ML17309A461
| ML17309A461 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 12/31/1990 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9105070229 | |
| Download: ML17309A461 (132) | |
Text
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S 05000244 NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
ACCESSION NBR: 9105070229 DOC. DATE: 90/12/31 NOTARIZED: NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas
& Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
"Annual Radiological Environ Operating Rept for 1990,RE Ginna Nuclear Plant." W/910430 ltr.
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ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 14649-0001 TCLCPHONC ARC* COOC 7ld 546.2700 April 30, 1991 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Subject:
Annual Radiological Environmental Operating Report R.E.
Ginna Nuclear Power Plant Docket No. 50-244
Dear Sirs:
The enclosed information is being submitted in accordance with the requirement of Technical.,Specification.Section 6.9.1.3.
This information is a
summary of all analyses performed as part of the Radiological Environment Monitoring requirements of Section 3.16 of the R.E.
Ginna Technical Specifications.
Trend plots of gross beta data for air and selected water samples are included for the year 1990 and the years of 1968 to 1990 and gamma measurements from TLD's surrounding the R.E.
Ginna site.
From the data collected, there does not appear to be any measurable effect to the environment from the operation of the R.E.
Ginna plant.
Very truly yours, Robert C. Mecr dy Pi05070225'0i23i PDR ADOCK 05000244 R
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Copies to:
Mr. Thomas T. Martin Regional Administrator U.S. Nuclear Regulatory Commission Region 1
475 Allendale Road King of Prussia, PA 19406 Resident NRC Inspector Ginna Station Ms.
Donna Ross New York State Energy Office Empire State Plaza
- Albany, NY 12223 Mr. James C.
Huang New York State Dept. of Health Empire State Plaza
- Albany, NY '12237
" American Nuclear Insurers MAELU The Exchange Suite 245 270 Farmington Avenue Farmington, CT 06032
'ATTN:
Winthrop Hayes Central Records, Ginna Station Category 2.22.2
l
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT R.E.
Ginna Nuclear Plant Rochester Gas
& Electric Docket No. 50-244 9105070229
0
TABLE OF CONTENTS 1.0
SUMMARY
2.0 SURVEILLANCE PROGRAM 2.1 Regulatory Limits 2.2 Regulatory Fulfillment 2.3 Deviations from the Sampling Schedule 3.0 DATA
SUMMARY
3.1 Analytical Results 3.2 Air Samples 3.3 Mater Samples 3.4 Milk Samples 3.5 Fish Samples 3.6 Vegetation Samples 3.7 External Penetrating Radiation 4.0 LAND USE CENSUS 5 '
EXTERNAL INFLUENCES 6.0 EPA INTERLABORATORY COMPARISON STUDY Page 16 16 17 31 47 49 52 55 58 61 61
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LIST OF TABLES Table No.
- Environmental-Radiological Monitoring Program Summary Tech Spec Table 3.16-1 Page 2-1 2-2 3-1 A 3-2 B
3-2 A 3-2 B
3-3 A 3-3 B
'3-'3 'C 3-3 D
3-4 3-5 'A 3-5 B
3-5 C
3-6 3-7 3-8 3-9 3-10 3-11 3-12 A
3-12 B
3-13 3-14 3-15 3-16 3-17
'3-17B 3-18 6-1 Environmental Monitoring Program Tech Spec Table 4.10-1 Maximum Values of LLD Lover Limit of Detection (LLD)
Direction and Distance to Sample Points Onsite Samplers, January June
'Onsite Samplers, July - December Offsite Samplers, January June Offsite Samplers, July December 13 Week Composite Gamma Isotopic Analyses First Quarter 13 Week Composite Gamma Isotopic Analyses Second Quarter
'13'eek Composite Gamma Isotopic Analyses Third Quarter 13 Week Composite Gamma Isotopic Analyses Fourth Quarter Charcoal Cartridges for Iodine Environmental Water Samples Gross Beta Analyses Environmental= Water Samples Gross Beta Analyses Fallout Ontario Water District Water Gamma Isotopic Analyses Circ. Outlet Water Gamma -Isotopic Analyses Russell Station Water Gamma Isotopic Analyses Tap Water Gamma Isotopic Analyses Well "B" Water Gamma Isotopic Analyses Deer Creek Water Gamma Isotopic Analyses Environmental Water Samples Tritium Analyses Fallout Tritium Analyses Iodine in Water Milk Fish Samples Lake Samples Vegetation Samples Comparison of Ginna,Soil Sampling..Results External Penetrating Radiation EPA Interlaboratory Comparison Program 6
9 11 12 19
- 20 21 22 23 24 25 26 27
'4 3 3
,.34 35 38 39 40 41 42 43 44 45 46 48 50 51 53
,54, 56 62
4 P-
LIST OF MAPS Map No.
2-1 2-2 2-3 Onsite Sample Locations Offsite Sample Locations Water Sample and Milk Farm Locations Land Use Census Page 13 14 15 59 LIST OF TREND PLOTS Onsite Air Monitors, Gross Beta Analysis Offsite Air Monitors, Gross Beta Analysis Annual Trending of Air Activity Environmental Water Samples, Gross Beta Analysis Annual Trending of Environmental Waters EPA Interlaboratory Comparison
- Program, Normalized Deviation from EPA Known 28 29 30 36 37 64 65
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RADIOLOGICAL ENVIRONMENTAL SURVEY Janua December 1990
SUMMARY
During
- 1990, there were no measurable influences from radioactive effluent releases.
Routine measurements are taken in the areas surrounding the R.E.
Ginna Nuclear Power Plant to determine if man-made radioactivity is being released at a level that would cause an influence to the environs surrounding the plant.
Samples are collected on an established schedule for regular testing to determine if measurable levels of activity exist that may be attributed to the operation of the plant.
The information obtained from measurements of these environmental samples is compared to the calculated levels.
of potential activity at the sampling locations from normal plant releases as determined by monitors within the plant effluent streams.
Samples of water, air, fallout, fish, vegetation, milk and direct radiation are collected from locations near the plant that were determined to be at the point of highest concentra-tion from releases through the plant and containment
.vents and from additional locations at distances ranging out to eighteen miles.
A group of soil samples were taken in 1989 and the results are included in this report.
Reference samples for background measuiements are collected concurrently from locations calculated to have radioactivity concentrations less than 14 of those from the closer sampling locations.
These background samples provide continuous background data which makes it possible to distinguish between significant radioactivity introduced into the environment from the operation of the plant and that introduced from other sources.
During
- 1990, 1391 samples were obtained and analyzed for beta and gamma emitters through gross activity counting techniques and gamma spectroscopy.
These total 868 air
- samples, 293 water
- samples, 15 fish samples, 8 vegetation
- samples, 56 milk samples and 149 thermoluminescent dosimeter measurements.
As part of a required quality control program, 15 EPA Interlaboratory Comparison Studies samples (comparable to normal samples taken by the environmental program) were analyzed and reported.
A summary of the data collected indicating the results of all data for indicator and control locations is given in Table 1-1.
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I (P325WAY SAMPLED Table 2-2 RQCfgi~ZR GAS AND ELECTRIC CO~MTICN ENFZRNKWZALMDIOICGICALMONZIURING PRXRBM
SUMMARY
R.E.
GINNA KJCLEK RN2R PLANT DOQCFZ NO. 50-244 PAYNE~ NZÃ'ORK REFORLZNG PERIOD.2990 (TYPE AND BRUTAL(
(INDICATOR LAdQ'ECNS(
IOCATION VZZH HIGFKST ANNUAL MEAN COiV1R7L ~')TIONS(
MJMBER OF
( LLD
(
MEAN (2)
NAME
(
MEAN (1)
(
MEAN (2)
ANALYSES MNGE DISTANCE AND DIRECTION MNGE MvVGE (AIR-PARTICXKMZ I
(pCi/CU.M.)
IODINE (GRKS BETA 615(0.003(0.025 (357/357)
I
- 0. 003 0. 039 GMCA SCAM 48 2
<'LD 0 28 I
(0.02-(
GAMMA SCAN 205 0.08 CLLD 0 102 (CNSZIZ LCCMICN ¹5 (0.026 (52/52)
(0.015 (258/258 160 M 185 0.004 0.029 0.003 0.028
<LLD 0 20 I < LLD 0 104 (DIECT RADIATI'CN: (3) (
I I
I I
I TLD (GAMMA 249( 5.0 (23-8 (66/66)
(CNSZTE IDCPQ'ICN ¹4 (25-3 (4/4)
(11-3 (79/79) mR AIVZR
- 10. 7 30.8 250 M 240
- 14. 8 16.0 7.5 25. 8 (MTZR: DRINKING
(~/LZRZR)
I I
I 1
SURFACE
(~/LZIZR)
I I
I
((2KGS BETA 73( 1.2 (2.06 (73/73)
I 1.26 4.32 (WELL "B" 640 M 150 (GAMI&SCAN 50(
(2)
(Ra-226 32 (22/50) (E "B" 11 - 45 640 M 250 IODINE 33 0.24
< LLD 0 33 (GROSS BETA 260( 2-2 (2.26 (160/260)
I 2.29 5.27 (GMCA SCM 50(
(2)
(RR-226 27 (4/50) 9 - 24 42 0.24
< LID 0 32 (DZKR CRE2K 200 M 235 (DEER C2KPK 200 M 235 IODZNZ i2.69 (22/12) 2.28 4.32 (Ra-226 31,(22/12)
(
12 45 (2.92 (12/12)
- 2. 07 5.27 (2.10 (49/49) 2.35 3.85 (Ra-226 1,7(4/50)
( < LLD (0/22) 9 - 24
<LLD 0 11 RAINFALL
.M da (MILK:
(pCi/IVIZR)
(GKGS BFZA 60( 1.2 (5.38 (24/24)
(STRATI'QV ¹3
( 6.22 (12/12)
(5.21, (49/49) 1.40 14.5 420 M 120 1.44 13.3 2.25 20.3 I IODINE 56(0-24
(<LLD (0/38)
(
I I~ (0/18)
I GNC65 SCM 56 2
< LID 0 38
< LID 0 18 (FISH:
(VtKETATICN:
(GAMMA SCAN 15(
(2)
(Cs-237 35 (7/7)
(DISCKSGE PLUME (Cs-237 35 (7/7)
(Cs-137 23(7/8) 28 49 28 49 15 33 (GAMMASCM 8(
(2) (<UD (0/6)
. I I
(< LLD (0/2)
(2)
Mean and range based on detectable ireasuramrits only.
Fraction of'etectable neasurenants at specified locations in parentheses.
(2)
Table of'LD vaZues attached for gamma scan measurements.
(3)
One direct radiation location has been deleted from this surrmazy since it vas affected by the contaminated equipment storage location 50 meters avay.
The average reading at this location is 24 mR/Quarter during 2990-
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24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> follcaring filter change.
Perform gamma isotopic analysis on each sample for which gross beta activity is
> 10 times the mean of offsite samples.
Perform gamma isotopic analysis on composite (by location) sample at least once per 92 days.
Gamma dose quarterly.
TEXXKICALSEKCZFXCATION TAEKE 3-16.1 (Oontinued)
Eh~sure Pathway 3.
HATERBOHNE
- a. Surface
- b. Drinlcing RADIOIl3GICAL
%sober of Samples le Iocations 1 control (Russell Station) 1 indicator (Gondenser Water Discharge) 1 indicator (Ontario Water District Intake)
MDNZIORING PRQGRM Sampling and Collection Gaqmsite~
sample collected over a period of < 31 days.
Type and Frecpency of Anal sis Gross beta and gamma isotopic analysis of each ccaaposite sample.
Tritium analysis of one composite sample at least once per 92 days.
- OarDEesite sample to be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
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TECHNICAL SPECIFICATION TAKE 3-16. 1 (Continued)
RADIOIDGICAL Rgmsure Pathway 4.
INGESTION Number of Samples le locations Sampling and.
Collection Type and Frecpency of Anal is
- a. Milk 1 control 3 indicator June thru October each of 3 farms At least once per 15 days+
Gamma isotopic and I-131 analysis of each sample.
1 control 1 indicator Nav~ thru May one of the farms At least once per 31 days'amma isotopic and I-131 analysis of each sample.
- b. Fish
- c. Food Prochcts 4 control 4 indicator (Off shore at Ginna) 1 corrtrol 2 indicator (On site) 1 control 2 indicator (On site garden or nearest offsite garden within 5 miles in the highest D/Q meteorological sector)
Twice during fishing seamn including at least four species.
Annual at time of harvest.
Sample fram two of the follmring:
1 apples
- 2. cherries 3 o grapes At time of harvest.
One sample of:
- 1. broad leaf vegetation
- 2. other vegetable Gamma isotopic analysis on edible portions of each sample Gamma isotopic analysis on edible portion of sample.
Gamma isotopic analysis on edible portions of each sample.
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The maximum LLD values as defined by Tech Specs Table 4.10-1 are:
A~AlR1 Bie Hater
~Col Airborne Particulate or Gas ci m3~
Fish (pCi/kg,
~wet Milk
~Col Food
.Particulate (pCi/kg, gross beta 4a 1 x 10 2 3H 54Mn 59Fe 58 60co 652'n 95Zr-Nb 2000(1000a) 15 30 15 30 15b 130 260 130 260 131'34 137Cs 15(10a),18 7 x 10-2 1 x 10-2 130 15 60 60 140Sa-La 15b 15b a.
LLD for drinking water b.
Total for parent and daughter
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LLD TABLE NOTATION
~
~
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""The "LLD is the-smallest-concentration-of-radioactive material..in a
sample that will yield a net count (above system background) that will be detected with 954 probability with only 54 probability of= falsely concluding that a
blank observation represents a
"real" signal.
For' particular measurement system (which may include radio-chemical separation):
LLD =
4.66 Sb E V 2.22 Y exp [(-~t)
]
where LLD is the lower limit of detection as defined above (as pCi per unit mass or volume)
Sb's'he standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)
E is the counting efficiency (as counts per disintegration)
V is the sample size-(in -units of mass or volume) 2.22 is the number of disintegrations per minute per picocurie Y is the fractional radiochemical yield (when applicable)-
P, is the radioactive decay constant
-. for the particular radionuclide
~t is -the elapsed time between sample collection and counting The value of Sb used in the calculation of the LLD for a particular measurement system shall be based on the actual observed variance of the background counting rate or the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically
-predicted variance.
In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the
.background shall include the typical contribution of. other radionuclides normally present in the samples (e.g.,
potassium-40 in milk samples)
Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions.
Occasionally, back-ground fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable.
10
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Table 2-1 IQWER LIMIT OF DETECTION (LLD)
Air Filters (a)
Water Milk
'Ci/M pCi/liter pCi/liter Sample Size 3500 M /Qtr.
3.5 liters 3.5 liters Ave. Decay(c) 55 days 0.5 d 8 days 0.5 d Fish Vegetation(a) pCi/kg pCi/kg 2 kg 2 kg 6 days 0.5 days Be-7 K-40 Cr-51 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Ru-103 Ru-106 131 0.025 0.012
- 0. 035 0.002 0.005 0.002 0.002 0.004 0.005 0.004 0.004 0.014 28 31 29 35 3
3 5
6 3
3 4
4 6
6 6
6 3
3 3
3 28 28 0.03 (b) 4 Gamma 220 10 30 10 10 25 24 18 18 95 10 Gamma 15 95 10 20 10 13 22 17 10 12 100 12 Cs-134 Cs-137 BaLa-140 Ce-141 Ce-144 Ra-226 Beta
- 0. 002
- 0. 002
- 0. 064
- 0. 05 0.09 0.004 0.24 Beta 3
3 4
5 4
17 7
8 30 30 7
7 1.2 (1 liter) 0.24 Beta
'10 12 40 100 20 10 12 10 25 100 20 (a)
LLD value will vary due to different sample sizes.
Data based on 1990 background sample spectra.
(b)
Charcoal Cartridge (c)
Ave. decay-normal period from midpoint of sampling period to counting time.
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Table 2-2 DIRECTION AND DISTANCE All directions given in degrees and TO SAMPLE POINTS all distances given in meters Air -Sample Stations Direction Distance TLD Locations
.'Direction
-"Distance N2 87 I
3 11O 4
140 5
185 6
232 4
7 257 8
258 9
235 410 185 Ill 123 93 413 194 320 420 250 160 225 220 19200 11400 13100 11500 25100 690 Water Sample Locations Direct Dist.
15 130 105 260 150 640 Onsite Sink 110 420 185 160 258 19200 185 13100 93 25100 Milk Sample Locations Direct Dist.
Farm A Farm B
Farm C
Farm D
Fish Samples 113 9500 242 4400 156 4400 132 21600 Russell Station 270 25600 Ontario Water District Intake 70 2200 Circ Water Intake 0
420 Circ Water Discharge Deer Creek Well B Tap Rainfall g
3 Rainfall I 5 "Rainfall I 8 Rainfall N10 Rainfall N12 I 2 0
4 N5 I 6 4
8 N9 510Ill 413 414 415 N17 418 419 N2O
$ 21 N22 N23 N24 N25 N26 N27 N28 N29 430 N31 N32 N33 534 435 N36 437 538
$ 39 440 87 110 140 185 232 257 258 235 185 123 93 292 292 272 242 208 193 177 165 145 128 107 90 247 223 202 145 104 103 263 246 220 205 193 174 158 137 115 87 320 420 250 160 125 220 19200 11400 13100 11500 25100 230 770 850 900 500 650 400 680 600 810 680 630 14350 14800 14700 17700 13800 20500 7280 6850 7950 6850 7600 5650 6000 7070 6630 6630 Indicator Samples Lake Ontario Discharge Plume
Background
Samples Russell Station Produce Samples Indicator Samples Grown on property surrounding Plant
Background
Samples Purchased from farms
> 10 miles "I
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Onsite Sample Ihcations N
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Water 2-3 and Milk Farm Locations I Geacea
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3.0 DATA
SUMMARY
3.1 Anal tical Results The values listed on the following tables include the uncertainties stated as 2 standard deviations-(95% confidence level).
Ke Definitions Curie (Ci):
The cyxantity of any radionuclide in which the number of disintegrations per second is 37 billion.
'icocurie (pCi):
One millionth of a millionth of a curie or 0.037 disintegrations per second.
Cubic Meter (M ):
Approximately 35.3 cubic feet.
Liter (L):
Approximately 1. 06 quarts.
Lower Limit of Detection The Nuclear Regulatory Commission has requested that reported values be compared, to the Lower Limit of Detection (LLD) for each piece of equipment.
Table 2-1 is a listing of the LLD values for gamma isotopes using our Ge (Li) multichannel pulse height detector system.
These values are before the correction for decay.
An explanation of the calculation of the LLD is included
- before-Table 2-1.'ross detection limits are as follows:
Beta:
Air Water Milk Fallout Gamma:
Air 0.003 pCi/M gross beta for 400 m
sample.
1.2 pCi/L gross beta for 1 liter sample.
0.24 pCi/L iodine 131 for 4 liter sample.
1.1 pCi/m /day for 0.092 M collection area.
0.03 gCi/m iodine 131 on charcoal cartridge for 400 M
sample.
Radiation 5 millirem/quarter for one quarter exposure (TLD).
16
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Air Sam les Radioactive particles in air are collected by drawing approximately one cfm*through a two"inch diameter particulate filter.
The volume of air sampled,'is measured by a dry gas meter and corrected for the pressure drop across the filter.
The filters are changed weekly and allowed to decay for three days prior to counting to eliminate most of the natural radioactivity such as the short half-life daughter products of radon and thoron.
The decay period is used to give a
more sensitive measurement of long-lived man-made radio-activity.
A ring of 6 sampling stations is located on the plant site "from 150 to '300 -meters from the -reactor near the point -of the maximum annual average ground level concentration.
In
- addition, there is a ring of 5
sampling stations located approximately 7 to 17 miles from the site that serve as background stations.
Based on weekly comparisons, there was no statistical difference between the on-site and the background radioactive particulate concentrations.
The average concentrations for the on-site and background samples were 0.015+0.003 and 0.015+0.003 pCi/m respectively for the period of January to
- December, 1990.
Maximum weekly concentrations for,,each station were less than 0.039 pCi/m The major airborne activities released from the plant are noble gases, tritium,= radioiodines and carbon-14.... Most, of this activity is released in a gaseous form, however, some radioiodine is released as airborne paxticulate.
For airborne particulates, the average calculated concentration of particulate at the site boundary due to measurable plant releases would be 5.7E-6 pCi/m or 0.0194 of the average release concentration of 0.0317 pCi/m The survey cannot detect such a concentration which is
<1% of the LLD of 0.003 pCi/m3.
Table 3-1 is a list of values for the on-site samplers.
Table 3-2 is a list of values for the off-site samplers.
The particulate filters from each sampling location were saved and a
13 week composite was made.
A gamma isotopic analysis was done for each sampling location and corrected for decay.
The results of these analyses are listed in Tables 3-3 A to D.
Iodine cartridges are placed at four locations.
These cartridges are changed and counted each week.
A list of values for these cartridges is given in Table 3-4.
17
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0
Trend plots of the 1990 air filter data with a comparison to the 1989 air filter data is included.
The 1989 data indicating a higher trend during November and December is based on samples counted 'on.'alternate gross beta counting equipment while the environmental gross-.beta..counting equipment was removed from service for repair.
The alternate
- -equipment had'a higher background than the normal equipment and may have -influenced the data.
Additionally, a trend plot of the annual averages measured since 1968 is included to show the variation of data during the years that the R.E.
Ginna Nuclear Power Plant has been operational.
The peak activities measured correspond to the years whenatmospheric tests of nuclear weapons were being conducted.
18
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Table 3-1 A
On-Site Samplers Results in pCi/m Meek of 1/5 1/12 1/19 1/26 2/2 2/9 2/16 2/23 3/2 3/9 3/16 3/23 3/30 4/6 4/13 4/20 4/27 5/4 5/11 5/18 5/25 6/1 6/8 6/15 6/22 6/29 Sta.
¹2
.022+.002
.027+.002
.017+.002
.014+.002
.010+.001
~ 015'02
~ 016+.002
~ 010+. 001
~ 017+.002
.023'02
.013+
F 001
~ 015+.002
. 015+. 002
.005+
F 001
~ 013+.001
~ 015'02
~ 021+.002
~ 016'02
. 011+. 001
. 011+. 001
.003+.001
.011+.001
.013+.001
.015+.002
.015+.002
.008+.001 Sta.
¹3
.039'02
.027'02
.017'02
.016'02
.010+.001
.018'02
.016+.002
.019'02
.019+.002
.023+.002
.013+.001
.014+.003
.015'02
.005+.001
.013+.001
.015+.002
.020+.002
.015+.002
.010+.001
.012+.002
.003+.001
.009+.001
.013+.001
.014+.001
.015'02
.008+.001 Sta.
¹4
~ 028+.002
.029+.002
.017+.002
~ 016+.002
~ 012+.002
~ 018'02
~ 018+.002
~ 017'02
.020'02
~ 022'02
~ 014+.002
.013'02
~ 016+.002
.005+.001
.012+.002
~ 015+.002
.020+.002
~ 015+
~ 002
.010+.002
.010+.002
< ~ 003
.011+.002
.013+.002
~ 013+.001
.015+.002
.008+.002 Sta.
¹5 (b)
.029+.003
.018+.002
.018+.002
.010+.002
. 017+.002
.018+.002
. 019+.002
.019+.002
.024+.002
.015'02
.019+.003
.017+.002
.004'02
.012+.002
~ 015'02
.022+.002
~ 017'02
.012+.002
. 011+. 002
.003+.002
. 011+. 002
.015+.002
. 012+. 002
. 015+. 002
.007+.002 Sta.
¹6
.018'04
.024+.003 (a)
(a)
~ 008+.002
.017+.003
.016+.003
.019+.003
. 018+ ~ 003
.023+.003
.011+.002
.012+.002
.011'03
<.003
.013+.003
.013'03
.017'03
. 014+. 003
~ 010+. 002
.009+.002
< ~ 003
~ 009'02
~ 011'02
.011'02
.012+.003
.008+.002 Sta.
¹7
~ 026+.002
~ 025'02
~ 015'02
~ 015+.002
.010'01
~ 016+. 002 (a)
(a)
(a)
~ 015+.008
~ 012+.003
~ 013+.003
~ 012'02
.004'02
~ 011+. 002
.013+.003
.016+.003
.014'03
.009+.002
~ 010'02
<.003
.009+.002
.011+.002
.011+.002
.010+.002
.006+.002 Sta
¹13A
.027+.003
.033+.002
~ 038'02
~ 019'02
.014'02
.020+.002
~ 021+.002
.019+.002
.023'02
.031+.002
~ 016+.002
~ 017'02
.016+.002
.007+.002
.019+.002
~ 015'02
.023+.002
.017'02
~ 014+.002
.006+.002
.003+.001
.010'01
.012'01
. 012+
~ 001
~ 014+. 002
.008+.001 On-Site
~Avera e
.027
~ 028
~ 021
~ 016
~ 011
.016
~ 018
~ 017
~ 019
.023
~ 013
~ 015
~ 015
~ 005
.013
~ 015
~ 020
~ 015
~ 012
~ 010
~ 003
.011
~ 013
~ 013
~ 014
.008 HAXIHUH AVERAGE H IN I HUH
.027
.014
.003
. 039
.015
.003
.029
.015
.005
.029
. 015
.004
.024
.014
.008
~ 026
~ 003
~ 004
~ 038
.017
.003 (a)
(b)
UNIT OUT OF SERVICE FILTER OFF CENTER OR TORN
gr 4
~y%
I i II e
l I
~ +
'r yL
Table 3.1 8
On-Site Samplers Results in pCi/m3 ueek of 7/6 7/13 7/20 7/27 8/3 8/10 8/17 8/24 8/31 9/7 9/14 9/21 O
9/28 10/5 10/12 10/19 10/26 11/2 11/9 11/16 11/21 11/29
'1 2/7 12/14 12/21 12/28 Sta.
¹2
. 011+. 001
. 010+. 001
. 016+. 001
. 015+. 001
. 012+. 001
. 014+. 001
~ 015+.001
~ 013'01
~ 012+. 001
. 018+
~ 001
.015+. 001
.011+ ~ 001
~ 017+. 001
~ 016+. 001
.008+.001
.011+.001
. 014+. 001
. 013+. 001
. 018+
~ 001
. 013+. 001
.021+.002
.021+.001
.014+.001
.021+.002
.014+.001
~ 019+.001 Sta.
¹3
.010+.001
.009+.001
.019+.002
. 014+. 001
.012+.001
.015+.001
~ 017+.002
~ 016+.002
.013+.001
~ 018+.002
.016+.002
.012+.001
~ 012'02 (a)
<.003
.011+.002
.013+;002
~ 015+.001
.021'02
.015+.002
.023'02
.022+.002
~ 017+.002
.026+.002
.019+.002
.022+.002 Sta.
¹4
~ 011+. 002
~ 010+.002
.019+.002
~ 016+.002
.013+.002
.014+.002
.020+.002
~ 016'02
.015'02
.019+.002
.016+.002
.011+.002
.018+.002
.019+.002
. 010+. 001
.012+.002
.015+.002
. 013+. 001
.021+.002
~ 016+. 002
.023+.002
.022+.002
~ 015+.001
.022+.002
~ 016+. 002
~ 023+.002 Sta.
¹5
~ 011+ ~ 002
~ 010'02
.017'02
~ 017+.002
.012+.002
~ 015+.002
.019'02
~ 017+.002
~ 013+.002
~ 019+.002
~ 018+.002
~ 014'02
~ 020'02
.019'.002
~ 010+.002
.013+.002
~ 014+.002
.015+.002
.021+.002
.017+.002
.024+.002
.023+.002
.016+.002
~ 024'02
.018+.002
.024'02 Sta. ¹6,
.008+.002
.008+.002
~ 018+.003
.015+.003
.012+.002
.014+.003
.018+.003
~ 0'16+.003
.012+.002
.017+.002
.027+.003
.011+.001
.018+.002
.018+.002
. 011+. 001
. 013+. 001
. 013+. 002
. 014+. 001
.020+.002
.015+. 002
.020'02
~ 021+.002
~ 015+. 001
~ 023+.002
~ 016+ ~ 002
~ 020+.002 Sta.
¹7
.010+.002
.009'02
.014+.003
.012+.002
~ 011+.002
.013'03
.018'03
.015+.003
.013+.002
~ 016+.003
.015'03
.010+.002
. 018+. 003
.019+.003
.007+.002
.013'02
.014'02
.014'01
.019'02
~ 015+.001
.023'02
~ 021'02
.015+.001
'.023'02
~ 015+.001
.023+.002 Sta.
¹13A
~ 011+. 001
.008+.001
~ 017+. 002
~ 012+. 001
.012+.002
~ 012+.001
~ 016+. 002
~ 012+.001
~ 015+.002
. 015+. 002
~ 017+.002
.009+.001
.018+.002
~ 019+. 002
~ 010+. 001
~ 012+. 001
. 013+. 002
. 014+. 001
.020+.002
~ 016+.002
.020+.002
~ 019+.002
.015+.001
.023+.002
~ 018+.002
.021+.002 On-Site A~vera e
~ 010
.009
.017
~ 014
.012
.014
.018
.014
.013
~ 017
.018
.011
.017
~ 018
.009
.012
~ 014
~ 014
.020
.015
.022
~ 021
~ 015
.023
.017
.022 Haximum
~ 021 Average
.015 Hinimum
.008 (a) Unit out of service.
.026
.016
.009
.023
~ 016
.010
.024
.017
.010
.027
.016
~ 008
. 023
. 015
.007
~ 023
~ 015 F 008
Wt II 0
\\
4'
'Lg~).
Table 3-2 A
Off-Site Samplers Results in pCi/m lleek of 1/5 1/12 1/19 1/26 2/2 2/9 2/16 2/23 3/2 3/9 3/16 3/23 3/30 4/6 4/13 4/20 4/27 5/4 5/11 5/18 5/25 6/1 6/8 6/15 6/22 6/29 Sta.
¹8
.026+.002
.028'02
.018+.002
.015+.001
.011+.001
.019+.002
~ 020+.002
~ 016+.001
~ 019+.002
.026+.002
.013+.001
. 014+. 001
.015+.001,
~ 006'01
.013'01
~ 017+.002
.019'02
.016+.001
.013'01
.011'01
.003+.001
.011+.001
'012+.001
.013+.001
.015+.001
~ 009+.001 Sta. ¹9
~ 022+.002
~ 025+.002
~ 016+.002
.014+.002
.011+. 002
.019+.002
. 019+. 002
.023+.002
.020+.002
~ 026+.002
.013+.002
. 015+. 002
. 014+. 002
.007+.001
~ 014+.002
~ 016+.002
~ 021+.002
.015+.002
~ 012'02
~ 004+.001
.003+.001
.011'02
~ 012+ ~ 001
~ 013+.002
.014+.002
.009+.001 Sta.
¹10
~ 025+.002
~ 028'02
.019+.002
~ 017+.002
~ 012'02
.020+.002
~ 019+.002
.018+.002
~ 020+.002
.025+.002
.015'02
.016+.002
.0'l6+.002
.005+.001
.015+.002
. 018+ ~ 002
~ 0'l9+.002
~ 015+.002
~ 013+.002
~ 011'01
~ 003+.001
~ 009'01
~ 012'02
.013'02
.014'02
.009+.001 Sta.
¹11
.024+.002
.026+.002
. 017+. 002
~ 015+. 001
~ 011+. 001
~ 017+. 001
~ 022'02
~ 017+.002
~ 017+.002
~ 023+.002
~ 013+. 001
~ 014+. 001
~ 013+. 001 F 006+.001
~ 014+.001
~ 016+.001
..019+.002
~ 015+
~ 001
. 011+. 001
~ 008+.001
.003'01
. 010+. 001
~ 013+. 002
. 010+. 001
. 013+. 001
.009+.001 Sta.
¹12
.022+.002
~ 027'02
~ 018+.002
~ 015+.002
~ 011+.002
~ 019+.002
~ 013+.001
. 017+.002
~ 019+.002
~ 027'02
.014+.002
~ 014+ ~ 002
. 013+.002
~ 005+.001
~ 014+. 002
~ 017'02
.020+.002
~ 017'02
~ 014+.002
~ 008'02
~ 003'01
~ 009'02
.010+.002
.011'02
. 014+ ~ 002
~ 008'02 Off-Site
~Avera e
.024
.027
.018
.015
. 01'l
~ 019
. 019
.018
.019
.025
.014
.015
.014
.006
.014
.017
.020
.016
.013
.008
.003
.010
.012
.012
.014
.009 Naximum Average Hinimum
.028
.015
~ 003
.026
.015
.003
.028
~ 016
.003
.026
.014
~ 003
.027
.014
.003
J I'
%7 1$
Illa Why t II~
0
~ h
Table 3-2 8
Week of 7/6 7/13 7/20 7/27 8/3 8/10 8/17 8/24 8/31 9/7 9/14 9/21 9/28 10/5 10/12 10/19 10/26 11/2 11/9 11/16 11/21 11/29 12/7 12/14 12/21 12/28 Sta.
¹8
.012'01
~ 010'01
.017+.002
.014+.001
~ 013+.001
~ 014+.001
~ 017+.002
~ 015+.001
.015+.001
.017+.002
.015+.001
~ 010+.001
~ 016+.001
~ 019+.002
~ 013'02
.013'01
. 015+. 002
.014'02
.018'02
.019+.003
.021'03
.022'02
.015'02
.018+.003
.015'02
. 021+
~ 003 Sta.
¹9
. 011+ ~ 002
.009+.001
. 015+ ~ 002
. 014+. 002
. 011+. 001
. 014+. 002
.016+.002
. 013+. 001
.014+.002
.016+.002
.015+.002
.011+.001
.016+.002
~ 018+.002
~ 010+.001
~ 011+.001
~ 012+.002
.015+.002
~ 012+.001
.018+.007
. 018+. 004
.021+.002
. 015+. 002
.022+.002
.009+.001
.008'01 Off-Site Samplers Results in pCi/m3 Sta.
¹10
~ 012+.002
<.003
.015+.002
. 013+
~ 002
~ 01'i+.001
~ 012'01
.018'02
~ 014'02
~ 014'02
.015+.002
.016+.002
.010+.001
.015+.002
.019+.002
.010+.001
.011+.001
.014+.002
.013+.001
.025'03 (a)
(a)
. 021+
~ 002
~ 015+
~ 001
~ 022'02
.017+.002
~ 021+
~ 002 Sta.
¹11
.0'10+.001
.008+.001
. 014+. 001
.012+.001
.009'01
. 011+ ~ 001
. 017+ ~ 001
. 012+. 001
.012+.001
. 014+. 001
. 016+. 001
.010'01
.014'01
~ 017+. 001
.010+. 001
~ 010+. 001
.012+.002
~ 013+.001
.019+.002
~ 020+.003
~ 022+.003
~ 021+.003
.015'02
.025+.003
.016+.003
.021+.003 Sta.
¹12
.010'02
.008'02
~ 014+.002
.012+.002
.009+.002
.011+.002
.015+.002
.011+.002
.011+.002
.015+.002
.016+.002
.008+.002
.014+.002
.017+.002
.009+.002
.010'02
.012+.002
~ 012'01
.019+.002
.019+.002
~ 017+.002
~ 019'02
~ 014+. 002
~ 021+
~ 002
~ 01 7+ ~ 002
~ 019'02 Off-Site A~vere e
.01'i
.007
.0'l5
. 013
.011
.012
~ 016
~ 013
~ 013
. 015
. 016
. 010
. 015
. 018
. 014
. 013
. 013
~ 013
.019
. 019
.020
.021
. 015
.022
. 015
. 018 Maximum
.022 Average
.015 Minimum
.010 (a) Unit out of service.
.022
.014
.008
.025
.0'l5
.001
.025
~ 015 F 007
.021
.014
.008
A1g t
yr
~~<'0'
Gable 3-3 A 13 %uk Ocq~ite Gmna Xsvtcpia Anal Results in First Quarter Be
.084+.010
.08&1-.OlO Sta 10 Sta ll Sta 12 Sta 13A
.088+.014
.103+.016
.134+.044
.~.OIS
.085+.010
.089+.012
.091+.012
.078+.010
-089+-010
-095+.014 1R
<.001 CPl
<.014 Nr&
<.001 Pe 9
<.002 I
4 QR
=
<.001 Cb~
<.001 Zn65
<.001 ZP5
<.002 NkP5
<.001 Rd.~
<.001 Ru106
<.005
<.001
<.001 BaLa140
<.022 0+41
< 002 Cd.44
<.003
<.003
<.014
<.001
<.002
<.001
<.001
<.001
<.004
<.016
<.001
<.002
<.001
<.001
<.002
<.001
<.001
<.005
<.001
<.001
<.020
<.002
<.002
<.001
<.006
<.001
<.001
<.630
<.002
<.003
<.004
<.001
<.002
<.002
<.021
<.001
<.003
<.001
<.001
<.002
<.002
<.002
<.002
<.008
<.001
<.001
<.034
<.003
<.005
<.005
<.054
<.002
<.007
<.003
<.003
<.005
<.005
<.005
<.004
<.021
<.002
<.003
<.088
<.008
<.014
<.005
<.024
<.001
<.003
<.001
<.001
<.002
<.002
<.002
<.002
<.009
<.001
<.001
<.040
<.003
<.006
<.003
<.013
<.001
<.002
<.001
<.001
<.001
<.001
<.001
<.001
<.004
<.001
<.001
<.022
<.002
<.003
<.004
<.016
<.001
<.002
<.001
<.001
<.001
<.002
<.001
<.001
<.006
<.001
<.001
<.028
<.002
<.004
<.002
<.016
<.001
<.002
<.001
<.001
<.001
<.002
<.001
<.001
<.005
<.001
<.001
<.027
<.002
<.003
<.002
<.013
<.001
<.002
<.001
<.001
<.001
<.001
<.001
<.001
<.004
<.004
<.001
<.023
<.002
<.003
<.003
<.01S
<.001
<.003
<.001
<.001
<.002
<.002
<.002
<.002
<.006
<.001
<.001
<.031
<.002
<.004
<.004
<.019
<.001
<.003
<.001
<.001
<.002
<.002
<.002
<.002
<.007
<.001
<.001
<.036
<.003
<.004 Allvalues given as C are less than LLD
0 1$
PJ Alp 0
P.
Sta 2 Sta 3 Table 3-3 B 13~ Ocapcsite Gmaa Isotopic Aral
~ts in Seacaxl QuaxteL Sta 9 Sta 10 Sta 11 Sta 12 Sta 13A Be7
.08&-.013
.081+.012
.$&..016
.102+.025
.088+.032
.07&-..020.083+.013
.094+.017
.083+.015
.07%-.015
.053+.012
.08%..018
<.oo4 col
<.018 Mr&
<.001
<.OO2 I~
CXP
<.OO1 I
Cb~
<.001 Zn65
<.OO1 Zr95
<.OO2 NkP5
<.002 Rl 03
<.001 Su106
<.M4
<.001 Ch137
<.001 140
< 033 0+41
<.002 M44
<.oo4
<.001
<.017
<.001
<.002
<.001
<.001
<.001
<.002
<.001
<.001
<.006
<.001
<.001
<.035
<.002
<.003
<.006
<.022
<.001
<.003
<.001
<.001
<.002
<.002
<.002
<.002
<.007
<.001
<.001
<.046
<.003
<.004
<.013
<.031
<.001
<.004
<.002
<.001
<.022
<.003
<.003
<.002
<.009
<.001
<.001
<.063
<.004
<.005
<.012
<.044
<.001
<.006
<.002
<.001
<.003
<.004
<.004
<.003
<.012
<.001
<.002
<.001
<.005
<.008
<.008
<.041
<.001
<.005
<.002
<.001
<.OG3
<.004
<.004
<.003
<.Oll
<.001
<.001
<.021
<.001
<.003
<.001
<.001
<.001
<.002
<.002
<.001
<.005
<.001
<.099
<.005
<.008
<.051
<.002
<.053
.002+.001
<.001
<.005
<.027
<.001
<.003
<.001
<.001
<.002
<.002
<.002
<.002
<.006
<.001
<.001
<.079
<.003
<.004
<.005
<.004
<.004
<.005
<.027
<.001
<.003
<.001
<.001
<.002
<.002
<.002
<.002
<.026
<.001
<.003
<.001
<.001
<.001
<.002
<.002
<.002
<.022
<.001
<.003
<.034
<.001
<.004
<.001
<.001
<.001
<.001
<.002
<.002
<.002
<.001
<.002
<.003
<.003
<.002
<.001
<.001
<.079
<.003
<.004
<.001
<.079
<.079
<.003
<.003
<.001
<.001
<.001
<.001
<.072
<.003
<.003
<.001
<.004
<.004
<.006
<.006
<.005
<.007 Allvalues given as < are less than IXD
0
'j F
g,(
<ii I
plI' I
Sta 2 Sta 3 Table 3-3 C 13 Rack Gxgasite Gama Isotcpit Anal Results in Jhizd Quarter Sta 10 Be7
.084+.Oll
.088+.014
.U&.018
.10&..024
.119+.027
.092+.031
.0%H..016
.084+.018
.~.017
.08$ -.019
.107+.022
.082+.018 K40
<.001 Cr51
<.015 NnP4
<.001
<.OO2 QP
<.001 Cb~
<.001 Zn65
<.OO1 ZP
<.001 5kP5
<.001 Bx 03
<.001 Ru106
<.OO5
<.001
<.OO1 140
<.031 cd.41
<.019 C&44
<.OO3
<.002
<.002
<.001
<.001
<.001
<.ool
<.001
<.001
<.001
<.001
<.001
<.001
<.001
<.004
<.001
<.001
<.003
<.024
<.001
<.003
<.001
<.001
<.002
<.002
<.002
<.002
<.007
<.001
<.001
<.059
<.003
<.004
<.007
<.039
<.001
<.005
<.002
<.001
<.002
<.003
<.003
<.003
<.Oll
<.001
<.001
<.093
<.005
<.007
<.010
<.038
<.001
<.005
<.002
<.001
<.002
<.003
<.003
<.003
<.010
<.001
<.001
<.088
<.004
<.006
<.005
<.057
<.001
<.007
<.002
<.001
<.003
<.004
<.005
<.004
<.004
<.016
<.001
<.003
<.001
<.001
<.002
<.002
<.002
<.002
<.005
<.020
<.001
<.005
<.020
<.001
<.004
<.004
<.006
<.024
<.001
<.004
<.017
<.001
<.003
<.004
<.004
<.019
<.001
<.004
<.001
<.001
<.001
<.002
<.001
<.001
<.001
<.001
<.001
<.001
<.002
<.002
<.001
<.002
<.001
<.003
<.003
<.002
<.002
<.003
<.002
<.002
<.002
<.002
<.003
<.004
<.003
<.002
<.003
<.002
<.001
<.001
<.183
<.007 t
<.008
<.001
<.001
<.094
<.003
<.003
<.001
<.001
<.001
<.001
<.001
<.001
<.001
<.001
<.001
<.001
<.113
<.004
<.004
<. 122
<.004
<.004
<.102
<.003
<.003
<.175
<.142
<.004
<.005
<.005
<.004
<.012
<.005
<.006
<.006
<.005
<.008
<.006 Allvalues given as < are less than ZXD
t y
h 4
Sta 2 Sta 3 Table 3-3 D 13 %ek Qxgcaite Gme Isohpic Anal
~ts in Earth +ater Sta 10 Sta 11 Sta 12 Sta 13A Be7
.071+.Oll
.086+.017
.086+.013
.087+.014
.OEH..013
.082+.014
.068+.018
.07&-.018
.076+.018
.07CH..021
.067+.021
.068+.016
<.OO3 cr51
<.015 Nr&
<.001
<.OO2
~ QP I
ao60
<.001
<.001 Zn65
<.OO1 ZP5
<.Ool NkP5
<.001 p~103
< 001 ad.06
<.oo5 Cs~
<.001
<.OO1.
140
< 003 ce 41
< 002 Cd-44
<.OO3
<.006
<.024
<.001
<.003
<.001
<.001
<.002
<.002
<.002
<.002
<.007
<.001
<.001
<.048
<.003
<.004
<.008
<.020
<.001
<.003
<.001
<.001
<.002
<.002
<.006
<.025
<.001
<.004
<.001
<.001
<.002
<.002
<.004
<.018
<.001
<.002
<.001
<.001
<.001
<.002
<.002
<.006
<.001
<.001
<.043
<.003
<.004
<.002
<.007
<.001
<.001
<.048
<.003
<.005
<.001
<.005
<.001
<.001
<.037
<.002
<.003
<.002
<.002
<.002
<.001
<.019
<.001
<.002
<.001
<.001
<.001
<.002
<.006
<.027
<.001
<.004
<.001
<.001
<.002
<.003
<.001
<.006
<.001
<.001
<.039
<.002
<.004
<.002
<.008
<.001
<.001
<.059
<.003
<.005
<.002
<.003
<.005
<.025
<.001
<.003
<.001
<.001
<.002
<.002
<.002
<.002
<.007
<.001
<.001
<.060
<.003
<.004
<.006
<.034
<.001
<.004
<.001
<.001
<.002
<.003
<.003
<.002
<.007
<.001
<.001
<.095
<.004
<.005
<.006
<.036
<.001
<.004
<.001
<.001
<.002
<.003
<.003
<.002
<.OC8
<.001
<.001
<.096
<.004
<.005
<006
<.003
<.037
<.026
<.001
<.004
<.001
<.001
<.002
<.003
<.003
<.003
<.008
<.001
<.003
<.001
<.001
<.002
<.002
<.002
<.002
<.006
<.004
<.005
<.003
<.004
<.001
<.001
<.001
<.001
<.119
<.077 A11 valse+ given as < are less than IXD
F nk*
0
Table 3-4 Charcoal Cartridges Gamma Analysis Results in pCi/m for Iodine Wee o
1/5 1/12 1/19 1/26 2/2 2/9 2/16 2/23 3/2 3/9 3/16 3/23 3/30 4/6 4/13 4/20 4/27 5/4 5/11 5/18 5/25 6/1 6/8 6/15 6/22 6/29 7/6 7/13 7/20 7/27 8/3 8/10 8/17 8/24 8/31 9/7 9/14 9/21 9/28 10/5 10/12 10/19 10/26 11/2 11/9 11/15 11/21 11/29 12/7 12/14 12/21 12/28 st.
4
<0.036
<0,035
<0.035
<0.039
<0.032
<0.035
<0.036
<0.034
<0.037
<0.035
<0.036
<0.033
<0.046
<0.041
<0.035
<0.033
<0.033
<0.035
<0'35
<0.037
<0.042
<0.038
<0.036
<0.040
<0.040
<0.040
<0'45 40.046
<0.037
<0.044
<0.039
<0.040
<0.033
<0.034
<0.043
<0.037
<0.037
<0.035
<0.036
<0.032
<0.040
<0.037
<0.040
<0.032
<0.039
<0.041
<0.041.
<0.040
<0.032
<0.037
<0.037
<0.035
~St 7
<0.029
<Oo030
<0.030
<Oo029
<0.028
<0. 051 (a)
(a)
(a)
<Ool76(b)
<0.053
<0.053
<0.067
<0.064
<0.055
<0.063
<0.059
<0.063
<0'69
<0.067
<Oo073
<0.061
<0.067
<0.067
<0.078
<0.074
<0.070
<0.074
<0.067
<Oo071
<0.067
<Oo066
<0.073
<0.071
<0.071
<0.061
<0.074
<0.074
<0.072
<0.063
<0.063
<0.050
<0.038
<0.024
<0.034
<0.035
<0.040
<0.022
<0.030
<0.031
<0.032
<0.023 5
<0'38
<0.031
<0.033
<0.032
<0.033
<0.029
<Oo031
<0.042
<0.033
<Oo035
<0.031
<0.031
<0.031
<0.033
<0.029
<Oo031
<0.034
<0.028
<Oo033
<0.034
<Oo034
<0.038
<0.033
<0.038
<0.039
<0.034
<0.036
<0'36
<0.038
<0.038
<0.037
<0.038
<0.038
<0.037
<0.039
<0.041
<0.037
<0.038
<0.036
<0.038
<0.033
<0.039
<0.038
<0.034
<0.025
<0.238(b)
<0.112(b)
<0.052
<0.035
<0.041
<0.029
<0.068
<0.027
<0.029
<0.026
<0.029
<0.026
<0.027
<0.025
<0.026
<0.027
<0.026
<0.027
<0.028
<0.025
<0.026
<0.026
<0.027
<Oo027
<Oo028
<Oe028
<Oo028
<0.0)4
<Oo029
<0.041
<0.031
<0.030
<0.030
<0.030
<0.033
<0.031
<0.031
<0.031
<0.031
<0.031
<0.030
<0.037
<0.033
<0.031
<0.033
<0.038
<Oo076
<0.032
<0.031
<Oo031
<0.027
<0+037
<Op 080 (b)
<0. 090 (b)
<0.046
<0.064
<0.065
<0.069
<0.023 All values given as
< are less than (a) Unit out of service (b) unit run only partial week ONSITE AIR MONITORS GROSS BETA ANALYSIS R. E. GINNA NUCLEAR POWER STATION pCi/cu METER 0.08 0.06 IhJ CO I
0.04 0.02 5
9 13 17 21 25 29 33 37 41 45 49 WEEK NUMBER
~ 1988 ~ 1989 ~ 1990
l 0
OFFSITE AIR MONITORS GROSS BETA ANALYSIS R. E. GINNA NUCLEAR POWER STATION pCi/cu METER 0.08 0.06 0.04 0.02 5
9 13 17 21 25 29 33 37 41 45 49 WEEK NUMBER
~ 1988 ~ 1989 ~ 1990
e
ANNUAL TRENDING OF AIR ACTIVITY GROSS BETA ANALYSIS FOR 1968 - 1990 R. E. GINNA NUCLEAR POWER STATION pCi/cu METER 0.35 0.3 0.25 0.2 0.15 0.1 0.05 0
68 70 72 74 76 78 80 82
. 84 86 88 90 YEAR
~ ONSITE MONITORS ~ OFFSITE MONITORS PEAKS ARE INDICATIVEOF NUCLEAR DETONATIONS IN THE ATMOSPHERE.
4 4+i*
~
4 w ~
wh, 4lj'p 1+
3.3 Water Sam les Water samples are collected on a
regular schedule from
.locations surrounding the plant to demonstrate that there is no measurableinfluence-.os contamination....of drinking, or irrigation water from-liquid effluent releases:.or deposition from gaseous effluent releases.
Composite samples are collected weekly from Lake Ontario, upstream (Russell Station),
and downstream
.(Ontario Water District Plant - OWD), and analyzed for gross beta activity.
There was no significant difference between the upstream and downstream sample concentrations.
The 1990 averages were
- -2.10+0.9 and 2.02+0.9 pCi/liter for the upstream and downstream samples respectively.
Weekly composite samples are taken from the plant circulating water intake (Circ In) and discharge canal (Circ Out).
The yearly averages were 1.94+0.9 and 1.93+0.9 pCi/liter for the intake and discharge canal respectively.
These are essential-
'""ly the-same as the upstream and downstream values of 2.10+0.9 and 2.02+0.9 pCi/liter as they fall within the
+
2 sigma error band and range of the measurement.
A gamma isotopic analysis of biweekly composites of the OWD and the discharge canal is performed.
For all batch releases,-- the average concentration in the discharge canal from the identified activity during 1990 was 0.25 pCi/liter.
The normal 2
sigma variation for the activity calculation of -composite samples is 0.85 pCi/liter or 3 times the average concentration added by releases from the, plant.
Samples of tap water, the nearest well, and the creek which crosses the site are collected and analyzed monthly.
The results show no indication of plant influence.
Results for all beta analyses are listed in Table 3-5.
Gamma isotopic analysis is done on each monthly sample and each biweekly or monthly composite of weekly samples.
These are listed in Tables 3-6 to 3-11 and separated by source of sample.
Trend plots are included 'to show the 'weekly upstream and downstream beta activities.
A trend plot showing the annual average activity measured during the years 1968 to 1990 is included to show the data during the years the R.E.
Ginna Nuclear Power Plant has been in operation.
The peaks correspond to the years when atmospheric testing of nuclear weapons occurred.
31
g1
~ w p4 4}
I
<<>> I
Fallout Fallout is a
term used to denote radioactive material settling from the atmosphere to the ground.
At the sampling
- stations, the fallout settles as dust or is collected with rainfall by a
funnel and bottle.
There are two on-site sampling stations and three off-site.
Fallout generally increases in the spring months due to transfer of fission products from the upper to the lower atmosphere in conjunction with increased rainfall.
The onsite average and the offsite average were 5.40+0.65 and'5.96+0.65 pCi/m /day respectively.
Based on the two sigma error of the measurement, there was no significant difference between on-site and off-site samples for the period of January through
- December, 1990.
Table 3-5C lists the values for fallout samples.
Tritium Anal sis Tritium analysis is done on all water samples on a monthly basis.
Composites are made from the weekly composites and a
portion distilled for analysis to remove interfering elements or activity.
Tritium data is given in Tables 3-12 A 6 B.
In May, the liquid scintillation counter was moved to a
new location with a higher background increasing the value for LLD.
Iodine Anal sis All monthly composite water samples except the fallout samples are analyzed for Iodine-131.
The analysis is done by chemical separation using an added carrier solution and gross beta counting.
The analysis allows the determination of Iodine-131 activity of 1 pCi/liter.
Iodine data is given in Table 3-13.
32
<<4 I<<
)g r
(
I
~
~ l<<P
~ -
S<<<<<<
<<I I I<<1'<<
yp
Table 3-5 A Environmental Water Samples Gross Beta Analysis Results in pCi/L Week of 1/5 1/12 1/19 1/26 2/2 2/9 2/16 2/23 3/2 3/9 3/16 3/23 3/30 4/6 4/13 4/20 4/27 5/4 5/11 5/18 5/25 6/1 6/8 6/15 6/22 6/29 Russell 2.97+.88 3.29+.86 2.39+.82 2.90+.87 3.41+.86 3.47+.92 1.82+.77 3.85+.95 (a) 2.60+.83 3.18+.79 1.82+.86 1.74+.75 2.58+.83
<1.20 2.34+.75
<1.20 1.81+.71 2.51+.77 1.76+.85 1.51+.80 1.35+.85 2.79+.84 2.36+.77 2.36+.79 2.01+.75 O.W.D.
1.91+.79 2.36+.82 1.75+.78 2.01+.73 1.70+.81 2.54+.77 2.16+.78 2.49+.80 2.55+.83 3.65+.81 1.26+.79 1.69+.79 1.45+.65 2.38+.77 1.64+.69 1.88+.80 1.62+.80 1.69+.71 1.78+.75
<1.20 2.33+.81 (a) 1.86+.76 (a) 2.02+.81 1.44+.78 Circ In 3.58+.87 2.14+.78 3.42+.81 2.11+.76 (a) 1.90+.73 2.71+.79 3.37+.87 2.11+.80 2.78+.73 2.13+.77 2.38+.83 1.66+.67 1.80+.72 2.02+.75 1.45+.76 1.36+.75 2.80+.76 1.46+.74 1.80+.73 1.67+.76 1.59+.80 1.71+.71 1.38+.76 1.78+.74 1.35+.77 Circ Out 1.29+.75 2.35+.80 1.25+.76 1.41+.71 3.07+.87 2.76+.76 1.89+.76 1.60+.71 3.06+.84 2.76+.75 1.92+.74 1.90+.80 2.70+.78
<1.20 2.32+.75 2.02+.80 1.70+.77 1.91+.68 2.49+.80 2.27+.81 1.89+.86 (a) 1.57+.75 1.55+.79
<1.20 1 71+ 77 Deer Creek 2.32+.90 2.07+.91 3.59+.79 2.54+.82 2.57+.82 2.70+.96 Well
'B'1.20
<1.20
<1. 20 3.63+.99 1.67+.73 4.32+.93
- 1. 73+. 76
- 2. 30+. 93
<1.20 3.60+.99 l.59+. 67
- 2. 12+. 90 Maximum Average Minimum 3.85 2.37 1.35 3.65 1.98 1.26 3.58 2.06 1.35 3'7 1.99 1.29 3.59 2.63 2.07 1.73 1.43 1.59 4.32 2.86 2.12 (a) sample lost in collection or processing All values given as < are less than the LLD corrected for decay.
g Mr~
lg'
Table 3-5 Environmental Water Samples Gross Beta Analysis Results in pCi/L Week of 7/6 7/13 7/20 7/27.
8/3 8/10 8/17 8/24 8/31 9/7 9/14 9/21 9/28 10/5 10/12 10/19 10/26 11/2 11/9 11/16 11/23 11/30 12/7 12/14 12/21 12/28 Russell 1.54+.78 (a) 1.76+.77 2.27+.85 1.67+.74
<1.20 1.53+.76 1.85+.74 1.60+.69 2.23+.85
<1.20
<1.20 1.56+.77 2.03+.79 2.71+.83 1.50+.70 2.42+.81 1.78+.78 1.85+.77 1.57+.77 1.75+.79 1.35+.80 1.74+.78 1.50+.89 3.83+.87 O.W.D.
2.54+.82 1.89+.89 2.85+.88 2.40+.78
<1.20 1.79+.78 1.83+.76 1.82+.74 1.40+.74 1.96+.73 2.05+.77 1.31+.76 1.31+.79 2.39+.76 1.91+.79 1.32+.70 1.65+.83 1.89+.77 2.49+.80 3.28+.92 2.76+.85 2.31+.81 1.91+.90 2.17+.87 (a) 3.43+.87 Circ In 2.16+.79
<1.20
<1.20 1.98+.77 1.75+.75 1.34+.77 1.34+.72 1.95+.78 1.32+.73 1.93+.79 1.55+.75 1.33+.76 1.57+.79 2.40+.75 2.28+.78 2.13+.75
<1.20 1.39+.71 2.42+.80 1.92+.79 2.00+.78 1.55+.78 1.68+.81 2.33+.85 3.54+.89 (a)
Circ Out
<l.20
- 1. 31+. 86 2.15+.79 1.96+.75
<1.20 1.88+.88 2.16+.83 2.18+.77 1.53+.73 2.04+.85 1.90+.75
<1.20 2.31+.86 1.53+.72 2.40+.79 (a) 1.68+.86 1.75+.74 2.23+.79
<1.20 2.24+.79 1.81+.76 1.85+.78 2.20+.86 (a) 2.75+.82 Deer Creek Well
'B'.09+.88
'1.37+.70 1.28+.83 2.18+.89
- 1. 40+. 70
- 2. 30+. 89 2.34+.96 1.46+.75 3.58+.97 5.27+1.03 1.77+.69 3.72+.94 3.45+.97 1.63+.79 2.91+.94
- 3. 92+1. 00 l.46+. 89
- 1. 31+. 88 Maximum Average Minimum 3.83 1.82 1.35 3.43 2.07 1.31 3.54 1.83 1.32 2.75 1.86 1.31 5.27 3.21 2.09 1.77 1.52 1.37 3.72 2.52 1.28 (a)
Sample lost in collection or processing All values given as
< are less than the LLD corrected for decay
Table 3-5 C
Fallout Results in pCi/m /Day Sta.
3 Sta.
5 Sta.
8 Sta.
10 Sta.
12 January February March April 6.11+0.95 2.69+0.77 8.59+1.33 5.25+1.35 10.3+1.7 6.74+1.48 4.26+0.92 13.0+1.61 8.94+1.63 2.67+0.74 3.87+0 '2 17.7+2.8 7.70+1.77 5.16+0.87 4.58+1.00 6.06+2.*32 4.86+2.30
. 6.76+2.50
.'5.37+2.41 10.2+2.3 May June July August 3.53+2.17 9.25+1.24 5 '4+2 '6 10.9+1.4 2.64+1.00 2.62+1.01 4.34+1.39 2.34+1.32 1.40+2.02 4.55+1.78
<1.10 6.56+1.95 October November December
<1. 10
- 3. 18+1. 09 (a) 4.39+2.12 6 '2+1'8 8.42+1.54 5.49+2.59 3.28+1 '4 2.91+1.58 September
- 2. 71+1. 14
- 7. 95+1. 34
- 3. 38+1. 12
- 2. 76+1. 99
- 6. 06+2. 18
- 2. 51+1. 21 9 ~ 02+1. 15 1.47+1.00 10.5+1.3 3.45+1.41 4.45+1.11 2.78+1.25 2.87+0.99 4.64+2.40 10.8+3.1 8.26+1.49 9.99+1.35 4.77+1.36 3.13+1.51 Maximum Average Minimum 9'5 4.88 2'4
- 13. 0
- 8. 94 5.92 5.07 2.34 '.40 17
~ 7 5'4 1'7 10.8 7.47 2'7 All values given as
< are less than LLD corrected for decay (a) sample lost in processing ENVIRONMENTALWATER SAMPLES GROSS BETA ANALYSIS FOR 1990 R. E. GINNA NUCLEAR POWER STATION pci/liter 4
0 5
9 13 17 21 25 29 33 37 41 45 49 WEEK NUMBER
~ UPSTREAM, RUSSELL ~ DOWNSTREAM, OWD VALUES PLOTTED AT 1.00 pCI/L ARE LLD VALUES.
J L !
ANNUAL TRENDING QF ENVIRONMENTALWATERS GROSS BETA ANALYSIS R. E. GINNA NUCLEAR STATION pCi/liter 12 10 68 70 72 74 76 78 80 82 84 86 88 90 YEAR
~ UPSTREAM, RUSSELL ~ DOWNSTREAM, OWD YEARS 1968 " 1990
0
Table 3-6 Ontario Water District Water Gamma Isotopic Analyses Results in pCi/Liter 1
co I
Between Dates Of 12/28 - 1/4 1/4 1/19 1/19 - 2/2 2/2 - 2/16 2/16 - 3/2 3/2 - 3/16 3/16 - 3/30 3/30 - 4/13 4/13 4/27 4/27 - 5/11 5/11 - 5/25 5/25 6/8 6/8 - 6/22 6/22 - 7/6 7/6 7/20 7/20 8/3 8/3 - 8/17 8/17 8/31 8/31 9/14 9/14 - 9/28 9/28 -10/12 10/12 -10/26 10/26 -11/9 11/9
-11/21 11/21 -12/7 12/7
-12/21 12/21 - 1/4 7Be
<36
<28
<28
<32
<27
<29
<32
<28
<28
<30
<32
<37
<38
<36
<37
<37
<37
<35
<37
<35
<37
<37
<35
<35
<37
<36
<36 51C
<42
<35
<33
<38
<34
<33
<33
<33
<33
<35
<40
<39
<44
<42
<39
<43
<44
<43
<42
<41
<41
<41
<40
<40
<42
<41
<42
<3
<3
<3
<3
<3
<3
<3
<3
<3
<3
<4
<4
<4
<4
<4
<4
<4
<4
<3
<3
<3
<4
<3
<4
<4
<4 59F
<7
<6
<6
<6
<6
<5
<6
<5
<6
<7
<7
<7
<7
<7
<7
<8
<7
<8
<7
<8
<6
<8
<8
<8
<8
<6
<7 e
58
<3
<3
<3
<3
<3
<3
<3
<3
<3
<3
<4
<4
<4
<4
<4
<4
<4
<4
<4
<4
<3
<4
<4
<3
<4
<4 60Co
=<4
<4
<3
<3
<3
<3
<4
<4
<4
<4
<4
<4
<4
<4
<4
<4
<4
<4
<3
<3
<4
<4
<4
<4
<4
<3
<4 65z
<7
<6
<6
<6
<6
<6
<6
<6
<5
<6
<7
<7
<7
<7
<7
<7
<7
<7
<7
<8
<7
<7
<7
<7
<7
<7
<7 n
95Zr
<7
<6
<5
<6
<6
<6
<5
<5
<6
<5
<6
<7
<7
<7
<7
<6
<6
<7
<7
<7
<7
<7
<7
<7
<7
<7
<7 103Ru
<4
<4
<4
<4
<4
<4
<4
<3
<4
<3
<4
<5
<5
<4
<4
<4
<5
<4
<4
<4
<5
<4
<4
<4
<4
<5
<4
<37
<29
<27
<27
<3
<27
<29
<28
<28
<30
<33
<36
<34
<3.6
<37
<33
<35
<37
<39
<34
<35
<35
<32
<35
<35
<34
<37 134Cs
<4
<3
<3
<3
<3
<3
<3
<3
<3
<3
<3
<4
<4
<4
<3
<3
<3
<3
<3
<3
<3
<3
<3
<4
<3
<4
<4 137Cs
<4
<4
<4
<4
<4
<3
<3
<3
<4
<3
<4
<4
<5
<4
<5
<4
<4
<4
<4
<4
<4
<4
<4
<4
<4
<4
<4 140B
<20
<17
<16
<21
<17
<15
<15
<15
<16
<16
<20
<21
<23
<20
<21
<21
<23
<20
<21
<22
<20
<20
<22
<20
<21
<21
<20 141Ce
<9
<8
<7
<8
<8
<7
<7
<8
<8
<8
<9
<9
<9
<9
<9
<9
<9
<9
<9
<9
<9
<9
<9
<9
<9
<9
<9 144Ce
<37
<33
<30
<32
<31
<31
<32
<31
<32
<32
<34
<36
<38
<36
<37
<35
<37
<36
<37
<37
<37
<36
<37
<36
<37
<36
<37 226Ra
<8
<7
<7
<4
<7
<7
<7
<6
<6
<6
<8
<8
<8
<9
<8
<8
<8
<9
<8
<8
<8
<9
<9
<8
<9
<8
<8 All values given as.< are less than LLD corrected for decay.
Table 3-7 Circ. Outlet Water Gamma Isotopic Analyses Results in pCi/Liter Between 1/4 1/18 2/1 2/15 3/1 3/15
, 3/29 4/12 4/26 5/10 5/25 6/7 6/21 7/6 7/18 8/1 8/15 8/29 9/13 9/26 10/10 10/25 11/15 ll/30 12/12 1/18
- 2/1 2/15 3/1 3/15 3/29
- 4/12 4/26
- 5/10
- 5/25
- 6/7 6/21 7/6 7/18 8/1
- 8/15
- 8/29
- 9/13
- 9/26 10/10 10/25 11/15 11/30
- 12/12 12/27 Dates Of 7Be
<28
<28
<30
<29
<31
<29
<27
<27
<30
<29
<39
<38
<37
<37
<33
<34
<35
<41
<37
<36
<33
<39
<35
<37
<36 51Cr
<34
<34
<37
<33
<34
<33
<33
<33
<34
<37
<40
<42
<42
<39
<41
<40
<41
<50
<42
<41
<33
<42
<43
<41
<42 54Wn
<3
<3
<3
<3
<3
<3
<3
<3
<3
<3
<4
<4
<4
<4
<3
<4
<4
<4
<4
<4
<4
<4
<3
<4
<4 59Fe 58Co
<6
<3
<6
<3
<6
<3
<6
<3
<6
<3
<6
<3
<6
<3
<6
<3
<6
<3
<7
<3
<7
<4
<7
<4
<7
<4
<8
<4
<7
<4
<7
<4
<7
<4
<8
<4
<8
<4
<7
<4
<6
<4
<8
<4
<7
<4
<7
<4
<7
<4 60Co
<4
<4
<4
<4
<4
<4
<4
<4
<5
<3
<4
<3
<3
<4
<3
<4
<3
<3
<4
<4
<3
<4
<4
<4
<4 65Zn
<5
<5
<6
<6
<6
<6
<6
<5
<5
<6
<7
<7
<8
<7
<8
<7
<7
<7
<7
<7
<8
<7
<7
<7
<7 95Zr
<5
<6
<6
<5
<6
<6
<5
<6
<6
<6
<7
<7
<7
<8
<7
<7
<7
<8
<7
<7
<6
<7
<7
<7
<6
<3
<3
<4
<3
<3
<3
<3
<3
<4
<4
<4
<4
<4
<4
<4
<4
<4
<5
<5
<4
<4
<4
<4
<4
<4 103Ru
<4
<3
<4
<4
<3
<3
<3
<3
<4
<4
<5
<5
<4
<4
<4
'5
<5
<4
<4
<4
<5
<4
<4
<4 106Ru
<29
<26
<26
<28
<28
<28
<27
<27
<31
<31
<36
<35
<36
<35
<35
<33
<35
<30
<33
<36
<36
<35
<34
<32
<35 134Cs
<3
<3
<3
<3
<3
<3
<3
<3
<3
<3
<4
<3
<3
<3
<4
<4
<4
<4
<4
<3
<4
<4
<4
<3
<3 137Cs
<3
<4
<7
<3
<4
<3
<3
<5
<6
<4
<4
<4
<4
<4
<4
<5
<4
<4
<4
<4
<4
<4
<4
<4
<4 I40Ba
<17
<16
<22
<16
<16
<14
<16
<15
<16
<18
<21
<21
<22
<21
<20
<21
<19
<30
<21
<19
<14
<22
<22
<19
<19 141Ce
<8
<8
<9
<7
<8
<7
<7
<8
<8
<9
<9
<9
<9
<9
<9
<9
<9
<10
<9
<9
<7
<9
<9
<9
<9 144Ce
<31
<30
<30
<31
<31
<29
<30
<30
<33
<33
<37
<36
<37
<37
<37
<37
<37
<38
<37
<37
<36
<38
<38
<37
<38 226Ra
<6
<7
<6
<7
<7
<7
<7
<6
<6
<7
<8
<8
<9
<9
<8
<8
<9
<9
<9
<9
<9
<8
<8
<8
<9 Allvalues given as < are less than the LID corrected for decay
C 0
n
Russell Table 3-8 Station Water Gamma Isotopic Analyses Results in pCi/Liter Between 1/1 2/1 3/1 4/1 5/1 6/1 7/1 8/1 9/1 10/1 11/1 12/1 Dates Of 1/31 2/28 3/31 4/30 5/31 6/30 7/31 8/31
- 9/30
-10/31
-11/30
-12/31 7Be
<36
<27
<26
<30
<27
<36
<34
<32
<35
<34
<33
<35 51Cr
<36
<30
<31
<30
<30
<35
<37
<34
<37
<35
<37
<36 54mn
<4
<3
<3
<3
<3
<3
<4
<4
<4
<3
<3
<3 59Fe
<7
<5
<5
<6
<5
<6
<7
<6
<7
<6
<7
<7 58Co
<3
<3
<3
<3
<3
<4
<3
<4
<3
<4
<3
<4 60Co
<4
<4
<3
<4
<4
<4
<4
<3
<4
<4
<4
<4 Zn Zr
<7
<6
<6
<5
<6
<5
<6
<5
<6
<5
<7
<6
<7
<6
<8
<7
<7
<6
<8
<6
<7
<7
<7
<7
<4
<3
<3
<3
<3
<4
<4
<4
<4
<4
<4
<4 Between Dates Of 1/1 1/31 2/1 2/28 3/1 3/31 4/1 4/30 5/1 5/31 6/1 6/30 7/1 7/31 8/1 8/31 9/1 9/30 10/1
-10/31 11/1
-11/30 12/1
-12/31 103Ru
<4
<3
<3
<3
<3
<4
<4
<4
<4
<4
<4
<4 106Ru
<34
<26
<29
<27
<26
<36
<36
<35
<35
<34
<35
<34 134Cs
<4
<3
<3
<3
<3
<3
<4
<3
<3
<4
<4
<4 137Cs
<4
<3
<4
<4
<5
<5
<4
<4
<4
<4
<5
<4 140Ba
<15
<12
<ll
<12
<11
<15
<13
<14
<15
<15
<15
<15 141Ce
<8
<7
<7
<7
<7
<8
<8
<7
<8
<8
<8
<8 144Ce
<35
<30
<30
<32
<31
<35
<35
<36
<36
<37
<37
<37 226Ra
<8
<7
<6
<7
<7
<9
<8
<9
<8
<8
<8
<8 All values given as < are less than the LLD corrected for decay
't
Table 3-9 Tap Water Gamma Isotopic Analyses Results in pCi/Liter 1/1 2/1 3/1 4/1 5/1 6/1 7/1 8/1 9/1 10/1 11/1 12/1 1/31 2/28 3/31 4/30 5/31 6/30 7/31 8/31 9/30
-10/31
-11/30
-12/31 Between Dates Of 7Be
<30
<25
<27
<25
<28
<34
<31
<33
<33
<34
<33
<34 51Cr
<30
<26
<27
<27
<30
<35
<32
<34
<34
<34
<34
<35 54Wn
<3
<3
<3
<3
<3
<3
<3
<4
<4
<4
<3
<3 59Ze
<5
<4
<5
<5
<6
<6
<7
<7
<7
<6
<7
<7 58Co
<3
<3
<3
<3
<3
<4
<4
<4
<3
<4
<4
<4 60Co
<4
<3
<4
<3
<4
<4
<4
<4
<4
<4
<4 (4
65Zn
<6
<6
<6
<6
<6
<8
<6
<7
<6
<6
<7
<5
<5
<5
<5
<5
<6
<6
<6
<6
<7
<6
<8
<6 Zr 95Nb
<3
<3
<3
<3
<3
<4
<4 (4
<4
<4
<3
<4 1/1 2/1 3/1 4/1 5/1 6/1 7/1 8/1 9/1 10/1 11/1 12/1 1/31 2/28 3/31 4/30 5/31 6/30 7/31 8/31
- 9/30
-10/31
-11/30
-12/31 Between Dates Of 103Ru
<3
<3
<3
<3
<3
<4
<4
<4
<4
<4
<4
<4 106Ru
<28
<27
<28
<27
<27
<36
<33
<34
<34
<33
<37
<37 134Cs
<3
<3
<3
<3
<3
<3
<4
<3
<4
<3
<4
<4 137Cs
<3
<3
<4
<4
<4
<5
<4
<4
<4
<4
<4
<5 140Ba
<11
<10
<10
<10
<11
<15
<15
<14
<14
<14
<14
<14 141Ce
<7
<7
<6
<6
<7
<8
<8
<8
<7
<8
<8
<8 144Ce
<32
<30
<31
<30
<31
<36
<35
<37
<36
<36
<36
<37 226Ra
<7
<7
<6
<7
<7
<9
<8
<9
<8
<8
<8
<8 All values given as
< are less than the LLD corrected for decay
I 1
I"
Table 3-10 Well "B" Water Gamma Isotopic Analyses Results in pCi/Liter Between Dates 1/1 1/31 2/1 2/28 3/1 3/31 4/1 - 4/30 5/1 5/31 6/1 6/30 7/1 - 7/31 8/1 8/31 9/1 9/30 10/1
-10/31 11/1
-11/30 12/1
-12/31 Of 7Be
<28
<28
<27
<29
<27
<37
<33
<32
<35
<34
<35
<34 51Cr
<31
<31
<29
<31
<30
<37
<35
<35
<36
<35
<35
<35 54xn
<3
<3
<3
<3
<3
<4
<4
<3
<4
<3
<4
<4 59Pe 58Cp
<5
<3
<5
<3
<6
<3
<6
<3
<5
<3
<7
<4
<7
<4
<7
<3
<7
<4
<6
<4
<7
<4
<6
<4 60co
<4
<4 (4
<3
<4
<4
<4
<4
<4
<4
<4
<4 65Zn
<6
<5
<6
<6
<6
<7
<7
<7
<7
<8
<7
<8 95Zr 95Nb
<5
<3
<5
<3
<5
<3
<6
<3
<5
<3
<6
<4
<6
<4
<6
<4
<7
<3
<6
<4
<7
<4
<7
<4 Between Dates Of 1/1 - 1/31 2/1 2/28 3/1 3/31 4/1 4/30 5/1 - 5/31 6/1 6/30 7/1 - 7/31 8/1 - 8/31 9/1 - 9/30 10/1
-10/31 11/1
-11/30 12/1
-12/31 103Ru
<3
<3
<3
<3
<3
<4
<4
<4
<4
<4
<4
<4 106Ru
<29
<27
<29
<26
<28
<37
<31
<35
<35
<37
<34
<34 134Cs
<3
<3
<3
<3
<3
<4
<4
<3
<3
<3
<4
<4 137Cs
<4
<3
<3
<4
<4
<4
<4
<5
<5
<4
<4
<4 140Ba
<11
<13
<ll
<ll
<12
<14
<14
<14
<15
<14
<13
<15 141Ce
<7
<7
<7
<7
<7
<8
<8
<8
<8
<8
<8
<8 144Ce
<33
<30
<33
<32
<32
<37
<37
<36
<35
<37
<37
<37 226Ra 29+ 9 ll+ 6 45+ 8 36+ 9 26+ 9 41+ 9 37+11 29+10 33+11 24+
9
<ll 33+11 All values given as
< are less than the LLD corrected for decay
0 4t
~
q 1
P
Table 3-11 Deer Creek Water Gamma Isotopic Analyses Results in pCi/Liter Between Dates 1/1 1/31 2/1 - 2/28 3/1 - 3/31 4/1 - 4/30 5/1 5/31 6/1 6/30 7/1 7/31 8/1 8/31 9/1 9/30 10/1
-10/31 11/1
-11/30 12/1
-12/31 Of 7Be
<25
<27
<28
<29
<26
<33
<33
<30
<32
<34
<33
<32 51Cr
<30
<31
<27
<27
<28
<34
<35
<35
<35
<37
<37
<35 54mn
<3
<3
<3
<3
<3
<4
<4
<4
<4
<4
<4
<4 59pe 58CQ
<5
<3
<6
<3
<5
<3
<6
<3
<5
<3
<6
<3
<6
<3
<7
<3
<6
<3
<6
<3
<7
<4
<6
<4 60Co
<4
<4
<4
<4
<4
<4
<4
<4
<4
<4
<3
<4 65Zn
<6
<6
<6
<6
<5
<8
<8
<6
<7
<7
<7
<7 95Zr
<5
<5
<5
<5
<5
<6
<6
<6
<6
<6
<6
<6
<3
<3
<3
<3
<3
<4
<4
<4
<4 (4
<3
<3 Between Dates Of 1/1 1/31 2/1 2/28 3/1 3/31 4/1 4/30 5/1 5/31 6/1 6/30 7/1 7/31 8/1 8/31 9/1 9/30 10/1
-10/31 11/1
-11/30 12/1
-12/31 103Ru
<3
<3
<3
<3
<3
<4
<4
<4
<4
<4
<4
<4 106Ru
<27
<28
<28
<28
<29
<34
<33
<33
<33
<35
<33
<35 134Cs
<3
<3
<3
<3
<3
<3
<4
<3
<3
<3
<4
<4 137Cs
<4 6+4
<4
<4
<4 (4
<4
<4
<5
<4
<4
<4 140Ba
<12
<12
<10
<11
<ll
<14
<14
<14
<14
<13
<14
<14 141Ce
<7
<7
<7
<7
<6
<8
<8
<8
<8
<8
<8
<8 144Ce
<31
<31
<30
<31
<30
<37
<37
<36
<37
<37
<37
<37 226Ra
<8
<7
<8
<8 12+8 24+12 9+7
<11 23+11
<10
<9
<9 All values given as < are less than the LLD corrected for decay
l p'S
<<C P
p 1
Table 3-12 A Environmental Water Samples Tritium Analysis Results in pCi/L Month of Russell O.W. D.
Circ In Circ Out Deer Creek Well
'B'anuary February March April May July
<665
<670
<695 1220+430
<770
<860
<860
<665
<670
<695 997+430
<770
<860
<860
<665
<670
<695
<665
<770
<860
<860
<665
<670
<695
<665
<770
<860
<860
<665
<670
<695 676+416
<770
<860
<860
<665
<670
<695
<665
<770
<860
<860
<665
<670
<695
<665
<770
<860
<860 August September October November December
<950
<950
<950
<950 1140+250
<870
<870
<870
<960
<960
<960
<960
<860
<860
<860
<860 Sample lost due to equipment malfunction
<950
<870
<960
<860
<950
<870
<960
<860
<950
<870
<960
<860 All values given as
< are less than the LLD corrected for decay.
l al
Table 3-12 B
Fallout Tritium Analysis Results in pCi/L Month of Station 3
Station 5
Station 8
.Station 10
-Station 12 January February March April May
/
June July
<655
<670
<695
'665
<770
<860
<860
<655
<670
<695
<665
<770
<860
<860
<655
<670
<695
<665
<770
<860
<860
<655
<670
<695
<665
<770
<860
<860
<655
<670
<695 920+477
<770
<860
<860 August Sample September
<950 lost due to
-<950
<950
<950 equipment malfunction
<950 October
<870
<870
<870
<870
<870 November December
<960
<860
<960
<860
<960
<860
<960
<860
<960
<860 All values given as
< are less than the LLD corrected for decay.
\\
t[
A r
Table 3-13 Month of Russell O.W.D.
Iodine in Water Results in pCi/L Circ. In Circ. Out DeerCreek
~Ta e
January February March April May
<0.32
<0.36
<0.34
<0.27 (b)
<0.27
<0.28
<0.31
<0.33 (b)
June July August
<0.41
<0.27
<0.32 September
<0.34 October November
<0.35
<0.26
<0.28
<0.26
<0'2
<0.22
<0.27
<0.29 December
<0.27
<0.35 (a)
<0.38
<0.30
<0.24 (b)
<0.43
<0.39 (a)
<0'7
<0.37
<0.30 (a)
<0.26
<0.27
<0.29
<0.28 (b)
<0.29
<0.23
<0.29
<0.23
<0.28
<0.26
<0.27 (a)
<0.24
<0.30
<0.32
<0.27
<0.28
<0.32
<0.26
<0.25
<0.29
<0.28
<0.23 (a)
<0. 28
<0. 30
<0.29
<0.28
<0.28
<0.34
<0.29
<0.28
<0.32
<0.31
<0.23
<0.29 (a)
<0. 28
<0. 25
<0.26
<0'7
<0.29
<0.32
<0.32
<0.31
<0.25
<0.28 (a)
Sample lost in processing.
(b) sample omitted while laboratory moved All values given as
< are less than the LLD corrected for decay
3.4 Milk Sam les There are three dairy herds located three to five miles from the plant.
Milk samples are collected monthly during November through May from one of the three and biweekly during June through October from each.
A control farm sample is taken for each monthly sample and once during each biweekly period.
The milk is analyzed for Iodine-131 and also gamma scanned for major fission products.
The method involves chemical separation of iodine and gross beta counting.
The counting procedure is not specific for Iodine-131 and other isotopes may add to the count rate.
t During
The annual dose to the thyroid of an infant which could result from the measured plant release
- rate, was calculated by the method described in the Offsite Dose Calculation Manual using equation 13.
The maximum resultant annual thyroid dose for 1990 would be 0.61 mrem using the cow-milk-infant pathway for a hypothetical farm at the site boundary.
Using the maximum for the real farm with the highest D/Q which is 5 miles from the plant, the maximum calculated dose to the infant is 0.0020 mrem from plant releases during the growing season.
The annual average plant release rate during the grazing season would give a concentration of 0.04 pCi/liter of Iodine-131 in milk at this real farm.
This concentration is equal to 1/10 of the LLD for this analysis.
47
II II fl
Table 3-14 Milk Results in pCi/Liter C
D B
D A
D C
D B
D A
C B
D A
C B
D A
C B
D A
C B
DA' B
D A
C B
D A
C B
D A
C B
D A
C B
D A
C B
D A
C B
D A
D Date 1/22 1/25 2/13 2/15 3/13 3/15 4/17 4/19 5/15 5/17 6/6 6/7 6/12 6/14 6/19 6/2 1 6/2 6 6/28 7/3 7/5 7/10 7/12 7/17 7/19 7/24 7/26 7/31 8/2 8/6 8/9 8/14 8/15 8/21 8/23 8/28 8/30 9/4 9/6 9/11 9/13 9/18.
9/20 9/25 9/27 10/2 10/4 10/9 10/11 10/16 10/18 10/23 10/24 ll/13 11/14 12/11 12/13 I-131
<Oo32
<Oo35
<0.33
<0'9
<0 ~ 31
<0.28
<0.34
<0.38
<0.35
<0.30 (a)
(a)
<0 ~ 68
<Oo45
<0.29
<0.29
<0.29
<0.28
<0.36
<Oo33
<0.36
<0.33
<0.41
<0.36
<0'4
<0.26
<0.32
<0.29
<Oo35
<0.33
<0.30
<0.35
<0.23
<0.33
<0.25
<0.32
<0.27
<0.31
<0.26
<0+30
<0.24
<0.30
<0.35
<0.27
<0.31
<0.27
<0.34
<0.29
<0.35
<0.40
<0+27
<0.39
<0.34
<0.31
<0.28
<0.28 Cs-137
<4
<4 3+3
<4
<4
<4
<4
<4 3+3
<4
<5
<5
<4
<5
<5
<5
<5
<4
<5
<5
<5
<5
<5
<5
<5
<5
<5
<5
<5
<5
<5
<5
<5
<5
<5
<5
<5
<5
<5
<5
<5
<5
<5
<5
<5 (b)
<5
<5
<5
<5
<5
<5
<5
<5
<5
<5 Ba-140
<12
<11
<11
<12
<12
<12
<11
<12
<12
<12
<14
<14
<15
<15
<14
<14
<16
<15
<15
<15
<15
<14
<15
<15
<15
<15
<14
<15
<16
<15
<15
<15
<15
<15
<15
<14
<15
<15
<15
<16
<15
<15
<15
<14
<15 (b)
<15
<15
<15
<15
<15
<14
<16
<16
<14
<15 K-40 1213+101 1194+99 1343+98 1374+99 1251+96 13 14+96 1251+98 1316+98 1246+95 1219+97 1370+128 1461+128 1366+125 1292+122 1310+124 1413+125 1394+122 1388+122 1350+125 1424+132 1513+128 1367+124 1424+128 1571+130 1321+126 1328+127 1377+127 1304+122 1351+127 1352+124 13 15+129 1360+125 1303+125 1513+124 1302+115 1472+122 1428+124 1389+124 1175+117 1391+122 1304+125 1279+122 1292+121 1435+124 1436+122 (b) 1282+124 1307+124 1337+125 1323+126 1330+126 1373+125 1341+123 1265+126 1352+123 1288+128 All values given as
< are less than the LLD corrected ior decay (a)
Samples omitted while laboratory was moved (b) Samples discarded before realization that gamma scan lost during power outage
- 3. 5 Fish Sam les Indicator fish are caught in the plume from the Discharge Canal and tested for radioactivity ingested from liquid effluent releases from the plant.
The fish are filleted to represent that portion which would normally be eaten.
Additional fish are caught more than 15 miles away to be used as background indicators and are prepared in the same manner.
Four different species of fish are analyzed during each half year from the indicator and background locations if they are available.
During the second half of 1990, a fourth species of fish was not caught from the indicator location.
There was no real difference in the activity of the fish caught between the indicator and background locations.
Isotopic gamma concentrations (pCi/wet kilogram) are listed in Table 3-15.
Samples of algae (cladophora) and sand were obtained from the lake bottom in the discharge plume area.
Results of the gamma scan are included in Table 3-16.
49
r
Description Indicator Fish First Half 1990 Table 3-15 Fish Sasples Results in pCi/kgb Wet 40H 5ICr 54Hn 59Fe '8Co 60Co 652n 952r 95Hb 103Ru 106Ru 1311 134Cs 137Cs 140Ba 14ICe 144Ce 226Ra I
3803+337
<150 3272+201
< 92 3515+207
< 75 2595+183
<100
<10
<6
<6
<6
<25
<12 (12
<26
<22
<15
<18
< 8
<7
<15
<13
<9
<16
< 7
<7
<15
<13
<7
<17
< 7
<7
<15
<13
<9
<15
<9
<8
<9
<102
<51
<59
<46
<60
<20
<53
<59
<ll
<6
<6
<6 49+17 32+10 44+8 31+8
<98
<30
<102
<24 c76
<19
<59 c14
<46
<15
<55
<13
<87
<18
<54 I&13 Second Half 1990 BRCWN KKUT ATIANITCSAIH)N IAKE TROUT 2923+183
<103
<6 3851+271
<175
<9 2951+209
<84
<7
<19
<8
<6
<14
<13
<10
<9
<32
<12
<8
<22
<20
<17
<15
<16
<7
<8
<14
<14
<9
<8
<55
<73
<6
<80
<160
<8
<63
<24 c7 2yl8
<101
<20
<53
<12 30il3
<188
<33
<82
<18 28+9
<52
<17
<62
<14 Background Fish First Half 1990 Second Half 1990 2364+155
<76 2446+165
<58 3080+154
<55 3170+150
<48
<6
<5
<5
<4
<13
<6
<7
<13
<10
<7
<7
<14
<6
<7
<14
<10
<6
<6
<12
<5
<6
<12
<10 c6 c6
<11
<4
<6
<12
<8
<5
<5
<48
<30
<5
<6
<52
<15
<49
<10
<50
<13
<5 28+8
<31
<13
<53
<11
<44
<17
<4 15+6
<35
<12
<43
<9
<39
<10
<4 23+6
<25
<10
<40
<9 2811+171
<64
<5
<14 3425+188
<66
<6
<14 2978+245
<114
<8
<22 2661+173
<89
<6
<17
<6
<6
<8
<7 All values given as < are less than the LID corrected for decay
<6
<6
<10
<6
<13
<13
<11
<19
<18
<13
<13
<7
<7<ll
<9
<7
<7<ll
<9
<51
<20
<55
<18
<78
<36
<54
. <46
<5
<5
<8
<5 18+7
<44 28+9
<39 15+12 c71 33+8
<76
<13
<47
<11
<14
<49
<12
<21
<75
<18
<17
<52
<12
Table 3-16 Description Lake Samples Results in pCi/kgm K
51Cr 54Nn 59Fe 58Co 60Co 65Zn 95Zr 9 Nb Cladophora Lake Bottom 11710+250
<62
<7
<16
<7 2652+321
<147
<11
<25
<12
<12
<24
<24
<15
< 8
<17
<12
<8 Description 103Ru 106Ru 131$
134Cs 137C 140Ba 141Ce 144Ce 226Ra Cladophora Lake Bottom
<14
<7
<60
<10
<110
<46
<11
<7 27+14
<91 53+10
<30
<30
<14
<108 118+40
<62 216+20 All values given as < are less than LLD corrected for decay
3.6 Ve etation Sam les Crops are grown on the plant property and samples of the fruits and grains are collected at harvest time for testing.
Background
samples are purchased from farms greater than 10 miles from the plant.
There 'as no indication in the
'-- samples of any measurable activity.,Gamma. isotopic data is given in Table 3-17.
The large LLDs for lettuce are caused by the small sample weight per unit volume.
Soil samples were taken in 1989 for comparison to earlier soil samples taken in 1982.
The results were received in 1990 and are given in table 3-17B 52
ic Cii
Description 40K Table 3-17 Vegetation Samples Results in pCi/kgm Wet 51Cr 54Mn 59pe 58Co 60Co-65Zn 95Zr 95Nb LETTUCE APPIZS CHERRIES CORN GRAPES SQUASH 2271+234
<70 633+125
<40 1686+176
<51 2118+157
<47 2169+155
<42 1532+165
<47
<8
<4
<6
<5
<5
<5
<15
<8
<10
<10
<10
<10
<8
<5
<50
<5
<5
<8
<5
<6
<5
<5
<6
<16
<10
<12
<12
<11
<11
<14
<8
<10
<8
<8
<9
<8
<5
<6
<4
<5
<5 Control Vegetation Samples APPLES LETTUCE 701+125
<41 2995+299
<89
<5
<8
<10
<20
<5
<10
<4
<12
<10
<24
<7
<4
<18
<10 Description LETTUCE APPLES CHERRIES CORN GRAPES SQUASH 103Ru
<8
<5
<6
<5
<5
<5 106Ru
<73
<42
<53
<47
<45
<50
<9
<5
<7
<6
<6
<6
<8
<5
<6
<5
<5
<6 131I 134Cs 137Cs 140~
141Ce 144Ce 226Ra
<7
<29
<15
<71
<19
<4
<16
< 9
<42
<10
<6
<20
<11
<53
<12
<5
<18
<10
<45
<11
<4
<18
< 9
<43
<10
<5
<19
<10
<48
<12 Control Vegetation Samples APPIZS LETTUCE
<5
<10
<42
<95
<5
<4
<11
<9 5+4
<17 18+9
<38
<9
<19
<43
<10
<89
<22 All values given as
< are less than LLD corrected for decay
TA
-17B COMPARISON 0 A SOIL SAMPLING RESULTS 1989 Sam le Location of Cs-137 Cs-137 Sr-90 RADIONUCLIDECONCENTRATIONS IN SOIL Sr-90 Cs-134 Cs-134 Ci/,11 si ma Co-60 Co-60 Pu-238 Pu-238 Number Soil Sam ie June 89 Ma brune 82 June 89 Ma dune 82 June 89 Ma 4une 82 June 89 Ma Qune82 June89 Ma brune 82 Back round ¹I 1300 m 255'.37&.02 0.28&.03 NA'.088&.022
< 0.01 1 0.~.007
( 0.011 0.0233 0.003 NA
( 0.13 Back round ¹2 790m 295'ack round ¹3 0.23&.01 0.27M.Ot NA'.056fO.OI4
< 0.011 0.028M.009
< 0.0092
< 0.01 NA
< 0.14 11260 m 240'.2010.01 NL 0.~.014 NL-
< 0.012 NL"
< 0.0083 NL' 0.0018 NL" AirSam er¹3 480 m 110'.31&.02 Sam leM 0.498).02 0.19%.03 Sam le M NA (0.013 Sam le M ND'"
< 0.0095 Sam IeM ND
< 0.0038 Sam le M NA AlrSam er¹4 350m 1404 0.94&.05 22f:1
< 0.064 0.78607
< 0.015 10.~.2 0.11&.01
'1.3f0.3
< 0.0029 Onsite Garden 730m 142'.37&.02 Sam leE 0.9~.05 0.03%0.012 Sam eE
< 0.10
< 0.014 Sam leE 0.25f0.02
< 0.0096 Sam leE 0.29IO.OI 0.0020f0.0005 Sam le E 7
Lake Road at SGTR Plume Centerline 0.67&.03 0.6~.03 0.1 510.01 NA
< 0.016 0.31M.03 0.046f0.002 0.30I0.02
< 0.0032 NA 8
INT: Knickerbocker
& Baile Roads 0.095'.07 NA'A
< 0.0097 0.06&0.01 5
< 0.0074 ND-NA'A 9
INT: Knickerbocker
& Ken on Roads 0.36%.02 0.0378).015 NA' (0.014 0.06310.013
< 0.010 ND-NA'A 10 INT: Furnace &
Baile Roads INT: Lake &
Furnace Roads 0.92%.09 0.26%.01 0.14&.01 0.18&.02 NA'A'A NA
< 0.018
< 0.012 0.042f0.008
< 0.014 O.OQEO.OI 4 0.025f0.003 NPO41 NA'A NA'A'2 INT: Lake & Stone Lonesome Roads 0.3%0.02 0.4~.02 NA' 0.016 0.061M.010
< 0.011 NPeeo NA'A
'NAmeans the sam le wasn't ana zed for this radionudide.
"NLmeans new locaten no sam le was collected at this location in 1982.
'"NDmeans this radionudide was not detected b the anal sis.
8/24/90
E
3.7 External Penetratin Radiation A thermoluminescent dosimeter (TLD) with a sensitivity of 5 millirem/quarter is issued as part of the environmental monitoring program.
Thirty-nine TLD badges are currently placed in four rings around the plant.
These rings range from less than 1000 feet to 15 miles and have been dispersed to give indications in each of the nine land based sectors around the plant should an excessive release occur from the plant.
Badges are changed and read after approximately 3
months exposure.
TLD location N7 is influenced by its close proximity to the Contaminated Equipment Storage Area established in 1983 and will normally read 20-40 mRem/quarter.
For the year of
- 1990, omitting location 7, on-site exposure ranged between ll and 31 mrem/quarter, with an average exposure of 13.8 mrem/quarter and off-site 8
to 16 mrem/quarter with an average exposure of 11.3 mrem/quarter.
Table 3-18 gives TLD readings for each quarter.
Six TLDs were wet at. the time of being read and their values are deleted.
The NRC also obtains TLD measurements around the plant.
The following is a
comparison of the data for the first and second quarters of 1990 using NRC data from NUREG-0837 Vol.
9, No.
1 and 2.
Results in mrem/quarter:
~G'na NEEC
<2 miles 2-5 miles
>5 miles First 13.5 9.7 9.6 Second Third k
12.4 '3.2 12.2 11.3 10.7 10.4 14 ~ 4 13
~ 5 13.7
- 14. 6
- 14. 2 14 ~ 3 15.9 15.2 15.3 First Second Third There are three stations at the same location.
These comparisons are:
A B
C
- 10. 1 12 ~ 5 10.7
. 13.0 9 '
11.1 12.7 11.6 10 '
15-5 15.5 15.3 13.9 14.7 15.0 13.8 No data 17.3
> Ct V
~cat~o Table 3-18 External Penetrating Radiation Thermoluminescent Dosimetry 1990 Units
{}uarter Mr/91 Day 3rd arte
¹14 - ¹16 are located along a line 3000 ft. west of the plant.
¹17 - ¹21 are located along Lake Road.
¹22 - ¹24 are located along the east site boundary line.
¹25 - ¹30 are offsite at a distance of 8 to 15 miles.
¹31 - ¹40 are located in an arc at a distance of 4 - 5 miles.
2 3
4 5
6 7
8 9
10ll 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 ion 37 (a)
TLD missing at, collect time (b) TLD wet when read 38 39 40
¹2 - ¹7 plus ¹13 are on-site near the line of the. highest annual average ground level concentration.
¹8 - ¹12 are offsite at a distance of 8 to 15 mileso 15.4+3.9 13.9+3.5 15.0+3.8 13.8+3.5 11.6+2.9 23.0+5.8 11.4+2.9 8.5+2.2 9.9+2.5 10.0+2.5 9.4+2.4 16.0+F 0 13.2+3.3 14.6+3.7 14.4+3.6 13.9+3.5 14.2+3.6 11.7+2.9 14 1+3.5 12.5+3.2 12.5+3.2 11.3+2.8 11.5+2.9 9.3+2.3 8 8+2 2 10.5+2.7 10.4+2 '
9.6+2.4 7.6+1.9 10.1+2.5 8.7+2.2 9.2+2 3
10.6+2.7 9.8+2.5 8.9+2 2 9.6+2.4 9.9+2.5 10.7+2.7 9.3+2.3 13 2+3 3 12.4+3.1 14.8+3.7 13.9+3 '
10.7+2.7 24.6+6.2 11.6+2.9 9.8+2.5 10.4+2.6 11.0+2.8 11.2+2.8 13.1+3.3 10.9+2 7
13.7+3.5 12.0+3.0 11.1+F 8 13 0+3.3 11.7+2.9 12.0+3.0 12.0+3.0 (b) 10.9+2+7 12.3+3.1 10.2+2.6 (b) 11.5+2.9 11 8+3.0 10.6+2.7 9.3+2.3 12.5+3.1 11.1+2 8
13.3+3.3 12;6+3.2 12.9+3.2 11.0+2.8 (a) 12 '+3.1 13 '+3 '
11.1+2.8 13.4+3.4 12.1+3.1 15.5+3.9 14.3+3.6 11.0+2.8 24 F 1+6.1 11.5+2.9 7.5+1.9 11.0+2.8 11.7+3.0 10.3+2.6 13.6+3.4 12.7+3.2 14.7+3.7 11.7+2.9 13.4+3.4 13.1+3.3 15 F 8+4.0 13.4+3.4 12.2+3.1 12.1+3.0 11.8+3.0 13.9+3.5 10.6+2.7 8.3+2.1 12.0+3.0 12.3+3.1 10.6+2.7
- 8.3+2.1 12.7+3.2 (a) 10.9+2.8 12.1+3.0 12.5+3.1 10.1+2.6 9.6+2.4 12.0+3.0 11.6+2.9 10.7+2.7 17.8t4.5 15.2+3.8 16.0+4.0 15.6+3.9 14.4+3 6
24.8+6.3.
13.8+3.5 11.9+3.0 12.3+3.1 13.4+3.4 12 7+3.3 30.8+7.7 13.2+3.3 15.6+3.9 14.9+3.7 13.9+3-5 17 4+4.4 15.0+3.8 16.4+4.1 15.2+3.8 (b) 14.4+3.6 15.1+3.8 12.5+3.2 (b) 13.1+3.3 14.7+3.7 12.8+3.2 10.8+2 7
14 F 0+3.5 12.9+3 3
15.8+4.0 15.0+F 8 15.4+3.9 12 2+3.1 13.7+3.4 14.8+3.7 (a) 12.7+3 2
EXTERNAL PENETRATING RADIATION THERMOLUMINESCENT DOSIMETRY R. E.
G INN A NUCLEAR POWER STATION AVE mRem/QTR 24 22 20 18 16 14 12 10 8
2 4
6 8
10 12 14 16 18 20 22242628303234363840 TLD LOCATION NUMBER
~ 1990 LOCATION AE7 OMITTED
ti I~
4<
t1vJ
4.0 LAND USE CENSUS A land use census is done each year to determine any major changes in the use of the land within 5 miles of the plant.
There were no major changes.
The land use remains mainly agricultural in nature.
There were several private homes constructed, but no new housing developments or large business construction projects.
The three dairy operations nearest the plant continued in operation with an average of 40 to 70 milking cows.
There are no goats used for milk on a regular basis within the 5 mile radius.
Beef cattle are still raised on 3 farms within 2 miles of the plant as in the past.
A copy of the Land Use Census is attached.
58
eo
'THE E5
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TABLE I CE-9:3 ESE SSE SSW WSW Distance to Nearest Residence I I'ld~
q3o~
hAAW~
gQO~
iso~~
( DO
/b 0Q~
i$ 6D~
I Distance to Nearest Garde
/200 qoo~
CoO~
9S6 ~~~
( dO+~
'75 0 ~W~
iC 60 ~~
iydd~~
Distance to Milk.
Producing mals PgdO~
5'/QD~
Changes from previous year:
Milk animal locations:
Ad 45LJ pnlll(
Gcggns Land Use Census Completed By:
D~g~; 7~II90 7~
VO 60
'1 fJ
5.0 EXTERNAL INFLUENCES During
- 1990, there were no external influences such as atmospheric weapons testing or accidents at other nuclear facilities which caused an influence on the data reported.
The annual trending graphs for air and water indicate a
level effect in the measured activity.
6.0 EPA INTERLABORATORY COMPARISON STUDY An indication of the laboratory's ability to analyze samples and achieve results consistent with other laboratories is the aim of the EPA Interlaboratory Comparison.
Selected unknowns are received and analyzed by our procedures and the results are sent to the EPA Environmental Monitoring Systems Laboratory.
A report is returned from them indicating the concentrations with which the samples were spiked and how we compared to other laboratories analyzing the same samples.
Table 6-1 is a tabulation of the samples analyzed during 1990.
61
TABLE 6-1 EPA INTERLABORATORY COMPARISON PROGRAM 1990 Alpha/Beta in Water (Results in pCi/1)
Date 1/26/90 5/1/90 9/1/90 Sample A~nal sis Alpha Beta Alpha*
Beta Alpha Beta Experimental Data 7
6 5
9 9
9 5
6 12 9
13 16 8
17 14 14 9 ll EPA Value
+la 12+5 12+5 22+6 15+5 10+5 10+5 Gamma in Water (Results in pCi/1) 2/9/90 6/8/90 10/5/90 Co-60 Zn-65 Ru-106 Cs-134 Cs-137 Ba-133 Co-60 Zn-65 Ru-106 Ba-133 Cs-134 Cs-137 Co-60 Zn-65 Ru-106 Ba-133 Cs-134 Cs-137 15 13 16 136 134 136 129 122 123 15 14 15 21 19 21 77 76 75 31 31 30 168 159 150 185 222 224 110 106 102 26 25 28 35 30 28 28 24 24 124 123 130 147 175 169 123 117 130 ll 12 12 15 16 19 15+ 5 139+14 139+14'8+
5 18+ 5 74+ 7 24+ 5 148+15 210+21 99+10 24+ 5 25+ 5 20+ 5 115+12 151+15 110+11 12+ 5 12+ 5 Iodine-131 in Water (Results in pCi/1) 8/10/90 I-131 42 43 40 39+6 i
62
TAKE 6-1 (Qcnt'd)
CCKKKSCN HKCBRf 1990 AirFilters 3/30/90
($ssults in @CD/filter) 8/33/90 8
8 7
27 27 27 16 17 17 35 35 15 51 52 54 26 29 28 E% Ualm
+10 5+5 31+5 10%5 l(H6 62+5 2~
MQk (Results in~)
4/27/90 9/28/90 I -131
~137 K-40 I -131 CS-137 K-40 98 95 98 24 25 28 1460 3340 1470 67 63 67 32 28 24 3800 1810 1770 99+10 2W 5 355OH30 58+ 6 2(H 5 1700H35 Tritium in Mter (Results in~)
2/23/90 "3
6/22/90 H-3 10/20/90 H-3 6250 5800 5600 2880 3704 3380 6940 6520 6340 498(H500 293%.360 72'-720 Average of results rex:eted exceecHnp + 2 sigm.
\\
3he rental effiaiemy'se5 far alpha satples cmhxininy soli'ar ahearptim of~
activity was ~axently incarrect.
A mv calibrate curve far effiahxxy vs. ag of soliih ms @merited, hut the changes were rat signifiamt. '
1
EPA INTERLABORATORYCOMPARISON P ROGRAM 1990 RESULTS NORMALIZED DEVIATIONS FROM EPA KNOWN 5
UCL
. UWL 0
LWL LCL
~ ALPHA ANALYSES ~ BETA ANALYSES ~ TRITIUM ANALYSES LABORATORY ACCURACY EPA REPORT COLUMN 9
l~
0
EPA INTERLABORATORYCOMPARISON PROGRAM 1990 ISOTOPIC ANALYSIS RESULTS NORMALIZED DEVIATIONS FROM EPA KNOWN 3
UGL UWL X
LWL LGL Go-60 Gs "137
+
Zn-65 0
Ba-133 Ru-106 I-131
~ Gs-134 z
K-40 LABORATORY AGGURAGY EPA REPORT COLUMN S
t