ML20205P921
| ML20205P921 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 12/31/1985 |
| From: | Opeka J NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES, NORTHEAST UTILITIES SERVICE CO. |
| To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| B12054, NUDOCS 8605280051 | |
| Download: ML20205P921 (109) | |
Text
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MILLSTONE POINT SITE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL ENVIRONMENTAL OPERATING REPORT PART B PERIOD JANUARY 1, 1985 - DECEMBER 31, 1985 MILLSTONE UNIT 1, DOCKET NO. 50-245 MILLSTONE UNIT 2, DOCKET N0. 50-336 MILLSTONE UNIT 3, DOCKET NO. 50-423 PREPARED FOR THE NORTHEAST NUCLEAR ENERGY COMPANY HARTFORD, CONNECTICUT BY THE NORTHEAST UTILITIES SERVICE COMPANY BERLIN, CONNECTICUT l
I MILLSTONE POINT SITE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL ENVIRONMENTAL OPERATING REPORT PART B PERIOD JANUARY 1, 1985 - DECEMBER 31, 1985 MILLSTONE UNIT 1, DOCKET NO. 50-245 MILLSTONE UNIT 2, DOCKET NO. 50-336 MILLSTONE UNIT 3, DOCKET NO. 50-423 PREPARED FOR THE NORTHEAST NUCLEAR ENERGY COMPANY HARTFORD, CONNECTICUT BY THE NORTHEAST UTILITIES SERVICE COMPANY BERLIN, CONNECTICUT
EM General Offices
- Selden Street, Berlin, Connecticut sY ves5Ncw=
P.O. BOX 270
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HARTFORD. CONNECTICUT 06141-0270 L
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(203) 66s-5000 April 22,1986 Docket Nos. 50-245 50-336 50-423 B12054 Dr. Thomas E. Murley, Regional Administrator Region i U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 Gentlemen:
Millstone Nuclear Power Station, Unit Nos.1,2, and 3 Annual Environmental Operating Reports, Part B: Radiological In accordance with the requirements of Appendix B to the operating licenses of Millstone Units I and 2 Environmental Technical Specitication 3.6.1.a, two (2) copies of the Annual Environmental Operating Report, Part B: Radiological, are herewith submitted. Copies of this report are being distributed in accordance with Regulatory Guide 10.1.
Although the Radiological Effluent Technical Specifications became effective l
for Millstone Units 1 and 2 on January 1,1986, this report covers the last 12 month period in which the Environmental Specifications were in effect. As such, this report is written to the format requirements of the Environmental Technical Specifications in effect during the January to December 1985 time period. Any l
reference to the Technical Specification limits in.the attached report is in reference to such Environmental Technical Specifications. However, since this report is being submitted in 1986, it is being forwarded in accordance with the schedule requirements of Technical Specifications Section 6.9.1.10 for Millstone Units 1 and 2, and Section 6.9.1.3 for Millstone Unit 3. Subsequent reports will follow all the requirements specified in the Radiological Effluent Technical 5pecifications.
This report also satisfies the reporting requirements fer Millstone Unit 3, since it received a low power level license on November 25, 1985. Since it did not achieve initial criticality until January 23, 1986 and no radioactivity was observed in its gaseous and liquid effluents during 1985, the text of the report only addresses the operation of Units 1 and 2.
Very truly yours, l
NORTilEAST NUCLEAR ENERGY COMPANY 4
- b duls_
h J. F. OpeWa L
A Senior Vice President gy cc C.1. Grimes y
)v g{g A. C. Thadani V. S. Noonan
TABLE OF CONTENTS 4
Page No.
1.0 Summary 1-1 2.0 Program Description 2-1 2.1 Sampling Schedule and Locations 2-1 2.2 Samples Collected During Report Period 2-7 3.0 Radiochemical Results 3-1 3.1 Summary Table 3-1 3.2 Data Tables 3-21 4.0 Discussion of Results 4-1 5.0 Offsite Dose Consequences 5-1 r
6.0 Discussion 6-1 Appendix A - Cow and Goat Census for 1985 A-1 Appendix B - QA Program B-1
l 1.0 SUfHARY The radiological environmental monitoring program for the Millstone Nuclear Power Station was continued for the period January through December 1985, 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 Clean Harbors, Inc. Yankee Atomic Electric Company and Teledyne Isotopes, Inc. were 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 ganana 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. 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 thermoluminescent dosimeter (TLD) values for the months of November and December, 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 were also so low as to be not 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-137 in eels; cobalt-58, cobalt-60, zinc-65, and silver-110m in oysters; cobalt-60 in clams; and cobalt-58 and cobalt-60 in crabs. Except for cobalt-60 1-1
l in aquatic flora, the levels of these radionuclides were similar to the levels observed for the last six years.
Increased levels of Co-60 in aquatic flora have been observed for the past three years.
l All activity levels were below those of the higher discharge period of 1974-1975 (before the augmented 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 j
the 1960's and not a result of plant operation. This can be concluded based on the facts that:
insufficient quantities (at least 1000 times less) of these isotopes have been released by the plant to account for the measured concentrations, 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.
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 contributions from both "skyshine" and station effluents.
The average whole body dose to an individual residing within 50 miles of the station was 0.00038 millirem. These doses are 6.0 percent and 0.0015 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 inconsequential 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.
1-2
2.0 PROGRAM DESCRIPTION 2.1 Sampling Schedule and Locations The sample locations and the sample types and frequency of analysis are given in Table 2-1 and 2-2 and Figures 2.1, 2.2 and 2.3.
The program as described here is that which is required by Environmental Technical Specification 3.2.
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I Figure 2.3 AQUATIC SAMPLING STATIONS Millstone Nuclear Power Station 2-4
Table 2-1 Hillstone Radiological Environmental Honitoring Program-Terrestrial Stations Sample Type (b) and Analrais(c)
Distance Gamuna Air locations and Direction *)
Dose Farticulate *)(1)
Soil I
I 1.
Onsite--Old Millstone Road 0.6 miles NNW M
W1 - H2 - QS 2.
Onsite-Weather Shack O.3 miles S M
W1 - M2 - QS 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.
Onsite-Quarry Discharge Canal Fence 0.3 miles SSE N
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.
Pleasure Beach 1.2 miles E N
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 N
- 13. Mystic, Connecticut
- 11.5 miles ENE M
W1 - M2 - QS
- 14. Ledyard, Connecticut
- 11.5 miles NE M
W1 - M2 - Q5(f)
A2.5
- 15. Montville, Connecticut
- 14.0 miles N N
W1 - M2 - Q5 A2,5
- 16. Old Lyme, Connecticut
- 9.0 miles W M
W1 - M2 - QS Milk (de 8)
Croundwater Fruit Vegetables SA1,2,4,5
- 17. Well No. 1 1.5 miles SA1,2,4,5
- 18. Well No. 2 1.0 miles
- 19. Dairy Fara No. 1 6.0 miles N M3,5
- 20. Dairy Fara No. 2 9.5 miles UNW M3,5
- 21. Dairy Farm No. 3 11.0 miles NE M3,5
- 22. Dairy Fara No. 4
- 15.0 miles NNW M3,5
- 23. Coat Faru No. 1 2.0 miles ENE TM3-M5 (composite) 24.
Goat Fara No. 2
- 14.0 miles NE TM3-H5 (composite) 75 Fruit and Vegetables SA2,5(h)
SA2,5(h) e.
From Millstone Unit 1 (stack) to nearest half mile b.
W = weekly, TM = twice a month, M= monthly, Q = quarterly, SA = semiannual, A = annual c.
1 = grocs beta; 2 = gsmaa spectrum; 3 = I-131; 4 = H-3; 5 = Sr-89. Sr 90, Cs-137.
d.
During the period April through October and once in February, Analyses are done on monthly and quarterly composites of the weekly air particulate samples collected at each station.
e.
f.
Includes a charcoal filter to be analyzed weekly for I-131 at inhalation dose levels.
3 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 stearion concept.
Cuntrol Station
Table 2-2 Millstone Radiological Environmental Monitoring Program-Aquatic Stations Type. Frequency (b) and h lysisICI g,)
Oysterye 1.obster(e)
Fin Fish (d.e)
Bottom r
Distance Class Eater Locations and Direction Sediment Flora Mussels 4.7 miles NW Q2,3,5 Q2,3,5 1.
Golden Spur
- SA2,3
'1.8 miles W SA2,3 SA2,3 Q2,3,5 Q2,3,5 2.
Niantic Shoals 3.
Within 500 feet of SA2,3 SA2,3 Q2,3,5 Q2.3,5 Q2,3,5 Q2,3,5 Q1,2,3.4 Discharge Canal Q1,2,3,4 1.6 miles ESE SA2,3 SA2.3 4.
Seaside Point 5.
Thames River (Yacht Club) 4.0 miles ENE SA2,3 SA2,3 Q2.3.5 Q2.3.5 Q2.3.5 Q1,2,3,4 6.
Niantic Bay 0.3 miles WW 7.
Black Point 2.6 miles WSW SA2,3 SA2,3 Q2,3,5 Q2,3,5 Q2.3.5 Q1,2,3,4 8.
Giants Neck
- 3.5 miles W SA2,3 SA2,3 9.
Commercial Shellfish Q2.3.5 Bed #316 0.1 miles S
~~
l 7
- 10. Waterford Shell fish Bed #1 0.5 miles WW Q2,3,5 m
l s.
From Discharge Quarry to nearest half mile.
I t.
Q = quarterly, SA = semi-annual c.
1 = gross beta, 2 = gamma spectrum, 3 = Sr-89, Sr-90, Cs-137 Co-60, 4 = H-3, 5 = I-131 l
4.
Flounder and one other type of edible fin fish, Sampling of crustacea, mollusk and fin fish to be staggered for each month of the quarter.
e.
e Control Stations
1 2.2 Samples Collected During Report Period The following table sumarizes the number of required samples of each type collected during the present reporting period:
Sample Type Number of Samples Gama Exposure (TLD) 192 Air Particulates 571 Air Iodine 209 Soil 6
Dairy Milk 32 Goat Milk 26 Pasture Grass 1
Well Water 4
Fruit and Vegetables 8
Sea Water 16 Bottom Sediment 14 Aquatic Flora 12 Fish 16 Mussels 11 Oysters / Clams 28 Lobster 12 Total All Types 1,158 t
2-7
3.0 RADI0 CHEMICAL RESULTS 3.1 Sumary Table In accordance witn Environmental Technical Specification 5.6.la., Table 5.6-1, a sumary table of the radiochemical results has been prepared and is presented in Table 3-1.
In the determination of the mean the data was handled as recomended by Health and Safety Laboratory, Idaho: all valid data, including negative values and zeroes were used in the determination of the mean (see part 3.2).
A more detailed analysis of the data is given in section 4.0 where a discussion of the variations in the data brings to light many aspects that are not evident in the sumary table because of the basic limitation of such an approach.
3-1
l i
j TABLE 3-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SUPMARY
~
MILLSTONE NUCLEAR POWER STATION, UNITS 1 and 2 DOCKET 50-245 and 50-336 JANUARY - DECEMBER 1985 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 SAPFLED PERFORMED (MDL's)(a)
Mean (Range)
AND DIRECTION Mean (Range)
Mean (Range)
(c)
Ganma Dose 132,60(d) 1.5 9.9 (6.4 - 14.1)
Weather Shack 13.5 (12.7 - 14.1) 9.3 (8.1 - 12.0) 0 (uR/hr) 0.3 Miles S Air Particulate 311,260 Bird Sanctuary and q
and Iodine Beta 0.01(e) 0.021 (0.008 - 0.038)
Albacore Orive 0.023 (0.011 - 0.033) 0.020 (0.007 - 0.034) 0 (pC1/mJ) 0.3 Miles NE and 0.023 (0.009 - 0.033).
1.0 Miles N 1
Albacore Drive-Nal 155,52 0.04 0.014
(-0.03 - 0.07) and Ledyard 0.021
(-0.01 - 0.07) 0.021-(-0.03 - 0.07) 0
)
1-131 1.0 Miles N and 0.021
(-0.03 - 0.07) 11.5 Miles NE Ge(Li) 72.60 0.025(f) 0.000
(-0.003 - 0003)
Montvi1le 0.0005 (-0.001 - 0.002) 0.000
(-0.002 - 0.003)
O Cs-137 14 Miles N Cs-134 0.02(f) 0.000
(-0.005 - 0.002)
Bird Sanctuary 0.0003 (-0.005 - 0.002) 0.000
(-0.003 - 0.003) 0 0.3 Miles NE Ru-103
-0.0002 (-0.006 - 0.004)
Pleasure Beach 0.0003 (-0.001 - 0.002)
-0.0003 (-0.004 - 0.004) 0 0.3 Miles E Zr-95 0.000
(-0.006 - 0.006)
Ledyard 0.0017 (-0.001 - 0.010) 0.000
(-0.005 - 0.010) 0 11.5 Miles NE~
l Nb-95 0.000
(-0.006 - 0.006)
Old Lyme 0.0008 (-0.001 - 0.002) 0.000
(-0.004 - 0.005) 0 9 Miles W l
TABLE 3-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SUPMARY MILLSTONE NUCLEAR POWER STATION, UNITS 1 and 2 DOCKET 50-245 and 50-336 JANUARY - DECEMBER 1985 ANALYSIS AND MINIMUM ALL INDICATOR LOCATION WITH HIGHEST ANNUAL MEAN CONTROL LOCATIONS f 0F
}
MEDIUM OR TOTAL NtMBER DETECTABLE LOCATIONS i
PATHWAY OF ANALYSES LEVELS (b)
NAE, DISTANCE (b)
(b)
NRMs i
SAffLED PERFORMED (MOL's)(a)
Mean (Rangel AND DIRECTION Mean (Range)
Mean (Range)
(c)
Cs 24.20 0.001(e)(g) 0.00005 (-0.0001 - 0.0002)
Old Lyme 0.0001 (0.00005 - 0.00013) 0.00006 (-0.00005 - 0.00016) 0 9 Miles W Sr 24.20 0.002(e)(9) -0.00013 (-0.0016 - 0.0009)
Montville 0.00048 (0.0001 - 0.0014) 0.00022 (-0.0007 - 0.0014) O 14 Miles N Sr-89 Sr-90 0.001(e)(9) 0.00020 (0.00001 - 0.0006)
Pleasure Beach 0.00028 (0.00012 - 0.000059) 0.00012 (0.00003 - 0.00021) 0 1.2 Miles E Albacore Drive, Soll Sr 4.2 0.072
-0.002
(-0.0005 - 0.000)
Pleasure Beach 0.00 N/A(h)
-0.002
(-0.004 - 0.000) 0
)
i and Montville (pC1/g)
Sr-89 l
1 Mile N, 1.2 Miles E l
and 14 Miles N Sr-90 0.036 0.104 (0.018 - 0.226)
Montville 0.229 N/A 0.131 (0.034-0.229) 0 14 Miles N 1
l New London Ge(L1) 4.2 0.07 1.08 (0.44 - 1.55)
Country Club 1.55 N/A 0.80 (0.51 - 1.09)
O 1.6 Miles ENE Cs-137 New London Cs-134 0.06 0.02 (0.01 - 0.04)
Country Club 0.04 N/A 0.03 (0.02 - 0.04)
O and Montville 1.6 Miles ENE and 14 Miles N
_ _ _ _ _... _ _ _ _ _ _ - ~ _ _ _ _ ~ _ _ _ _ _ _. _ _. _ _.._
__ ~_
TABLE 3-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SUPMARY MILLSTONE NUCLEAR POWER STATION, UNITS 1 and 2 DOCKET 50-245 and 50-336 JANUARY - DECEMBER 1985 ANALYSIS AND MINIMUM ALL INDICATOR LOCATION WITH HIGHEST ANNUAL MEAN CONTROL LOCATIONS MEDIUM OR TOTAL NUMBER DETECTABLE LOCATIONS 7 OF j
PATHWAY OF ANALYSES LEVELS (b)
NAME DISTANCE (b)
-(b)
NRMs SAMPLED PERFORMED (MOL's)(a)
Mean (Range)
AND DIRECTION Mean (Range)
Mean (Range)
(c)_
Ledyard and Montville Mn-54
-0.02
(-0.02 - 0.01) 11.5 Miles NE and 0.00 N/A 0.00 0
14 Miles N Albacore Drive Co-58
-0.01
(-0.01 - 0.00)-
and New London 0.00 N/A
-0.01 0-Country Club.
1 Mile N and 1.6 Miles ENE Co-60 0.02 (0.01 - 0.03)
Albacore Drive 0.03 N/A
-0.005
(-0.01 - 0.00) 0 1 Mile N i
i i
Albacore Drive i
Zr-95 0.01 (0.00 - 0.04) and Montville 0.04 N/A 0.02 (0.00-0.04) 0 1 Mile N and 14 Miles N j
l Nb-95 0.027 (0.00 - 0.05)
Montville 0.06 N/A 0.045 (0.03 - 0.06) 0 14 Miles N i
K-40 7.8 (7.0 - 8.5)
Bird Sanctuary 8.5 N/A 7.4 (7.0 - 7.7) 0 0.3 Miles NE i
i Ra-226 0.61 (0.48 - 0.77)
Montville 0.79 N/A 0.71 (0.63 - 0.79) 0 14 Miles N Milk (Dairy)
Iodine 36.12 0.5 0.12
(-0.02 - 0.50)
Dairy Farm #2 0.13
(-0.01 - 0.50) 0.11
(-0.09 - 0.44) 0 l
I
{
(pC1/l)
I-131 9.5 Miles WNW l
l c.
w-
TABLE 3-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SUPNARY MILLSTONE NUCLEAR POWER STATION, UNITS 1 and 2 DOCKET 50-245 and 50-336 JANUARY - DECEfGER 1985 ANALYSIS AND MINIMUM ALL INDICATOR LOCATION WITH HIGHEST ANNUAL MEAN CONTROL LOCATIONS f 0F PEDIUM OR TOTAL NUPEER DETECTABLE LOCATIONS PATHWAY OF ANALYSES LEVELS (b)
NAME, DISTANCE (b)
(b)
NRMs SAMLED PERFORMED (MDL's)(a)
Mean (Range)
AND DIRECTION Mean (Range)
Mean (Range)
(c)
Sr 36.12 2
-0.2
(-10. - 2.3)
Dairy Farm #2 0.42
(-1.2 - 2.3) 0.15
(-1.2 - 1.6) 0 9.5 Miles WNW l
Sr-89 l
Sr-90 1
5.9 (1.4 - 13.7)
Dairy Fars #3 8.5 (5.0 - 13.7) 4.0 (2.8 - 6.1) 0 11 Miles NE Ge(Li) 36.12 6
8.6 (0 - 30)
Dairy Farm #1 13.1 (4 - 30) 3.5 (0 - 8)
O 6 Miles N Cs-137 Cs-134 6
0.2
( 3)
Dairy Farm #2 0.3
(-l - 2) 0.0
(-l - 1) 0 9.5 Miles WNW f
Goat Milk Iodine 19.12 0.5 0.10
(-0.04 - 0.48)
Goat Farm #2 0.17
(-0.05-0.70) 0.17
(-0.05 - 0.70) 0 14 Miles NE j
(pCf/1)
I-131 l
l Sr 19.12 2
0.37
(-2.0 - 4.0)
Goat Fars #1 0.37
(-2.0 - 4.0)
-0.02
(-2.0 - 2.0) 0 l
2 Miles ENE Sr-89 Sr-90 1
21.1 (9.8 - 33.9)
Goat Farm #1 21.1 (9.8 - 33.9) 6.9 (3.4 - 12.7) 0 l
2 Miles ENE j
1 Ge(Li) 19.12 6
100 (63-151)
Goat Farm #1 100 (63 - 151) 15.7 (4
41)
O 2 Miles ENE Cs-137 Cs-134 6
0.2
( 3)
Goat Farm #2 0.7
(-l - 2) 0.7
(-l -2) 0 14 Miles NE Pasture Grass Sr 0, 1 0.018 N/A Goat Farm #2 0.0 N/A 0.0 N/A 0
14.0 Miles NE (pC1/g)
Sr-89 s
l I
.. - ~
. ~..
i l
TABLE 3-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SUPMARY 3
MILLSTONE NUCLEAR POWER STATION, UNITS 1 and 2-DOCKET 50-245 and 50-336 l
JANUARY - DECEMBER 1985 l
ANALYSIS AND MINIMUM ALL INDICATOR LOCATION WITH HIGHEST ANNUAL MEAN CONTROL LOCATIONS MEDIUM OR TOTAL NUMBER DETECTABLE LOCATIONS
- OF '
i PATHWAY OF ANALYSES LEVELS (b)
NAME, DISTANCE (b)
(b)
NRMs -
SAMPLED PERFORMED (MDL's)(a)
Mean (Range)
AND DIRECTION Mean (Range)
Mean (Range)
(c)
Sr-90 0.009 N/A Goat Farm #2 0.127 N/A 0.127 N/A 0
{
14.0 Miles NE Ge(L1) O. 1 0.034 N/A Goat Farm #2 0.033 N/A.
0.033 N/A 0
Cs-137 14.0 Miles NE I
I-131 0.05 N/A Goat Farm #2 0.0 N/A 0.0 N/A 0
14.0 Miles NE t
Groundwater Sr 4
2 0.25 (0.0 - 0.4)
Well #1 0.30 (0.2 - 0.4)
N/A 0
(pCi/1)
Sr-89 1.5 Miles NNE Sr-90 1
0.45 (0.3 - 0.7)
Well #2 0.50 (0.3 - 0.7)
N/A 0
1.0 Miles NNE Ge(L1) 4 6
1.5 (1 - 2)
Well #1 2
(2 - 2)
N/A 0
Cs-137 1.5 Miles NNE J
I-131 30**
1.8
( 10)
Well #2 5
(0 - 10)
N/A 0
1 Mile NNE Cs-134 6
1 (0 - 2)
Well #1 1.5 (1 - 2)
N/A 0
1.5 Miles NNE i
Co-58 6
-0.8
( 0)
Well #1
-0.5
( 0)
N/A 0
1.5 Miles NNE
- at time of counting i
TABLE 3-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SupWiARf MILLSTONE NUCLEAR POWER STATION, UNITS 1 and 2 DOCKET 50-245 and 50-336 JANUARY - DECEteER 1985 ANALYSIS AND MINIMUM ALL INDICATOR LOCATION WITH HIGHEST ANNUAL MEAN CONTROL LOCATIONS
- OF MEDIUM OR TOTAL NUMBER DETECTABLE LOCATIONS PATHWAY OF ANALYSES LEVELS (b)
NAME, DISTANCE (b)
(b)
NRMs SAPFLED PERFORMED (MDL's)(a)
Mean (Range)
AND DIRECTION _
Mean (Range)
Mean (Range)
(c)
Co-60 6
0.3
( 1)
Well #1 0.5 (0 - 1)
N/A 0
1.5 Miles NNE Ph-54 6
-0.3
( 1)
Well #1 0.5 (0 - 1)
N/A 0
1.5 Miles NME Tritium 4 60 66 (0 - 100)
Well #1 99 (97 - 100)
N/A 0
1.5 Mile NME l
Beta 4
1 4.4 (2.4 - 6.0)
Well #1 5.9 (5.8 - 6.0)
N/A 0
(
1.5 Miles NME B
Vaetables Sr 4.4 0.018 0.001
(-0.003 - 0.01)
Within 10 Miles 0.001
(-0.003 - 0.01) 0.000
(-0.005 - 0.003) 0 Fruits and (pC1/g)
Sr-89 Sr-90 0.009 0.045 (0.006 - 0.103)
Within 10 Miles 0.045 (0.006 - 0.103) 0.018 (0.009 - 0.031) 0 Ge(Li) 4.4 0.034 0.002
(-0.010 - 0.012)
Within 10 Miles 0.002
(-0.010 - 0.012) 0.001
(-0.001 - 0.006)
(-0.010-0.020)
Within 10 Miles 0.004
(-0.010 - 0.020) 0.002 (0.000 - 0.007)
O Cs-134 0.025 0.002
(-0.001 - 0.008)
Within 10 Miles 0.002
(-0.001 - 0.008) 0.000
(-0.006 - 0.007)
O Mn-54 0.001
(-0.004 - 0.009)
Beyond 10 Miles 0.003
(-0.002 - 0.009) 0.003
(-0.002 - 0.009) 0
TAPLE 3-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM Sl W N!Y MILLSTONE NUCLEAR POWER STATION, UNITS 1 and 2 DOCKET 50.245 and 50-336 JANUARY - DECEMBER 1995 ANALYSl$ AND MINIMUM ALL INDICATOR LOCATIOM WITH HIGHEST ANNUAL MEA %
C0hTR0t. LOCATIONS MEDIUM OR TOTAL NUMBER DETECTABLE LOCATIONS
- OF PATHWAY OF ANALYSES LEVELS (b)
MAME, DISTANCE (b)
(b)
NRMs SAMPLED PERFORMED (MDL's)(a)
Mean (Range)
AN3 OIRECTION Mean (Range)
Mean (Range)
(c)
Co-58
-0.005
('0.010 - -0.001)
Seyond 10 Miles 0.000
(-0.005 - 0.004) 0.000
(-0.005 - 0.004) 0 Co-60 0.002
(-0.0C2 - 0.010)
Within 10 Miles 0.002
(-0.002 - 0.010) 0.00 0
K-40 2.2 (0.9 - 4.1)
Within 10 Miles 2.2 (0.9 - 4.1) 2.1 (0.6 - 3.7) 0 Ra-226 0.01
(-0.01 - 0.02)
Within 10 Miles 0.01
(-0.01 - 0.02) 0.00
(-0.01 - C.01) 0 Th-228 0.02
(-0.02 - 0.03)
Within 10 Miles 0.02
(-0.02 - 0.03) 0.00
(-0.01 - 0.10)
O Seawater Sr 12.4 2
-0.1
(-0.5 - 0.3)
Giant's Ne-ck 0.1 (0.0 - 0.4) 0.1 (0.0 - 0.4) 0 (pCi/1)
Sr-89 3.5 Miles W Sr-90 1
0.3 (0.1 --0.6)
Seaside Point 0.41 (0.15 - 0.6) 0.2 (0,0-0.3) 0 1.6 Miles ESE Ge(L1) 12,4 6
0.2
( 3)
Within 500 feet 1.0
( 3)
-0.5
(-I - 1) 0 Cs-137 of Discharge I-131 3.3
( 50)
Giant's Neck 30 (0 - 80) 30 (0 - 80) 0 3.5 Miles W i
Within E00 feet of I
Cs-134 13 0.8 (0 - 2)
Discharge e d 1
(0 - 2) 0.5 (0 - 1) 0 Seaside Point i
1.6 Miles ESE l
l
TABLE 3-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM S'JMMARY MILLSTONE NUCLEAR POWER STATION, U* TITS 1 and 2 DOCKET 50-245 and 50-336 JANUARY - DECEMBER 1985 ANALYSIS AND MINIMUM ALL INDICATOR LOCATION WITH HIGHEST ANNUAL MEAN __
CONTROL LOCATIONS
- OF MEDIUM OR TOTAL NUMBER DETECTABLE LOCATIONS PATHWAY OF ANALYSES LEVELS (b)
NAME DISTANCE (b)
(b)
NRMS SAMPLED PERFORMED (MDL's)(a)
Mean (Range)
AND DIRECTION Mean (Range)
Mean (Range)
(c)
Mn-54 13 0.0
( 3)
Giant's Neck 1
( 3) 1
( 3) 0 3.5 Miles W l
Co-58 13
-0.8
( 2)
Giant's Neck
-0.3
( 1)
-0.3
( 1) 0 3.5 Miles W l
Co-60 13 0.3
( 3)
Niantic Bay 1.5 (0 - 3) 0
( 1) 0 1
0.3 Miles WNW l
Tritium 12,4 60 194 (0 - 920)
Within 500 feet 348 (0 - 920) 44 (0 - 120) 0 l
H-3 of Discharge l
Nb-95 13
-0.1
( 3)
Within 500 feet 0.8
( 3) 0
(-2.-2) 0 of Discharge K-40 328 (240 - 390)
Within 500 feet 360 (330 - 390) 338 (240 - 370) 0 of Discharge l
Beta 12.4 1.7 0.22
(-0.2 - 1.2)
Within 500 feet 0.3
(-0.2 - 1.2) 0.05
(-0.2 - 0.7) 0 Fraction I of Discharge Beta 1.7 2.5 (0.9 - 5.0)
Seaside Point 2.9 (1.5 - 5.0) 2.8 (1.1 - 4.7) 0 Fraction II 1.6 Miles ESE Beta 1.7 0.41 (0.1 - 0.7)
Giant's Neck 0.45 (0.2 - 0.7) 0.45 (0.2 - 0.7) 0 Fraction III 3.5 Miles W l
l l
TABLE 3-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
SUMMARY
MILLSTONE NUCLEAR POWER STATION, UNITS 1 and 2 DOCKET 50-245 and 50-336 JANUARY - DECEMBER 1985 ANALYSIS AND MINIMUM ALL INDICATOR LOCATION WITH HIGHEST ANNUAL MEAN CONTROL LOCATIONS MEDIUM OR TOTAL NUMBER DETECTABLE LOCATIONS d 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)
Beta 1.7 0.66 (0.0 - 2.9)
Within 500 feet 0.97 (0.0 - 2.9) 0.25
(-0.1 - 0.8) 0 fraction IV of Discharge Bottom Sediment Sr 10,4 0.072
-0.002
(-0.011 - 0.003)
Vithin 500 feet 0.003 (0.002 - 0.003)
-0.001
(-0.005 - 0.002) 0 (pCi/g)
Sr-89 of Discharge Sr-90 0.036 0.005 (0.001 - 0.012)
Niantic Shoals 0.008 (0.003 - 0.012) 0.005
'(0.002 - 0.010) 0 1.8 Miles NW Ge(Li) 10.4 0.064 0.02
(-0.01 - 0.03)
Golden Spur 0.41 (0.28 - 0.55) 0.20
(-0.02 - 0.55)
O Cs-137 4.7 Miles NNW I-131 0.00
(-0.04 - 0.02)
Black Point 0.02 (0.01 - 0.02)
-0.02
(-0.10 - 0.03) 0 2.6 Miles WSW Cs-134 0.06 0.02 (0.00 - 0.06)
Golden Spur 0.06 (0.02 - 0.11) 0.03 (0.00 - 0.11) 0 4.7 Miles NNW l
Within 500 feet Mn-54
-0.02
(-0.03 - 0.01) of Discharge 0.00 (0.00 - 0.00)
-0.01
(-0.03 - 0.00)
O and Thames River 0.00
(-0.01 - 0.01)
Yacht Club 4 Miles ENE Co-58 0.00
(-0.02 - 0.02)
Black Point 0.01 (0.00 - 0.02)
-0.01
(-0.02 - 0.01) 0 2.6 Miles WSW l
I l
eae
TABLE 3-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SUPMARY MILLSTONE NUCLEAR POWER STATION, UNITS 1 and 2 DOCKET 50-245 and 50-336 JANUARY - DECEMBER 1985 ANALYSIS AND MINIMUM ALL INDICATOR LOCATION WITH HIGHEST ANNUAL MEAN CONTROL LOCATIOMT, MEDIUM OR TOTAL NUMBER DETECTABLE LOCATIONS i 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)_
0.00
( 0.02 - 0.01)
Golden Spur 0.02 (0.00 - 0.05) 0.02 (0.00 - 0.05) 0 Co-60 4.7 Miles NNW 0.01
(-0.01 - 0.03)
Golden Spur 0.03
-0.04 - 0.11) 0.03
(-0.04 - 0.11) 0 Zr-95 4.7 Miles NNW Nb-95 0.01
(-0.01 - 0.03)
Golden Spur 0.04 (0.01 - 0.08) 0.03 (0.00 - 0.08) 0 4.7 Miles NNW K-40 11.1 (7.8 - 14.0)
Golden Spur 20.2 (10.4 - 30.0) 16.0 (10.4 - 30.0) 0 4.7 Miles NNW Aquatic Flora Sr 10.2 0.01 0.003
(-0.01 - 0.02)
Within 500 feet 0.015 (0.01 - 0.02)
-0.003
(-0.005 - 0.000) 0 (pC1/g)
Sr-89 of Discharge Sr-90 0.009 0.010 (0.001 - 0.021)
Niantic Shoals 0.015 (0.008 - 0.021) 0.008 0
1.8 Miles NW Ge(Li) 10,2 0.034 0.006
(-0.01 - 0.03)
Within 500 feet 0.025 (0.02 - 0.03) 0.005 (0.00 - 0.01)
O Cs-137 of Discharge I-131 0.05 0.009
(-0.02 - 0.10)
Niantic Shoals 0.05 (0.00 - 0.10)
-0.02
(-0.02 - 0.01) 0 1.8 Miles NW
TABLE 3-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SUPNARY MILLSTONE NUCLEAR POWER STATION, UNITS 1 and 2 DOCKET 50-245 and 50-336 JANUARY - DECEMBER 1985 ANALYSIS AND MINIMUM ALL INDICATOR LOCATION WITH HIGHEST ANNUAL MEAN CONTROL LOCATIONS i
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)
Seaside Point, Cs-134 0.025 0.00
(-0.01 - 0.01)
Black Point and 0.005 (0.00-0.01) 0.005 (0.00 - 0.01) 0 Giant's Neck
'1.6 Miles ESE, i
2.6 Miles WSW and 3.5 Miles W Mn-54 0.05 0.00
(-0.02 - 0.03)
-Within 500 feet 0.015 (0.00 - 0.03) 0.00
(-0.02 - 0.01) 0 of Discharge r
Co-58 0.05 0.02
(-0.01 - 0.16)
Within 500 feet 0.09 (0.02 - 0.16) 0.00 0
of Discharge
[O Co-60 0.05 0.03
(-0.01 - 0.18)
Within 500 feet 0.13 (0.09 - 0.18) 0.00 of Discharge j
Zr-95 0.01
(-0 01 - 0.04)
Seaside Point 0.03 (0.02 - 0.04) 0.00
(-0.01 - 0.00) 0 1.6 Miles ESE Nb-95 0.003 (0.00 - 0.008)
Giant's Neck 0.015 (0.00 - 0.03) 0.00
(-0.02 - 0.014)'
O 3.5 Miles W l
Thames River Ag-110m 0.003
(-0.00 - 0.01)
Yacht Club 0.01
-0.02
(-0.02 - -0.01) 0 l
.4 Miles ENE Fish-Flounder Sr 8
0.018 0.000
(-0.004 - 0.002)
Within 500 feet 0.000
(-0.002 - 0.002)
N/A 0
(pC1/g)
Sr-89 of Discharge.
4 4
TABLE 3-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SUPNARY MILLSTONE NUCLEAR POWER STATION, UNITS 1 and 2 DOCKET 50-245 and 50-336 JANUARY - DECEMBER 1985 ANALYSIS AND MINIMUM ALL INDICATOR LOCATION WITH HIGHEST ANNUAL MEAN CONTROL LOCATIONS f 0F MEDIUM OR TOTAL NUMBER DETECTABLE LOCATIONS PATHWAY OF ANALYSES LEVELS (b)
NAME, DISTANCE (b)
(b)
NRMs SAMPLED PERFORMED (MDL's)(a)
Mean (Range)
AND DIRECTION Mean (Range)
Mean (Range)
(c)
Sr-90 0.009 0.003 (0.001 - 0.007)
Niantic Bay 0.003 (0.001 - 0.007)
N/A 0
0.3 Miles WNW Ge(L1) 8 0.056 0.005 (0.00 - 0.01)
Within 500 feet 0.005 (0.00 - 0.01)
N/A 0
of Discharge and Cs-137 Niantic Bay 0.3 Miles WNW I-131
-0.001
(-0.05 - 0.03)
Niantic Bay 0.008
(-0.01 - 0.03)
N/A 0
0.3 Miles WNW i
Cs-134 0.05 0.001
(-0.01-0.01)
Niantic Bay 0.001
(-0.01 - 0.01)
N/A 0
0.3 Miles WNW I
Mn-54 0.05
-0.002
(-0.01 - 0.01)
Within 500 feet
-0.002 (-0.01 - 0.01)
N/A 0
of Discharge Co-58 0.05
-0.004
(-0.02 - 0.01)
Niantic Bay
-0.003 (-0.02 - 0.01)
N/A C
0.3 Miles WNW Co-60 0.05 0.005 (0.00 - 0.01)
Within 500 feet 0-.007 (0.00 - 0.01)
N/A 0
of Discharge
-0.005
(-0.02 - 0.01)
Within 500 feet
-0.003 (-0.02 0.01)
N/A 0'
Zr-95 of'01scharge J
l 1
l
,~
TABLE 3-1 ENVIRONMENTAL RADIOLOGICAL MONITORINr PROGRAR
SUMMARY
MILLSTONE NUCLEAR POWER STATIDM, UNITS 1 a6d 2 DOCKET 50-245 and 50-33C JANUARY - DECEMBER 1985 ANALYSIS AND MINIMUM ALL INDICATOR LOCATION WITH HIGHEST ANNUAL MEAN CONTROL LOCATIJNS MEDIUM OR TOTAL NUMBER DETECTABLE LOCATIONS i 0F PATtf4AY OF ANALYSES LEVELS (b)
NAME, DISTANCE (b)
(b NRMs SAMPLED PERFORMED (MDL's)(a)
Mean
_ (Range)
AND DIRECTION Mean (Ranqe)
Mean (Range (c)
Nb-95 0.003
(-0.01 - 0.01)
Within 500 feet 0.003
(-0.01 - 0.01)
N/A 0
of Discharge K-40 3.0 (1.7 - 3.9)
Within 500 feet 3.0 (1.7 - 3.9)
N/A 0
of Discharge Fish-Other Sr 8
0.018 0.000
(-0.002 - 0.003)
Within 500 feet 0.001 (0.000 - 0.003)
N/A 0
(pCi/g)
Sr-89 of Discharge Sr-90 0.009 0.002 (0.002 - 0.004)
Niantic Bay 0.003 (0.002 - 0.004)
N/A 0
0.3 Miles WNW Ge(Li) 3 0.056 0.008
(-0.005 - 0.02)
Within 500 feet 0.009 (0.000 - 0.02)
N/A 0
Cs-137 of Discharge I-131 0.005
(-0.01 - 0.02)
Within 500 feet 0.01
(-0.01 - 0.02)
N/A 0
of Discharge Cs-134 0.05 0.001
(-0.006 - 0.01)
Within 500 feet 0.002 (0.000 - 0.006)
N/A 0
of Discharge Mn-54 0.05 0.001
(-0.01 - 0.003)
Within 500 feet 0.001 (0.000 - 0.003)
N/A 0
l of Discharge Co-58 0.05
-0.003
(-0.01 - 0.001)
Niantic Bay
-0.001 (-0.004 - 0.000)
N/A 0
0.3 Miles WNW
TABLE 3-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SUPNARY MILLSTONE NUCLEAR POWER STATION, UNITS 1 and 2 DOCKET 50-245 and 50-336 JANUARY - DECEMBER 1985 ANALYSIS AND MINIMUM ALL INDICATOR LOCATION _WITH HIGHEST ANNUAL MEAN CONTROL LOCATIONS
- OF MEDIUM OR TOTAL NUMBER DETECTABLE LOCATIONS PATHWAY OF ANALYSES LEVELS (b)
NAME, DISTANCE (b)
(b)
NRMs SAPFLED PERFORMED (MDL's)(a)
Mean (Range)
AND OIRECTION Mean (Range)
Mean (Range)
(c)
Within 500 feet Co-60 0.05 0.001
(-0.01 - 0.01) of Discharge 0.001
(-0.01-0.01)
N/A 0
and Niantic Bay 0.3 Miles WNW Zr-95 0.001
(-0.01 - 0.02)
Niantic Bay 0.003
(-0.01 - 0.02)
N/A 0
0.3 Miles WNW Within 500 feet 0.006
(-0.005 - 0.02) of Discharge and 0.006
(-0.005 - 0.02)
N/A 0
Nb-95 Niantic Bay 0.006 (0.00 - 0.02) 1 l
0.3 Miles WNW K-40 2.2 (0.9 - 3.5)
Within 500 feet 2.3 (0.9 - 3.1)
N/A 0
of Discharge i
Musse1s Sr 7.4 0.018 0.002
(-0.008 - 0.02)
Niantic Shoals 0.005
(-0.003 - 0.02) 0.001
(-0.001 - 0.003) 0 (pCi/g)
Sr-89 1.8 Miles NW Sr-90 0.009 0.002
(-0.001 - 0.005)
Golden Spur 0.003 (0.002 - 0.004) 0.003 (0.002 - 0.004) 0 4.7 Miles NNW l
Ge(Li) 7.4 0.056 0.008
(-0.005 - 0.05)
Within 500 feet 0.014
(-0.005 - 0.05) 0.003 (0.000 - 0.01) 0 l
-0.003
(-0.04 - 0.02)
Golden Spur 0.01
(-0.01 - 0.04) 0.01
(-0.01 - 0.04) 0 4.7 Miles NNW i
i
TABLE 3-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRN1 SUMHARY MILLSTONE NUCLEAR POWER STATION, UNITS 1 and 2 DOCKET 50-245 and 50-336 JANUARY - DECEMBER 1985 ANALYSIS AND MINIMUM ALL INDICATOR LOCATION WITH HIGHEST ANNUAL MEAN CONTROL LOCATIONS i 0F MEDIUM OR TOTAL NUMBER DETECTABLE LOCATIONS PATHWAY OF ANALYSES LEVELS (b)
NAME DISTANCE (b)
(b)
NRMs SAMPLED PERFORMED (MDL's)(a)
Mean (Range)
AND DIRECTION Mean (Range)
Mean (Range)
(c)_
Cs-134 0.05
-0.003
(-0.01 - 0.01)
Golden Spur 0.001
(-0.005 - 0.01) 0.001
(-0.005-0.01) 0 4.7 Miles NNW Mn-54 0.05
-0.003
(-0.02 - 0.01)
Golden Spur 0.01 0.01 0
4.7 Miles NYd Co-58 0.05 0.007-(-0.005 - 0.014)
Within 500 feet 0.011 (0.01 - 0.012)
-0.008
(-0.02 - 0.01) 0 of Discharge Co-60 0.05 0.011 (0.000 - 0.03)
Niantic Shoals 0.011 (0.000 - 0.03) 0.008
(-0.01 - 0.03) 0 1.8 Miles Ed Zr-95
-0.009
(-0.03 - 0.01)
Golden Spur 0.008 (0.000 - 0.02) 0.003 (0.000 - 0.02) 0 4.7 Miles NNW 0.000
(-0.02 - 0.011)
Golden Spur 0.005
(-0.01 - 0.02) 0.005
(-0.01 - 0.02) 0 Nb-95 4.7 Miles NNW K-40 1.7 (1.2 - 2.3)
Within 500 feet 1.8 (1.2 - 2.3) 1.2 (1.0 - 1.5) 0 i
of Discharge Oysters / Clams Sr 20.8 0.018 0.000
(-0.004 - 0.007)
Niantic Shoals 0.002 (0.000 - 0.007) 0.001
(-0.002 - 0.007) 0 i
l (pC1/g)
Sr-89 1.8 Miles NW Thames River Sr-90 0.009 0.002
(-0.001 - 0.011)
Yacht Club 0.006 (0.002 - 0.011) 0.001 (0.000 - 0.003) 0 4 Miles ENE l
TABLE 3-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SupMARY MILLSTONE NUCLEAR POWER STATION, UNITS 1 and 2 DOCKET 50-245 and 50-336 JANUARY - DECEMBER 1985 ANALYSIS AND MINIMUM ALL INDICATOR LOCATION WITH HIGHEST ANNUAL MEAN CONTROL LOCATIONS MEDItM 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)
Golden Spur and Within Ge(Li) 20.8 0.056 0.00
(-0.02 - 0.02) 500 feet of D1scharge 0.008
-0.01 - 0.03 0.003
(-0.03 - 0.03)
O Cs-137 4.7 Miles NNW 0.On8 0.000 - 0.02 I-131
-0.007
(-0.04 - 0.02)
Black Point 0.00
(-0.02 - 0.01)
-0.01
(-0.05 - 0.03) 0 2.6 Miles WSW Cs-134 0.05
-0.002
(-0.01 - 0.01)
Golden Spur 0.006 (0.000 - 0.01) 0.004
(-0.001 - 0.01) 0 4.7 Miles NNW Waterford Shellfish Mn-54 0.05
-0.001
(-0.02 - 0.03)
Bed #1 0.011
(-0.004 - 0.03) 0.000
(-0.02 - 0.02) 0 0.5 Miles WNW Co-58 0.05 0.01
(-0.01 - 0.14)
Within 500 feet 0.06 (0.00 - 0.14) 0.000
(-0.007 - 0.01) 0 of Discharge Co-60 0.05 0.05
(-0.01 - 0.51)
Within 500 feet 0.21 (0.02 - 0.51) 0.003
(-0.01 - 0.02) 1 of Discharge Waterford Shellfish j
Zn-65 0.11
-0.003
(-0.07 - 0.05)
Bed #1 0.003
(-0.01 - 0.02)
-0.008
(-0.03 - 0.02) 0 0.5 Miles WNW j
Zr-95
-0.003
(-0.04 - 0.04)
Niantic Shoals 0.005
(-0.01 - 0.04)
-0.006
(-0.05 - 0.03) 0 1.8 Miles NW t
O.'
i 7f
, a(
~
TABLE 3-1 j
ENVIRONMENTAL RADIOLOGICAL MONITORING."ROGRAM SUP94ARY MILLSTONE NUCLEAR POWER STATION, UMITS 1 snd 2 DOCKET 50-245 and 50-336 JANUARY - DECEMBER 1985 *
<4NALYSIS AND MINIMUM ALL INDICATOR LOCATION WITH HIGHEST ANNUAL MEAN CONTROL LOCATIONS e
< MEDIUM OR JTOTAL NUMBER DETICTABLE LOCATIONS
. NAME, DISTANCE m
' PATHWAY OF ANALYSES LEVELS (b)
- OF (b)
(b)
NRMs 4'.
SR9tED PERFORMED (MDL's)(a)
Mean (Range)
AND DIRECTION Mean (Ranoe)-
Mear ~
(Range)
(c)_
e' i
Ag-110m 0.01
(-0.02 - 0.22)
Within 500. feet 0.07 (0.01 - 0.22) 0.001
'(-0.01 - 0.01)'
0
/ q
\\.
[
of Discharge.
N t
K-f) 1.7 (1.0 - 4.8)
Black Point 2.2 (1.1 - 4.8) 1.6 (1 2',- 2.5)
J 2.6 litles WSW Lobsters Sr 8,4 0.018 0.000
(-0.013 - 0.007)
Niantic Bay 0.001
(-0.004 - 0.006)
-0.005 U.d2-0.004) 0 (pCi/g)
Sr-59 0.3 Miles WNW u.
L w,
(0.001 - 0.(/3)4 " !ON' Sr-90 0.009 0.009 (0.005 - 0.015)
Within 500 feet 0.011 (0.006 - 0.015) 0.005
% ('
of Discharge T
Ge(Li) 8,4 0.056 0.006 (0.000 - 0.02)
Within 500 feet 0.008 (0.000 - 0.02) 0Q03
(-0.01"-0.01) 0i.
Cs-137 of Discharge
-- 1 1,
3
<- 4 1-131 0.009
(-0.02 - 0.03)
Within 500 feet 0.01 (0.00 - 0.03)
< 0.p'h3 (0.000 - 0.02) 0 of Discharge a,
Cs-134 0.05 0.00
(-0.01 - 0.02)
Niantic Bay 0.003
(-0.Q' - 0.02)
-0.003
(-0.01 - 0.000) 0 0.3 Miles WNW
=
s Mn-54 0.05 0.01
(-0.01 - 0.02)
Niantic Bay 0.008
(-0.01 - 0.02) 0.003
' ( -0.01 - 0.01) 0 0.3 Miles WNW
',f'
~
Co-58 0.05 0.004
(-0.01 - 0.02)
Niantic Bay 0.004 (0.000 - 0.02) 0.003
(-0 91 - p al)'
O 0.3 Miles WNW l
TABLE 3-1 ENVIRONMENTAL RA010 LOGICAL MONITORING PROGRAM StM4ARY MILLSTONE NUCLEAR POWER STATION, UNITS 1 and 2 00CKET 50-245 and 50-336 JANUARY - DECEtBER 1985 ANALYSIS AND MINIMUM ALL INDICATOR LOCATION WITH HIGHEST ANNUAL EAN CONTROL LOCATIONS MEDIUM OR TOTAL NUMBER DETECTABLE LOCATIONS f CF PATHWAY
.OF ANALYSES LEVELS (b)
NAME, DISTANCE (b)
(b)
NRMs SAMPLED PERFORMED (MDL's)(a)-
Mean (Range)
AND DIRECTION Mean (Range)
Mean (Range)
(c)
Co-60 0.05 0.01
(-0.01 - 0.03)
Within 500 feet 0.02 (0.01 - 0.03) 0.01 (0.00-0.02) 0 of Discharge 0.005
(-0.03 - 0.03)
Within 500 feet 0.005
(-0.01 - 0.03)
-0.005
(-0.01 - 0.01) 0 Zr-95 of Discharge i
0.00
(-0.01 - 0.02)
Giant's Neck 0.003
(-0.01 - 0.01) 0.003
(-0.01 - 0.01) 0 Nb-95 3.5 Miles W Ag-110m 0.00
(-0.02 - 0.02)
Within 500 feet 0.005
(-0.01 - 0.02) 0.003 (0.000 - 0.01) 0 of Discharge
-.~
f FOOTNOTES For Ge(Li) measurements the NDL's E 2 x /EB where B = background.
a.
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.
1.
L 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 l
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.
3 e,
Assuming 270 m / paper.
3 f.
Assuming 1080 m.
g.
Quarterly composites.
l h.
N/A--Not Applicable.
i 4
f 4
1 l
i 4
5 3-20
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 5.
Air Particulates, Quarterly Strontium and Cesium 6.
Soil **
7.
Milk - Dairy Farms 8.
Milk - Goat Farms 9.
Pasture Grass *
- 10. Well Water
- 11. Reservoir Water
- 12. Fruits & Vegetables *
- 13. Meat, Poultry and Eggs *
- 14. 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.
3-21
LOCATION KEY FOR DATA TABLES Data Table Section 2.0 Location #
Location #
01 Old Millstone Rd. - NNW, 0.6 miles 1
02 Weather Shack - S, 0.3 miles 2
03 Bird Sanctuary - NE, 0.3 miles 3
04 Albacore Drive - N, 1 mile 4
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
08 Millstone Environmental Lab - SE, 0.3 miles 8
09 Bay Point Beach - W, 0.2 miles 9
10 Pleasure 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 15A Montville, Conn. - N, 14 miles 15 16A Old Lyme, Conn. W, 9 miles 16 17 Well #1 - NNE, 1.5 miles 17 18 Well #2 - NNE, 1 mile 18 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 24 Goat Farm #2 - NE, 14 miles 24 25 Within 10 miles of Plant 26A Beyond 10 miles of Plant 30A Golden Spur - NNW, 4.7 miles 1
31 Niantic Shoals - NW, 1.8 miles 2
32 Within 500' of Discharge 3
33 Seaside Point - ESE, 1.6 miles 4
34 Thames River Yacht Club - ENE, 4.0 miles 5
35 Niantic Bay - WNW, 0.3 mile 6
36 Black Point - WSW, 2.6 miles 7
37A Giant's Neck - W, 3.5 miles 8
38 Waterford Shellfish Bed #1 - WNW, 0.5 miles 10 398 Jordan Cove - NNE, 0.2 miles 408 Discharge Quarry SOB Myrock Avenue - ENE, 3.2 miles 518 Groton Reservoir - ENE, 7.5 miles 528 Lake Konomoc - NNW, 7.5 miles 538 Niantic (CL&P) - WNW, 1.7 miles 548 Billow Road - WSW, 2.4 miles 55B Black Point - SW, 2.6 miles A - Control Stations B - Site not required by ETS
2 l
MILLSTONE POINT TABLE 1A MONTHLY GAMMA EXFOSURE RATEttN/HR1 PERIDO L0CATIOHS ENDING 01 02 03 04 05 06 07 03 09 10 11 1/31/85 (a) 8.7 (b) 13.0 8.3 8.6 7.8 8.9 10.8 10.3 10.6 8.6 8.1 2/28/85 9.3 13.6 8.9 8.9 8.3 9.8 11.2 11.1 11.3 8.9 8.1 3/31/85 9.2 13.7 8.7 9.0 8.0 9.1 11.1 10.9 11.0 8.8 8.6 4/30/85 9.7 14.1 8.9 9.3 8.6 9.9 11.5 11.4 11.6 9.3 8.6 5/31/85 9.2 13.7 8.6 9.4 8.6 9.2 11.1 11.2 11.1 8.7 8.7 6/30/85 9.5 13.9 8.8 9.3 9.1 9.8 11.2 11.5 11.2 9.0 8.5 7/31/85 9.0 13.6 8.4 9.4 8.5 9.1 11.0 11.2 11.3 8.5 8.6 8/31/85 9.6 13.9 8.9 9.6 8.6 9.7 11.7 13.1(c) 11.6 9.1 8.7 9/30/85 9.0 13.2 8.4 9.2 7.3 8.9 11.0 13.6 11.1 8.3 8.4 10/31/85 9.2 13.3 8.6 9.3 7.0 9.4 10.7 13.5 11.1 8.9 8.4 11/30/85 9.3 12.9 8.6 9.4 6.4 8.9 10.3 13.1 9.9 9.1 8.7 12/31/85 9.1 12.7 8.6 9.3 6.5 9.3 10.4 13.2 10.2 8.8 8.2 12A 13A 14A 15A 16A 50B 53B 548 SSB
_ =___
1/31/85 8.1 8.5 10.5 8.3 8.1 8.3 8.3 8.6 7.6 2/28/85 8.7 9.4 10.9 9.0 8.2 9.0 9.0 9.4 8.0 3/31/85 8.6 9.3 11.4 8.8 8.3 8.5 8.5 8.9 7.9 4/30/85 8.9 9.8 11.6 9.5 8.5 9.0 9.1 9.7 8.3 5/31/85 8.6 9.1 11.5 8.9 8.3 8.7 8.5 9.2 8.1 6/30/85 8.3 9.9 11.7 9.7 8.5 8.7 8.9 9.5 8.1 7/31/85 8.5 8.9 11.4 8.9 c.2 8.1 8.4 9.0 8.0 8/31/85 9.1 9.5 12.0 10.1 8.2 8.3 8.9 9.6 8.1 9/30/85 8.3 9.0 11.4 8.9 8.5 8.0 8.3 8.9 7.7 10/31/85 8.3 9.5 11.3 9.5 8.3 8.4 8.8 9.2 7.9 11/30/85 8.8 9.2 11.6 9.0 8.5 8.4 8.0 9.0 7.8 j
12/31/85 8.4 9.4 11.3 9.6 8.2 8.4 8.8 9.1 7.7
}
I i
{
TABLE IB SEMIAt,NUAL GAMMA EXF05URE R ATE (UR/HR1 PERIOD t0 CATIONS ENDING 01 02 03 04 05 06 07 08 09 10 11 6/30/85 9.3 13.7 8.7 9.1 8.4 9.4 11.1 11.1 11.1 8.9 8.4 12/31/85 9.2 13.3 8.6 9.4 7.4 9.2 10.8 12.9 10.9 8.8 8.5
{
12A 13A 14A ISA 16A 50B 53B 54B SSB
_ _ _ _ _ _ -. _ _ _ _ _ _ _ _. _ _ _ _. - - _ _ _ _. _ _ _ _ _ _ _ _ _ _.... _ _....... _........ - - _ _...... =
__=___._
6/30/85 8.5 9.3 11.3 9.0 8.3 8.7 8.7 9.2 8.0 12/31/85 8.6 9.2 11.5 9.3 8.3 8.3 8.7 9.1 7.9 (a) Not actual dates, TLD's are changed near the end of the month.
(b) Results are +/- 10%.
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.001 0.001 0.001 0.001 0.001 0.002 0.0 0.003 0.003 0.011
.010 0.030 0.001 0.004 0.130 0.030 0.001 0.002 14A 0.0 0.002
.001 0.002 0.003 0.004 0.001 0.005 0.0 0.020
.030 0.050
.007 0.006 0.140 0.040 0.002 0.004 15A
.001 0.002 0.0 0.002
.001 0.003
.001 0.004 0.0 0.020
.070 0.030 0.003 0.005 0.110 0.030 0.001 0.003 16A 0.0 0.002 0.0 0.002 0.0 0.002 0.0 0.004 0.0 0.013
.010 0.030 0.003 0.004 0.150 0.030 0.0 0.003 538 0.0 0.003 0.001 0.002 0.001 0.004
.001 0.006 0.010 0.020
.050 0.050 0.005 0.007 0.120 0.040
.003 0.005 TABLE 4D AIR PARTICULATES GAMMA SPECTRA - AFR (FCI/N3)
ANALY$ES LOCATICN CS-137 CS-134 RU-103 ZR-95 RU(RH)-106 K-40 TH-228 EE-7 US-95
-__=....-.......................................................
(+/-)
(+/-)
(+/-)
(+/-)
(+/-)
(+/-)
(+/-)
(+/-l
(+/-)
1
.001 0.002 0.0 0.002
.002 0.003 0.001 0.003
.00S 0.014
.030 0.030 0.001 0.004 0.130 0.030 0.001 0.003 2
0.001 0.002 0.0 0.002 0.0 0.003 0.003 0.004 0.0 0.020
.020 0.040 0.001 0.005 0.130 0.030 0.001 0.003 3
0.001 0.003 0.001 0.004
.003 0.005
.001 0.007 0.020 0.030 0.0 0.070 0.005 0.009 0.160 0.050 0.006 0.006 4
0.0 0.003 0.0 0.003
.000 0.006 0.002 0.007
.020 0.030 0.0 0.070 0.003 0.009 0.140 0.050 0.003 0.006 10 0.001 0.002 0.0 0.002 0.0 0.003 0.001 0.003
.008 0.015 0.0 0.040 0.0 0.004 0.120 0.030 0.002 0.003 11 0.0 0.004 0.001 0.003
.001 0.005 0.003 0.007 0.030 0.030 0.0 0.060 0.002 0.007 0.120 0.050 0.003 0.006 124 0.0 0.002 0.0 0.002 0.001 0.003 0.002 0.003 0.008 0.014
.050 0.030 0.001 0.004 0.110 0.030 0.0 0.003 134
.001 0.002 0.0 0.002 0.0 0.003
.002 0.004 0.004 0.014 0.030 0.040 0.0 0.004 0.110 0.030 0.001 0.003 14A
.002 0.003 0.003 0.003 0.0 0.005 0.005 0.007 0.010 0.030
.080 0.060
.004 0.009 0.130 0.050 0.002 0.005 ISA
.001 0.003 0.0 0.003
.001 0.005
.003 0.007
.020 0.030
.100 0.050 0.003 0.009 0.110 0.040
.001 0.004 16A
.001 0.002 0.0 0.002
.001 0.003
.001 0.005 0.0 0.020
.050 0.040
.003 0.005 0.170 0.040 0.0 0.003 538 0.001 0.003 0.0 0.003
.002 0.005 0.003 0.009 0.0 0.030
.050 0.060 0.001 0.008 0.140 0.050
.001 0.006
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TA?LE 4G AIR PARTICULATES NP GAMMA SPECTRA - JUL (PCI/H3)
ANALYSES LDCATIDH CS-137 CS-134 RU-103 ZR-95 RUIPH)-106 K-40 TH-228 BE-7 HD-95
(+/-)
(+/.)
(+/-)
(+/-)
(+/-)
(+/-)
(+/-)
(+/-)
(+/-)
1 0.0 0.002 0.0 0.002
.001 0.003
.004 0.003 0.006 0.014 0.010 0.030
.004 0.005 0.070 0.030 0.0 0.002 2
0.0 0.002
.001 0.002 0.001 0.003 0.001 0.004
.020 0.020 0.0 0.030
.001 0.004 0.120 0.030
.001 0.003 3
0.002 0.003
.001 0.003
.002 0.005
.004 0.007 0.010 0.030 0.050 0.070
.008 0.003 0.140 0.050
.003 0.005 4
0.002 0.003
.001 0.003 0.0 0.005 0.001 0.007 0.010 0.030 0.020 0.060 0.0 0.008 0.160 0.050
.004 0.004 10 0.0 0.002
.001 0.002 0.0 0.003
.002 0.004
.003 0.015 0.030 0.040 0.001 0.004 0.140 0.030 0.0 0.002 11
.002 0.003
.001 0.003 0.002 0.005 0.002 0.006
.010 0.030 0.020 0.060 0.003 0.008 0.100 0.040
.001 0.004 12A
.001 0.002
.001 0.002
.001 0.003
.001 0.003 0.0 0.015 0.020 0.040 0.001 0.004 0.090 0.030 0.001 0.003 13A 0.0 0.002
.002 0.002 0.002 0.003 0.001 0.004 0.0 0.014
.030 0.030
.001 0.004 0.110 0.030
.001 0.002 14A 0.001 0.003
.001 0.003 0.002 0.005 0.0 0.006
.010 0.020 0.030 0.060
.004 0.006 0.120 0.040 0.001 0.005 15A 0.0 0.003 0.0 0.003 0.004 0.004
.005 0.005 0.010 0.030 0.060 0.060
.006 0.006 0.110 0.040
.001 0.005 16A 0.002 0.002
.001 0.002
.002 0.003 0.003 0.004 0.0 0.020
.010 0.040 0.0 0.005 0.120 0.030 0.0 0.003 538 0.0 0.004 0.002 0.003
.003 0.005
.005 0.007 0.0 0.030 0.120 0.080
.003 0.008 0.120 0.040 0.001 0.005 TABLE 4H AIR PARTICULATES GAMMA SPECTRA - AUG (FCI/M3)
AHALYSES LOCATION CS-137 CS-134 RU-103 ZR-95 RU(RH)-106 K-40 TH-228 BE-7 UB-95
(+/-)
(+/-)
(+/-)
I+/-)
(+/-)
(+/-)
(+/-)
(+/-)
1+/-)
1 0.0 0.001 0.000 0.001
.001 0.003 0.001 0.003
.005 0.013
.030 0.020 0.001 0.003 0.100 0.030 0.001 0.003 2
0.001 0.002 0.001 0.001
.001 0.003 0.0 0.003
.004 0.014 0.020 0.030
.002 0.004 0.120 0.030 0.001 0.003 3
.001 0.003 0.001 0.002
.001 0.005 0.001 0.006 0.0 0.020 0.010 0.050 0.002 0.007 0.090 0.040
.002 0.005 4
0.0 0.002 0.0 0.002 0.001 0.005 0.001 0.006 0.020 0.020 0.040 0.050 0.0 0.006 0.120 0.040 0.0 0.006 10 0.001 0.001 0.000 0.001 0.002 0.003 0.001 0.003 0.005 0.010 0.020 0.030 0.002 0.004 0.100 0.030 0.001 0.003 11
.002 0.002 0.001 0.003 0.004 0.005 0.002 0.007 0.010 0.020 0.090 0.050
.007 0.006 0.100 0.040
.001 0.005 12A 0.0 0.001 0.001 0.001 0.0 0.003 001 0.003
.005 0.013 0.010 0.030 0.003 0.003 0.090 0.020
.002 0.002 13A 0.0 0.001
.001 0.001 0.001 0.003 0.001 0.004
.003 0.012 0.020 0.030
.004 0.003 0.080 0.020 0.001 0.003 14A 0.001 0.002
.001 0.002 0.001 0.005 0.001 0.006
.010 0.020 0.020 0.050
.003 0.006 0.100 0.040 0.003 0.005 ISA 0.002 0.002 0.0 0.002 0.0 0.004 0.004 0.006 0.0 0.020 0.030 0.050 004 0.006 0.130 0.040 0.003 0.004 16A 0.0 0.001 0.001 0.001 0.002 0.002 0.001 0.003
.010 0.013 0.030 0.030 0.001 0.003 0.110 0.030 0.001 0.002 53B 0.001 0.003 0.0 0.003
.006 0.006 0.005 0.006 0.0 0.020 0.060 0.060
.006 0.007 0.090 0.040 0.001 0.005 i
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l TABLE 4K AIR PARTICULATES MP GAMMA SPECTRA - HOV (PCI/M3) l ANALYSES LOCATION CS-137 CJ-134 RU-103 ZR-95 RUtRH3-106 K-40 TH-228 BE-7 NS-95 j
_ =_=
(+/-)
(+/-l 1+/-)
(+/-)
(+/-)
(+/-)
(+/-)
(+/-)
(+/-)
1
.001 0.002 0.001 0.002
.002 0.003 002 0.004
.010 0.020 0.090 0.040 0.002 0.005 0.090 0.030 0.002 0.003 l
2
.001 0.002
.001 0.002 0.0 0.003 0.002 0.004 0.0 0.020 010 0.030 0.001 0.005 0.110 0.030 0.001 0.003 3
.001 0.004 0.002 0.004 0.004 0.006
.005 0.009 0.0 0.030 0.050 0.070
.001 0.009 0.070 0.040 0.001 0.007 4
.001 0.003 0.0 0.003 0.0 0.006
.003 0.008 0.0 0.030 0.030 0.070
.004 0.009 0.070 0.040
.003 0.006 10 0.001 0.002
.002 0.002 0.002 0.003
.002 0.004 0.0 0.020
.020 0.030 0.0 0.005 0.050 0.030 0.0 0.003 l
11
.001 0.003 0.001 0.003 0.0 0.005
.004 0.007 0.0 0.030 0.040 0.060
.002 0.008 0.060 0.040
.006 0.005 12A
.001 0.001
.001 0.002
.001 0.003 0.002 0.003
.003 0.015 0.030 0.030 0.0 0.005 0.060 0.020 003 0.003 13A 0.0 0.002 0.0 0.002
.001 0.003 0.0 0.004
.004 0.013 0.010 0.040 0.002 0.004 0.060 0.020
.001 0.003 l
14A
.001 0.003 0.001 0.003 0.0 0.006
.001 0.005
.010 0.030
.070 0.060 0.0 0.007 0.060 0.040
.002 0.006 j
15A 0.002 0.003
.002 0.003
.002 0.005
.001 0.006
.020 0.030 0.050 0.060
.004 0.008 0.090 0.040 0.001 0.006 16A 0.005 0.006 0.0 0.002 0.0 0.003
.002 0.004 0.010 0.020
.010 0.030
.004 0.004 0.090 0.030 0.001 0.003 53B 0.001 0.003 0.0 0.003
.004 0.006 0.004 0.007
.010 0.030
.010 0.060 0.002 0.009 0.120 0.040 0.002 0.007 l
1 TABLE 4L j
AIR PARTICULATES 1
GANNA SPECTRA - DEC
{
(PCI/M3)
ANALYSES l
LOCATION CS-137 CS-134 RU-103 ZR-95 PUERH)-106 K-40 TH-228 BE-7 HS-95 i
(+/-)
(+/-)
I+/-)
(+/-)
t+/-)
(+/-)
(+/-)
(+/-l
(+/-)
1 0.0 0.001 0.0 0.001 0.0 0.002 0.003 0.003 0.002 0.012
.010 0.030 0.002 0.004 0.080 0.020 0.002 0.002 2
0.001 0.002 0.0 0.002 0.0 0.002
.001 0.003 0.002 0.014
.010 0.030 0.001 0.004 0.100 0.020 0.002 0.002 4
3
.002 0.003 0.001 0.003 0.001 0.004 0.001 0.005 010 0.020 0.080 0.060
.001 0.008 0.070 0.030 0.0 0.004 4
.000 0.003 0.001 0.003 0.001 0.004 0.001 0.004
.010 0.030 0.040 0.060
.003 0.007 0.130 0.040
.002 0.003 10 0.0 0.001 0.0 0.001 0.0 0.002 0.0 0.003 0.006 0.011 0.0 0.030
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a
. TABLE 10 WELL WATER MP (PCI/L)
COLLECTION LDCATION DATE SR-89 SR-90 CS-137 I-131 CS-13+
NH-54 CO-58
== = ___...........
j 17 6/12/85 0.2 0.5 0.5 0.2 2.0 _ (+/ )
(+/-)
(+/-)
(+/-)
(+/-)
l
(+/.)
(+/-)
2.0 0.
20.
2.
3.
O.
3.
O.
3.
17 9/10/85 0.4 0.5 0.3 0.2 2.0 3.0
-3.
5.
1.
3.
1.
2.
-1.
2.
-l 18 6/12/85 0.0 0.6 0.3 0.3 1.0 3.0 10.
20.
O.
2.
-1.
3.
-1.
3.
18 9/10/85 0.4 0.9 0.7 0.4 1.0 2.0 0.
5.
1.
2.
-1.
2.
-1.
-2.
4 i
.ZR-95 RU(RH)-106 CR-51 K-40
= _
_______...............==_
1
(+/-)
(+/-)
(+/-)
(+/-)
(+/-)
(+/-)
(+/-)
3 17 6/12/85 1.
3.
2.
8.
-7.
6.
4.
5.
-10.
20.
-30.
40.
20, 50.
j 17 9/10/85 0.
3.
-3.
6.
1.
6.
1.
4.
O.
20.
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20.
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50.
i 18 6/12/85 1.
3.
2.
8.
-5.
6.
2.
5.
10.
30.
10.
40.
50.
50.
18 9/10/85
-1.
3.
2.
6.
3.
6.
-3.
4.
10.
20, 0.
20.
40.
50.
BI-214
.TH-228 BE-7 NB-95 H-3 GROSS BETA
_______.............. __...................=__ --
(+/-)
(+/-)
(+/-)
(+/-)
(+/-)
(+/-)
17 6/12/85
-1.
5.
7.
7.
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O.
2.
4.
97.
55.
5.8 0.5 17 9/10/85 18, 5.
9.
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100.
60.
6.0 0.4 18 6/12/85
-6.
5.
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2.
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2.4 0.3 18 9/10/85
-1.
5.
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7.
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O.
O.
3.
O.
40.
3.4 0.3
TABLE 11 CESERVOI3 MATEJ PAGE 1 MP iPCI/LI COLLECTION LOCATION DATE SR-89 SR-90 CS-137 I-131 CS-134 191-54 CO-58
_=_--.............. -- _ _.....
(+/-)
(+/-)
(+/-)
(+/-)
(+/-)
(+/-)
(+/.)
CO-60 FE-59 ZN-65 ZR-95 RU(RH)-106 CR-51 K-40
(+/-)
(+/-)
(+/-)
(+/-)
(+/.)
(+/.I
(+/.3 NA-226 TM-228 BE-7 68-95 H-3 GROSS BETA
_ =-
(+/-)
(+/-)
f+/-)
(+/-)
(+/-)
(+/-)
These samples are not required.
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m TABLE 13 MP f*E AT. FOULTRY A EGGS (PCI/G)
COLLECTION LOCATIDI DATE TYPE
$R-89 SR-90 CS-137 I-131 CS-134 114-54
(+/.I
(+/-)
(+/.1
(+/-l
(+/.)
(+/.1 CD-58 CO-60 FE-59 ZN-65 ZR-95 rut #H3-106
_ _.. -.............................__.. =_--_ _ ___...
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(+/-)
t+/.I
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- A-2:6 TH-228 BE-7 NB-95
=..............
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TA8LE 14 SEA WATER PAGE 2 MP (PCI/LI COLLECTION LOCATIDH DATE PA-226 TH-228 BE-7 NB-95 H-3 BETA FR I BETA FR II
(+/-l
(+/-)
(+/-l
(+/-)
(+/-l
(+/-1
(+/-l 32 1/26/85
-1.
5.
3.
7.
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0.4 0.4 2.4 0.8 32 4/27/85
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4.0 DISCUSSION OF RADI0 CHEMICAL RESULTS Gamma Exposure Rate (Table 1)
The gama exposure rate is determined from the integrated exposure measured over a time period of approximately one month using CaF (Mn) thermoluminescent dosimeters. These glass bulb dosimeters 2
are subject to inherent self-irradiation which has been experimentally 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 1 uR/hr.
The exposure rate measurements exhibit the same trends as those since 1978. These measurements demonstrate the general variations in natural background radiation between the various on-site and off-site locations and include gama exposure from all sources including 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 Lyme (locations 13A, 15A, and 16A).
Evaluation of the monthly data indicates a noticeable increase starting in August at the Environmental Laboratory (location 8).
This increase is due to the repositioning of the TLD location, 25 feet in the soothwest direction to allow for facility expansion.
The new position is in closer proximity to granite beds.
Further evaluation of the data reveals a decrease in background at all locations during January of 1985, most probably caused by the large snowfall during this month and its resultant shielding effect.
Another decrease at some of the on-site locations only, is noted l
during the months of November and December. The data during this time frame indicates exposure levels slightly lower at some of the on-site locations (Weather Shack (02), Navy Laboratory (05), Fox Island (07), Millstone Environmental Latoratory (08), and Bay Point Beach (09)). This effect is attributable to Unit 1 being shutdown for refueling and is consistent with data of past years.
During Unit 1 operation, a small increase in exposure rates is caused by the direct exposure pathway of "skyshine" (i.e., scattered radiation from nitrogen-16 decay in the turbine; this pathway is unique to boiling water reactors). This direct exposure pathway decreases rapidly with distance from the turbine building, to levels that are virtually undetectable at the off-site locations. Special surveys performed during 1980 with a high pressure ion chamber support this 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.
Exposure rate levels in 1985 are larger than levels measured for the past few years. Five years prior to 1985, a trend of decreasing exposure rates had been observed (see Figure 4-1) due to photomuliplier tube aging.
In October 1984, a new TLD reader was 4-1
placed into service and since, measured exposure rates are comparable to those of years prior to 1980.
With the installation of the augmented off-gas treatment system in May of 1978, the plant effluents have decreased significantly to 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.
Air Particulates and Iodine (Tables 2, 3, 4A-L and 5)
Air is continuously sampled at seven inner ring and five outer ring locations by passing it through glass fiber particulate filters.
The filters are collected weekly and analyzed for gross beta activity. Results are shown in Figure 4-2 and Table 2.
Gross beta activity remained at levels similar to those seen in 1982-1984.
It failed to show the typical increase in gross beta activity in the spring and sumer from fallout 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 a slight variation between the activity measured at the inner and outer monitoring stations and as such, it is concluded that the plant contribution is negligible.
Charcoal cartridges are included at six of the air particulate stations for the selective collection of atmospheric iodine. These cartridges are analyzed on a weekly basis for I-131.
Data in Table 3 shows fourteen samples where I-131 was detected above its MDL and many other numerous positive values. All values above the MDL occur in the cold season, a period when increased use of wood and coal stoves causes higher particulate concentrations. The particulates create interference from radium-226 and its daughters.
GeLi analyses of these samples indicate no I-131 presence, verifying an interference problem. This and the fact that these values occur at both indicator and control locations suggests that all values above the I-131 MDL are attributable to statistical fluctuations in counting and counting interference. This premise is supported by the absence of I-131 in any of the cow milk samples. Milk from cows are much more sensitive indicators of environmental I-131.
The air particulate samples that are utilized for the weekly gross beta analyses are composited monthly and analyzed for gama emitting isotopes. The results, as shown in Tables 4A-4L, indicate the presence of naturally occurring Be-7, which is produced by cosmic processes. All other positive results are attributable to statistical fluctuations in counting. These analyses indicate the lack of plant effects.
For the measurement of Sr-89, Sr-90 and total cesium (Cs), the air 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 4-2
environmental radioactivity than gamma spectrum analyses, because of the larger sample volume as a result of compositing and the higher efficiency of beta counting. However, this higher sensitivity suffers from the drawback that it does not allow the separation of Cs-137 and Cs-134. Therefore, the results presented in Table 5 include total cesium along with Sr-89 and Sr-90. The cesium levels, as usual, followed the same trend as the gross beta results.
Indicator (inner ring) and control (outer ring) locations had comparable results, thus indicating that the total cesium is a result of fallout from weapons testing.
The Sr-90 results exhibit the same trends as the gross beta and Cs-137 results, remaining at low levels throughout 1985. 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 gama 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 eleven 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 uost sensitive indicator of fission product existence in the 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 range of results were 1.4 to 13.7 pCi/1 and 0 to 30 pCi/1 for Sr-90 and Cs-137, respectively.
Detailed analysis of this data has concluded that these levels are from weapons testing and are not plant related (see Section 6.0 for details to this argument). Only one Sr-89 value exists above the MDL. However, its value is due to statistical fluctuations in counting (confirmed by the fact that a couple of large negative values also appear). Sr-89 has only been seen in these samples during episodes of fresh fallout from weapons testing. This confirms that the presence of Sr-90 is the result of weapons testing.
4-3
Prior to 1982, Cs-137 for these samples was determined by cesium chemistry and represented as total cesium. Analysis of the 1979-1981 samples by gama 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 gama spectrometry has been improved and cesium chemistry discontinued. The only nuclide other than Cs-137, detected by gama 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 years' results. Two samples did indicate the presence of I-131. However, one value is a control location sample where the presence of I-131 is highly unlikely. Therefore, both values are probably due to statistical fluctuations. 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 is dependent on a number of parameters, including: metabolism of these animals, feeding habits, and feed type.
Samples taken during weapons testing periods have demonstrated higher uptake of fresh fallout nuclides (Sr-89 and I-131) at the indicator goat location.
This trend helps to explain the usual, higher than normal Sr-90 and Cs-137 concentrations at the indicator location as compared to the control location. Three Sr-89 values appear as possible positive values. However, reanalysis of the highest sample showed a lack of any Sr-89 presence, indicating the original value as being caused by counting statistics. This is also probably the cause of the positive results in the other two samples. 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.
Iodine releases were signficantly lower this year compared with those from past years.
For this reason there were no detectable levels above the MDL at the indicator location.
One measurement was above the MDL at the control location, however this and the other positive values are due to statistical fluctuations. Therefore, no plant related I-131 was seen in this media.
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 either goat location.
In April a grass sample was taken at goat location #2. The results are consistent with previous year's 4-4
results. Other data listed in this table are actually the results for samples of broad leaf vegetation. Two samples were 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 Cs-134 in these samples, it is concluded that no plant effects are seen in this media.
Well Water (Table 10)
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 levels similar to those of the past nine years; comparable to background concentrations shown at other locations (e.g., see Haddam Neck Station Radiological Environmental Monitoring Program). There was no station related activity measured in this media.
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 ef fluents 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.
Sr-90 and Cs-137 remained at levels similar to those observed for the past nine 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 Eqqs (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, ne 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 eight 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 4-5
background levels of H-3 are shown in all but one sample; during the fourth quarter there is an elevated concentration shown near the discharge area (location 32). Thus station effects are indicated.
The level is similar to those observed in 1981.
Due to the decay characteristics of H-3, the dose consequence of the observed H-3 concentration is negligible (see Section 5.0 for a discussion of the maximum dose consequences). One Beta Fraction II value and two Beta Fraction IV values were observed at higher levels. The remaining values of each were consistent among locations. The variability seen is within detection limits, therefore, the observance of H-3 was the only plant effect.
Bottom Sedinent (Table 15)
Similar to previous years, most bottom sediment samples exhibited the presenct of the naturally occurring radionuclides of K-40, Ra-226 and Tn-2281. Cosmic produced Be-7 was also observed in a one s6mple near its detection limita Some of the samples exhibited puttive values of Sr-90 at levels below its MDL.
No detectable Sr-69 was tbserved. Cs-137 was detected at a level ab0ve the MDL at a control locatior. However, the absence of Cs-134 in this sample and the relfti <e distance and direction of this sample location indicate 4
that this Cs-137 is not plant related.
Traces of Cs-137 were detected in a few other samples, however, its values do not increase wt% prorfatty to the plant.
Therefore these values seem fallout relcted.
Aquitic Flora (Tanle 16)
Consistent with previous observations, the naturally occurring radiottaclide, K-40, was observed in all of the aquatic flora san; oles. Sr-90 was also observed in all samples at positive levels, uselly below che MDL. Due to its consistency and the absence of detectable Sr-89, it is believ6d to be a result of weapons fallout and nut plant related. Like the sam;sles from 1983 and 1984, there was no I-131 seen in t%ca sacples. Fhwever, there were other indicatiens of plant effluents in this media.
Co-58 and Co-60 were observed at levels near those of 1983 and 1984. These levels are
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well below those seen in 1975-1976. Samp'iing of this meiia provides useful information because it is very sensitive to plant Mscharges, However, since seaweed in this area is not consumed, other nedia are i
utilized in the determination of dese consecuences (e.g., see shellfish and fish resuits).
Fish Floander (Table 17A)
The activity in this media is the same as that fe te past nine years. The Sre90 data consistea;1y :,howed positive va!ues, at levels below its MDL. The only radionuclide detected above the MDL was naturally occurring K-40.
Trerafore, it is concluded that plant effects for this sampling m6dia are insignificant at all locationsi 4--6 6
f
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 were detected in the quarry samples (i.e., location 408).
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.
However, using the concentrations measured in the quarry and diluting them by the appropriate near field dilution factor for quarry discharges into 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.
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 408) locations; the latter being an extra location.
The remaining locations utilize stocked oysters; trays are kept at these sampling areas to guarantee samples and facilitate sample collection.
The primary activity in most samples continues to be K-40.
Low positive values of Sr-90 were observed at random levels at all locations.
One sample shows the level of Sr-90 above the MDL.
However, all levels of Sr-90 are probably just traces of fallout confirmed 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 408). This activity included Co-58, Co-60, Zn-65, Ag-110m, and possible traces of Cs-137. 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 seven 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.
Clms (Table 20)
The predominant activity in clams was naturally occurring K-40.
Similar to 1980 samples, a cmall trace of plant related Co-60 was 4-7
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 318 (Niantic Shoals) are scallops while for location 408 (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.
The crab samples showed plant related concentrations of Co-58 and Co-60. 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.
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.
The only other detectable activity seen was K-40.
No plant related radioactivity was detected. These levels were similar to past data.
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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 0 to 50 mile population dose comitment. 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 comparison 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 gama 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 a m ming they are from an area within 500 feet of the station discharge.
As indicated by Table 5.1, there is also a direct gama dose attributable to the operation of Unit I.
This direct dose is inherent to BWR's (Boiling Water Reactors).
It is due to direct and scattered radiation (skyshine) of the high energy gama rays from Nitrogen-16 in the radioactive steam which circulates through the turbine.
It should be noted that the indicated dose due to direct radiation is to the maximum individual and is corrected for periods when Unit I is not operating (i.e., there is no direct dose when steam is not generated).
Summarizing the data in Table 5.1, the maximum total doses to an individual are: 1.5 mrem whole body to an adult, 0.14 mrem to an child's thyroid, and 0.15 mrem to an adult's GI (LLI) (gastrointestinal tract-lower large intestine).
Since the maximum dose consequence to an individial is at the 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 1985 for the average individual:
5-1
ANNUAL WHOLE BODf DOSE DUE TO AIRBORNE EFFLUENTS = 0.00021 mrem ANNUAL WHOLE B0DY 00SE DUE TO LIQUID EFFLUENTS = 0.00017 mrem 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 1985 on the allowable maximum dose to an individual of the general public are given in 40CFR190 as 25 mrem whole body, 75 mrem thyroid, and 25 mrem any other organ. These standards are a fraction of the normal background radiation dose of 125 mrem per year and are designed to be inconsequential in regard to public health and safety.
Since plant related doses are even a smaller fraction of natural background, they have insignificant public health consequences.
In fact, the plant related doses to the maximum individual are less than of the variation in natural background in Connecticut.
5-2
TABLE 5.1 COMPARISON OF DOSE CALCULATION METHODS MILLSTONE NUCLEAR POWER STATION JANUARY-DECEMBER 1985 ANNUAL DOSE * (MILLIREM)
PATHWAY ORGAN METHOD 1(j)
METHOD 2(j)
Unit 1 Unit 2 Total (BWR)
(PWR)
AIRBORNt FFLUENTS
- 1. External Gamma Dose (2) Max. Ind.-Whole Body 0.007 0.015 0.022 NAD(5)
- 2. a.
Inhalation Max. Ind.-Thyroid 0.0007 0.038 0.039 ND,( ) < 0.6 b.
Vegetables Max. Ind.-Thyroid 0.0071 0.064 0.071 ND c.
Goat's Milk Max. Ind.-Thyroid 0.050 0.026 0.076
< 0.4 LIQUID EFFLUENTS
- 1. Fish Max. Ind.-Whole Body 0.0027 0.0186 0.021 0.024 Max. Ind.-GI(LLI)(4) 0.00109 0.0678 0.069 0.0023 Max. Ind.-Liver 0.00402 0.0265 0.031 0.033
- 2. Shellfish Max. Ind.-Whole Body 0.00062 0.0104 0.011 0.0022(8)
Max. Ind.-GI(LLI) 0.00185 0.0830 0.085 0.020(8)
DIRECT DOSE
- 1. Skyshine Max. Ind.-Whole Body 1.4(7)
N/A(6) 1,4 1,4(9)
Table 5.1 (continued)
(1) Method 1 uses measured station discharges and meteorological data as input,,arameters 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 (teen 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 NNW. The doses for inhalation and vegetable consumption assume that the individual resides at the point of maximum quarterly dose. Therefore, his residence is subject to variation for conservatism.
(3) 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)
NAD - High pressure ion chamber was out of service for most of 1985. TLD's cannot detect levels which are such a small fraction of natural background.
(6)
Not applicable.
(7)
Based on calculations performed utilizing the computer code, SKYSHINE, developed by Oak Ridge National Laboratories.
(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 pressure ion chamber and ratioed to the actual operating power.
6.0 DISCUSSION The evaluation of the effects of station operation on the environment requires the careful consideration of many factors.
Those factors depend upon the media being effected. They include station release rates, effluent dispersion, occurrence of nuclear weapons tests, seasonal variability of fallout, local environment, and locational variability of fallout. Additional factors affecting the uptake of radionuclides in milk include soil conditions (mineral content, pH, etc.), quality o' fertilization, quality of land management (e.g., irrigation), pasturing habits of animals, and type of pasturage. Any of these factors could cause significant variations in the measured radioactivity. A failure to consider these factors could cause erroneous conclusions.
Consider, for example, the problem of deciphering the effect of station releases on the radioactivity measured in milk samples.
This is an important problem because this product is widely consumed and fission products readily concentrate in this media. Some of these fission products, such as I-131 and Sr-89 are relatively short-lived. Therefore they result from either plant effluents or from recent nuclear weapons tests. Sr-89's lifetime is longer than I-131's, therefore it must be remembared that it will remain around for much longer periods of time.
Problems are caused by the long-lived fission products, Sr-90 and Cs-137. These isotopes are still remaining from the high weapons testing era of the 1960's. This results in significant amounts of Sr-90 and Cs-137 appearing in milk samples. Distinguishing between this " background" of fallout activity and plant effects is a difficult problem.
In reviewing the Sr-90 and Cs-137 measured in cow and goat milk in the areas around the Millstone and Haddam Neck stations, a casual observer could notice that in some cases the levels of these iso. topes are higher at farms closer to the station than at those further away from the stations. The stations effluents might at first appear to be responsible. However, the investigation of the following facts prove this conclusion wrong.
1.
The stations accurately measure many fission products, including Sr-90 and Cs-137 in their releases. Based on there measurements and proven models developed by the Nuclear l
Regulatory Commission, concentrations in the environment can be l
calculated. These calculations (generally conservative, see Section 5.0) show that insufficient quantities (by more than a factor of 1000) of Sr-90 and Cs-137 have been released from the stations to yield the measured concentrations in milk.
2.
Based on the ratio of Sr-89 to Sr-90 in the measured releases from the stations and on the similar chemical properties of the two nuclides, plant-related Sr-90 cannot be detected in milk without also detecting plant related Sr-89. During 1981 (and a few other occassions), Sr-89 has been detected in many of the milk samples. To investigate the source of Sr-89, air particulate data has been evaluated.
Evaluation shows that airborne Sr-89 is generally uniform at all the indicator and 6-1
=&
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 inmediate station areas have always shown higher levels of weapons fallout related Sr-90 and Cs-137 (see Figures 6-1 and 6-2).
The ratio of activity between the locations has not changed with plant operation. All areas show the same significant decrease in radioactivity since the 1964 Nuclear Test Ban Treaty.
5.
Local variability of Sr-90 and Cs-137 in milk is common through-out the United States. Due to the variability in soil conditions, pasturing methods, rainfall, etc., it is the rule rather than the exception. Therefore, it is not surprising that certain farms have higher levels of radioactivity than other farms.
In fact, there are some cases where the farms further from the station have higher Sr-90 and Cs-137 values than the farms that are closer to the station (e.g., see Haddam Neck Goat Milk data.)
6.
The goat farm with the highest levels of Sr-90 and Cs-137 has 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 Comission, Environmental Protection Agency and Connecticut Department of Environmental Protection.
i l
6-3
CY Start-up M1 Start-up Mt Stsrt-up i
l i
FIGURE 6-1 STRONTIUM-90 IN MILK c
22.Si 20.Di c
=
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=
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I T
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2.Si 61 62 63 64 65 66 67 68 69 70 71 72 73 74 75 76 77 78 79 80 81 82 83 84 85 YEAR C = CENTRAL CONN. ARER--SAMPLES OF POOLED MILK--YEARLY AVERAGE OF MONTHLY DATR H = HADDRM NECK AREA--RVERAGE OF INDIVIDUAL FARM SAMPLES SOURCE--1966 - 1973 CONNECTICUT STATE DEPARTMENT OF HEALTH 1974 - 1985 NORTHERST UTILITIES ORTA M = MILLSTONE AREA--AVERAGE OF INDIVILUAL FARM SAMPLES SOURCE--1966 - 1973 CONNECTICUT STATE DEPARTMENT OF HEALTH 1974 - 1985 NORTHEAST UTILITIES DATR
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APPENDIX A Cow and Goat Census for 1985 1
1 i
A-1
DAIRY COWS WITIIIN 15 MILES OF Fill 3SIONE POINT AS OF APRIL 1985 DIlliI'rION DISTANCE NAME AND ADDRESS NO. OF 00WS N
O Pl.
S. Douglas Morgan 4
16 Douglas Lane Waterford, CT 0G385 N
7 M.
Waterford Country School 3
78 Hunts 13 rook Rd.
Quaker 11111, Cr OG375 N
12.5 M.
Conrad fielson 108 486 Fitch 11111 Rd.
Uncasville, Cr 00382
- !1ontville -
N 12.5 M.
Leo VIrobel 39 200 Fitch 11111 !!d.
Uncasville, CT 00332
- Montville -
?!
14 M.
tlauwecus Fann Dairy G5 HFD #3, Wauwecus 11111 Rd.
Norwich, CT OG360
- 130zrah -
NE 11 M.
Doris Lamb G
99 lambton Hd IAxtyard, Cr 06339 NE 13.S M.
Ilenry Morgan 60 11R) #7, llox 1114 Ledyard, Cr 06339 NE 14 M.
Hobert Cote 2
48 Town Fann Rd.
14x! yard, Cr OG339 ENE 13 M.
Charles Perkins 21 RFU #1 Stonington, Cr OG378
I DAIRY COWS WITHIN 15 MILES OF ',11ILS'IONE IUINT AS OF APRIL 1985 DIRPCPION
_ DISTANCE NAME AND ADDRESS NO. OF WWS ENE 14 M.
Stone Acres Farm, Inc.
34 E. Piver,P, tanager Iku 222 Stonington, Cr OG378 hTiW 9.5 M.
.I.
Ely liarding 54 Ashlawn Farm Old Lyme, Cr OG371
- Lyme -
WNW 11 M.
Tiffany Fanns 60 Sterling City ikt.
Old Lyme, CT 0G371
- Lyme -
NNW 8 Ef.
Raymon<l!!uschinsky 23 Grassy 11111 Ikl.
East Lyme, Cr 0G333 NNW 11.5 M.
Valley View Farn 30 Eugene Wiczewski Darling Iki.
Salem, Cr 06415 NNW 13 M.
Stuart Gadbois 108 Route 82 Salem, Cr OG415 NNW 13 ?!.
Garry Vaill 42 Forsythe Ikl.
Sal (m, Cr OG415
DAIRY GOATS WITHIN 20 MILES OF MILLSTONE POINT AS OF JULY 1985 DIRECTION DISTANCE NAME AND ADDRESS NO. OF GOATS N
2 M.
Mary Mingo 2
69 Spithead Road Waterford, CT 06385 NNE 1.8 M.
Allen Moran 4
204 Rope Ferry Road Waterford, CT 06385 NE 13.5 M.
Robert Cote 4
Town Farm Road Ledyard, CT 06339 NE 14 M.
Robert Ruest 5
15 Mathewson Mill Road Ledyard, CT 06339 ENE 2
M.
Bertram Smith 5
9 Braman Road Waterford, CT 06385 W
16.5 M.
Victor Trudeau 6
174 Horse Hill Road Westbrook, CT 06498 WNW 8
M.
Peter LaFolla 1
Town Woods Road Old Lyme, CT 06371 WNW 17.5 M.
David Recchia 1
RFD #1 Deep River, CT 06417 WNW 19.5 M.
Chris Harris 1
218 Reservoir Road Killingworth, CT 06417
m.
a_,--
4 9
DAIRY GOATS WITHIN 20 MILES OF MILLSTONE POINT AS OF JULY 1985 i
i DIRECTION DISTANCE NAME AND ADDRESS NO. OF GOATS I
WNW 20 M.
Vicki Forteneau 2
)
312 Old Deep River Tkpe.
)
Killingworth, CT 06417 l
1 i
NW 5
M.
Ron Birchall 7
f 339 Boston Post Road East Lyme, CT 06333 NW 5
M.
George Scacciaferro 17 338 Boston Post Road i
East Lyme, CT 06333 l
NW 7
M.
Tina Korineck 5
233 Upper Pattagansett Road East Lyme, CT 06333 m.
APPENDIX B Quality Control 4
B-1
Introduction
. Northeast Utilities Service Company (NUSCO), acting as the agent for both the Northeast Nuclear Energy Company (NNECO) and the Connecticut Yankee Atomic Power Company (CYAPC0), maintains a quality assurance (QA) program of its primary contractor of radiological analyses, Clean Harbors, Inc.,
(Teledyne for H-3 in water samples). This is accomplished by the use of the three quality control methods that are specified in Radioassay Procedures for Environmental Samples, U.S.
Department of Health, Education, and Welfare (January 1967).
These three quality control methods are:
a)
Duplicate analyses of actual surveillance samples with one laboratory. This type of quality control allows an evaluation of the contractor's precision or reproducibility of results.
b)
Cross-check analyses of actual surveillance samples with more than one laboratory. This intercomparison allows the determination of what agreement the primary contractor has with another laboratory, c)
Analyses of " spiked" samples. This type of quality control allows a check on the contractor's accuracy of results.
Additional QA programs are performed, these include:
- 1) Clean Harbor's internal QA program, 2) Clean Harbor's participation in EPA's Environmental Radioactivity Laboratory Intercomparison Studies Program, and 3) Nuclear Regulatory Commission - State of Connecticut Independent Verification Program.
Method The number and type of QA samples are given in Table 1.
In general, the objective was to obtain between 10 and 20 percent of the samples as QA samples. The results of the program are shown in Tables 2, 3, and 4.
These three tables correspond to the above methods of quality control.
For I-131 spikes in milk, the acceptance criteria is based on the requirement that the measured value be within 30 percent of the spike.
The acceptance criteria for the remaining QA samples is based on the standard deviation in counting statistics (1 sigma, c) only. The standard deviation is divided into the difference between the two measurements (A). The result then should satisfy the acceptance criteria as developed from the above-mentioned U.S. Department of Health, Education, and Welfare document.
For all GeLi analyses the acceptance criteria is that a/o be less than or equal to 3.
For chemistry and beta counting, where the overall error is expected to be higher than the calculated error based on counting statistics only, the acceptance criteria is that a/o be less than or equal to 4.
Results.
For Precision (Table 2), the requirement is that the unacceptable results be less than 10 percent of the number of measurements for that type of B-2
measurement as shown for the totals. General statistics indicate that this value should be approximately 2.5 percent for counting statistics, but other non-counting statistical errors exist such as sample volume, 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) analyses and just exceeded for H-3 analyses (11.1 percentunacceptable). The small number of H-3 samples makes evaluation difficult. However, 18 percent of the Sr-90 analyses were unacceptable, even after reanalysis. Two of the unacceptable Sr-90 measurements were analyses of fish, a sample difficult to get an exact duplicate of because of its non-uniformity. The remaining unacceptable Sr-90 results were measurements in milk indicating a possible problem in Sr analyses which is being investigated.
For Interlaboratory Comparisons (Table 3) the requirement is less stringent than both Precision and Accuracy, that is the unacceptable results be less than 20 percent of the number of measurements for that type of measurement. As indicated by the totals on the bottom of Table 3, the results are acceptable.
For the case of Accuracy, only the primary contractor need satisfy the acceptance criteria. The secondary contractor receives only a small number of samples thus making the evaluation of the secondary contractor difficult. The requirement that need be satisfied by the primary contractor here is the same as that for Precision, that the unacceptable results be less than 10 percent of the number of measurements for that type of measurement. From the totals at the bottom of Table 4 this requirement is satisfied for I-131 (in milk) and Sr-89 analyses.
This requirement is just exceeded for Ge(L1), H-3 and gross beta (in air) analyses (12, 13 and 13 percent, respectively).
Investigations were performed for the other analyses that did not meet the acceptance criteria.
Four unacceptable Sr-90 results occurred in air particulates, a media in which reanalysis is not possible since the whole sample is destructively analyzed. The remaining unacceptable Sr-90 results occurred in milk and aquatic samples.
Investigations into possible Sr analysis problems is in progress.
Air particulate Cs (chemistry) spikes had only two of eight spikes exceeding the acceptance criteria. However, of the two, one was within 20 percent of the known. Cs (chemistry) is being discontinued with the approv11 of the new Connecticut Yankee Environmental Technical Specifications due to the improved accuracy of gama spectroscopy and the difficulty in performing this analysis.
The small number of H-3 samples makes evaluation difficult; only one result was unacceptable, and it was only 6% low. Since the primary contractor's past and EPA QA results have shown good agreement for H-3 spike analyses, these analyses are acceptable.
For I-131 in air analyses, only two of twelve results were unacceptable.
One unacceptable result was due to a problem in spiking the sample and using a different counting geometry.
B-3
In 1984 a problem related to the geometry of spiking filter papers with gross beta activity existed. This problem has been resolved. Only two of sixteen measurements were unacceptable, and both were within 8 percent of the known.
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.
B-4 L
Table 1 Number of Quality Contro1* Samples Number of Number of Routin 'D Sample Type QC Samples Required Samples Milk 52 112 c
W:>11 Water 17 28 c
Sea Water 2
16 c
River Water 7
8 Soil 0
16 Bottom Sediment 4
26 Aquatic Flora 4
12 Fish 10 40 Shellfish 4
52 Lobster 0
12 Fruits and Vegetables 0
16 Air Particulate - Gross Beta 16 1092
- Iodine 12 416
- Geli 26 252
- Chemistry 8
84 cAn 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 33.
B-5 L
Table 2 Precision Acceptance Number of Measurements Media Analysis Criteria
- Acceptable Unacceptable 90 Milk Sr 4
25 5
89 Sr 4
30 0
Cs137(Geli) 3 30 0
Water H-3 4
8 1
Soil &
Geff's 3
2 0
Bottom Sr 4
2 0
Sediment
. Aquatic Geff's 3
6 0
Life Sr 4
4 2
90 Total Sr 4
31 7
Geli 3
38 0
H-3 4
8 1
- The acceptance criteria is defined as: a measurement is acceptable if the delta / sigma is less than or equal to the values listed below, where:
delta = difference between the two values sigma = standard deviation B-6
~ - _.
Table 3 Interlaboratory Comparisons Acceptance Number of Measurements Media Analysis Criteria
- Acceptable Unacceptable 90 Milk-Sr 4
12 0
89 Sr 4
12 0
Csl37(Geli) 3 12 0
90 Water Sr 4
8 0
H-3 4
11 1
Soil ~ &
Geg's 3
2 0
Bottom Sr 4
2 0
Sediment Aquatic Geg's 3
10 0
Life Sr 4
10 0
90 Total Sr 4
32 0
H-3.
4 11 1
Geli 3
24 0
- The acceptance criteria is defined as: the measurement is acceptable if the delta / sigma is less than or equal to the values listed below, where:
delta = difference between the.two values sigma = standard deviation B-7
Table 4 Accuracy (Results of Spikes)
Number of Measurements Acceptable Unacceptable Acceptance Primary Secondary Primary Secondary Media Analysis Criteria
- Contractor Contractor Contractor Contractor 131 Milk 1
30%
22 6
2 0
90 Sr 4
4 4
2 0
89 Sr 4
6 4
0 0
l37 Cs 3
6 4
0 0
134 Cs 3
6 4
0 0
3 11 6
1 0
Water Geff Sr 4
12 6
0 0
89 Sr 4
12 6
0 0
H-3 4
7 4
1 0
3 0
1 1
0 Aquatic Geff Food and Sr 4
0 1
1 0
89 Flora Sr 4
1 1
0 0
Air Gross 4
14 2
Particulate Geli 3
21 3
Cshchemistry) 4 6
2 g
4 4
4 Sy31 I
4 10 2
I Total I
(milk) 30%
22 6
2 0
Sr 4
20 11 7
0 89 Sr 4
19 11 0
0 Cs (chemistry) 4 6
2 Geli 3
38 11 5
0 4
7 4
1 0
H]j(air) 7 I
4 10 2
Gross (air) 4 14 2
OThe acceptance criteria for I-131 in milk is that the delta be less than or equal to 30%. For all the other measurements, the measurement is acceptable if the delta / sigma is less than or equal to the values listed below, where:
delta = difference between the two values sigma = standard deviation B-8
_ _ _ _ _