerous positive values. However, these occur at both indicator and contrcl locations and are, therefore, attributable to statistical fluctuations in counting rather than actual I-131.
l 1 This premise is supported by the absence of I-131 in any of the cow i milk samples. Milk from cows are much more sensitive indicators of i environmental I-131.
! The air particulate samples that are utilized for the weekly gross
! beta analyses are composited monthly and analyzed for gamma emitting isotopes. The results, as shown in Tables 4A-4L, indicate the presence of naturally occurring Be-7, which is produced by cosmic j processes. All other positive results are attributable to statistical fluctuations in counting. These analyses indicate the lack of plant j effects.
l For the measurement of Sr-89, Sr-90 and total cesium (Cs), the air i particulate filters are composited quarterly and analyzed by radio-chemical separation and appropriate counting techniques. The results presented in Table 5 are much more sensitive indicators of i
j environmental radioactivity than gamma spectrum analyses, because of j the larger sample volume as a result of compositing and the higher efficiency of beta counting. However, this higher sensitivity tuffers from the drawback that it does not allow the separation of Cs-137 and Cs-134. Therefore, the results presented in Table 5 include total cesium along with Sr-89 and Sr-90. The cesium levels, l
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.
4-2
. - - . ~ . . - --
The Sr-90 results exhibit the same trends as the gross beta and Cs-137 results, remaining at low levels throughout 1984. As usual, with the absence of fresh fallout, there were no detectable levels of Sr-89 observed. Since there was no difference in measured levels of Sr-90 between indicator and control locations and no measurable Sr-89, there are no indications of any plant effects.
Soil (Table 6)
Soil samples are collected annually at six of the air particulate monitoring locations. These samples are analyzed for strontium and gamma emitting radionuclides. Detectable activity in soil samples consisted of the fallout related nuclides of Sr-90 and Cs-137 and the naturally occurring radionuclides, K-40, Ra-226 and Th-228. The similarity of Sr-90 and Cs-137 levels to those observed for the past ten years and the absence of the short lived nuclide of Sr-89 once again indicate that these two nuclides result from weapons testing and not from plant releases.
Cow Milk (Table 7)
The most sensitive indicator of fission product existence in the 7
terrestrial environment is usually the analysis of milk samples.
Airborne releases will typically be detected first in this media.
This in combination with the fact that milk is a widely consumed food results in this pathway being the most critical. This pathway also shows significant amounts of weapons testing fallout. Therefore, this media should be carefully evaluated when trying to decipher what are the actual plant effects.
Sr-90 and Cs-137 were routinely observed at levels similar to those of the past. The three indicator locations exhibited higher values than the control location. The range of results were 2.6 to 13.7 pCi/1 and 0 to 41 pCi/1 for Sr-90 and Cs-137, respectively. Detailed analysis of this data has conel.uded that these levels are from weapons testing and are not plant related (see Section 6.0 for details to this argument). Sr-89 was not detected above the random fluctuations in counting statistics. This is one indication that the presence of Sr-90 is the result of weapons testing. Sr-89 has only been seen in these samples during episodes of fresh fallout from weapons testing.
Prior to 1982, Cs-137 for these samples was determined by cesium chemistry and represented as total cesium. Analyses for the past few years by gamma spectrometry have confirmed the cesium to be Cs-137. Cesium chemistry allows a higher degree of sensitivity but suffers the problem of possible interferences from other nuclides, specifically Cs-134. In order to maintain " state-of-the-art" techniques, the gamma spectrometry has been improved and cesium chemistry discontinued. The only other nuclide detected by gamma spectrometry was K-40.
No samples showed I-131 detectable at levels greater than the MDL of 0.5 pCi/1. These results are consistent with previous y ers' i 4-3 l
.. .- = _- . -_ ...-.
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l i results. Only during periods immediately following atmospheric testing of nuclear weapons is I-131 usually detected.
Goat Milk (Table 8)
Goat milk samples can be a more sensitive indicator of fission products in the terrestrial environment than cow milk samples. This i is dependent on a number of parameters, including: metabolism of these animals, feeding habits, and feed type. Samples taken during i weapons testing periods have demonstrated higher uptake of fresh fallout nuclides (Sr-89 and I-131) at the indicator goat location.
This reason helps to explain the usual, higher than normal Sr-90 and Cs-137 concentrations at the indicator location as compared to the control location. One Sr-89 value exists above the MDL but is due l
to statistical fluctuations in counting (confirmed by the fact that a couple of large negative values also appear). The absence of detectable Sr-89 seems to indicate the lack of any plant effects.
Therefore the levels of Sr-90 and Cs-137, consistent with those of cow milk, are due to the influence of previous fallout. For a complete discussion of the variability of these nuclides, see Section 6.0.
Two samples had an I-131 concentration above its MDL. Other positive values were detected below the MDL. These levels are probably plant related and as such the dose consequence is discussed in Section 5.0.
Pasture Grass (Table 9)
When the routine milk samples are unavailable, samples of pasture grass are required as a replacement. These samples may also be taken to further investigate the levels of radioactivity in milk.
In February, these samples were not available as a replacement at l 1
either goat location. The data listed in this table are actually the results for samples of broad leaf vegetation. Two samples were l
- collected in June and September as part of a new program. The
! presence of Sr-90 and Cs-137 in these samples is consistent with values seen in pasture grass samples of past years. Their presence is most probably due to fallout. Because of the lack of Sr-89 and i
Cs-134 in these samples, it is concluded that no plant effects are seen in this media. 4 Well Water (Table 10) i i The only detectable activity above the respective MDL's in well water samples was that of H-3 and gross beta. Sr-90 was measured in all samples, in all cases below its MDL. All were detected at
~
i levels similar to those'of the past eight years; comparable to background concentrations shown at other locations (e.g., see Haddam i Neck Station Radiological Environmental Monitoring Program). There i
was no station related activity measured in this media.
i 4-4 l
Reservoir Water (Table 11)
Reservoir water samples are special samples not required by the Environmental Technical Specifications. Previous data has shown the lack of detectable station activity in this media. This fact and the extremely unlikely possibility of observing routine plant effluents in this media has resulted in discontinuing these samples.
In the event of widespread plant contamination, these samples would be collected.
Fruits and Vegetables (Table 12)
Consistent with past years, this media did not show any plant effects. Concentrations of Sr-90 and Cs-137 remained at levels similar to those observed for the past eight years. The absence of detectable Sr-89 indicates that the Sr-90 is from weapons fallout.
The only other activity detected was naturally occurring K-40.
Meat, Poultry, and Eggs (Table 13)
The Environmental Technical Specifications require that these samples be collected on an annual basis if they are available and if their feed is grown within 10 miles of the station. However, no such samples were available, therefore, none were obtained.
Sea Water (Table 14)
These quarterly composites of weekly grab samples show similar results to that of the previous seven years. The only detectable activities observed above the respective MDL's are for K-40, H-3, Beta Fraction II and Beta Fraction IV. Sr-90 was detected, below its MDL, at positive levels relatively consistent among locations, suggesting that these levels are due solely to fallout. Typical background levels of H-3 are shown in all samples. This is unlike 1981 and 1983 when some plant related activity was detected. Values for Beta Fraction II were consistent among locations while that for Beta Fraction IV was higher at two of the indicator locations. The variability is within detection limits, therefore, no plant effects are observed.
Bottom Sediment (Table 15)
Similar to previous years, most bottom sediment samples exhibited the presence of the naturally occurring radionuclides of K-40, Ra-226 and Th-228. Cosmic produced Be-7 was also observed in a few samples near its detection limits. Some of the samples exhibited positive values of Sr-90 at levels below its MDL. No detectable Sr-89 was observed. Cs-137 was detected at a level above the MDL at an indicator location. However, the dose consequence of such a level is much lower than those discussed in Section 5.0 and, therefore, is considered insignificant. Traces of Cs-137 were detected in a few other samples, however, its values do not increase with proximity to the plant. Therefore these values seem fallout related.
4-5
Aquatic Flora (Table 16)
Consistent with previous observations, the naturally occurring radionuclide, K-40, was observed in all of the aquatic flora samples.
Sr-90 was also observed in all samples at positive levels, usually below the MDL. Due to its consistency and the absence of detectable Sr-89, it is believed to be a result of weapons fallout and not plant related. Like the samples from 1983, there was no I-131 seen in these samples. However, there were other indications of plant effluents in this media. Co-58 and Co-60 were observed at levels near those of 1983. These levels are well below those seen in 1975-1976.
Sampling of this media provides useful information because it is very sensitive to plant discharges. However, since seaweed in this area is not consumed, other media are utilized in the determination of dose consequences (e.g., see shellfish and fish results).
Fish Flounder (Table 17A) ,
The activity in this media is the same as that for the past eight years. The Sr-90 data consistently showed positive values, usually at levels below its MDL. The only other radionuclide detected above the MDL was naturally occurring K-40. Therefore, it is concluded that plant effects for this sampling media are insignificant at all locations.
Fish - Other (Table 17B)
Except for the quarry location, these fish samples exhibited data similar to the flounder samples. For the off-site samples, the only detectable activity seen above the MDL was K-40. However, as in previous years some traces of plant related activity (Cs-137, Cs-134, and Co-60) were detected in one of the quarry samples (i.e.,
location 40B). The quarry location is not accessible to members of the general public and with the dilution of the Long Island Sound, the levels of radioactivity become undetectable in these samples outside of the quarry. Hcwevec, using the concentrations measured in the quarry and diluting tbtm by the appropriate near field dilution factor for quarry discharges ini: the Sound, doses to the maximum individual can be calculated. See Section 5.0 for these results.
Mussels (Table 18)
As in previous years, positive values of Sr-89 and Sr-90 were observed in many of the samples at levels below their respective MDLs. The only other radioactivity observed in mussels consisted of naturally occurring K-40 and cosmic produced Be-7. Therefore, it is concluded that plant effects for this sampling media are insignificant at all locations.
Oysters (Table 19)
Native oysters are sampled at the Golden Spur (Location 30A) and Quarry Discharge (Location 40B) locations; the latter being an extra 4-6 1
location. The remaining locations utilize stocked oysters; trays are kept at these sampling areas to guarantee samples and facilitate sample collection. However, during the fourth quarter, the tray at Black Point (Location 36) was destroyed by surf action.
The primary activity in most samples continued to be K-40. Low positive values of Sr-90 were observed at random levels at all locations. Two samples show the level of Sr-90 just above the MDL.
However, both levels occur at control locations, too distant from the plant for the radioactivity to be plant related. Therefore, all levels of Sr-90 are probably just traces of fallout. Further confirmation of this is shown by the lack of detectable Sr-89.
Plant related activity is shown at two locations, the area within 500 feet of the discharge (Location 32) and the quarry discharge (Location 40B). This activity included Co-60, 2n-65, Ag-110m, and possible traces of Zr-95 and Ru-106. These locations are within the plant discharge area, the one within 500 feet is actually at the end of the quarry. Therefore, these samples tend to show higher levels of activity than the mussel, clam, and lobster samples. The levels of Co-60 and Ag-110m observed are similar to those seen for the past six years. Since these two sample locations are onsite and not available for public use, the actual concentration of radionuclides in oysters available for public consumption is much less. The dose consequence of radioactivity via this pathway is discussed in Section 5.0.
Clams (Table 20)
The predominant activity in clams was naturally occurring K-40.
Similar to the 1980 and unlike the 1981-1983 samples, plant related Co-60 was apparent in this sampling media. These samples further demonstrate that the activity seen in the oyster samples decreases rapidly with distance from the station.
Scallops (Table 21)
Samples for location 31B (Niantic Shoals) are scallops while for location 40B (Quarry Discharge) they are crabs. Neither of these species are required by the Environment Technical Specifications.
The only detectable activity seen in the scallop samples was naturally occurring K-40. Sr-90 was observed at positive levels usually below the HDL, but these levels are probably fallout produced. Two samples listed as being from location 40B (Discharge Quarry) are actually crab samples taken from the quarry. The crab samples showed plant related concentrations of Co-60, Ag-110ru and possible traces of Ru-106. As mentioned above, these samples are within the plant discharge, and as such, concentrations in food that the public consumes would be much less. See Section 5.0 for a discussion of the dose consequences.
i 4-7
Lobsters (and crabs) (Table 22)
Strontium analyses indicated the presence of Sr-90 in many of the samples, near and above the MDL, and Sr-89 below its MDL in all samples. The Sr-90 levels were, on the average, similar to past data. Due to the absence of detectable Sr-89, the Sr-90 is concluded to be fallout related and not a result of plant effluents. Aside from naturally occurring K-40, there were traces of plant related Co-60 and Ag-110m seen here. These levels were similar to past data.
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1 5.0 0FFSITE DOSE CONSEQUENCES )
The off-site dose consequences of the stations' radioactive liquid and airborne effluents have been evaluated using two methods.
The first method utilizes the stations' measured radioactive dis-charges as input parameters into conservative models to simulate the transport mechanism through the environment to man. This results in the calculation of the maximum dose consequences to individuals and the O to 50 mile population dose commitment. 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. This method, which is usually conservative (i.e. , computes higher doses than that which actually occur), has the advantage of approximating an upper bound to the dose consequences. This is important in those cases where the actual dose consequence cannot be measured because they are so small as to be well below the capabilities of conventional monitoring techniques.
The second method utilizes the actual measurements of the concentrations of radioactivity in various environmental media (e.g., milk, fish) and then computes the dose consequences resulting from the consumption of these foods.
The results of both methods are compared in Table 5.1 for those pathways where a potential dose consequence exists and a co p rison is possible. The doses presented in this table are the maximum doses to an individual. 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 external gamma dose is calculated for the site boundary location which is not only the nearest but also has the greatest directional wind frequency and fish and shellfish doses are calculated assuming they are from an area within 500 feet of the station discharge.
As indicated by Table 5.1, there is also a direct gamma dose attributable to the operation of Unit I. This direct dose is inherent to BWR's (Boiling Water Reactors) and is due to direct and scattered radiation (skyshine) of Nitrogen-16 high energy gamma rays from radioactive steam in the turbine. It should be noted that the indicated dose due to direct radiation is to the maximam individual and is corrected for periods when Unit I is not operating (i.e. , there is no direct dose when steam is not benerated). Summarizing the data in Table 5.1, the maximum total doses to an individual are: 1.5 mrem whole body to an adult, 3.2 mrem to an child's thyroid, and 0.05 mrem to an l
adult's GI (LLI) (gastrointestinal tract-lower large intestine).
I Since the maximum dose consequence to an individial is at the I
location of highest dose consequence, doses will be less for all other locations. The average dose to an individual within 50 miles from the site cannot be calculated using the second method. However, the first method yields the following results for the period January-
! December 1984 for the average individual:
5-1 l
. .. .-. - -. . . . . . - - .- .- .= _ =._ - . . . __ .
d 1
ANNUAL WHOLE BODY DOSE DUE TO AIRBORNE EFFLUENTS = 0.00076 mrem ANNUAL WHOLE BODY DOSE DUE TO LIQUID FFFLUENTS = 0.000098 mrem 4
Thus, it can be seen that the average dose to an individual is much less than the maximum dose to an individual.
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 j 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 l l fraction of the normal background radiation dose of 125 mrem per l year and are designed to be inconsequential in regard to public j health and safety. Since plant related doses are even a smaller l
fraction of natural background, they have insignificant public j health consequences. In fact, the plant related doses to the I maximum individual are less than of the variation in natural background i in Connecticut.
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_ - - _ _ . . - _ . - . . . . _ __ _ _- . -- - - - - _= . -- - _ _ - -
TABLE 5.1 COMPARISON OF DOSE CALCULATION METHODS MILLSTONE NUCLEAR POWER STATION JANUARY-DECEMBER 1984 ANNUAL DOSE * (MILLIREM)
PATHWAY ORGAN METHOD 1( METHOD 2( }
Unit 1 Unit 2 Total (BWR) (PWR)
AIRBORNE EFFLUENTS
- 1. External Gamuna Dose (2) Max. Ind.-Whole Body 0.036 0.110 0.15 0.07(5)
- 2. a. Inhalation Max. Ind.-Thyroid 0.0015 0.129 0.13 ND,( <0.6
- b. Vegetables Max. Ind.-Thyroid 0.0080 1.54 1.55 ND
- c. Goat's Milk Max. Ind.-Thyroid 0.065 1.43 1.50 1.1 LIQUID EFFLUEh"fS
- 1. Fish Max. Ind.-Whole .Rody 0.00010 0.0150 0.015 0.025 Max. Ind.-GI(LLI)( ) 0.00032 0.0149 0.015 0.010 Max. Ind.-Liver 0.00014 0.0201 0.020 0.034 0.0049 0.0009 )
- 2. Shellfish Max. Ind.-Whole Body 0.00009 0.0050 t Max. Ind.-GI(LLI) 0.00064 0.0287 0.029 0.040(
DIRECT DOSE
- 1. Skyshine Max. Ind.-Whole Body 1.3( N/A( 1.3 1.3(
i
Table 5.1 (crintinued)
(1) Method I uses measured station discharges and meteorological data as input. parameters into conservative transport to man models. Method 2 uses the actual measured concentrations in environmental media.
(2) Maximum individual - The maximum individual dose is the dose to the most critical age group (child for inhalation, infant for milk, child for vegetables, and adult for the remaining), at the location of maximum concentration of plant related activity. These locations are: external gamma dose-780m NE, goats milk-3200m ENE, skyshine-1000m NNV. The doses for inhalation and vegetable consumption assume that the individual resides a t. the peint of raximam quarterly dose. Therefore, his residence is subject to variation for conservatism.
(3) ND - Not detectable - No plant related activity could be detected above natural background or above the minimum detectable level (MDL). The value reported is the dose corresponding to the MDL.
(4) GI(LLI) - Gastro Intestinal Tract - Lower Large Intestine - the organ receiving the maximum dose via the fish and shellfish pathways.
(5) Based on measurements taken with a high pressure ion chamber.
(6) Not applicable.
(7) Based on calculations performed utilizing the computer code, SKYS 111NE, developed by Oak Ridge National Labo ra to ries .
(8) Based on measured levels in oysters. Doses due to consumption of clams would be approximately the same.
(9) Based on prior measurements performed with a high pre:sure ion chamber.
i 4
6.0 DISCUSSION The evaluation of the effects of station operation on the environment requires the careful consideration of many fectors. 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 1-131 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 196C's. This results in significant aavunts 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 migLt 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 part'.culate data has been evaluated. Evaluation shows that airborne Sc-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. 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 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 tallout 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 milk is common through-out the United States. Due to the variability la 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 hi.her 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 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 farms failed to find any link to the plant.
Based on these facts, the observation that the station effluents are responsible is obviously false. The cause must be one or more of the other variables.
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
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.
1 1
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i 6-3 l
L -. _ -_. ._ _. __ __. _ . . _ . _ _ _ _ _ _
/
APPENDIX A Cow and Goat Census for 1984 A-1 i
DAIRY C0WS WITHIN 15 MILES OF MILLSTONE POINT
, AS OF APRIL 1984 t
DIRECTION DISTANCE NAME AND ADDRESS NO. OF COWS 1
N 6 M. 5. Douglas Morgan 7 16 Douglas !.ane Waterford, CT 06385 N 12 5 M. Conrad Nelson 108 486 Fitch Hill Rd.
- Uncasville, CT 06382
- Montville - -
N 12.5 M. Leo Wrobel 39 290 Fitch Hill Rd.
Uncasville, CT 06382
- Montville -
N 14 M. Wauwecus Farm Dairy 40 RFD #2, Wauwecus Hill Rd.
Norwich, CT 06360
- Bozrah -
NNE 13 M. Geer Hill Farm 41 947 Co. Ledyard Hwy.
Ledyard, CT 06339
, NE 11 M. Doris Lamb 6 l 99 Lambtown Rd.
Ledyard, CT 06339 NE 13.5 M. Henry Morgan 58 RFD #7, Box 1114 Ledyard, CT'06339 NE 14 M. Robert Cote 2
< 48 Town Farm Rd.
i Ledyard, CT 06339 ENE 13 M. Charles Perkins
- 28 RFD #1 Stonington, CT 06378 i
ENE 14 M. Stone Acres Farm, Inc. 31 E. Piver, Mgr.
Box 222 Stonington, CT 06378
! WNW 9 5 M. J. Ely Harding 60 l Ashlawn Farm Old Lyme, CT 06371
- Lyme -
1 l
l
, - . , .--, -,-------.,n-n. -
DAIRY COWS WITHIN 15 MILES OF MILL 5'ONE P0lNT AS OF APRIL 1984 DIRECTION DISTANCE NAME AND ADDRESS NO. OF COWS 4
WNW 11 M. Tiffany Farms 70 Sterling City Rd.
Old Lyme, CT 06371
- Lyme -
NNW 8 M. Raymond Muschinsky 27
' Grassy Hill Rd.
i East Lyme, CT 06333 NNW 11.5 M. Valley View Farm 24 Eugene Wiczewski Darling Rd.
I Salem, CT 06415 NNW 12 M. Robin & William Houser 24 Salem 4 Corners Salem, CT 06415 NNW 13 M. Stuart cadbois 225 Route 82 Salem, CT 06415 NNW 13 M. Garry Vaill 34 Forsythe Rd.
Salem, CT 06415 1,
l i
l l
l l
_ . _ _ - - ,_ - ._ __ -, _ _ . - - - _ _ _ _ . . _ . . - - . ~ . . . - _ . ,
DAIRY GOATS WITHIN 20 MILES OF MILLSTONE POINT AS OF MAY 1984 DIRECTION DISTANCE NAME AND ADDRESS NO. OF GOATS N 2 M. Mary Mingo 3 69 Spithead Rd.
Waterford, CT 06385 N 16 M. Henry Rianhard 1 Scott Hill Rd.
Bozrah, CT 06334 NNE I.8 M. Allen Moran 2 204 Rope Ferry Rd.
Waterford, CT 06385 NE 13 5 M. Robert Cote r 3 2 Town Farn. Rd. i Ledyard, CT 06339 i NE 14 M. Robert Ruest 8 15 Mathewson Mil! Rd.
Ledyard, CT 06339 ,
ENE 2 M. Bertram Smith , 2 9 Braman Rd.
Waterford,, CT 06385
( \
W 16.5 M. Victor Trudeau '
5 174 Horse Hill Rd.' g, Westbrook, CT 06492 WNW 8 M. Peter LaPolla 2 Town Woods Rd,3 Old Lyme, CT 06371 WNW 17 5 M. David Recchia 1 RFD'#1 Deep Rive,r, CT 06417 e
WNW 19 5 M. Chris Harris 2 218 Reservoir Rd.
Killingworth, CT 06417 l
._ i
)
~
DAIRY GOATS WITHIN 20 MILES OF MILLSTONE POINT AS OF MAY 1984 DIRECTION DISTANCE NAME AND ADDRESS NO. OF GOATS WNW 20 M. Vicki Fonteneau 2 312 Old Deep River Tkpe.
Killingworth, CT 06417 NV 5 M. Ron Birchall 6 339 Boston Post Rd.
East Lyme, CT 06333 NW 5 M. George Scacciaferro 13 338 Boston Post Rd.
East Lyme, CT 06333 i
NW 7 M. Tina Korineck 6 233 Upper Pattagansett Rd.
East Lyme, CT 06333 NW 14 M. Burton Tucker 2 A.P. Gates Rd.
East Hadda'.#, CT 06423 NNW 13.5 M. Joseph DeVito 5 1 A94 Old Colchester Rd.
Oakdale, CT 06370 1
NW 18 M. MaryAnn Halpin 3 Town St.
East Haddam, CT 06423
l l
APPENDIX B Quality Control i
B-1 l
I Introduction Northeast Utilities Service Company (NUSCO), acting as the agent for both !
the Northeast Nuclear Energy Company (NNECO) and the Connecticut Yankee i Atomic Power Company (CYAPCO), maintains a quality assurance (QA) program j 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).
i i These three quality control methods are:
L j a) Duplicate analyses of actual surveillance samples with one laborato ry. This type of quality control allows an evaluation of j the contractor's precision or reproducibility of results.
I b) Cross-check analyses of actual surveillance samples with more than one laboratory. This intercomparison allows the determination of 4
what agreement the primary contractor has with another laboratory.
A c) Analyses of " spiked" samples. This type of quality control allows a check on the contractor's accuracy of results.
4 i Additional QA programs are performed, these include: 1) Chemical Waste Management's internal QA program, 2) Chemical Waste Management's l I
l participation in EPA's Environmental Radioactivity Laboratory l Intercomparison Studies Program, and 3) Nuclear Regulatory Commission - !
State of Connecticut Independent Verification Program.
l 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 i 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, 0) only. The standard deviation is divided into the difference between the two l 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 l
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.
l 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 l
t
- , _ - . . , , . . - . - . _ . - , ~ . . . _ . - . , _ . . . , _ . , , , - -
mecsurement 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-90 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 conse rvative.
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 contrictor 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 PdI 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.
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. Reanalysis for Sr-89 was acceptable. For the three unacceptable Sr-90 and two unacceptable Sr-89 results in water, five samples w3re 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 i 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 l B-3
~ 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. i l
For the GeLi results, the calibration factors were at fault and these have t een 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.
Conclusion 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 conclusion.
I B-4
Table 1 Number of Quality Contro1* Samples Number of Number of Routine Sample Type QC Samples Required Samples "'b 1
Milk 51 112 Well Water
- 17 28 c 16 Sea Water 2 C
River Water 7 8
! Soil 3 16 Bottom Sediment 4 26 Aquatic Flora 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
- -. _ -.- . - _= ._. ._ _-..
i 9
Table 2 a Precision
- Acceptance Number of Measurements Media Analysis Criteria Acceptable Unacceptable 4
Milk Sr 90 A/01 4* 25 3 9
i Sr A/of 4 27 1 i
Csl37 (Geli) A/05 3 27 1 Water H-3 A/a5 4 8 0
} Soil &
Geff's A/of 3 3 0 Bottom Sr A/05 4 2 1 Sediment Aquatic Geff's A/of 3 5 0 Life Sr A/oS 4 5 0 i
90 Total Sr A/o$ 4 32 4 Geli A/a5 3 35 1 H-3 A/of 4 8 0 I
- A = difference between the two values a = standard deviation l B-6
Table 3 Interlaboratory Coaparisons Acceptance Number of Measurements Media Analysis Criteria Acceptable Unacceptable 9
Milk Sr 8 A/ 5 4* 11 0
. Sr A/c$ 4 11 0 13 Cs (Geli) A/05 3 11 0 Water Sr A/of 4 7 0 j H-3 A/05 4 11 1 Soil & Gegg's A/of 3 4 0 Bottom Sr A/of 4 4 0 Sediment l Aquatic Gegg's A/c5 3 10 0 Life Sr A/of 4 9 1 90 Total Sr A/of 4 31 1 H-3 A/c5 4 11 1 Geli A/oS 3 25 0 i *A = difference between the two values a = standard deviation i
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Table 4 Accuracy 4 (Results of Spikes) i i
i Number of Measurements Acceptable Unacceptable Acceptance Primary Secondary Primary Secondary Media Analysis Criteria Contractor Contractor Contractor Contractor 131 18 6 6 0 Milk I A 5 30%
90 0 Sr 9
A/a 5 4 7 4 1 Sr A/a 5 4 7 4 1 0 Cs A/a 5 3 8 4 0 0 Cs A/o 5 3 7 4 1 0 Water Gegg A/o 5 3 11 6 1 0 Sr g9 A/o 5 4 9 6 3 0 Sr A/o 5 4 10 6 2 0 H-3 A/a 5 4 8 4 0 0 Aquatic Geff A/o 5 3 0 1 2 1 Food and Sr 89 A/a 5 4 0 2 2 0 Flora Sr A/a 5 4 2 2 0 0 Air Gross $ A/c 5 4 3 -
10 -
Particulate Geli A/a 5 3 21 -
3 -
Csfchemistry) 9 A/o 5 4 2 - 6 -
~
S f31 O!" ' ' -
I A/a 5 4 11 -
0 -
Total I (milk) A 5 30% 18 6 6 0 9
Sr 89 A/a 5 4 22 12 8 0 Sr A/a 5 4 19 12 3 0 Cs (chemistry) A/a 5 4 2 -
6 -
Geli A/a 5 3 40 11 6 1 A/o 5 4 8 4 0 0 H
I g (air) A/o 5 4 11 -
0 -
Gross S (air) A/o 5 4 3 -
10 -
t
- A = difference between the two values a = standard deviation i
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se3e'.t.St amt e4 f ed4Gv CNe8s* (203) 665-5000 March 27, 1985 Docket No. 50-245 50-336 B11501 Dr. T. E. Murley Regional Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406
Dear Dr. Murley:
MILLSTONE NUCLEAR POWER STATION, UNIT 1 AND UNIT 2 ANNUAL ENVIRONMENTAL OPERATING REPORTS, PART B: RADIOLOGICAL In accordance with the requirements of Appendix B to the operating licenses 01 Units 1 and 2 Environmental Technical Specification 5.6.1.a, two (2) copics of the Annual Environmental Operating Report, Part B:
Radiological, are herewith submitted. Canies of this report are being distributed in accordance with Regulatory Guide 10.1.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY
/ cI2#
W.'G. Counsil Senior Vice President c: J. R. Miller J. A. Zwolinski
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