ML18086B404
| ML18086B404 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/31/1982 |
| From: | RADIATION MANAGEMENT CORP. (RMC) |
| To: | |
| Shared Package | |
| ML18086B403 | List: |
| References | |
| RMC-TR-82-01, RMC-TR-82-01-DRFT, RMC-TR-82-1, RMC-TR-82-1-DRFT, NUDOCS 8204080475 | |
| Download: ML18086B404 (113) | |
Text
SUBJECT:
1981 ANNUAL RADIOLOGICAL REPORT.
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50-272/311 SALEM NUCLEAR GENERATING STATIONS UNITS 1&2/
PUBLIC SERVICE ELECTRIC AND GAS COMPANY D -
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RMC-TR-82-01
- 1981 INTERIM ~EPORT PENDING THE COMPILATION OF ADDITIONAL RESULTS ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM January 1 to December 31, 1981 Prepared for Public Service Electric and Gas Company by Radiation Management Corporation March 1982
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TABLE OF CONTENTS PAGE
SUMMARY
1 INTRODUCTION 2
THE PROGRAM 3
Objectives 3
Sample Collection 3
Data Interpretation 5
Program Changes 6
RESULTS AND DISCUSSION 7
Airborne 7
Precipitation 10 Direct 10 Water 11 Aquatic 15 Ingestion 16 Fodder Crops 19 CONCLUSIONS 20 REFERENCES 21 APPENDIX A - PROGRAM
SUMMARY
23 APPENDIX B - SAMPLE DESIGNATION r~ LOCATIONS 31 APPENDIX C - 1981 DATA TABLES 39 APPENDIX D - SYNOPSIS OF ANALYTICAL PROCEDURES
&7 APPENDIX E -
SUMMARY
OF HffERLABORATORY COMPARISONS 107 APPENDIX F - SYNOPSIS OF DAIRY AND VEGETABLE GARDEN SURVEY i15 i
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I LIST OF FIGURES NUMBER PAGE
. 1.
Comparison of Average Concentrations of Beta Emitters in Precipitation and in Air Particulates, 1973 through 1981. ~~..
8
- 2.
Average Ambient Radiation Levels from Monthly TLDs in
.the Vicinity of Artificial Island, 1973 through 1981~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~..
9
- 3.
Average Concentrations of Tritium in the Delaware River in the Vicinity of Artificial Island, 1973 through 1981 ~~~..
12
- 4.
- Average Concentrations of Beta Emitters and Potass.ium-40 in the Delaware River in the Vicinity of Artificial Island, 1973 through 1981. ~ ~ ~ ~ ~ ~. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~.~ ~ ~. ~ ~ ~..
13
- s.
Average Concentrations of Iodine-131 in Milk in the Vicinity of Artificial Island, May 1974 through December 1981. ~~~~-~..
17 ii
SUMMARY
During the period January 1 to December 31, 1981, Radiation Management Corporation *
(RMC) participated in the Operational Radi_ological Environmental Mani taring Program conducted by Public Se-rvice Electric and Gas Company (PSE&G) at Artificial. Island,.
New Jersey. Salem Nuclear Generating Station (SNGS) Unit #1 became critical on Decerrber 11, 1976, thereby initiating the op~rational phase of the Radiological Environmental Jtmitoring Program (REMP). This program was designed to identify and
- quantify concentrations of radioactivity in various environmental media and to quan-tify ambient radiation levels in the environs of Artificial -Island. Unit #2 achieved initial criticality on August 2, 1980.
- During the operational phase, the program will monitor the operations of SNGS Units #1 and #2 and will fulfill the requirements of the SNGS Environmental Technical Specifications. Thfs *rep9r-t.pr.eseJits the re-sults of thermoluminescent dosimetry and radiochemical analyses of environmental samples collected during 1981.
A total of 2299 analyses were performed on 1422 environmental samples during the period covered by this report. Samples of air particulates, air iodine, surface, ground and drinking water, benthos, sediment, milk, fish, crabs, vegetables, game, fodder crops, and precipitation were collected. Thermoluminescent dosimeters were used to measure ambient radiation levels.
A variety of radionuclides, both naturally occurring and ~an-made, were found in the above samples. These nuclides were detected at levels similar to those found during the preoperational phase of this 'program. In general, results at indicator stations compared favorably to control stations. It is concluded that the radiological charac-teristics of the environment around Artificial Island during 1981 were not affected by the operation of SNGS Units #1 and #2.
1
I NT RO DU CTI ON Radiation Management Corporation has participated in the Artificial Island Radio-ological Env_ironmental Monitoring Program since January 1973.
RMC has previously reported results from the preoperational phase of the REMP for 1973( 1), 19.74(2),
1975(3) and 1976(4).
On December.11, 1976, SNGS Unit #1 first achieved criticalitv thereby initiating the operational phase.of the REMP.
RMC lias also reported re-sul ts from the initial operating p'eriod between December l1 and December 31, 1976(5),
January 1. and December 31, 1977 (6), January 1 and December 31, 197a (7), January 1 and December 31, 1979 (8) and Janu*ary 1 and December.31, 1980 (9). This report summarizes the operational period between January 1 and December 31, 1981.
Artificial Island is the site of two nuclear.*power reactor which are part of the Salem Nuclear Generating* Station. Units #1 and #2 are pressurized water reactors (PWR), 1090 MWe and 1115 MWe respectively. Both are presently opera..
tional.
Artificial Island is actually a man-made peninsula in the Delaware River, created by the deposition of dredging spoils. It is located in Lower Alloways Township, Salem County, New Jersey. The environment around Artificial Island is character-ized*~tnainly by the Delaware River and Bay, extensive tidal marshes, and grass lands.
These land*types make up approximately 85% of the land *area within five miles of the site. Most of the. remaining land is used for agri cultural production (lo).
More specific infonnation on the demography~ hydrology, riaeteorology, and land use characteristics of the local area may be found in the Environmental Report (10),
Environmental Statement (ll), and the Final Safety Analyses Report (Units 1 and 2 for SNGS ( 12).
2
THE PROGRAM In the operational phase of the REMP, the program was conducted in accordance with Section*3.2 of the SNGS Environmental Technical Specifications (ETS).: Radioanalytical data were collected and compared with results from the preoperational phase. Differences between these periods were examined statistically, where applicable, to detennine whether any station operational effects existed.
Objectives
- The objectives of the operational radiological environmental program are:*
- 1. *To fulfill the obligations of the Radiological Surveillance-Environmental sections of the Environmental Technical Specifications for SNGSe
- 2.
To detennine whether any significant increase occurs in the concentration of radionuclides in critical pathways.
- 3.
To detenni ne if SNGS has. caused an increase in the radioactive inventory of long.1 i ved radi onucl ides.
- 4.
To detect any change in anbient gal'Tllla radiation levels.
- 5.
To verify that SNGS operations have no detrimental effects on the heal th and safety of the public or on the environment.
This report as required by Section 5.6 of the Salem ETS (13) summarizes the findings of the 1981 REMP.
Results o*f the four year preoperational program have been summarized for purposes of comparison with subsequent operational reports. (4)
Sample Collection In order to meet the stated objectives, an appropriate operational REMP was developed by RMC in cooperation with Public Service Electric and Gas Company. Samples of various media were selected to obtain data for the evaluation of the radiation dose to man and other organisms. The selection of sample types was based on: (1) established critical pathways for the transfer of radionuclides through the environment to man, and (2) experience gained during the pre6perational phase. Sampling locations were determined from site meteorology, Delaware estuarine hydrology, local demography, and land uses.
Sampling locations were divided into two classes--indicator and control. Indicator stations are those which are expected to marii*fest station effects, if any exist; con-trol samples are collected at locations which are believed to be unaffected by station operations.* Fluctuations in the levels of radionuclides and direct radiation at indi-cator stations are evaluated with respect to analogous fluctuations at control stations, which are unaffected by station operation. Indicator and control station data are also evaluated relative to preoperational data. The REMP for the Artificial Island Site in-cludes additional samples and analyses not specifically required by the Salem ETS.
The
-summary tables in this report include these additional samples and analyses.
3
Air particulates were collected on Schleicher-Schuell No. 25 glass fiber filters with low-volume afr samplers. Iodine was collected from air by absorption on TEDA charcoal cartridges connected in series behind the air particulate filters. Air sample volumes were measured with calibrated dry-gas meters correctedto standard tent>erature and pressure.
-Precipitation was collected on a 95-square*inch rain gauge. Samples were collected monthly and transferred to new polyethylene bottles. The rain gauge was rinsed at collection with distilled water to include residual particulates in *the precipita-tion samples. Results of subsequent analyses were corrected for the increase in volume. Tritium results were also corrected for the tritium content of the dis-tilled water.
Ant>ient radiation levels in the environs were neasured with energy-compensated caso4 (Tm) thermal uminescen~ dosimeters. (TLDs). Packets containing four TLDs each were placed on and a*round the Artificial Island Site at various distances and were exposed*on a monthly, quarterly and semi-annual basis.
Monthly well and potable water samples were taken in new two-gallon polyethylene bottles. Separate raw and treated *potable water samples were composited daily by personnel of the Salem Water Company.
Surface water samples were collected by lcthyological Associated and shipped to RMC for analysis in new polyethylene bottles. *sample containers were rinsed twice with the sample medium prior to collection. Edible fish and crabs were taken by net, sealed in-a bag or jar and shipped frozen. Benthos and sedinent were taken with a bottom grab sampler.
Milk samples were taken in new polyethylene bottles and shipped fresh.
Food products~ fodder crops, game and bovine thyroid samples were taken and sealed in plastic bags or jars. Perishable samples were frozen at the time of sampling without any preservatives.
Appendix A describes and summarizes, in the format of Table 5.6-1 of the Salem ETS, the entire operational program as perforned in 1981. Appendix B describes the RMC coding system, which specifies sample type and relative locatfons at a glance. Also in Appendix B, Table B-1 gives the pertinent information on indivi-dual sampling locations, while maps B-1 and B-2 show t~e sampling locations.
4
~--
Data Interpretation Radiation Management Corporation has an extensive quality assurance program designed to maximize confidence in the analytical procedures used. lhe analytical methods utilized tn this program are surrmarized in Appendix* D *.
Approximately 20% of the total analytical.effort is spent on quality control, including process quality control,. instrument quality control, inter-1 aboratory cross-check analyses, :and comprehensive data' review. Results of the EPA inter-1 aboratory comparison program appear in Appendix*E. A full discusston of these results can be found in the "Quality Control Data 1981 - Annual Report" ( 14).
Several factors are important in the interpretation of the data. These factors are discussed here to avoid repetition in sections that follow.
Grab sampling is* a useful and acceptable procedure for taking environmental sample~ of a medium in which the concentration of radionuclides is expected to vary slowly with time or where intermittent sampling is deemed sufficient to establish the radiological characteristics of.the mediume This method, however, is only representative of the sampled medium for that specific location and instant of time.
As a result, variation in the radionuclide concentrations of the samples will *normally occur. Since these variations will tend to counterbalance one another! the extraction of averages based upon repetitive grab samples is valid.
Within the data tables (Appendix C) an approximate 95% (+/-2 sigma) confidence interval is supplied for those data points above the lower limit of*detection (LLD).
An exception to this is Sr-89 and -90 detection capabilities which are based on the mi_nimum detectable limit (MDL). These intervals represent the range of values into which 95% of repeated analyses of the same sample should fall.
Results for each type of sample were grouped according to the analysis per-formed.
Means and standard deviations of these results were calculated when applicable. The calculated standard deviations of grouped data found in Appendix C represent sample and not analytical variability. When a group of data was composed of mainly (>50%) LLD values, averages were not calculated.
It is characteristic of environmental monitoring data that many results occur at or below the.lower limit of detections For reporting and calculation of averages, any result occurring at or below the lower limit of detection is considered to be at that limit.
As a result, averages obtained using this method are biased high.
5
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Program Changes Beginning on October 1, 1981, modifications were made to the portion of the Radio-logical Environmental Monitoring Program for the Salem Nuclear Generatfng Station performed by RMC.
The following is a list of analyses no longer analyzed bY RMC.
It should be noted that all analyses not performed by RMC are being analyzed by the Research Corp., a wholly owned subsidiary-.of PSE&G.
- 1. Air Particulates - all analyses (gross alpha, gross beta, gamma emitters, Sr-89 and -90) have been discontinued by RMC.
- 2. Soil - analyses for Sr-90 and gamma emitters have been discontinued by RMC.
- 3.
Well Water - tritium and Sr-89 and -90 analyses have been discontinued by RMC.
- 4. Rain Water - tritium analyses have been discontinued by RMC.
In order to insure quality of the results obtained by their laboratory, PSE&G has instituted a quality assurance program in which a portion of those samples analyzed by PSE&G will also be analyzed by RMC.
This program is discussed below.
- 1. Milk - Station MLK-3G1 will continue to be analyzed for Sr-89 and -90 on a monthly basis by RMC.
Each month one additional station will be chosen by Public Service Electric & Gas Company to receive Sr-89 and -90 analyses.
- 2. Surface Water - Station SWA-12C1 will continue to be analyzed for tritium on a monthly basis, and for Sr-89 and -90 on a quarterly composite basis by RMC.
In addition, one other station will be chosen by PSEf"G to receive monthly tritium analyses and quarterly composite Sr-89 and -90 analyses.
- 3. Potable Water - Monthly tritium analyses and quarterly composite analyses for Sr-89 and -90 will be continued on station P~H-2F3 by RMC.
6
RESULTS AND DISCUSSION The analytical results of the 1981 REMP samples are divided into categories based on exposure pathways: airborne, direct, water, aquatic and ingestion,. The anal-ytical results for the 1981 REMP samples are surmnarized in Appendix*A.
The data for individual samples are presented in Appendix c.
Airborne Air Particulates (Tables C-1, C-2, C-3, C-4)
Air particulate samples were analyzed for alpha, beta, ganma emitters, and Sr-89 and -90. The weekly air particulate samples were analyzed for gross beta* activity at eight stations and for gross alpha activity at two stations. Quarterly composites were prepared using the weekly samples from each station* and analyzed for Sr-39, Sr-90 and specific garmia emitters.
W~ekly gross beta analyses.showed corycentrat~ons raryging from 0~02j to ~.471 pCi/m3 with the average for the eight sampling stations being 0.141 pCi/m
- Figure 1 shows the relation between gross beta activity in air and precipitation for the preoperational and the operational periods, showing both seasonal and weapons-testing fluctuations.
Of the 78 weekly air particulate samples (two stations) analyzed for gross alpha emitters, 66 were *above detectable c~ncentrations. The range o~ gross alpha acti-vity was from*o.0006 to 0.0027 pCi/m and averaged 0.0013 pCi/m
- Results of gamma spectrometry showed detectable levels of several radionuclides, both naturally occurring and man-made (Be*7, K-40, Mn-54, Nb-95, Zr-95, Ru-103, Ru-106, Sb-125, Cs-137, Ce-141 and Ce-144). The level of man-made nuclides de-tected during the first and second quart~rs can be attributed primarily to fallout from the October 16, 1980 atmospheric nuclear weapons test. Concentrations of these nuclides decreased significantly during the third quarter. The presence of Be-7 throughout the year can -~e attributed to cosmic ray activity. The highest activity detected was 0.12 pCi/m of Nb-95 in the second quarter composite for station APT-5Dl.
The Sr-89 analyses performed on the quarterly composites showed 23 out 3f 24 samples with detectable activity. 3These ranged between 0.0007 and*o.0093 p*ci/m with the average being 0.0052 pCi/m
- The positive Sr-89 results can also be attributed to the fallout from the atmospheri§ nuclear weapons test. Sr-90 concen~rations ranged between 0.0003 and 0.0022 pCi/m with the average being 0.0009 pCi/m
- Air Ibdine (Table C-5)
Iodine cartridges were connected in series behind each of the air particulate filters for absorption of air iodine. The absorption inedi a used in these cartridges was "TEDA" impregnated cha3coal. All results for I-131 were below the LLD and ranged from <0.0054 to <0.026 pCi/m
- 7
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PreCipitation (Tables C-7, C-8)
Although not specifically required by the Salem ETS, precipitation wa~ sant>led con-tinuously and collected monthly at tbe Sa*lem substation sarr~:>>l ing location. The precipitation was analyzed for tritium, gross alpha and gross beta emitters on a roonthly basis. Tritium.activity was detected in three sarrt>les and ranged from 86 to 124 pCi/l. The LLDs ranged from <87 to <124 pCi/l. Of the twelve roonthly rain water.samples analyzed for gross alpha emitters, three showed detectable*concentra-tions *. *The range of gross alpha activity was from* 1.2 to 2.3 pCi/l :with the average being 1.6 pCi/l. The LLDs ranged from <0.6 to <1.2 pCi/l. Gross beta emitter con-centrations* were detected in all samples and ranged from 4.7 to 70 pCi/l with an average of 30 pCi/l.
Quarterly composites of precipitation were analyzed for radiostrontium and gamma e~itters. Sr-89 analyses showed positive results for the first three quarters of 1981. The concentrations ranged from*o.6 to 7.5 pCi/l, and averaged*3.8 pCi/l.
Sr-90 concentrations ranged between*o.a and* 1.4 pCi/l with the average being 1.1 pCi/l. Results of gamna spectrometry showed detectable levels of several radio-nuclides. All of the detected nuclides are man-made and can be attributed to fallout from the October 16, 1980 atmos"heric nuclear weapons test. By the fourth quarter, activities had returned to LLD levels.
Direct (Tables C-9, C-10, C-11)
Direct radiation measurements were made at 41 different locations, 24 monthly and quarterly locations and 17 semi-annual locations using CaS04 (Tm) therrooluminescent dosimeters. During 1981, 288 monthly, 96 quarterly and 34 semi-annual TLD packets were collected. Each packet included four dosimeters for a total of 1672 analyses.
These analyses resulted in an average dose rate of 5.47 mrads/standard roonth for roonthly TLDs,*5.37 mrads/standard roonth for quarterly TLDs and 5.54 mrads/standard TOOnth for semi-annual TLDs. All TLD results presented in this report have been
- nonnal ized to a standard roonth (30.4 days) to eliminate the apparent differences caused by variations in exposure periods.
When the roonthlY. data is plotted as in Figure 2, a slight peak is observed after June 1979. This peak is attributed to the elevated readings from two on-site TLD stations. Since the two stations, lOSl and llSl, are on-site they do not represent any environmental dose to the public.
A comparison of the direct radiation data*for 1981 shows a similarity bet\\\\Een the average roonthly dose for both indicator stations (5.40 mrads/std. month) and con-trol stations (5.84 mrads/std. roonth).
10
In order to better evaluate the variation between TLD results, a statistical model which is capable of separating a contribution by SNGS from the background component has been developed. The statistical method utilized is a linear regression analysis which involves determining the functions which best describe the background component by the least squares method. Six models were originally tested and are described in a separate publication (14). The equation which describes the model selected is:
where:
f Yjmi
- x. J CON;m COT;
= f (X. (CON.
I COT.) (COT. I COT )
J 1m 1
1 p
= denotes a function of
= predicted value for station j, month m, and year i
= preoperational mean for station j
= average of the control stations for month m and year i
= average of the control station for year i (a 11p 11 in pl ace of "i 11 represents the preoperational period)
A computer program was developed for multiple regression analysis. The least squares fit (LSF) line based on all 1931 data was determined along with the statistics for this line. The data for 1981 was tested against predicted values and prediction limits determined from the model period line. Differences between predicted and observed values are termed residuals. Residuals outside the pre-diction limits of the predicted value are identified as outliers. For 1981, 22 outliers were predicted from a possible 288.
Four outliers at station 1051 and sixteen outliers at station 1151 can be attri-buted to the refueling of Unit #1. These stations are located in the vicinity of the Refueling Water Storage Tank. Since these locations are on-site they do not represent a dose to the public.
No TLDs located beyond the plant boundary indicated any additional dose from SNGS operation.
- The remaining two outliers at stations 7Sl and 1401 can be attributed to statis-tical fluctuations.
Water Surface Water (Tables C-12, C-13, C-14, C-15, C-16)
Monthly surface water samples were taken at five locations in the Delaware estuary.
One is downstream* from the outfall area, one is in the outfall area, and another is directly west of the outfall area at ~he mouth of the Appoquinimink River.
Two other stations are located upstream==one station is in the river and the other is in the Chesapeake and Del aware Canal. *The station located at the mouth of the
- Appoquinimink River serves as the operational control. Surface water samples were analyzed for tritium, gross alpha emitters, gross beta emitters, strontium-89 and
-90, and gamma emitters.
11
FIGURE 3 AVERAGE CONCENTRATIONS OF TRITIUM IN THE DELAWARE RIVER IN THE VICINITY OF ARTIFICIAL ISLAND, 1973 THROUGH 1981 10,ooor-------------.... ---------------------------------------------------------------------------""1'1"'-----------------.
~ a.
1000 lOC 19.'ZL 19--2.'l.
19~
19...2.cL
~
't UIO...
c...
.... c
~
19--2.2._
19_J_L_
19-2L.
19..LL-
w FIGURE 4 AVERAr.E CONCENTRATIONS OF BETA EMITTERS All! POTASSJUM-40 IN THE DELAWARE RIVER IN THE VICllllTY OF ARTIFICIAL ISLAND, 1973 THROUr.H 1981 lOIJOr'------------~~----------------------------------------------------~-----------------P.-----------------.
gross beta
- - - - - O Potasstum-40 1
1, 19..2.L 19--2.t_
19-2.i:
19~
-u
- ~
c VI VI
,rt I
19...2.'.L
- I
'1 I
11 '
19.2£.
I' I
- ~
I I
I I
I I a 19....1.L 11 l'J u.......
1:
uo
";ii~
~gi
... c c
19..L£...
19...d'L.-
19 __
Analysis of surface water for tritium yielded an average concentration of 160 pCi/l and ranged from 58 to 412 pCi/J. These levels are similar to those measured in the preoperational program as shown in Figure 3. A gradual decrease in tritium activity from 1973 to.. '1981 can be attributed to general. reduction in the worl d~i de tritium inventory* wi"th *the cessation of routine atmospheric weapons testing.
Gross alpha concentrations were generally below LLD, which ranged from <0.2 to <1.3 pCi/l.
- Eleven of. the 55 samples analyzed showed detectable gross alpha activity.
The average (0.3 pCi/l) was within the same range as the LLDs for the year. Gross alpha activity may be expected in suspended solids from natur~lly occurring radio-nuclides especially during periods of high surface runoff *
. Gross beta concentrations ranged from 10 to 129 pCi /1 and averaged 51 pCi /1
- Nearly al 1 of the beta activity *was contributed by K-40, a natural component of salt and brackish waters, as illustrated in Figure 4, which compares gross beta and K-40 concentrations in the Delaware River.
Due to the flow rate varia-tions and the tidal nature of the estuarine environment, large variations in the gross beta concentrations were observed throughout the year *. Much of this varia-tion can be attributed to the tidal stage _at the time of sarrpl ing.
Levels of Sr-89 were below MDL (<0.6 to <2.3 pCi/l) in thirteen of seventeen sam-ples. Concentrations of detected Sr-89 ranged from*o.5 to*t.5 pCi/1, and averaged 0.8 pCi/l. Levels of detectable Sr-90 ranged from 0.4 to 1.3 pCi/l in four of the seventeen samples. The MDL values for the remaining samples ranged from <0.3 to
<0.9 pCi/l. The maximum level of Sr-90 detected in the preoperational program was
- 1.6 pCi/l (4).
Garmia spectrometric analysis of surface water samples showed detectable concen-trations of K-40. in 53 of 55 samples. The average K-40 concentration was 57 pCi/l and ranged from 20 to 120 pCi/l. K-40 is a naturally occurring radionu-clide which is expected to be found in salt and brackish waters.
Well Water (Tables C-17, C-18) tibnthly well water samples were taken from two indicator wells and one control well. All well water samples were analyzed for tritium, gross alpha and gross beta activity, and K-40 (by atomic absorption). Quarterly composites were analyzed for gamma emitters, and Sr-89 and Sr-90.
Detectable concentrations of tritium were observed in two of the twenty-seven samples with. levels of 106 and 268 pCi/l. The LLD~ ranged from <88 pCi/l to
<174 pCi/l. Gross alpha concentrations were generally below LLD which ranged from <0.8 to <3.6 pCi/l. Two of the 36 samples analyzed showed detectable gross alpha activity (1.7 and 2.2 pCi/l). The concentrations of gross beta emitters averaged 11 pCi/l and ranged from 2.6 to 16 pCi/1. The potassium--40 activity as determined by.atomic absorption averaged 8.5 pCi/l. This indicates that the gross beta activity observed in these samples is primarily the result of naturally occurring K-40, a beta emitter.
14
The only nuclide detected by gamna spectrometry was K-40 (19' to 22 pCi /1) in three of twelve samples. *All results for Sr-89 were below the MDL of <0.6 to <2.2 pCi/l. Sr-90 was.found in one sample with a concentration of*o.4 pCi/1. The range of MDLs for Sr-90 was <0.4 to <1.1 pCi/l.
Po~able Water (Tables C-19, C-20)
Both raw and treated water samples were taken.at* the. Salem Water Co111>any, the only drinking water processing.plant* in the vicinity of Artificial Island* The raw water source for this pl ant is Laurel* Lake (-a tributary of the Del aware River) and several adjacent" wells. Potable water samples were analyzed monthly for tritium, gross alpha and gross beta activity, and K-40 (by atomic absorption);
Sr-89 and -90, and gamma emitters were analyzed on a quarterly basis.
The concentration of tritium averaged 104 pCi/l for all analyses, with no signi-ficant differences between* the raw and treated samples~ Detectable gross alpha activity was observed in 15 of 24 samples ranging between*o.5 pCi/l and 1.8 pCi/l with an average of* 1.0 pCi/l *.
- Gross beta and K-40 concentrations were loYler than in the saline surface water,- as expected for fresh water, with K-40 *generally contributing less th*an 50% of the beta activity. The average gross beta concen-trations were*3.9 pCi/l (raw) and 2.7 pCi/l (treated). The average K-40 results were 1.4 pCi/l (raw) and 1.5 pCi/l (treated).
Quarterly composites of raw and treated samples were analyzed for ganrna emitters and Sr-$9 and*-9o. *No nuclides were detected by gamma spectrometry in any of the samples. Of the seven samples analyzed for Sr-89, two showed detectable concen-trations (0.5 and*o.7-pCi/l).-
The MDL range for Sr-89 was <0.7 to <0.9 pCi/l.
Sr-90 was observed in four*of the seven samples with concentrations ranging from 0.3 to 1.1 pCi/l, and the average being 0.7 pCi/l.
89uati c Benthos (Table C-21)
Benthic organisms were collected at four locations and *analyzed for Sr-89 and Sr-90. Levels of Sr-89 were below MDL (<0.2 to <169 pCi/g-dry) for all eight analyses. *Tne wi'de fluctuations in MDL values were* due to inconsistencies in sample size (0.01 to 9 grams dry). Three of eight samples showed detectable Sr-90 concentration averaging 1.2 pCi/g-dry. The detectable activity of these samples is within the.MDL range (<0.8 to <83 pCi/g-dry) of the other analyses.
The MDL for radiostrontium as required by the Environmental Tethnical Specifi-cations for benthic organisms was not met in all of the samples due to the impracticality of obtaining a sufficiently large sample size of benthic or-ganisms.
Sediment (Table C-22).-.
Sediment was collected semiannually at four locations and analyzed for Sr-90 and ganrna emitters..
Levels of Sr-90 were below MDL (<0.04 to <0.1 pCi/g-dry) in seven of the eight samples analyzed. The single concentration (0.04 pCi/g-dry) was within the MDL range.
15
Results of gamma spectromatry showed de'tecta~le levels of a variety of naturally occurring radionucl ides as well as man-made radionucl ides.
Various fallout nu-cl ides were observed intennittently in the sedimant samples.
Ingestion
- Milk (Tables C-23, C-24)
Milk samples were taken twice*a month from six local fanns during 1981 and analyzed for I-131; gamma emitters, Sr-89 and Sr-90 were analyzed monthly.
1-131 was not observed in any milk samples duri*ng 1981.
Figure 5 shows the average 1-131 concen-trations in milk.samples resulting from atnDspheric nuclear weapons tests by the Peoples Republic of China (June 1974, March 1978, and October 1980) and the Three Mile Island incident in 1979.
Gamma spectrometry showed detectable concentrations of. K-40 in all samples and Cs-137*in 36 of the 72 samples analyzed. The annual average concentrations were 1500 pCi/l for K-40 and 2.9 pCi/1 for Cs-137. These.levels were not significantly different between control and indicator stations.
Strontium-89 was detected in twelve of the sixty samples analyzed with results ranging between".1.8.pCi/l and 8.5 pCi/l. The range of MDL values for Sr-89 was <1.8 pCi/l to <37 pCi/L
- The wide range of values for the MDL was due to low chemical yields and long decay periods in some of the analyses. All of the positive results detected were within the MDL range.
The concentration of Sr-90 was positive in 53 of. the 60 samples analyzed and averaged* 3.6 pCi/l.
The MDL range tf:as* <0~7 pCi/l to <8.9 pCi/l.
- Sr-90 concentrations were similar at i ndi ca tor and contra 1 stations, i ndi ca ting no ct:Jntri bution from SNGS.
Due to the 28 year half-life and biological assimilation, Sr-90 can be expected to remain long after routine atmospheric.testing has ceased. All Sr-89 and
-90 analyses have been chemical yield verified by atomic absorption spectro-scopy.
Fi sh (Tab 1 es C-26, C-27)
- Edible fish samples (American Eel, White Perch, Channel Catfish, Spot, etc.)
were collected at three locations and analyzed for tritium and gamma emitters.
Fish bones were analyzed for Sr-89 and Sr-90.
Tri ti um analyses were performed on both *aqueous and organic fractions of the flesh portions of these samples.
The average concentration of tritium was 82.5 pCi/l,..,for*the aqueous fraction and 200 pCi/l for the organic fraction.
Of the six samples analyzed, all results are essentially the same as those found in surface water for the same period.
Garmna spectrometry of these samples showed K-40 in all six samples analyzed at an average concentration of 3.6 pCi/g-wet.with a range of 2.9-4.6 pCi/g-wet.
All six bone samples analyzed for Sr-.89 were below the MDL (<0.06 to <0.2 pCi/g-dry).
Two of the six samples analyzed for Sr-90 had detectable concentrations of 0.04-0.05 pCi/g-dry.
The maximum level *detected during the preope*rational period was 0.94 pCi/g-dry.
16
-1**
~=
ii~
atmospheric weapons test June 17, 1974 atmospheric weapons test Sept. 26, 1976 abnospherfc weapons test Sept. 17, 1977 LI pCt/1 abnospherf c weapons test March 14, 1978 Three Mile Island March 28, 1979 test e
0 e
~
8
<'..)
< n -
- 5>
-i<
-c..,
o~
"TIC'l
-iO
- ~
~:!i j!!:~
-i
~o r- :z
>V>..,
- z -
co c:
~o..,
-cg "'
-:z
~-...
-i-
- i:,.._
gz
- > :J:
- i:-
r-S!""
CD -i
,..,., -"' s
-I
Blue Crab (Tables C-28, C-29)
Blue crab samples were collected at two locations and the flesh was analyzed for tritium in the aqueous fraction,.garmta emitters and Sr-89 and -90. The shells were analyzed for Sr-89 and Sr-90.
One sample from station llAl showed detectable concentrations of tritium. The result (123+/-68 pCi /l) was comparable to tritium values found in surface water for this same period~
K-40 was the only ganrna emitter detected with an average of 2.1 pCi/g-wet.
Detectable concentrations of Sr-89 were found in two of the four shell samples, and averaged 1.3 pCi/g-dry. The MDL range for Sr-89 in shells was <0.03 to <0.1 pCi/g-dry. All results for Sr-89 in flesh were below MDL with a range of*o.01 to 0.08 pCi/g-dry.
Three of four samples showed detectable activity with concentrations of 0.007 to*o.07 pCi/g-wet of Sr-90 in flesh. The MDL value was.<0.007 pCi/g-wet. All of the shells had detectable activity of Sr-90. The range of activities was 0.24 to 1.0 pCi/g-dry with no difference observed between indicator and control stations.
Food Products (Table C-30)
A wide variety of other human food products was sampled and analyzed for gallFla emitters and Sr-89 and -90. These included cucumbers, asparagus, peppers, cabbage, corn, squash and tomatoes. All samples contained K-40 at concentrations from 1.5 to 5.9 pCi/g-wet.
No other gamma emitters were detected in these food products.
Sr-89 concentrations were all below MDL, which ranged from <0.006 to <0.2 pCi/g-wet.
Eight of the fourteen samples analyzed showed detectable Sr-90 activity ranging from*o.003 to 0.015 pCi/g-wet. The MDLs ranged from <0.003 to <0.007 pCi/g-wet.
Game (Table C-31)
Two samples of muskrat were taken during this period. Flesh from both samples was analyzed for gamma emitters while muskrat bones were analyzed for Sr-89 and Sr-90. Only naturally occurring K-40 was detected in the flesh samples ranging from 2.4 to 3.1 pCi/g.
Both results for Sr-89 in muskrat bones were below. MDL
(<0.2 and <0.9 pCi/g-dry). Detectable Sr-90 concentrations averaging 0.5 pCi/g-dry were observed in both samples.
Beef (Table C-31)
Three beef samples were collected during this reporting period. Only naturally occurring K-40 was detected in these samples at concentrations ranging between 1.7 and 2.7 pCi/g-wet.
Beef Thyroid (Table C-31)
Three beef thyroids were taken during this period and analyzed for gamma emitters.
One sample showed a detectable concentration of naturally occurring K-40 at a con-18
centration of*l.3 pCi/g-wet. The other samples had LLDs for K-40 of <0.6 and <1.1 pCi/g-wet.
No I-131 was detected in the samples with LLDs between <0.076 and <0.095 pCi/g-wet.
Fodder Crops (Table C-32).
Nine fodder crop samples were taken at six lpcal fanns and analyzed for gal'!llla emitters. Garmia spectrometry of. -these sampl'es showed several radionucl ides, both man-made and naturally occurring. Of the naturally occurring gamma.~mitters pre-sent, only K-40 was observed in all samples with an average of 11 pCi/g-dry. The other detected naturally occurring nuclide was Be-7 which occurred in one weed chop sample.
The man-made nuclide Cs-137 was observed in one soybean sample.
The presence of Cs-137 can be attributed to fallout from atmospheric nuclear weapons tests.
19
CONCLUSIONS The Radiological Environmental Monitoring Program for Salem Nuclear Generating Station at Artificial Island was conducted during 1981 in accorda~ce with the SNGS Environmental Technical Specifications. The objectives of the program were met during this period. The data collected assists in demonstrating that SNGS Units #1 and #2 were operated in compliance with Environmental Technical Specifications.
frQm the results obtained, it can be concluded that the levels and fluctuations of radioactivity in environmental samples were as expected for an estuarine environment.
In addition no increases were observed in either radionuclide concentrations in critical pathways or with respect to radionuclide build up.
Ambient ridiation levels were relatively low, averaging about 5.84 mrad/std.
month.
No other unusual radiological characteristics were observed in the environs of Artificial Island. The operation of SNGS Units #1 and #2 had no discernable effect on the radiological characteristics of the environs of Artificial Island.
20
.~~~~-~-*-,,_,,..._.
~** --.*
REFERENCES (1)
Radiation Management Corporation.
"Salem Nuclear Generating Station -
Radial ogi cal Environmental Monitoring Program - 1973.
11 RMC-TR-74-09, w~.
~
(2)
Radiation Management Corporation.
"Artificial Island Radiological En vi ronmenta 1 Monitoring Program - 197!+ Annua 1 Report.
11 RMC-TR-75-04, 1975.
(3)
Radiation Management Corporation.
"Artificial Island Radiological Environmental Monitoring Program - 1975 Annual Report.
11 RMC-TR-76-04, W76.
(4)
Radiation Management Corporation.
11ArtifiCial Island Radiological Environmental Monitoring Program - Preoperational Su11111ary - 1973 through 1976.
11
. RMC-TR-77-03, 1978.
(5)
Radiation Management Corporation.
11Artifi ci al Isl and Radiological Environmental Monitoring Program - Decent>er 11 to Deceni>er 31, 1976.
11 RMC-TR-77-02, 1977 *
. (6)
Radiation Management Corporation. "Artificial Island Radiological Environmental Monitoring Program - 1977 Annual Report.
11 RMC-TR-78-04A, 1978.
(7)
Radiation Management Corporation.
"Artificial Island Radiological Environmental Monitoring Program - 1978 Annual Report.
11 RMC-TR-79-03, 1979.
(8)
Radiation Management Corporation.
"Artificial Island Radiological Environmental Monitoring Program - 1979 Annual Report.
11 RMC-TR-80-03, 1980 *
. (9)
Radiation Management Corporation.
"Artificial Island Radiological Environmental Monitoring Program - 1980 Annual Report.
11 RMC-TR-81-03~
1981.
( 10)
Puhl i c Service Electric and Gas Company.
11Envi ronmental Report, Operating License Stage... Salem Nuclear Generating Station Units 1 and 2.
11 1971.
(11)
United States Atomic Energy Conmission.
"Final Environmental Statement -
Salem Nuclear Generating Station, Units 1 and 2.
11 Docket No. 50-272 and 50-311, 1973.
(12)
Public Service Electric and Gas Company.
"Final Safety Analysis Report -
Salem Nuclear Generating Station, Units 1.and 2.
11 1972.
(13)
Public Service Electric and Gas Company.
"Environmental Technical Specifications - Salem Nuclear Generating Station Units 1 and 2.
11 1976.
(14)
Radiation Management Corporation.
11Qual i ty Control Data 1981 - Annual Report", 1982.
21
REFERENCES (cont.)
(15)
Radiation Management Corporation.
"Artificial Island Radiological Environmental Monitoring Program - Statistical Interpretation of Results of the Thenool uminescent Dosimetry Program" RMC-TR-78-ll, 1978.
22
I
\\
\\
APPENDIX A PROGRAM
SUMMARY
23
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL f<<ltfITORING PROGRAM SUMHARY SALEf4 NUCLEAR GENERATING STATION DOCKET NO. 50-272 SALB~ COUNTY, NEW JERSEY JANUARY 1, 1981 TO DECEMBER 31, 1981 1:
l; i:
ANALYSIS AND
- LOWER NUMBER OF
! ~*
{ !
MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NOHROUTINE
'1 SAMPLED OF ANALYSES DETECTION MEAN**
NAME MEAN MEAN REPORTED
- ,
- n (UNIT OF MEASUREMENT)
PERFORMED (LLD)*
(RANGE)
DISTANCE AND DIRECTION (RANGE)
(RANGE)
MEASUREMENTS I' r Air Particulates Alpha 78 0.6
- 1.4 (31/39) 16E1*4.1 m1 NNW 1.4 (31/39) 1.2 (35/39) 0
~ :
(lo-3 pCi/m3)
(0.6-2.7)
(0.6-2.7)
(0.6-2.1)
! ~
Beta 312 141 (273/273) 2F2 8. 7 m1 MNE 146 (39/39) 144 (39/39) 0 f:.
(29-471)
(33-471)
(32-386)
,\\
e
,:i Sr-89 24
- o.o 5.4 (20/21) 16E1 4.1 mi NNW 6.95 (2/3) 5.8 (3/3l 0
1:
(0.7-9.3)
(6.9-7.0i (1.3-8.7 fl'
!i Sr-90 24 0.8 0.9 (20/21) 3H3 110 mi NE 1.3 (3/3
- 1.3 (3/3 0
(O.J.;-2.2)
(0.8-2.2 (0.8-2.2
~;
I Ganma 24 i
Be-7 01 (21/21) 2S2 0.4 mi NNE 93 (3/3~
75 (3/3) 0 (48-110)
(69-110 (57-92)
- ~
1*
K-40 6.1
'6.4 (6/21) 2F2 8.7 mf NNE 7.9 (1/3) 6.1 (113) 0 N
(4.9-7.9)
(7.9)
(6.1)
'1' U1 Mn-54 0.6
. 1.8 (10/21) 5s1*1.o m1 E 2.2 (1/3) 2.1 (113).
0 (Q.6.;.2.8)
(2.2)
(2.1)
~ :
lODl 3.9 mi.1*.SSW 2~2 (1/3) 61 (21/21)
(2.2)
Nb-95 2s2*0.4 m1 NNE 67 (3/3~
62 (3/3~
0 (14-120)
(17-100 (17-110 Zr-95 24 (21/21) 2S2 0.4 m1 NNE 29 (3/3}
25 (3/3~
0
,\\;*
(5.1-46)
(6.6-40 (6.4-42 Ru-103 0.9 11 (15/21) 2F2 8. 7 mf NNE 14 (2/3 9.5 (3/3) 0
~.. --'.
(1.1-15)
(13-15)
(1.4-14) e
- }:
Ru-106 6.1 16 (13-21) 2F2 8.7 mf NNE 24 ( 1/3) 15 (3/3J 0
(7.4-26)
(24)
(6.6-27 I..,:
Sb-125 1.7
- (0/21) 3H3 110 m1 NE 3.2 (2/3l 3.2 (2/3 0
( 3.0-3.4 (3.0-3.4 Cs-137
. 2.0 (21/21) 2F2 8.7 mf NNE 3.1 (3/3 2.5 (3/3 0
(0.9-5.5)
(1.4-5.1 (0.9-4.6 Ce-141 1.0 9.3 (14/21) 5S1 1.0 m1.E 10 (2/31 9.9 c2n 0
(6.4-12)
(B.1-12 (8. 7-lli Ce-144 50 (21/21) 5D1 3.5 mi E 56 (3/3 52 (3/3 0
(24-110)
(29-110 (25-100 Air Iodine 1-131 364 5.4
- (0/312)
None Detected
- (0/52) 0 (lo-3 pCf/m3)
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL l<<>NITORING PROGRAM SumARY SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272
- ~.
SALEM COUNTY. NEW JERSEY JANUARY 1. 1981 TO DECEllJER, 31 9 1981 i,,
ANALYSIS AND LOWER NUMBER OF
- ,l ::
MEDIIJll OR PATHWAY TOTAL NIJ4BER LIMIT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGfEST MEAN CONTROL LOCATION NONROUTINE
- 1.
SAff'LED OF ANALYSES DETECTION MEANH NAME MEAN MEAN REPORTED
~ i (UNIT OF MEASUREMENT)
PERFORMED (LLD)*
(RANGE)
DISTANCE AND DIRECTION (RANGE)
(RANGE)
MEASUREMENTS I,
J1
'i I,
Prtc:fltftation Alpha 12 0.6 1.6 (3/12) 2F2 8.7 m1 NNE 1.6 (3/12)
No r.ontrol 0
(pCi/1)
( 1.2-2.3)
( 1.2-2.3) location Beta 12 2.3
~ (12/12) 2F2 8. 7 m1 NNE 30 (12/12)
No r.ontrol 0
(4.7-70)
(4.7-70) location
. H-3 9
87 107 (3/9) 2F2 8. 7 m1 NNE 107 (3/9)
No r.ontrol 0
(86-124)
(86-124) location Sr-89 4
0.8 3.8 (3/4l 2F2 8. 7 m1 NNE 3.8 (3/4l No r.ontrol D
(0.6-7.5
. (0.6.;.7'J5 location s.... 90
- o.4 1.1 (2/4 2f2 8. 7 mi NNE 1.1 (2/4 No Control 0
(0.8-1.4 (0.8-1.4 location
~ :
Gamna 4
Be-7
. 7.6 34 (3/4) 2F2
- 8. 7 m1 NNE 34 (3/4)
No Control 0
(24-44)
(24-44)
Location
,j
~
Zr-95 0.6 4.3 (1/4) 2F2 8.7 m1 NNE 4.3 (1/4)
No Control 0
tN (4.3)
(4~3)
Locatfon
'. ! O'I Nb-95 o.6 11 (114) 2F2 8.7 mi NNE 11 (1/4)
No r.ontrol 0
(11)
(11)
Location Ru-103 (1) 4.7 (1/4) 2F2 8.7 mi NNE 4.7 (114)
No r.ontrol 0
(4.7)
(4.7) location Ce-141 (1) 3.4 (1/4) 2F2 8. 7 m1 NNE 3.4 (1/4)
No Control 0
(3.4)
(3.4) location D1 rect Radiation Gamna 288 5.40 (240/240) 11s1 0.09 mt SW 7.84 (12/121
. 5.84 (48/48) 0 (mrad/std. month)
Dose (nonthly)
( 3.28-16.511 (4.64-16.51 (4.97-7.14}
Ganma 96 5.31 (00/111 11Sl 0.09 m1 SW 8.18 (4/4) 5.64 (16/16}
0 Dose (quarterly) *
(3.31-14.45 (4.94-14.45)
(4.90-6.58)
Ganma 34 5.46 (28/28 11E2 5.0 mi SW 6.12 (2/2) 5.92 (6/6) 0 Dose (semi-annual)
(4.40-6.43)
(5.81-6.43)
(5.55-6.30)
Surface Water H-3 46 87 178 (15/35) 11Al 0.2 m1 SW 277 (3/8) 125 (8/11) 0 (pCi/1)
(77-412)
(97-412)
(58-246)
Alpha 55 0.2 0.4 (8/44) llAl 0.2 mi SW 0.5 (3/11) 0.3 (3/11) 0 (0.2-0.8}
(0.3-0.8)
(0.2-0.4)
Beta 55 50 (44/44}
7El 4.5 m1 SE 66 (11/11}
54 (11/11) 0 (10-129)
(33-122)
(lB-129)
Sr-89 17 0.6 0.9 (3/13}
1F2 7.1 mi N 1.1 (2/3~
0.6 (1/4}
0 (0.5-1.5}
(0.7-1.5
~0.6J Sr-90 17 0.3 o.o (4/13) llAl 0.2 m1 SW 1.3 (1/3 0/4 0
(0.4-1.3)
( 1.3)
Ganma 55 K-40 11 60 (42/44}
7El 4.5 mi SE 88 (11/11) 54 (11/11) 0 (20-120)
(49-120)
(22-85)
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL t<<ltHTORING PROGRAM
SUMMARY
SALB4 NUCLEAR GENERATING STATION DOCKET NO. 50-272
~I SALEM COUNTY, NEW JERSEY JANUARY 1, 1981 TO DECEMBER 31, 1981 t!
ANALYSIS AND
- LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN cornROL LOCATION NOHROUTINE SArf>LED OF ANALYSES DETECTION MEAN**
NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT)
PERFORMED (LLD)*
(RANGE)
DISTANCE AND DIRECTION (RANGE)
(RANGE)
MEASUREMENTS Well Water H-3 27 88 106 (1/18) 3El 4.1 mi NE 106 (1/18) 268 (1/9) 0 (pCi/1)
( 106)
(106)
(268)
Alpha 36 0.8 2.2 ( 1/24) 4Sl Site Well 15 ENE 2.2 (1/24)
- 1. 7 ( 1/12) 0 (2.2)
(2.2)
(1.7) e Beta 36 12 (24/24) 4Sl Site Well #5 ENE 13 (12/12) 9.2 (12/12) 0 (2.6-16)
(2.6-14)
(7.6-12)
K-40 36 9.1 (24/24) 4Sl Site Well #5 ENE 10 (12/12) 7.3 (12/12) 0 (2.2-14)
(2.6-14)
(1.7-9.6)
Sr-89 9
0.6
- (0/3)
None Detected
- (0/6) 0 l
Sr-90 9
0.4 0.4 (1/3) 4Sl Site Well 15 ENE 0.4 (1/3)
- (0/6) 0 (0.4)
(0.4)
Gamma 12 K-40 9.3 22 (114)
(22) 4Sl Site Well #5 ENE 22 ( 1/4)
(22) 20 (2/8)
(19-20) 0 N
Potable Water H-3 21 82 104 (5/21) 2F3 8.0 mi NNE 104 (5/21)
No Control 0
Raw-Treated (74-151)
(74-151)
Location Alpha 24 0.4 0.99 (15/24) 2F3 8.0 m1 NNE 0.99 (15/24)
No Control 0
(0.5-1.8)
(0.5-1.8)
Location Beta 24 3.3 (24/24) 2F3 8.0 mi.NNE 3.3 (24/24)
No Control 0
( 1.4-6.2!
(1.4-6.2 Location Sr-89 7
- 0.1 0.6 (2/7 2F3 8.0 mi NNE 0.6 (2/7 No Control 0
(0.5-0.7 (0.5-0.7 Location Sr-90 7
0.5 0.7 (4/7 2F3 8.0 mi NNE 0.7 (4/7 No Control 0
e (0.3-1.1 (0.3-1.1 Location*
K-40 24 1.4 (24/24) 2F3 8.0 m1 NNE 1.4 (24/24)
No Control 0
(0.9-3.0)
(0.9-3.0)
Location Gamma 8
- (0/8)
None Detected
- (0/8)
No Control 0
Location Benthos Sr-89 8
0.2
- '(0/6)
None Detected
- (0/2) 0 (pCf/g-dry) 3.0 ( 1/2)
Sr-90 8
0.3 1.2 (3/6) 16Fl 6.9 mf NNW
- (0/2) 0 (0.2-3.0)
(3.0)
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SIJ*\\J.1ARY SALEM NUCLEAR GENERATING STATION DOCKET t<<>. 50-272 SALEr~ COUNTY, NEW JERSEY JANUARY 1, 1981 TO DECEMBER 31, 1981 ANALYSIS ANO LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGIEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN**
NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT)
PERFORMED (LLD)*
(RANGE)
DISTANCE ANO DIRECTION (RANGE)
(RANGE)
MEASUREMENTS Sediment Sr-90 8
0.04 0.04 (1/6) 12Cl 2.5 m1. WSW 0.04 (1/2)
- (0/2) 0 (pC1/g-dry)
(0.04)
(0.04)
Ganma B
e K-40 14 (6/6) 12Cl 2.5 m1. WSW 16 (2/2) 16 (2/2) 0
( 13-18)
(16) p6)
Co-60 0.03 0.19 ( 1/6) llAl 0.2 m1. SW 0.19 (1/2) 0/2) 0 (0.19)
(0.19)
Zr-95 0.06 0.17 ( 1/6) 16Fl 6.9 mi. NNW 0.17 (1/2)
- (0/2) 0 (0.17)
(0.17) tl>-95 0.06 0.2 (3/6) 16Fl 6.9 mi. NNW 0.44 (1/2)
- (0/2) 0 (0.08-0.44)
(0.44)
Cs-137 0.04 0.1 (4/6) llAl 0.2 mi. SW 0.15 (2/2)
- (0/2) 0 (0.04.;.0.17)
(0.13-0.17)
- o.54 (6/6)
UA1*0.2 m1. SW 0.61 (2/2) o.54 c212i 0
N (0.46-0.65)
(0.57-0.65)
(0.48-0.60) c:>
Th-232 0.78 (6/6J 16Fl 6.9 mi. NNW 1.0 (2/2) 0~88 (2/2J 0
(0.47-1.0 (l.O)
(0.86.;.0.9 Fn.tfts a*veJetables Sr-89 14 0.006
- (0/7)
None Detected
- (0/7) 0 (pCf/g-wet Sr-90 14 0.003 0.009 (3/7) 1F3*5.9 m1. N 0.015 (1/1) 0.005 (5/7) 0 (0.004-0.015)
(0.015)
(0.003-0.o13)
Ganma 14 e
K-40 2.2 (7!7J 3H4 BB mi. NE 3.1 (4!4J 2.8 (7!7J 0
( 1.5-2.8
( 1.5-5.9 (1.5-5.9 Game Sr-89 2
0.2
- (0/1)
None Detected
- (0/1) 0 (pCi/g-dry)
(bones)
Sr-90 2
0.50 (1/1) 3El 4.1 m1. NE 0.05 (1/1) 0.5 (1/1) 0 (bones)
(0.50)
(0.05)
(0.5) 11El 4-5 mi. SW 0.5 (1/1)
(0.5)
( pCf I g-wet)
Galllia 2
(flesh)
K-40 2.4 (1/1) llEl 4-5 mi. SW 3.1 {1~1) 3.1 (l~l) 0 (2.4)
(3$1 (3.1
- 1
'. ~
I ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL r<<lNITORING PROGRAM surt!ARY tJ SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272 SALEr4 COUNTY, NEW JERSEY JANUARY 1, 1931 TO DECEMBER 31, 1931 i
I ANALYSIS AND LOWER NUMBER OF i*
MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF
. ALL. INDICATOR. LOCATIONS
. "LOCATION.WITH HIGHEST.MEAN CONTROL LOCATION NON ROUTINE I
SAMPLED OF ANALYSES DETECTION MEAN**
NAME MEAN MEAN REPORTED i
(UNIT OF MEASUREMENT)
PIERFORMED (LLD)*
(RANGE)
DISTANCE AND DIRECTION (RANGE)
(RANGE)
MEASUREMENTS ii i
Milk 1-131 144 0.04
- (0/120)
None Detected
- (0/24).
0 i
I.
(pC1/1)
Sr-89 60 1.8
'3.8 (8/48) 15Fl 5.2 m1 NW
- -6.6 (2/12) 3.9 (4/12) 0 I
I (1.8-8.5)
(4. 7.;.3.sJ (3.0-4.9) e f
s.... 90 60 0.7 "3.4 (42/48) 5F2 7.0 m1 E 4.9 (8/9 4.0 ( 11/12) 0 (0.6.;.6.8)
(0.6.;.6.8)
(2.9.;.5.3) f t
Ga11111a 72 l
K-40 1472 (60/60) 2F4*6.3 mf NNE 1533 (12/12) 1375 (12/12) 0 (1200-2000J
( 1300-1900)
( 1100-1700)
I i Cs-137 1.2 2.8 (31/60 5F2 7.0 mf E
. 3.5 (8/12)
. 3.2 (5/12) 0
'I
( 1.~6_.4)
(l.4-6.4)
(1.5-4.4) ij Edible Fish H-3 6
86 82.5 (2/4) 7El. 4.5 m1 SE 83 (1/2)
- (0/2) 0 II
,1 (pCf/1)
(aqueous)
(82-83)
(83)
N H-3 6
112 200 (3/41 llAl 0.2 mf SW 317 (112)
- (0/2).
- o
"° (organic)
(126-317 (317)
(pCt/g-dry) s.... 89 6
- 0.06
- (0/4)
None Detected
- (0/2) 0 (bones)
Sr-90 6
- 0.04 o.os (1/4) 7El 4.5 mi SE
- o.os (112)
'0.04 (1/2) 0 (bones)
(0.05)
(0.05).
(0.04)
(pCi/g-wet)
Galllllil 6
'3.6 (4/4J 7E1*4.5 mi SE 4.0 (2/2)
- 3.5 c212I 0
(2.9-4.;6 (3.3-4.6)
(3.2-3.8 e
Cs-137 0.008
- 0.016 (114) 7El.4.5 mi SE
. 0.016 (1/2)
- (0/2) 0 (0.016)
(0.016)
Blue Crab Sr-89 4
- 0.08 o.8 (112) 12Cl 2.5 m1 WSW 1.7 (1/2)
- 1.7 (l/2) 0 (pCt/g-dry)
(shells)
(O:.*a)
( 1. 7)
(1. 7)
Sr-90 4
- o.59 (212) 12Cl
- 2.5 mi WSW 0.64 (2/2~
0.64 (2/2~
0 (shells)
(0.24.;.0.94)
(0.28-1.0 (0.28,-1.0 (pCf/1)
H-3 4
86 123 (112) llAl 0.2 m1 SW
- 123 (1/2)
- (0/2) 0 (flesh) p23)
(123)
(pCi /g-wet)
Sr-89 4
- 0.01 0/2)
. None Detected
- (0/2) 0 (flesh)
Sr-90 4
0.007 0.07 ( 1/2) llAl 0.2 mi SW 0.07 ( 1/2) 0.02 (2/2) 0 (flesh)
(0.07)
(0.07)
(0.02)
Ga nm a 4
K-40 1.9 (212J 12Cl 2.5 mf WSW 2~3 (2/2) 2.3 (2/2) 0 (1.7.;.2.1 (2.3)
(2.3)
w
'0 ARTIFICIAL ISLAND RADIOLOGICAL ENVIROtr**EHTAL MOtlITORltlG PROGRAf.t
SUMMARY
SALEf4 NUCLEAR GEl~ERATING STATION OOCKET NO. 50-272 SALEt4 COUNTY I NEW JERSEY JANUARY 1, 1981 TO DECEMBER 31, 1931 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NlJl'IBER LirUT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN-HAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT)
PERF0"1ED (LLD)*
(RANGE)
DISTANCE AND DIRECTION (RANGE)
(RANGE)
MEASUREMENTS Beef Gamna 3
(pC1/g-wet)
K-40 2.2 (212J 3El.4.1 m1. tlE 2.2 (2/2~
1.7 (1/1) 0 (1.7-2.7 (1.7-2.7 (1.7)
Beef Thyroid Ganrna 3
(pCi /g-wet)
K-40 0.6 1.3* (1/2) 3El 4.1 mi. NE 1.3 (1/2)
- (0/1) 0 (1.3)
(1.3)
Fodder Crops Ganna 9
(pCi/g-dry)
Be-7 0.1 2.3 (1/7) 15F1*5.2 mi. NW 2.3 ( 1/3)
- (0/2) 0 (2.3)
(2.3)
K-40 9.9 (7/7) 3El 4.1 mi.* NE 16 (1/1) 15 (2/2) 0 (5.2-16)
(16)
(8. 7-21)
Cs-137 0.2
- 0.04 (1/7) 3El 4.1 mi. HE 0.04 (1/1)
- - (0/2) 0 (0.04)
(0.04)
LLn listed is the lowest calculated LLD during reporting period.* Strontium-89 and -90 detection levels are Minimum Detectable Levels (MDLs).
Mean calculated using values above LLD or MDL only. Fraction of measurements above LLD or MDL are in parentheses.
Indicates that no LLD was calculated for that nuclide in that media.
(1) r1 i-i:
I 1:
t:1 r
- l.
e t:
c:
I I
APPENDIX B SAMPLE DESIGNATION AND LOCATIONS 31
~*-*..... *****'* --*-.
APPENDIX B Sample Designation RMC identifies samples by a three part code. The first two letters are the power.station identifi.cation code, in this case 11SA 11
- The next three letters are for the media sampled.
AIO = Air Iodine GAM = Game APT = Air Particulates GAD = Deer ECH = Hard Shell Blue Crab IDM = Invrers ion Dose (TLD)
ESB = Benthos MLK = Milk ESF = Edible Fish PWA = Potable Water; (PWR = raw, PWT = treated)
ESS = Sedil!l!nt RWA = Rain Water FPB = Beef SWA = Surface Water FPV = Food Products, Various THB
=* Bovine Thyroid FPG = Corn VGT = Fodder Crops FPL = Green Leafy Vegetables WWA = Well Water The last four symbols are a location code based on direction and distance from the site. Of these, the first two represent each of the sixteen angular sectors of 22.5 degrees centered about the reactor site.
Sector one is divided evenly by the north axis and other sectors are num-bered in a clockwise direction;* i~e., 2=NNE, 3=NE, 4=ENE, etc. The next digit is a letter which represents the radial distance from the plant:
s
= On-site location E
= 4-5 miles off-site A
= 0-1 miles off-site F
= 5-10 miles off-site B
= 1-2 miles off-site G
= 10-20 miles off-site c
= 2-3 miles off-site H
= >20 miles off-site D
= 3-4 miles off-site The last number is the station numerical designation within each sector and zone; e~g., 1,2,3, * ~
- For example, the designation SA-WWA-501 would indicate a sample in the SNGS program SA, consisting of well water (WWA), which had been collected in the 22.5 degree sector centered on each axis (5), at a distance of 3 to 4 miles off-site (D). The number 1 indicates that this is sampling station #1 in the designated area.
33
Sampling Locations All sampling locations.and specific infonnation about the individual locations are given in Table B~l. Maps B-1 and B-2 show the locations of sampling stations with respect to the site.
TABLE B.-1 STATION STATION CODE LOCATION lFl
- s.a mi. N of vent; Fort Elfsborg 1F2
- 1.1 mi. N of vent; midpoint of Delaware River 1F3 5.9 mi. N of vent; local fann lGl 13 mi. N of vent; local fann 163 19 mi. N of vent; Wilmington, Delaware 2S2 0.4 mi. NNE of vent 2El
- 4.4 mi. NNE of vent; local fann 2F2
- a.7 mi. NNE of vent; Salem Substation.
2F3
- a.o mi. NNE of vent; Salem Water Company 2F4
- 6.3 mi. NNE of vent; local fann 2F5
- 7.4 mi. NNE of vent; Salem High School 2Hl 34 mi. NNE of vent; RMC, Phil a.
3El 4.1 mi. NE of vent; local fann 3F2 5.1 mi. NE of vent; Hancocks Bridge Municipal Bldg.
3F3 8.6 mi. NE of vent; Quinton Township School 3Gl 17 mi. NE of vent; local fann 31-11 32 mio NE of vent; National Park, N.J.
3H3 110 mi. NE of vent; Maplewood Laboratories 3H4 88 mi. NE of vent; local fann 4Sl 1400 ft. ENE of vent; site well #5 402
- 3.7 mi. ENE of vent; Alloway Creek Neck.Road 34 SAMPLE TYPES APT,IDM SWA FPL FPG IDM APT,AIO, I OM IDM,FPV APT,AIO,RWA,IDM PWR,Pin MLK,VGT IDM IDM I DM,WWA, THB, FPV,FPG,GAM, FPB IDM IDM IDM,MLK,FPG,VGT IDM APT,AIO, I DM FPV,FPG WWA IDM
1-. ----
TABLE B-1 (CONT.)
STATION STATION CODE LOCATION 5Sl
- 1.0 mi. E of vent; site access road 501
- 3.5 mi. E of vent; local fann 5Fl
- s.o mi. E of vent 5F2 7.o mi. E of vent; local fann 6S2 0.2 mi. ESE of vent; observation bldg.
6Fl 6.4 mi. ESE of vent; Stow Neck Road 7Sl 0.12 mi. SE of vent; station personnel gate 7El
- 4.5 mi. SE of vent; 1 rni. W of Mad Horse Creek 7F2 9.1 mi. SE of vent; Bayside, New Jersey 9El
- 4.2 mi. S of vent lOSl 0.14 mi. SSW of vent; site shoreline 1001 3.9 mi. SSW of vent; Taylor's Bridge Spur 10F2 5.8 rni. SSW of vent lOGl 12 mi. SSW of vent; SfllYrna, Delaware llSl 0.09 mi. SW of vent; site shoreline llAl 0.2 mi. SW of vent; outfall area 1101
- 2.5 mi. WSW of vent; west bank of Delaware river 35 SAMPLE TYPES APT,AIO,IDM APT,AIO, IDM WWA,FPV IDM,FPV MLK IDM IDM IDM SWA,ESB,ESS,ESF IDM IDM IDM APT,AIO, IDM IDM IDM IDM SWA,ESB,ESS, ESF,ECH GAM GAM IDM IDM SWA,ESF,ECH, ESB,ESS
TABLE B-1 (CONT.)
STATION STATION CODE LOCATION 12El
- 4~4 mi. WSW of vent; Thomas Landing 12Fl
- 9e4 mi. WSW of vent; Townsend Ele~ntary School 13El
- 4.2 mi. W of vent; Diehl House Lab 13E3
~4.9 mi. W of vent; local farm 13Fl
- 9.a mi. W of vent; Middletown, Delaware 13F2
- 6~5 mi. W of vent; Odessa, Del aware 13F3
- 9. 3 mi. W of vent; Redding Middle School,- Middletown, DE 14Dl
- 3.4 mi. WNW of vent; Bai View, Del aware 14Fl 5.5 mi *. WNW of vent; local fann 14F2
- 6.6 mi. WNW of vent; Boyds Corner 14F3
- 5.0 mi. WNW of vent; local fann 15Fl 5.2 mi. NW of vent; local fann 15F3
- 5.4 mi. NW of vent 16El
- 4.1 mi. NNW of vent; Port Penn 16Fl 6.9 mi. NNW of vent; C & D Canal 16F2
- a.1 mi. NNW of vent; Delaware. City Public School 16Gl 15 mi. NNW of vent; Greater Wilmington Airport 36 SAMPLE TYPES IDM IDM IDM MLK,VGT IDM IDM IDM IDM MLK,FPB,THB,VGT IDM FPV,FPG MLK,FPG,VGT IDM APT,AIO,IDM SWA,ESB,ESS IDM Ill~
~
0 I
I i
L::
r=::::J SCALI Of IAI LIS MAP 8-1 ON SITE SAMPl ING LOCATIONS ARTIFICIAL ISLAND 3i
- ** __
- __..;J_. ____ _
- -------~-,*,.. *:~-~...
MAP B-2 OFF SITE SAMPLING LOCATIONS ARTIFICIAL ISLAND 1Df2
- a:ai_=-3_. :+/- __ ;._____.
1cau ** *n11 lOCI
\\
98
r 1
~
~.*:-"<*..: ---~
.* ~.:. -. --
APPENDIX C 1981 DATA TABLES 39
~---------
'_.._.\\:.-
4' ** ** * ** -
DATA TABLES
~
Appendix C presents the -analytical results of.the 1981 Artificial Island Radiological Environmental Monitoring Program for the period of January 1 to Deceni>er 31.
TABLE NUMBER TABLE TITLE PAGE C-1 Concentrations of Gross/ Alpha Emitters in Ai.r Par.ti cul ate~ : ~ ~..
43 C-2 Concentrations of Gross Beta Emitters in Air Particulates* : ~ ~* ~..
44 C-3 Concentrations of Gamma Emitters in Quarterly Composites of Air Particulates ******* ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~; ~-. ~ ~ ~ ~ ~ ~ ~ ~ ~........
45*
C-4 Concentrations of Strontium-89 an*d -90 in Quarterly Composites
- of Air Particulate Samples**~~~~~~:~~~:~~~~~~~~~-~:~::~~::~~ ****
48 C-5 Concentrations of Iodine-131 in Filtered Air*.~::~:~:.~: *** : ***, 49 C-6 Sampling Dates for Air Samples
- e***C1*~******~*******~*****e*a 51 C-7 Concentrations of Tri ti um, Gross Alpha and Gross Beta Emitters i n Pre c i pi tat i on *. * ~ ~ ** ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ * ~ ~ ~ ~ ~ ~ ~- ~ ~ ~ ~ ~ ~ * ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~. ~ *.
- 56 C-8 Concentrations of Strontium-89 and -90 and Gamma Emitters in Quarterly Composites of Precipitation * ~::~:::::::::::::~.::::.. 57 C-9 C-10*
Direct Radiation Measuremef)tS - Monthly TLD Results Direct Radiation Measurements - Quarterly TLD Results 58 59 C-11 Di re ct Radiation Measurements - Semi-Annual TLD Results * * ~:: * * *
- 60 C-12 Concentrations of Tri ti um in Surface Water* **.*.*.*. ~~~~~~~..*. 61 C-13 Concentrations of Gross Alpha Emitters in Surface Water * * * * * *
- 62 C-14 Concentrations of Gross Beta Emitters in Surface Water........ 63 C-15 Concentrations of Gamma Emitters in Surface Water :.:::::.: ****
64 C-16 Concentrations of Strontium-89 and -90 in Surface Water**:.::~.. 65 C-17 Concentrations of Tritium, Gross Alpha and Gross Beta Emitters, and Potassium-40 in Well Water * :~::.:: ** :.:::::~:~:::.~ *** :: *** 66 C-13 Concentrations of Strontium-89 and -90, and Gamma Emitters in Quarterly Composites of Well Water** *** :.:~:::::.~.:~~.:.:: ** : **
67
. C-19 Concentrations of Tritium, Gross Alpha and Gross Beta Emitters, and Potassium-40 in Raw and Treated Potable Water ************* 68 41
1-*
DATA TABLES (cont.)
TABLE TABLE TITLE PAGE NUMBER C-20 Concentrations of Stronti um-89 and -90, and Garmna Emitters* in Quarterly Composites of Potable Water.~.~-~-~~~-~-~~~~~~~...
69 C-21
- Concentrati ans of Stronti um-89 and -90 in Benthos * ~ ~ ~. ~. ~...
70 C-22 Concentrations of Strontium-90 and Gamma Emitters in C-23 Concentrations of Iodine-131 in Milk * ~~~-~~-~-~~-~~-~~-~~~ **
C-24 Concentrations of Gamma Emitters and Strontium-89 and -90 in C-25 C-26 Sampling Dates for t~ilk ~amples* * ** ~~~-~~~ *..*..**.*.....**..
Concentrations of Gamma Emitters in Edible Fish * ~~~-~~~~ ****
72 75 77 C-27 Concentrations of Strontium-89 and -90, and Tritium in Edible Fish-Samples**~-~-~-~-~-~~~~~~-~~-~~~.*~.~~.... ~~......
78 C-28 C-29 Concentrations of Gamma Emitters in Blue Crab Samples......
Concentrations of Stronti um-89 and -90, and Tri ti um in Blue Crab Samples
- ~~~~~~~ ***********************
C-30 Concentrations of Gamma Emitters and Strontium-89 and -90 79 80 C-31
- Concentrations of Gamma Emitters and Strontium-89 and -90 in Meat, Game and Bovine Thyroid * *~~~~-~~~~~~~~~~~-~........
82 C-32 C-33 Concentrations of Garrma Emitters in Fodder Crop Samples....
LLDs for Garrrna Spectrometry
.~.~.~-~ ** ~~ ** ~ ** ~~~ *** ~.~ ******
42
~-.....,*-:~*** *,* -...
83 84
12/1 rec. 1/20/82 TABLE C-1 CONCENTRATIONS OF GROSS ALPHA EMITTERS IN AIR PARTICULATES
...i:=.
w Results in Units of lo-3 pCi/m3 +/- 2 sigma:
STATION NIJllER SA-APT-16El SA-APT-3H3 (Control Station)
STATION NUMBER SA-APT-16El SA-APT-3H3 (Control Station)
JANUARY*
1.5+/-0.8 1.7+/-0.7 1.6+/-0.9 1.1+/-0.6 0.6+/-0.6 1.4+/-0.R
. 1.2+/-0.7 1.5+/-0.9 1.2+/-0.7 1.6+/-0. 7 JUNE 0.9+/-0.6
<0.9 1.5+/-0.6 1.7+/-0.8 1.4+/-0.7 1.0+/-0.6 1.1+/-0.6
- 0.1+/-0.6 Saq>l1ng dates can be found on Table C-6.
FEBRUARY 1.9+/-0.7 1.3+/-0.5 1.1+/-0.6 1.1+/-0.8 1.3+/-0.7
. 1~2+/-0.4 1.3+/-0.*7 1.0+/-0.7 JULY
<0.8 1.5+/-0.6 1.4+/-0. 7
<0.7
<1.2 0.7+/-0.6 1.2+/-0.6 1.1+/-0.6 0.8+/-0.5
<1.1 Program <111scontinuerf by "~C after the third quarter.
MARCH
<0.7 2.0+/-0.9 1.4+/-0.6 2.7+/-0.8 0.6+/-0.6 1.2+/-0.6 1.1+/-0.6 2.1+/-0.7 AUGUST 1.2+/-0.6 1.6+/-0.7
<0.7 0.9+/-0.7 1.2+/-0.7 1.4+/-0.6 1.1+/-0.6 1.5+/-0.7 APRIL 1.2+/-0.7 1.1+/-0.6 1.0+/-0.6 0.9+/-0.6 0.9+/-0.6 1.8+/-0.7 1.3+/-0.6 0.9+/-0.6 SEPTEMBER**
1.3+/-0.7 1.9+/-0.8 1.3+/-0.8 1.2+/-0.4 1.5+/-0.7 1.4+/-0.8 1.2+/-0.7 1.0+/-0.4 MAY
<1.1 0.9+/-0.6 0.9+/-0.8 1.4+/-0.6
<1.2
<1.1
<0.6 0.9+/-0.7 1.2+/-0.6
<l.O AVERAGE 1.3+/-0.9 1.2+/-0.6 e
- 1/1 rec. 1/20/82 TABLE c-2 CONCENTRATIONS OF BETA EMITTERS IN AIR PARTICULATES Res1.1lts in Units of 10,.3 pCi/m3 :1: 2 sip
- -** STATION. NO *.
r<<>NTH SA-APT-2S2 SA-APT-5Sl SA-APT-501 SA-APT-100!.
SA-APT-16El SA-APT-lFl
~-APT-2F2 SA-APT-3H3 AVERAGE JANUARY*
. 76+/-8 62:1:6 84+/-8 79+/-8 72+/-7 82+/-8 83+/-8 103+/-10 80+/-23 5b6
. 52:1:6 59+/-7
~3+/-6.
52:1:6 74:!:7 62+/-7 62+/-7 58+/-16 91:1:9 99:1:10 102+/-10 113+/-11 107+/-11 94:1:9 97+/-10 95+/-10 100+/-15 138+/-14 128+/-13 157+/-16 157+/-16 132+/-13 142+/-14 146+/-15 129+/-13 141+/-23 210+/-21 134+/-13 i42+/-14 100:1:10 93:1:9 115+/-12 116+/-12 114+/-11 128+/-74" FEBRUARY 219:1:22
'97+/-10 103+/-10 89:1:9 87:1:9 101+/-10 101:1:10 106+/-11 113+/-87 109+/-11 88:!:9 106:1:11 101:1:10 85:1:9 123+/-12 117+/-12 117+/-12 106+/-28 145+/-14 110:1:11 135:tlY 132+/-13 128+/-13 117+/-12 130+/-13 136+/-14 129+/-22 122+/-12 152+/-15 102+/-10 92:1:9 101+/-10 109+/-11 123+/-12 114+/-11 114+/-37
. MARCH 113+/-11 78+/-8 79+/-8 90:1:9 86+/-9 109+/-11 83+/-8 84+/-8 90+/-27 201+/-20 201+/-20 204+/-20 208+/-21 253+/-25 231+/-23 202+/-20 154+/-15 207+/-57 196+/-20 136+/-14 140+/-14 154+/-15 136+/-14 162+/-16 128+/-13 159+/-16 151+/-44 238:1:24 237+/-24 234+/-23 234+/-23 205+/-20 218+/-22 243+/-24 254+/-25 233+/-30 APRIL 383+/-38 331+/-33 376+/-38 427+/-43 381+/-38 363+/-46 471+/-47 373+/-37 388+/-85 239+/-24 237+/-24 229:1:23 249+/-25 243t24 233+/-23 260+/-26 263+/-26 244+/-25 233+/-23 268+/-27 250+/-25 267+/-27 283+/-28 283+/-28 249+/-25 269+/-27 263:1:35 224:1:22 232+/-23 252:1:25
' 209:1:21 211+/-21 229+/-23 224+/-22 179+/-18 220+/-43 M.\\Y 221:1:22 219+/-22 229+/-23 219+/-22 244+/-24 237+/-24 251+/-25 266+/-27 236+/-34 172+/-17 184+/-18 183+/-18 201+/-20 163:1:16 199+/-20 184+/-18 196+/-20 185+/-27 285:1:28 282+/-28 287+/-29 294+/-29 285:1:29 287+/-29 321+/-32 271+/-27 289+/-29 345+/-35 360+/-36 394+/-39 359+/-36 352+/-35 4000:1:2300(l) 338+/-34 386+/-39 362+/-41 200+/-20 190:1:19 1~8:!:20 184+/-18 185+/-19 183+/-18 210+/-21 200+/-20 194+/-19 JUNE 158+/-16 156+/-16 157+/-16 149+/-15 162+/-16 159+/-16
' 165+/-16 180+/-18 161+/-18 144+/-14 124+/-12 i38:t14 134+/-13 135+/-13 129+/-13 148+/-15 173+/-17 141+/-30 113+/-11 99+/-10 98:1:10 124+/-12 116+/-12.
112+/-11 109+/-11 106+/-11 110+/-17 138+/-14 146+/-15 164+/-16 142+/-14 131+/-13 134+/-13 150+/-15 119+/-12 141+/-27 JULY 94:1:9 95:1:10 96+/-10 84:1:9 87:1:9 86:1:9 95+/-10 100+/-10 92+/-11 190+/-19 194+/-19 192+/-19
'179+/-18.
175+/-17 203+/-20 203+/-21 204+/-20 193+/-24 109+/-11 112:1:11 123+/-12 95+/-10 94:1:9 115+/-11 108+/-11 127+/-13 110+/-24 91:1:9 95+/-10 101:1:10 96+/-10 100:1:10 113+/-11 101:1:10 94+/-9 99+/-14 69+/-7 67+/-7 75+/-8 67+/-8 69+/-8 67+/-8 78:!:8 86+/-9 72+/-14 AUGUST 40:1:5 46:1:6 42:1:6 42:1:6 39+/-5 50+/-7 51+/-7 65+/-7 47+/-17 51:1:6 61+/-7 59+/-7 58:1:7 58+/-7 63:1:8 66+/-8 63+/-7 60+/-9 61:1:6 67+/-7 70+/-7 70+/-7 69+/-7 8):1:8 68+/-7 69+/-7 69+/-10 37+/-5 52+/-7 4~+/-7 40:1:6 42:1:6 46t6 48:!:6 46+/-6 44+/-9 SEPTEJeER**
40+/-5 36:1:6 46:1:6 42+/-6 41+/-5 41+/-6 37:!:5 49+/-6 42+/-9 47:1:6 52+/-8
. 42+/-8 57+/-7 44':t6 46+/-7 57+/-8 42+/-6 48+/-12 35+/-5 37+/-7 33+/-6 29+/-6 34:1:6 37:1:6 33+/-6 38+/-6 35+/-6 34:1:5 33+/-6 35+/-7 40:1:6 37+/-6 29:1:6 35+/-6 32+/-5 34+/-7 AVERAGE 145+/-175 137+/-169 143+/-179 140+/-183 136+/-178 137+/-159 146+/-191 144+/-177 141+/-175 Sa~lfng dates can be fo..-id on Table C.-6.
Program discontinued by RMC after the.third quarter.
(1)
High result due to low sa111>le vohane. This result wu not tncluded in the averages.
44
I..
f 3/1 rec. 2/05/82 TABLE C-3 CONCENTRATIONS OF GA1l4A E14ITTERS* IN QUARTERLY cor.f>OSITES OF AIR PARTICULATES Results fn Unfts of 10-3 pCf/m3 +/- 2 s1gna STATION NlMIER AND DATE Be-7 K-40 Mn-54 Nb-95 Zr-95 Ru-103 Ru-106 Sb-125 Cs-137 Ce-141 Ce-144 SA-APT-2S2 12-29-aJ to 69+/-7
- 6.6:t:5.2
- o.6:t0.3 85+/-9 40+/-4 15+/-2
- 8.1+/-4.o
<2.3 1.2:!0.4 11+/-1.
31+/-3 3-30-81 e
3-30-81 to 99+/-10
<7.2
- 2.3+/-0.5 100+/-10 39+/-4 13+/-1 26+/-5
<2.3
- 4.6+/-0.5
. 7.9+/-1.2 89+/-9 6-29-81 6-29-81**
to 110+/-11
<11
<0.9 17+/-2 6.6+/-0.9 1.1+/-0.7 9.7+/-4.4
<2.0
- 1.9+/-0.5
<1.7 30+/-3 9-28-81 SA-APT-551
~
U1 12-29-aJ to 67+/-7
- 4.9+/-4.3
<0.7 63+/-6 29+/-3 13+/-1
<6.1
<2.1
- 1.1+/-0.4 12+/-1 28t:3 3-30-81 3-30-81 to 83+/-9
<13
- 2.2:t0.6 110+/-11 39+/-4 11+/-1 23+/-6
. <2.9
- 4.7:t0.6 8.1+/-1.4 95+/-10 6-29-81 6-29-81**
to 92+/-9
<15
- <0.9 17+/-2 6.0+/-1.1
<1.4
<11
<2.5
- 2.0+/-0.6
<1.9 29+/-4 9-28-81 SA-APT-5D1 12-29-aJ
't to 65+/-7 5.0+/-4.7
<0.6 61+/-6 27+/-3 12+/-1
<8.3
<2.2 0.9+/-0.5 11+/-1
. 30+/-3 3-30-81 3-30-81 to 91+/-10
<9.1 2.1+/-0.5 120+/-12 46+/-5 13+/-2 24+/-7
<3.2 5.1+/-0.7 8.3+/-1.4 110+/-11 6-29-81 6-29-81**
to 87+/-9
<15
<1.0 14+/-1
- 1.2+/-1.2
<1.4 7.4+/-4.8
<2.8 2.5+/-0.6
<1.9 29+/-4 9-28-81
14/l rec. 2/05/82 TABLE C-3 (cont.)
-~.
CONCENTRATIONS OF GArl-tA EMITIERS* IN QUARTERLY COMPOSITES OF AIR PARTICULATES Results 1n Units of 10*3 pC1/m3 +/- 2 s1~
STATION NUteER AND DATE Be-7 K-40 Mn-54 Nb-95 Zr-95 Ru-103 Ru-106 Sb-125 Cs-137 Ce-141 Ce-144 SA-APT-10D1 12-29-8) to 48+/-6
<8.8
<0.6 52+/-5 21+/-2 10+/-1
. 8.4+/-4.1
<1.9 1.1+/-0.4 lO:tl 24+/-2 e
3-31-81 3-31-81 to 84+/-9
<13
.. 2.2+/-0.6 100+/-10 40+/-4 11+/-1 20+/-6
<3.0 4.9+/-0.6 6.4+/-1.4 95+/-10 6-JJ-81 6-JJ-81**
to 88+/-9
<13
<0.9 15+/-2
- 5.1:1:1.0
<1.3
<8.4
<2.4
- 2.4+/-0.6
<2,1 30+/-4 9-28-81 g: SA-APT-16El 12-29-00 to 65+/-7
- 6.9+/-5.2
<0.6 60+/-6
. 26+/-3 12+/-1
. 7.6+/-4.1
<2.2
- 1.4+/-0.5 11+/-1 29+/-3 3-31-81 3'o31-81 to 78+/-10
<15 2.0+/-0.6 100+/-10 38+/-4 9.8+/-1.3 17+/-6
<3.3 5.5+/-0.8 6,7+/-1.5 83+/-8 6-JJ-81
),.
6-JJ-81**
e I
to 88+/-9
<8.2
.. <0.6 16+/-2 5.9+/-0.8
<0.9 13+/-5
<l.7
- 2.1:1:0.5
<1,8 34+/-4 9-28-81 SA-APT-lFl 12-29-8) to 49+/-8
<9.7
<0.9 60+/-6 25+/-3 11+/-1
<8.4
<2.2 1.2+/-0.5 12+/-1
. 29:1:3 3-I>-81 3-JJ-81 to 74+/-9
<9.8
- 2.8+/-0.6 89+/-9 33+/-3
. 8.8+/-1.3 19+/-5
<2.8 4.2+/-0.7 6.8:1:1.6 86+/-9 6-29-81 6-29-81**
to 95+/-10 6.9+/-5.5 0.9+/-0.5 16+/-2
- 6.5+/-0.9
<0.9
<9.2
<2.0 2.2+/-0.5
<1.9 34+/-4 9-28-81
17/1 rec. 2/05/82 TABLE C-4 CONCENTRATIOHS OF STROHTIU:*,-39* AND -90 Itl QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES 00 Results in Units of 10-3 pCi/m3 +/- 2 sigma
,January to March Aprn to June STATION NLMBER Sr-89 Sr-90 Sr-39 Sr-90 SA-APT-?.S2 7.5+/-0.8 0.4:!:0.3 6.5+/-0.8 2.2+/-0.3 SA-APT-551
- 1.0+/-0.8 0.4+/-0.3 7.6+/-0.9 1.7+/-0.4 SA-APT-501
'9.3+/-1.3
<0.8 5.9+/-1.3 1.2+/-0.7 SA-APT-1001 7.3+/-0.8 0.5+/-0.3 7.8+/-1.0
- 1.4+/-0.4 SA-APT-16El 6.9+/-0.8 0.4+/-0.4 7.0+/-1.0 1.7+/-0.4 SA-APT-lFl
'6.9+/-0.9 0.6+/-0.4 8.3+/-1.0 0.8+/-0.4 SA-APT-2F2
'6.6+/-1.0 0.7+/-0.4
- 1.2+/-0.9
. 1.6+/-0.4 SA-APT-3H3
. 7.3+/-1.0 0.3+/-0.4 8.7+/-0.9 2.2+/-0.4 (Control Station)
Average 7.4+/-1.7 0.6+/-0.4 7.4+/-1.8 1.6+/-1.0 Strontium-89 results are corrected for decay to sample stop date.
Program discontinued by RMC after the third quarter.
July to September**
Sr-39 Sr-90 0.3+/-0.5 0.5+/-0.2 1.0+/-0.5 o.s+/-0.2 0.7+/-0.6 0.6+/-0.2 0.7+/-0.5 0.4+/-0.2
<0.8 0.6+/-0.2 1.3+/-0.6 0.3+/-0.2 0.3+/-0.6 0.7+/-0.3 1.3+/-0.5 0.8+/-0.2 0.9+/-0.5 0.6+/-0.3
'(
i e {
f
\\:
i I:
~. '
- 13/1 rec. 1/20/82 TABLE C-5 CONCENTRATIONS OF IODINE-131* IN FILTERED AIR Results in Units of 10-3 pC1/m3 STATION NO.
r<<>NTH SA-AI0-2S2 SA-AI0-5Sl SA-AI0-501 SA-AI0-1001 SA-AI0-16El SA-AI0-2F2 SA-AI0-3H3
~Control Station)* *.
JANUARY**
<12
<9.1
<12
<9.9
<11
<11
<12
<11.
<9.0
<11
<B.l
<9.1
<11
<11
<12
<9.2
<12
<12
<14
<11 (13
<12
<9.6
<12
<8.3
.<9.7
<11
<11 e
<12
<8.6
<11
<11
<13
<10
<11 FEBRUARY
<11
<9.3
<11
<8.2
<9.4
<11
<11
<9.9
<B.O
<9.6
<9.5
<12
<9.4
<9.9
<13
<13
<13
<10
<10
<12
<14
<12
<8.9
<12
<12
<14
<10
<11 MARCH
<11
<11
<11
<8.8
<8.7
<10
<12
<12
<9.5
<12
<12
<13
<9.8
<10.
..J::::a
<11
<9.8
.<11
<8.5
<9.0
<9.6
<10 I
!J:)
<11
<11
<11
<11
<10
<10
<11 APRIL
<12
<12
<13
<13
<12
<13
<12
<16
<15
<20
<14
<16
<17
<17
<10
<12
<12
<14
<13
<10
<12
<13 (13
<15
<15
<14.
<12
<14 MAY
<9.1
<10
<11
<11
<9.7
<9.9
<11
<6.2"
<6.5
<7.0
<5.6
<5.4
<6.2
<6.4
<10
<11
<11
<13
<12
<11
<12
<8.8
<10
<11
<8.6
<7.9
<8.8
<9.8
<11
<14
<14
<15
<15
<11
<33 JUNE
<15
<15
<21
<14
<15
<17
<17
<11
<11
<14
<13
<14
<12
<12
<9.1
<11
<12
<9.3
<8.8
<9.7
<11
<11
<14
<12
<11
<9.7
<12
<11
~ -
- 14/1 rec. 2/16/82 TABLE C-5 (cont.)
~.
CONCENTRATIONS OF IODINE-131* IN FILTERED *AIR Results in Units of 10-3 pCi/m3 I:
~ :
STATION NO.
'f f'
MONTH SA-AI0-2S2 SA-AI0-5Sl SA-AI0-5Dl SA-AIO-lODl SA-AI0-16El SA-AI0-2F2 SA-AI0-3H3 Ceontrol Station) 1 ;I
! i JULY
<12
<15
<14
<15
<13
<11
<12
! :I
~
~
<12
<16
<14
<10
<9.3
<14
<12 r*.
! (
<11
<14
<13
<11
<9.8
<12
<11 I:
<12
<16
<13
<12
<11
<12
<13 e
<11
<13
<13
<14
<12
<13
<12 r:
AUGUST
<11
<15
<13
<10
<9.4
<12
<13 l'
<11
<14
<13
<11
<10
<13
<12
<11
<15
<12
<11
<11
<12
<12 I
<11
<16
<14
<13
<13
<12
<11
~
~
SEPTEMJER
<9.2
<14
<11
<10
<9.3
<IO
<11
<19
<26
<25
<17
<16
<20
<19
<11
<16
<14
<15
<14
<13
<12
<11
<15
<16
<13
<12
<11
<12
<86(1)
(.J'1 OCTOBER
<10
<12
<14
<12
<11
. <12 0
<9.1
<14
<12
<11
<9.5
<10
<9.8
<18
<23
<16
<15
<15
<14
<16 i.'
<8.3
<13
<12
<8.5
<8.8
<9.1
<9.9
<9.7
<17
<14
<15
<16
<8.8
<13 i I:
NOV Be ER
<11
<14
<13
<9.9
<10
<11
<12
<9.3
<14
<12
<12
<13
<11
<11
<9.1
. <13
<13
<8.9
<11
<11
<10
<16
<22
<18
<18
<19
<17
<21 e
DECE!eER
<14
<15
<13
<13
<18
<9.7
<14
<26
<16
<12
<12
<12
<1210 (2)
<13
<9.9
<12
<12
<9.7
<12
<11
<11
<9.0
<14
<10
<9.6
<11
<9.6
<13
~
1-131 results are corrected for decay to saf1'4lle stop date.
Actual sampling dates can be found on Table C-fi.
u~
Hi!tl LLD due to low sample volulll! resulting from a power outage.
High LLD due to low sample volume caused by an obstruction in the air filter line.
18/l rec. 1/20/82 TABLE C-6 SAMPLING DATES FOR AIR SAMPLES STATION NO.
!<<>NTH 2S2 5Sl 501 1001 16El
!Fl 2F2 3H3 JANUARY 12-29-80 12-29-80 12-29-80 12-29-80 12-29-80 1-29-80 12-29-80 12-29-80 to to to to to to to to 1-05-81 1-05-81 1-05-81 1-05-81 1-05-81
. 1-05-81 1-05-81 1-05-81 1-05-81 1-05-81 1-05-81 1-05-81 1-05-81 1-05-81 1-05-81 1-05-81 to to to to to to to to e
1-12-81 1-12-81 1-12-81 1-13-81 1-13-81
. 1-12-81 1-12-81 1-12-81 1-12-81
.1-12-81 1-12-81 1-13-81 1-13-81 1-12-81 1-12-81 1-12-81 to to to to to to to to 1-19-81 1-19-81 1-19-81 1-19-81 1-19-81 1.:.19-81 1-19-81 1-19-81 1-19-81 1-19-81 1-19-81 1-19-81 1-19-81 1-19-81 1-19-81 1-19-81 to to to to to to to to 1-26-81 1-26-81 1-26-81 1-27-81 1-27-81 l"".26-81 1-26-81 1.. 26-81 1-26-81 1-26-81 1-26-81 1-27-81 1-27-81 1-26-81 1-26-81 1-26-81 U'I to to to to to to to to
~
2-02-81 2-02-81
~-02-81 2-02-81 2-02-81 2-02-81 2-02-81
- 2-02-81 FEBRUARY 2-02-81 2-02-81 2-02-81 2-02-81 2-02-81 2-02-81 2-02-81 2-02-81 to to to to to to to to 2-09-81 2-09-81 2-09-81 2-10-81 2-10-81 2-09-81 2-09-81 2-09-81 2-09-81 2-09-81 2-09-81 2-10-81 2-10-81 2-09-81 2-09-81 2-09-81 to to to to to to to to 2-17-81 2-17-81 2-17-:81 2-17-81 2-17-81 2-17-81 2-17-81 2-17-81 e
2-17-81 2-17-81 2-17-81 2-17-81 2-17-81 2-17-81 2-17-81 2-17-81 to to to to to to to to 2-23-81 2-23-81 2-23-81 2-24-81 2-24-81 2-23-81 2-23-81 2-23-81 2-23-81 2-23-81 2-23-81 2-24-81 2-24-81 2-23-81 2-23-81 2-23-81 to to to to to to to to 3-02-81 3-02-81 3-02-81 3-02-81 3-02-81 3-02-81 3-02-81 3-02-81 MARCH 3-02-81 3-02-81 3-02-81 3-02-81 3-02-81 3-02-81 3-02-81 3-02-81 to to to to to to to to.
3-09-81 3-09-81 3-09-81 3-10-81 3-10-81 3-09-81 3-09-81 3-09-81 3-09-81 3-09-81 3-09-81 3-10-81 3-10-81 3-09-81 3-09-81 3-09-81 to to to to to to to to 3-16-81 3-16-81 3-16-81 3-16-81 3-16-81 3-16-81 3-16-81 3-16-81
19/1 rec. 1/20/82 C-6 (can't.)
TABLE SAMPLING DATES FOR AIR SAMPLES r<<>NTH 2S2 5Sl STATION ~~
501 1001 16£1 lFl 2F2 3H3 MARCH 3-16-81 3-16-81 3-16-81 3-16-81 3-16-81 3-16-81 3-16-81 3-16-81 to to to to to to to to I
3-23-81 3-23-81 3-23-81 3-24-81 3-24-81 3-23-81 3-23-81 3-23-81 r i i
3-23-81 3-23-81 3-23-81 3-24-81 3-24-81 3-23-81 3-23-81 3-23-81 to to to to to to to to 3-30-81 3-30-81 3-30-81 3-31-81 3-31-81 3-30-81 3-30-81 3-30*81 e
APRIL 3-30-81 3-30-81 3-30-81 3-31-81 3-31-81 3-30-81 3-30-81 3-30-81 to
- to to to to to to to 4-06-81 4-06-81 4-06-81 4-06-81 4-06-81 4-06-81 4-06-81 4-06-81 4-06-81 4-06-81 4-06-81 4-06-81 4-06-81 4-06-81 4-06-81 4.:06-81 to to to to to to to to 4-13-01 4-13-81 4-13-81 4-14-81 4-14-81 4-13-81 4-13-81 4-13-81 4-13-81 4-13-81 4-13-81 4-14-81 4-14-81 4-13-81 4-13-81 4-13-81
. U1 to to to to to to to to N
4-20-81 4-20-81 4-20-81 4-20-81 4-20-81 4-20-81 4-20-81 4-20-81 4-20-31 4-20-81 4.-20-81 4-20-81 4-20-81 4-20.;81 4-20-81 4-20-81 to to to to to to to to 4-27-81 4-27-81 4-27-81 4-27-81 4-27-81 4-27-81 4-27-81 4-27-81 HAY 4-27-81 4-27-81 4-27-81 4-27-81 4-27-81 4-27-81 4-27-81 4-27-81
- -1 to to to to to to to to
~
5-04-81 5-04-81 5-04-81 5-04-81 5-04-81 5-04-81 5-04-81 5-04-81 I
5-04-81 5-04-81 5-04-81 5-04-81 5-04-81 5-04-81 5-04-81 5-04-81 e
to
'to to to to to to to 5-11-81 5-11-81 5-11-81
. 5-12-81.
5-12-81 5-11-81 5-11-81 5-11-81 5-11-81 5-11-81 5-11-81 5-12-81 5-12-81 5-11-81 5-11-81 5-11-81 to to to to to to to to 5-18-81 5-18-81 5-18-81 5-18-81 5-18-81 5-18-81 5-18-81 5-18-81..*
5-18-81 5-18-81 5-18-81 5-18-81 5-18-81 5-18-81 5-18-81 5-18-81 to to to to to to to to 5-26-81 5-26-81 5-26-81 5-27-81 5-27-81 5-26-81 5-26-81 5-26-81 5-26-81 5-26-81 5-26-81 5-27-81 5-27-8l 5-26-31 5-26-81 5-26-81 to to to to to to to to 6-01-81 6-01-81 6-01-81 6-01-81 6-01-31 6-01-31 6-01-31 6-01-81
110/l rec. 1/20/82 TABLE C-6 (,cont.)
SAMPLING DATES FOR AIR SAMPLES STATION NO.
M>NTH 2S2 5s*1 501 1001 16El lfl 2F2 3H3 i.:
l; JUNE 6-01-81 6-01-81 6-01-81 6-01-31 6-01-31 6-01-31 6-01-31 6-01-31 i !.
to to to to to to to to 1'
6-08-81 6-08-81 6-08-81 6-09-81 6-09-81 6-08-31 6-08-81 6-08-81 ji t*:
6-08-81 6-03-81 6-08-81 6-09-81 6-09-81 6-08-81 6-08-81 6-08-81
~ : i to to to to to to to to*
e 6-15..;81 6-15-81 6-15-81 6-15-81 6~15-81 6-15-81 6-15-81 6-15-81
)';
6-15-81 6-15-81 6-15-81 6-15-81 6-15-81 6-15-81 6-15-81 6-15-81 t ~
to to to to to to to to
~ :
6-22-81 6-22-81 6-22-81 6-23-81 6-23-81 6-22-81 6-22-81 6-22-81
~ :
6-22-81 6-22-81 6-22-81 6-23-81 6-23-81 6-22-81 6-22-81 6-22-81 to to to to to to
.to to
.6-29-81 6-29-81 6-29-81 6-30-81 6-30-81 6-29-81 6-29-81 6-29-81 JULY 6-29-81 6-29-81 6-29-81 6-30-81 6-30-81 6-29-81 6-29-81 6-29-81 to to to to to to to
- to U'1 w
7-06-81 7-06-81 7-06-81 7-06-81 7-06-81 7-06-81 7-07-81 7-06-81 7-06-81 7-06-81 7-06-81 7-06-81 7-06-81 7-06-81 7-07-81 7-06-81 I
to to to to to to to to 7-13-81 7-13-81 7-13-81 7-14-81 7-14-81 7-13-81 7-13-81 7-13-81
~ ?
7-13-81 7-13-81 7-13-81 7-14-81 7-14-81 7-13-81 7-13-81 7-13-81 to to to to to to to to I
7~20-81 7-20-81 7-20-81 7-21-81 7-21-81 7-20-81 7-20-81 7-20-81 e
7-20-81 7.;.20-01 7-20-81 7-21-81 7-21-31 7-20-81 7-20-81 7-20-81 to to to to to to to to 7-27-81 7-27-81 7-27-81 7-28-31 7-28-81 7-27-81 7-27-81 7-27-81 7-27-81 7-27-81 7-27-81 7-28-81 7-28-81 7-27-81 7-27-81 7-27-81 to to to to to to to to 8-03-81 B-03-81 8-03-81 8-03-81 8-03-81 8-03-81 8-03-31 8-03-81 AUGUST 8-03-81 8-03-81 8-03-81 8-03-81 8-03-81 8-03-81 8-03-81 8-03-81 to to to to to to to to 8-10-81 8-10-81 8-10-~1 8-11-81 8-11-31 8-10-81 8-10-81 8-10-81 8-10-31 8-10-81 8-10-31 8-11-81 8-11-81 8-10-81 8-10-81 8-10-81 to to to to to to to to 8-17-31 8-17-31 8-17-31 8-18-31 8-18-81 8-17-81 8-17-81 8-17-31
111/1 rec. 1/20/82 C-6 (cont.)
TABLE SAMPLING DATES FOR AIR SAlf>LES STATION NO.
MONTH 2S2 5S'l 5Dl lODl 16El lfl 2F2 3H3 AUGUST B-17-81 8-17-81 8-17-81 8-18-81 8-18-81 8-17-81 8-17-81 8-17-81 to to to to to to to to 8-24-81 8-24-81 8-24-81 8-25-81 8-25-81 8-24-81 8-24-81 8-24-81 8-24-81 8-24-81 8-24-81 8-25-81 8-25-81 8-24-81 8-24-81 8-24-81 to to to to to to to to
\\
8-31-81 8-31-81 8-31-81 8-31-81 B-31-81 8-31-81 8-31-81 0-31.:.81 e
i I
SEPTEMJER 8-31-81 8-31-81 8-31-81 8-31-81 8-31-81 8-31-81 8-31-81 8-31-81 to
- to to to to to to to i
9-08-81 9-08-81 9-08-81 9-08-81 9-08-81 9-08-81 9-08-81 9-08-81 9-08-81 9-08-81 9-08-81 9-08-81 9-08-81 9-08-81 9-08-81 9-08-81 to to to to to to to to 9-14-81 9-14-81 9-14-81 9-15-81 9-15-81 9-14-81 9-14-81 9-14-81 9-14-81 9-14-81 9-14-81 9-15-81 9-15-81 9-14-81 9-14-81 9-14-81
. U'1 to to to to to to to to
...i::.
9-21-81 9-21-81 9-21-81 9-21-81 9-21-81 9-21-81 9-21-81 21-81 9-21-81 9-21-81 9-21-81 9-21-81 9-21-81 9-21-81 9-21-81 9-21-81 to to to to to to to to 9-28-81 9-28-81 9-28-81 9-28-81 9-28-81 9-28-81 9-28-81 9-28-81 OCTOBER*
9-28-81 9-28-81 9-28-81 9-28-81 9-28-81 9-28-81 9-28-81 to to to to to to to 10-05-81 10-05-81 10-05-81 10-05-81 10-05-81 10-05-81 10-05-81 10-05-81 10.. 05-81 10-05-81 10-05-81 10-05-81 10-05-81 10-05-81 e
to "to to to to to to 10-13-81 10-13-81 10-13-81 10".'13-81 10-13-81 10-13-81 10-13-81 10-13-81 10-13-81 10-13-81 10-13-81 10-13-81 10-13-81 10-13-81 to.
to to to to to to 10-19-81 10-19-81 10-19-81 10-19-81 10-19-81 10-19-81 10-19-81 10-19-81 10-19-81 10-19-81 10-19-81 10-19-81 10-19-81 10-19-81 to to to to to to to 10-26-81 10-26-81 10-26-81 10-27-81 10-27-81 10-26-81 10-26-81 10-26-81 10-26-81 10-26-81 10-27-81 10-27-81 10-26-81 10-26-81 to to to to to to to 11-02-81 11-02-81 11-02-81 11-02-81 11-02-81 11-02-81 11-02-81
- 12/1 rec. 1/20/82 TABLE C-6 (cont.)
SAMPLING DATES FOR AIR SAMPLES STATION NO.
fil)NTif 252 551 501 1001 16El lFl 2F2 3H3 NOVEfeER 11-02-81 11-02-81 11-02-81 11-02-81 11-02-81 11-02-81 11-02-81
- to to to to to to to 11-09-81 11-09-81 11-09-81.
11-10-81 11-10-81 11-09-81 11-09-81 11-09-81 11-09-81 11-09-81 11-10-81 11-10-81 11-09-81 11-09-81 to to to to to to to 11-16-81 11-16-81 11-16-81 11-16-81 11-16-81 11-16-81 11-1&-81 e
11-16.;81 11-16-81 U-16-81 11-16-81 11-16-81 11-16-81 11-16-81 to to to to to to to 11-23-81 11-23-81 11-23-81 11-24-81 11-24-81 11-23-81 11-23-81 11-23-81 11-23-81 11-23-81 11-24-81 11-24-81 11-23-81 11-23-81 to to to to to to to 11-30.;.81 11-30-81 ll-:IJ-81 12-01-81 12-01-81 11-30-81 ll-:IJ-81 U1 DECEMJER 11-~-81 11-30-81 11-30-81 12-01-81 12-01-81 11-30-81 11-30-81 U1 to to to to to to to 12-07-81 12-07-81 12-07-81 12-07-81 12-07-81 12-08-81
. 12-07-81 12-07-81 12-07-81 12-07-81 12-07-81 12-07-81 12-08-81 12-07-81 to to to to to to to 12-14-81 12-14-81 12-14-81 12-14-81 12-15-81 12-14-81 12-14-81 12-14-81 12-14-81 12-14-81 12-14-81 12-15-81 12-14-81 12-14-81 to to to to to to to 12-21-81 12-21-81 12-21-81 12-22-81 12-22-81 12-21-81 12-21-81 12-21-81 12-21-81 12-21-81 12-22-81 12-22-81 12-21-81 12-21-81 e
to to to to to to to 12-28-81 12-28-81 12-28-81 12-29-81 12-29-81 12-28-81 12-28-81 Afr Particulate program dfscontfnued by RnC after the thfrd quarter.
. -_ i
~ -
TABLE C-7 CONCENTRATIONS OF TRITIUM. GROSS ALPHA AND GROSS BETA EMITTERS IN PRECIPITATION STATION SA-RWA-2F2 Results in Units of pCill +/- 2 si!JIB COLLECTION PERIOD H-3*
ALPHA BETA 12-29-80 to 2-02-81
<123
<1.1 46+/-5 2-02-81 to 3-03-81
<113
<0.7 35+/-4 3-03-81 to 3-30-81 124+/-59 2.3+/-1.2 67+/-7 3-30-81 to 4-28-81
<100
<0.6 70+/-7 4-28-81 to 6-01-81
<87
<0.9 51+/-5 6-01-81 to 6-29-81 86+/-68
<0.8 19+/-2 6-29-81 to 8-03-81
<109 1.2+/-0.8 30+/-4 8-03-81 to 9-01-81 111+/-74
<0.9 9.1+/-1.6 9-01-81 to 9-28-81
<124
<1.2 8.1+/-1.6 9-28-81 to 11-02-81
<0.7 5.9+/-1.9 11-02-81 to 11-30-81 1.2+/-0.8 14+/-3 11-30-81 to 12-29-81
<0.6 4.7+/-1.8 Average 30+/-48 Program discontinued by RMC after the third quarter.
56
01 TABLE C-8 CONCIENTRATIONS OF ~TRONTIUM-89* AND.:go AND rJUfll\\ EMITIERS** IN QUARTERL y COMPOSITES OF PRECIPITATION STATION:
SA-RWA-2F2 Results in Units of pCi/1 +/- 2 sigma 12-29-80 3-~-oo 6-29-31 9-28-81 to to to to NUCLIDE 3-30-81 6-29-81 9-28-81 12-29-81 Sr-89 7.5+/-0.9
. 3.4+/-0.7 0.6+/-0.4
<0.8 Sr-90
<0.9
- o.n+/-0.4
<0.4 1.4+/-0.3 Be-7 35+/-10 44+/-8 24+/-8
<7.6 Zr-95
'4.3+/-1.3
<0.8+
<0.8+
<0.6+
l'l>-95 11+/-1
+
<0.8
<0.8+
<0.6+
Ru-103 4.7+/-1.2 Ce-141
+
3.4+/-1.7 Sr-89 results are corrected for decay to sample stop date.
All other gamma emitters searched for were <LLD; t.Ypical LLDs are given in Table C-33. Nuclides not routinely searched for are* indicated by a dash (-).
LLD for Zr-95 and Nb-95 is that of Zrtl>-95.
e
- I
~
r l
!1
~ I
~.
i.
'*I 1
-~**~*-**~..
. - ~ ***- *-*.
e e
TABLE C-9 DIRECT RADIATION MEASUREMENTS - r<<lNTHLY llD RESULTS mrad/standard month*
STATION NlttBER JANUARY FEBRUARY MARCH APRIL MAY JUNE SA-IDM-2S2 5.00+/-0.43 6.38+/-0.52
- 5.83+/-0.14
- 5.00+/-0.68
'4.82+/-0.13 5.18+/-0.30 SA-1Il4-5Sl 4.53+/-0.24 5.33+/-0.94 5.15+/-0.34 4.58+/-0.77 3.65+/-0.34 4.44+/-0.39 SA-IDM-6S2 5.11+/-0.34 6.02+/-0.36 5.65+/-0.37 4.77+/-0.75 4.16+/-0.14 4.33+/-0.58 SA-IDM-7Sl 6.18+/-0.67 7.43+/-0.41 7.35+/-0.96 5.63+/-1.31 5.34+/-0.18 5.28+/-0.73 SA-IDM-lOSl 8.25+/-0.48
- 0.31+/-0.69 7.92+/-1.~
5.97+/-0.89 5.78+/-0.46 6.00+/-0.87 SA-IIJll-llSl 16.51+/-0.93 12.02+/-0.59 9.00+/-0.52 7.00+/-0.82 6.98+/-1.19 5.74+/-0.31 SA-I l>>l-501 4.77+/-0.50
- 5.01+/-0.33 5.45+/-1.10
'4.61+/-0.74 4.31+/-0.16 4.67+/-0.53 SA-IDM-1001 5.69+/-0.42 6.42+/-0.56
- 6.26+/-0.66 6.10+/-0.36 4.73+/-0.69 5.58+/-0.54 SA-IDM-1401 5.64+/-0.24 6.64+/-0.33 6.42+/-0.70 5.56+/-0.31 4.87+/-0.29 4.96+/-0.43 SA-IDM-2El 5.13+/-0.10 6.25+/-0.63 6.43+/-1.28
- 5.48+/-0.62*
4.39+/-0.65
. 5.17+/-0.19 SA-I 1>>1-3E 1 4.75+/-0.17
'6.09+/-0.84 5.89+/-0.89 5.04+/-0.14 4.28+/-0.23 4.37+/-0.59 SA-IDM-13El 4.93+/-0.37 6.16+/-0.92 6.18+/-0.54 5.26+/-0.54
. 4.35+/-0.16 4.61+/-0.57 SA-IDM-16El 5.39+/-0.26 6.86+/-0.52 6.75+/-0.75
- 5.46+/-0.38 4.95+/-0.58 4.93+/-0.32 SA-IDM-lFl 5.3>+/-0.35 6.55+/-0.59 6029+/-0.06
- 5.31+/-0.66 4.94+/-0.59 5.39+/-0.44 SA-ID."1-2 F2 4.40+/-0.21 5.10+/-0.32 5.07+/-0.65 4.39+/-0.16 3.63+/-0.69 4.24+/-0.57 SA-IDM-5Fl 4.00+/-0.14 6.17+/-1.02 6.45+/-0.30
. 4.65+/-0.13 4.55+/-0.37 4.99+/-0.43 SA-I Il4-6 Fl 4.22+/-0.16 5.24+/-0.41 5.26+/-0.78
. '4.36+/-0.33 3.60+/-0.30 4.13+/-0.56 SA-I 1>>1-7F2 3.61+/-0.22 4.49+/-0.41
. 4.77+/-0.51
'3.87+/-0.20 3.23+/-0.61 4.21+/-0.23 SA-I DM-11 Fl 5.62+/-0.31 6.99+/-0.83 6.64+/-0.25 5.77+/-0.79 4.37+/-0.36 5.66+/-1.10 SA-IDM-13Fl 5.01+/-0.53 6.02+/-0.18 5.98+/-0.26
. 5.15+/-0.41 4.73+/-0.31 4.33+/-0.36 SA-Il>>l-3Gl 5.69+/-0.43 6.87+/-0.53 6.63+/-0.80 5.71+/-0.22 4.97+/-0.67 5.96+/-0.51 SA-I Il4-2H 1 5.61+/-0.23 6.92+/-0.77 7.14+/-0.92 5.46+/-0.64 5.91+/-0.93 5.23+/-0.72 SA-IDM-3Hl 5.58+/-0.84 6.87+/-0.22 6.65+/-0.88 5.73+/-0.85 5.03+/-0.81 5.86+/-0.25 SA-1Il4-3H3 5.23+/-0.38 6.50+/-0.58 6.52+/-0.70 5.84+/-0.18 5.01+/-0.58 5.55+/-0.49 AVERAGE 5.71+/-4.91 6.56+/-2.82 6.32+/-1.88 5.32+/-1.56 4.72+/-1.62 5.08+/-1.14 STATION NUMBER JULY AUGUST SEPTEHBER OCTOBER NOVEMBER DECB*IDER AVERAGE SA-IIJll-2S2 4.71+/-0.57 4.75+/-0.17 5.54+/-0.31 4.89+/-0.33 4.88+/-0.57 5.72+/-1.06 5.23+/-1.05 SA-IDM-5Sl 4.61+/-0.30 4.05+/-0.25 4.56+/-0.23 4.65+/-0.78 4.25+/-0.23 4.97+/-0.33 4.56+/-0.92 SA-IDM-6S2 5.62+/-0.42
- 4.60+/-0.27 4.96+/-0.20 5.60+/-0.47 5.16+/-0.39 5.73+/-0.39 5.14+/-1.19 SA-IDM-751 5.42+/-0.64 5.28+/-0.45 6.10+/-0.91 6.29+/-0.70 5.61+/-0.33 6.13+/-0.41 6.00+/-1.49 SA-I DM-lOS 1
- 6. 35+/-1.13 5.34+/-0.49 6.29+/-0.38 6.06+/-0.21 6.81+/-0.64 6.48+/-0.49 6.63+/-1.99 SA-IDM-llSl 5.53+/-1.07 4.64+/-0.27 5.07+/-0.56 5.78+/-0.54 9.24+/-0.90 5.73+/-0.46 7.34+/-6.96 SA-IDM-501 4.64+/-0.39 4.. 66+/-0.18 4.99+/-0.26 5.31+/-1.29 4.83+/-0.63 5.51+/-0.19 4.96+/-0.91 SA-IDM-1001 6.13+/-1.03 5.43+/-0.41 5.91+/-0.51 5.94+/-0.29 5.37+/-0.61 5.66+/-0.30 5.77+/-0.93 SA-IDM-1401 7.27+/-3.21 5.54+/-0.60 5.74+/-0.90 5.68+/-0.:JJ 5.26+/-0.77.
5.98+/-0.30 5.80+/-1.39 SA-Il>>l-2El 5.29+/-0.22 4.88+/-0.32
- 5.74+/-0.25 5.39+/-0.80 5.08+/-0.79 5.71+/-0.24 5.41+/-1~13 SA-IDM-3El 5.65+/-0.61 4.87+/-0.81 5.43+/-0.48 5.26+/-0.31 4.71+/-0.19 5.50+/-0.45 5.20+/-1.07 SA-IDM-13El 5.02+/-0.54 4.80+/-0.89 4.91+/-0.56 5.49+/-0.15 4.81+/-0.56 5.25+/-0.43 5.15+/-1.13 SA-I DM-16El 5.85+/-0.71 4.83+/-0.48 5.84+/-0.79 5.14+/-1.25 5.09+/-0.40 5.47+/-0.23 5.55+/-1.35 SA-I l>>l-1 Fl 5.20+/-0.38 5.00+/-0.47 5.35+/-0.91 5.68+/-0.25 5.63+/-0.64 5.80+/-0.20 5.54:!0.98 SA-Il>>l-2F2 4.02+/-0.23 3.95+/-0.51
'4.35+/-0.38 4.37+/-0.55 4.22+/-0.25 4.56+/-0.77 4.36+/-0.84 SA-IIJll-5Fl 4.85+/-0.47 4.84+/-0.64 5.10+/-0.25 5.73+/-0.46
- 5.26+/-0.48
- 5.26+/-0.83 5.22+/-1.20 SA-IDM-6Fl 4.10+/-0.20 3.96+/-0.76 4.52+/-0.64 4.63+/-0.91 4.15+/-0.34 5.14+/-0. 75 4.45+/-1.07 SA-IDM-7F2 3.59+/-0.43
'3.77+/-0.23 3.99+/-0.40
- 4.26+/-0.46 3.93+/-0.37 4.87+/-0.30 4.05+/-0.97 SA-IDM-11 Fl 5.74+/-0.44
- 5.24+/-0.83 6.29+/-0.73 6.32+/-0.86
- 5.66+/-0.01 6.04+/-0.58 5.90+/-1.13 SA-I 1Jtl-l 3Fl 4.91+/-0.28 4.86+/-0.83 5.65+/-0.21 5.37+/-0.64 5.22+/-0.65 5.78+/-0.47 5.30+/-0.91 SA-I l>>l-3Gl 6.04+/-1.05 5.3U0.41 5.84+/-0.61 5.95+/-0.92
- 5.56+/-0.45 5.80+/-0.36 5.36+/-1.03 SA-IIJ1-2Hl 5.90+/-0.91 5.27+/-0.86 5.78+/-0.42
. 5.94+/-0.95 5.63+/-0.32 6.29+/-0.56 5.92+/-1.20 SA-IDM-3Hl 5.21+/-0.63 5.19+/-0.40 5.92+/-0.51 5.97+/-0.28 5.10+/-0.54 6.51+/-0.56 5.31+/-1.24 SA-Il>>l-3H3 5.15+/-0.61 5.29+/-0.58 5.97+/-0.76 5.86+/-0.71 5.88+/-0.73 6.20+/-0.46 5.75+/-1.02 AVERAGE 5.28+/-1.62 4.85+/-0.99 5.41+/-1.26 5.48+/-1.15 5.31+/-2.10 5.67+/-0.99 5.47+/-2.32 The standard nDnth ~ 3>.4 days.
58
TABLE C*lO
~
DIRECT RADIATION MEASUREMENTS
- QUARTERLY TLD RESULTS mrad/standard month*
JANUARY APRIL JULY OClOBER to to to to AVERAGE STATION NIMIER MARCH JUNE SEPTEMBER DECEHBER SA*llJ1-2S2
- 5.67+/-0.18 4.70+/-0.40 4.09+/-0.68 4.93+/-0.73 4.85+/-1.31 SA-IDM-551 5.06+/-0.23
'3.93+/-0.43 4.32+/-0.19 4.28+/-0.61 4.40+/-0.95 SA-I C>>l-652
'6.00:t0.82
'4.73:t0.39
- 4. 74:t0. ll 5.02:t0.62 5.12+/-1.20 SA-llJ1-7Sl
'6.77+/-1.01
. 5.53+/-0.29 5.82+/-0.41 5.99+/-0.14 6.03+/-1.06 SA-IIJ1-10Sl
. 8.93+/-0.44
'6.26:t0.49 5.32+/-0.46
- 5.os+/-0.60 6.59+/-3.21 SA* I IJt-llS 1 14.45+/-1.57 6.29:t0.80
'4.94+/-0.78 7.03+/-0.93 8.18+/-8.54 SA-11Jt-5Dl
. 5.:h+/-0.48
'4.59+/-0.64 4.68+/-0.31 5.11+/-0.51
'4.92+/-0.69 SA-111.,* lODl
'6.29+/-0.41
- 5.25+/-0.37
- 5.36+/-0.56 5.49+/-0.36 5.60+/-0.94 SA-11Jt-14Dl
'6.14+/-0.58
'4.92+/-0.52
- 5.13+/-0.31
. 5.71+/-0.22 5.48+/-1.11 SA-Im-2El
'6.41+/-0.29
'4.87+/-0.30
'4.97+/-0.41 5.:11+/-0.45 5.39+/-1.41 SA-IIJ1-3El
- 5.95+/-0.rn
. 4.60+/-0.43 4.83+/-0.34
. 5.10+/-0.22 5.12+/-1.18 SA-I 1Jt-13El
- 5.62+/-0.26
'4.43+/-0.15 4.81+/-0.40 5.10+/-0.36 4.99+/-1.00 SA-IIJ1-16El 6.18+/-0.52
'4.97+/-0.37 5.16+/-0.20 5~65+/-0.26 5.49+/-1.08 SA-1114-lFl
'6.41+/-0.46 4.89+/-0.17
- 5.02+/-0.33 5.46+/-0.18
- 5.45+/-1.38 SA-IDM-2F2
- 5.15+/-0.45
. 3.92+/-0.22
'3.87+/-0.32
. 4.01+/-0.44 4.24+/-1.22 U1 SA-I IJ.t-5Fl
- 5.16+/-0.81
'4.69+/-0.25 4.67+/-0.90 4.72+/-1.15 4.g.fi+/-l.07 I~
SA-llJ1-6Fl
'4.82+/-0.30
'3.94+/-0.03 4.11+/-0.12 4.75+/-0.39 4.41+/-0.89 SA* I IJt-7F2
'4.39+/-0.3)
. 3.31+/-0.79 3.51+/-0.32 4.03+/-0.28 3.81+/-0.98 SA-IDM-llFl 6.35+/-0.99 5.71+/-0.53 5.81+/-0.16
- s.65+/-0.37 5.88+/-0.64 SA-llJ1-13Fl 6.26+/-0.54 4.95+/-0.18 5.11+/-0.43 4.97+/-0.36
- 5.32+/-1.26 SA-IDM-361
'6.45+/-0.84 5.12+/-0.24 5.33+/-0.09 5.42+/-0.30 5.58+/-1.19 SA-1114-2Hl 6.58+/-0.49
. 4.90+/-0~ 15
. 5.29+/-0.52 5.83+/-0.33
- 5.65+/-1.46 SA*IDM-3Hl 6.57+/-0.58 5.46+/-0.97 5.67+/-0.46 5.75+/-0.67 5.86+/-0.97 SA-I 1Jt-3H3 5.97+/-0.82 5.03+/-0.30 5.14+/-0.48 5.73+/-0.48 5.47+/-0.91 AVERAGE
'6.40+/-3.84 4.87+/-1.40 4.90+/-1.18 5.29+/-1.34 5.37+/-2.52 e
The standard nnnth = 30.4 days.
TABLE C-11 DIRECT.RADIATION r.£ASUREMENTS - SEHI-ANNUAL TLD RESULTS mrad/standard 111>nth*
SEPTEMBER APRIL STATION r<<l.
TO TO AVERAG'E MARCH SEPTEHBER SA-IDM-402
- 5.91+/-0.45
- '4.97+/-0.46 5.44+/-1.33 SA-l()l-9El.
- 6.13+/-0.90 5.52+/-0.74 5.83+/-0.86 SA-I IJil-llE2
- 6.43+/-0.57 5.81+/-0.68 6.12:!0~88 SA-IDM-12El 6.12+/-0.33 5.77+/-0.27 5.95+/-0.49 SA-IDM-2F5 5.28+/-0.19 4.98+/-0.32 5.13+/-0.42 SA-l()l-3F2 5.27+/-0.24 4.61+/-0.32 4.94+/-0.93 SA-Ior~3F3 4.92+/-0.31 4.40+/-0.26 4.66+/-0.74 SA-IDM-10F2
. 5.83+/-0. 70 5.50+/-0.13 5.67+/-0.47 SA-I lJ.1-12Fl 5.88+/-0.90 5.34+/-0.33 5.61+/-0.76 SA-IDM-13F2 5.76+/-0.87 5.12+/-0.21 5.44+/-0.91 SA-Im-13F3 5.80+/-0.93 5.11+/-0.33 5.46+/-0.98 SA-IIJ1-14F2 5.58+/-1.06 5.02+/-0.33 5.30+/-0.79 SA-IDM-15F3 6.11+/-0.59 5.84+/-0.39 5.98+/-0.38 SA-IDM-16F2 4.88+/-0.33 4.95+/-0.74 4.92+/-0.10 SA-IDM-163 5.91+/-0.09 6.30+/-0.74 6.11+/-0.55 SA-IDM-1061 5.55+/-0.18 5.71+/-0.51 5.63+/-0.23 SA-IDM-1661 5.84+/-0.22 6.23+/-0.81 6.04+/-0.55 AVERAGE 5.72+/-0.85 5.36+/-1.07 5.54+/-1.02 The standard month = 30.4 days.
. 60
TABLE C-12 CONCENTRATIONS OF TRITIUM IN SURFACE WATER Results in Units of pCi/1 +/- 2 sigma i r STATION NO.
2-17-81*
3-04-81 4-10-81 5-06-81 6-01-81 7-08-81 I ' ' ' i SA-SWA-llAl 412+/-79
<102
<103
<89 97+/-62
<115 i
SA-SWA-12Cl 99+/-76 75+/-65 206+/-63 58+/-54
<100
<115
- SA-SWA-7E1 102+/-76
<102
<103
<94
<100
<115 e
f.
SA-SWA-1F2 123+/-76
<102
<103 77+/-58
<87
<115 f
SA-SWA-16F1
'(123 77+/-65 238+/-63
<89
<100 128+/-64 i
i Average 172+/-270 92+/-29 151+/-132 81+/-29 97+/-11 118+/-12 i
t I* i O'I STATION NO.
8-05-81 9-08-81 10-07-81"'*
11-03-81 12-14-81 AVERAGE i
SA-SWA-11Al
<130 322+/-70 171+/-248 SA-SWA-12Cl
<131 246+/-69 113+/-73 113+/-64 93+/-71 123+/-111 SA-SWA-7El 133+/-8) 279+/-69 129+/-124 SA-SWA-1F2
<130
- 111+/-69 130+/-143 i*
SA-SWA-16 Fl
<131 82+/-65 195+/-74
<102 104+/-71 124+/-100 e
Average 131+/-2 246+/-192 154+/-116 108+/-16 99+/-16 134+/-146 No surface water sa1111les were collected in January.
Program was reduced after the third quarter. Station SWA-12Cl continues to be analyzed for trith111 on a roonthly basis.by Rf.tC; in addition, one station a quarter.15 *selected by PSE&G to receive a roon-thly tritium analysis.
TABLE C-13 CONCEITTRATIOHS OF GROSS ALPHA EMITTERS IN SURFACE WATER Results in Units of pCi/1 +/- 2 sigma STATION NO.
2-17-81*
3-04-81 4-10-81 5-06-81 6-01-81 7-03-81 SA-SWA-llAl
<0.3
<0.4
<0.3
<0.6
<0.5
<0.5 SA-SWA-12C1
<0.3
<0.4
- 0.2+/-0.2
<0.6
<0.3
<0.5 SA-SWA-7E1
<0.3
<0.4
<0.3
<0.5
<0.5
<0.5 SA-SWA-1F2
<0.3
<0.4
<0.3
<0.6
<0.5
<0.5 e
SA-SWA-16Fl
<0.4
<0.4
<0.3
<0.6
<0.8
<0.5 STATION NO.
8-05-81 9-08-81 10-05-81 11-03-31 12-14-31
. en N
SA-SWA-11A1
<0.4
<0.4
- 0.8+/-0.4 0.3+/-0.2 0.3+/-0.2 SA-SWA-12C1
<0.4
<0.4 0.4+/-0.3 0.2+/-0.2
<0.2 SA-SWA-7El
<0.4
<0.4
<0.5 0.3+/-0.3
<0.2 SA-SWA-1F2
<0.4
<0.4
<0.4 0.2+/-0.2 0.2+/-0.1 SA-SWA-16F1
<0.4 0.3+/-0.3 0.4+/-0.3
<0.5
<1.3 No surface water samples were collected in January.
e
TABLE C-15 CONCENTRATIONS OF r1'\\rfilA ElUTIERS* IN SURFACE WATER Results in Units of pCi/l +/- 2 sigma STATION r<<>.
NUCLIDE 2-17-81**
3-04-31 4-10-81 5-06-81 6-01-81 7-08-81 SA-SWA-llAl K-40 84+/-10 78+/-9(l)
<11 66+/-9 45+/-8 33+/-10 SA-SWA-12Cl K-40 45+/-9 46+/-8 39+/-8 56+/-9 22+/-3 47+/-10 SA-SWA-7El K-40 85+/-9 77+/-9 71+/-9 120+/-12 76+/-10 83+/-10 e
SA-SWA-1F2 K-40 30+/-8
<11 20+/-8 27+/-7 24+/-9 23+/-9 SA-SWA-16Fl K-40 33+/-9 36+/-3 37+/-10 38+/-8 22+/-8 26+/-10 Average 55+/-54 50+/-57 36+/-46 61+/-72 38+/-47 42+/-49
. en STATION r<<>.
NUCLIDE 8-05-81 9-08-81 10-05-81 11-03-81 12-14-81 AVERAGE
..i::.
SA-SWA-llAl K-40 43+/-12 67+/-9 74+/-9 68+/-8 100+/-10 61+/-51 SA-SWA-12Cl K-40 59+/-9 72+/-9 50+/-10 85+/-9 69+/-10 54+/-35 SA-SWA-7El K-40 120+/-13 99+/-10 49+/-10 95+/-10 89+/-9 88+/-42 SA-SWA-1F2 K-40 27+/-10 68+/-9 90+/-17 50+/-9 68+/-9 40+/-51 SA-SWA-16Fl K-40 70+/-9 58+/-9 34+/-10 36+/-8 99+/-11 44+/-45 Average 64+/-71 73+/-31 59+/-45 67+/-49 85+/-31 57+/-55 By ganma spectrometry, all other gillmla emitters searched for were <LLD; typical LLDs are given in Table C-33.
No surface water samples were collected in January.
(1)
ZrNb-95 was also observed in this sample with a concentration of 1.8+/-0.8 pCi/l.
. en CJ'1 TABLE C-16 CONCENTRATIONS OF STRONTIUM-89* AND -90 IN SURFACE WATER
~sults in Units of pC1/1.+/- 2 sigma 2-17-81**
4-10-81 7-08-81 10-05-81***
STATION t.o t.o to to NlJlllJER 3-04-81 6-01-81 9-08-81 12-14-81 Sr-89 Sr-90 Sr-89 Sr-90 Sr-89 Sr-90 Sr-89 Sr-90 SA-SWA-llAl
<0.6
<0.3
<0.9 1.3+/-0.4
<1.6
<0.9 SA-SWA-12Cl
<0.8
<0.4
- 0.6+/-0.6
<0.5
<1.1
<0.6
<0.8
<0.5 SA-SWA-7El 0.5+/-0.5
<0.4
<0.8
<0.5
<1.4
<0.7 SA-SWA-1F2
<0.7 0.4+/-0.2
- 0.1+/-0.5
<0.5 1.5+/-1.2
<0.4 SA-SWA-16Fl
<0.8 0.5+/-0.3
<1.0
<0.6
<2.3 1.1+/-0.8
<0.8
<0.5 Sr-89 results are corrected for dee~ to sa8'Jle stop date.
No surface water sa8'Jles were collected 1n January.
Strontium program was reduced after the third quarter. Station 12Cl continues to be analyzed for Sr-89 and -90 on a quarterly basis by RMC; 1n addition, one station a quarter is selected by PSE&G to receive a quarterly coll{losite Sr-89 and -90 analysis.
- A_._,
-................. ~--*---.............. --..... :*. ~~-~*-*-*---
.... -*b~~*:....... ".-:a.*...... * *. -.:~~... *:...................... ~:.~*
TABLE C-17 CONCENTRATIO~IS OF TRITIUM, GROSS ALPHA AND GROSS BETA EMITIERS, AND POTASSIUM-40 IN WELL WATER Results in Units of pCi/1 +/- 2 sigma STATION NO.
RADIOACTIVITY 1-12-81 2-09-31 3-09-81 4-13-81 5-11-81
~-03-31 SA-WWA-4Sl H-3
<105
<122
<102
<103
<94
<158 Alpha
<2.5 2.2+/-1.6
<2.4
<2.8.
<2.2
<3.6 Beta 11+/-3 15+/-2 11+/-2 12+/-3 13+/-3 13+/-2 K-40 12+/-1 9.7+/-1.0 9.5+/-1.0 9.5+/-1.0 9.2+/-0.9.
13+/-1 SA-WWA-5Dl H-3
<88
<122
<102
<103
<94
<174 Alpha
<1.8
<1.1
<1.8
<2.2
<1.8
<2.9 Beta 3.8+/-2.3 3.9+/-1.3
. 2.6+/-1.2 14+/-3 14+/-3 15+/-2 K-40 2.9+/-0.3 2.4+/-0.2 2.2+/-0.2 10+/-1 10+/-1 14+/-1 SA-WWA-3El H-3
<88
<122
<102
<103
<94
<174 Alpha
<2.1 1.7+/-1.4
<2.2
<2.4
<1.9
<2.9 Beta 9.2+/-2.6 8.4+/-2.3 7.6+/-1.5 8.6+/-2.2 8.3+/-2.4 9.3+/-1.6 K-40 8.2+/-0.8 8.2+/-0.8 9.2+/-0.9 7.2+/-0.7 6.8+/-0.7 9.6+/-1.0 STATION NO.
RADIOACTIVITY 7-13-81 8-10-31 9-14-81 10-13-81*
11-09-31 12-14-31 SA-WWA-4Sl H-3
<91
<130 106+/-74 (1)
Alpha
<1.9
<3.1
<1.6
<1.1
<2.1
<2.3 Beta 15+/-3 16+/-3 13+/-2 12+/-2 13+/-3 14+/-3 K-40 14+/-1 2.6+/-0.3 11+/-1 11+/-1 9.6+/-1.0 8.5+/-0.9 SA-WWA-5Dl H-3
<91
<130
<120 Alpha
<1.6
<2.4
<l.?.
<0.8
<1.7
<2.0 Beta 12+/-2 15+/-3 12+/-2 15+/-3 16+/-3 16+/-3 K-40
- 13+/-1 2.6+/-0.3 11+/-1 12+/-1 11+/-1 8.5+/-0.9 SA-WWA-3El H-3
<91 268+/-8?.
<120 Alpha
<1.0
<2.5
<1.3
<0.9
<1.6
<2.0 Beta 9.8+/-1.5 12+/-2 9.0+/-1.7 10+/-2 8.3+/-2.4 8.3+/-2.5 K-40 9.5+/-1.0 1.7+/-0.2 7.8+/-0.8 7.8+/-0.8 5.8+/-0.6 5.4+/-0.5 Tritium program was discontinued by ll*IC after the third quarter.
(1)
Station WWA-451 was collected on 9-24-81.
66
TABLE C-18
TABLE C-19 CONCENTRATIONS OF TRITJIJl'.f, GROSS ALPHA AND GROSS BETA B.flTIERS, AND POTASSIUl.f-40 rn RAW AND TREATED POTABLE WATER STATION SA-PWA-2F3 i i Results in Units of pC1/1 +/- 2 sigma
~-
I' RADIOACTIVITY JANUARY FEBRUARY MARCH APRIL MAY JUNE
)
lRaw)
H-3.
<123
<82
<95
<100
<87
<110 I*
Treated)
<123
<113
<95
<100
<87 134+/-69 e
- 't*
Alpha lRaw) 0.8+/-0.4 1.2+/-0.5 0.6+/-0.6
- 1.8+/-0.7 1.3+/-0.7 1.2+/-0.7 1.;
Treated)
- o.9+/-0.6 0.6+/-0.4
<1.0 0.9+/-0.7 0.6+/-0.6
<0.8 1:
Beta lRaw) 2.4+/-0.4 4.3+/-0.5 3.8+/-0.5
. 3.6+/-0.4 6.2+/-0.6 5.2+/-0.5 i*
Treated)
. 2.6+/-0.4 2.9+/-0.4 2.9+/-0.4 3.1+/-0.4
'3.7+/-0.5 3.1+/-0.4
(,
.f K-40 lRaw) 1.0+/-0.l 0.90+/-0.09 1.1+/-0.l 1.0+/-0.l 1.1+/-0.l 1.7+/-0.2 Treated) 1.1+/-0.1
- 1.0+/-0.1
- 1.1+/-0.1
- 1.0+/-0.1 1.2+/-0.l 1.7+/-0.2
. O"I l*
OJ RADIOACTIVITY Jll.Y AUGUST SEPTEMBER OCTOBER*
HOVEMBER DECEMBER.
AVERAGE
~Raw) 85+/-67
<120 74+/-73 Treated) 74+/-67
<120
<119 151+/-77
<116
<122 Alpha
~Raw)
<0.8
<0.6 1.0+/-0.5
<0.4 0.5+/-0.4
- 1.5+/-0.6 1.0+/-0.9 Treated)
<1.1 0.8+/-0.7
<0.5
<0.4
<0.6 1.1+/-0.6 0.8+/-0.5 e
I Beta
~Raw) 5.2+/-0.5 3.4+/-0.5 3.1+/-0.5 2.9+/-0.4 2.6+/-0.5 4.0+/-0.5 3.9+/-2.3 Treated) 3.4+/-0.5 2.7+/-0.4 2.3+/-0.4 1.4+/-0.4 1.9+/-0.5 2.6+/-0.5
- 2.7+/-1.3 K-40 lRaw) 1.7+/-0.2 2.2+/-0.2 1.1+/-0.l 1.1+/-0.l 1.4+/-0. l 2.0+/-0.2 1.4+/-0.9 Treated) 2.1+/-0.2 3.0+/-0.3 1.2+/-0.l 1.2+/-0. l 1.4+/-0.l 1.7+/-0.2 1.5+/-1.2 Tritil.111 program for raw potable water samples was discontinued by RMC after the third quarter.
. C'I l.O TABLE C-20 CONCENTRATIONS OF STRONTIUM-89* AND -90, AND CWltA BUTTERS-IN QUARTERLY COff>OSITES OF POTABLE WATER STATION SA-PWA-2F3 Results in Units of pCi/1 ~ 2 si!JllCl 1-01-81 4-01-81 7-01-81 10-01-81***
to to to to SAMPLE 3-31-81 6-30-81 9-30-81 12-31-81 Raw Sr-89
- o.1:t:0.5
<0.8
<0.8 Sr-90
<0.5 0.6:!:0.3 0.7+/-0.3 Gallllla Emitters
<LLD
<LLD
<LLD
<LLD Treated Sr-89 0.5+/-0.5
<0.9
<0.7
<0.7 Sr-90
<0.5 1.1+/-0.3 0.3:!:0.3
<0.5 Gamma Emitters
<LLD
<LLD
<LLD
<LLD Sr-89 results are corrected for dee~ to sa~le stop date.
All other ganrna emitters searched for were <LLDi typical LLDs are given in Table C-33.
Strontium program for raw potable water samples was discontinue~ by RMC after the third quarter.
e i
I
- I
- o TABLE c-21 CONCENTRATIONS OF Sr-39* AND -90 IN BENTHOS Results in Units of pCi/g(dry) +/- 2 sigma STATION NUMBER DATE Sr-39 SA-ESB-llAl 6-02-81
<0.5 9-09-81
<0.2 SA-ESB-12Cltc.'\\
6-02-81
<23 9-09-81
<1.6 SA-ESB-7El 6-02-81
<2.7 9-09-81
<2.1 SA-ESB-16Fl 6-02-81
<14 9-09-81
<169**
Sr-89 results are decay corrected to sample stop date.
tifgh MDL due to small sample size.
Sr-90 0.2+/-0.1
- e
- o.36+/-0.09
<6.9
<0.8
<0.8
<1.1
- 3.0+/-2.3
<86-
- 11..
TABLE C-22 CONCENTRATIONS OF STRONTilJH-90 AND GArl~* EMITTERS IN SEDIMENT**
Results in Units of pCi/g(dry) :t 2 sigma STATION NO.
SA-ESS*llAl SA-ESS-12Cl DATE 6-01-81 9-09-81 6*01-31 9-09-81*
Sr-90 0.04+/-0.04
<0.95
<O.l
<0.04 K-40 13+/-1 15+/-2 16+/-2 16+/-2 Co-60
<0.06 0.19+/-0.05
<0.04*
<0.04 Zr-95
<0.08
<0.1
<0.09
<0.09 fl>-95
<0.06
<0.09
<0.07
<0.07 Cs-137 0.13+/-0.03 0.17+/-0.03
<0.04
<0.04 Ra-226
- o.57+/-0.06
- o.65+/-0.08
- 0.60+/-0.06
- o.48+/-0.06 Th-232 0.7+/-0.l 0.9+/-0.1
. 0.86+/-0.09.
- o.9+/-0.1 All other ganma emitters <LLD; ~pical LLDs are given in Table C-33.
Sediment Si1J11>1es included associated benthic organisms.
SA-ESS-7El 6-01-01 9~09-81
<0.05
<0.04 13+/-1 13+/-1
<0.03
<0.05
<0.06
<0.07
- 0.09+/-0.03 *0.00+/-0.04
- 0.01+/-0.02 *0.04+/-0.02
. 0.49+/-0.05 0.46+/-0.05 0.58+/-0.07. 0.47+/-0.08 SA-ESS-16Fl 6-01-81 9-09-81
<0.06
<0.05 13+/-1 18+/-2
<0.06
<0.05
- 0.11+/-0.05
<0.08 0.44+/-0.05 (0.* 07. I
<0.04
<0.04
- o.51+/-0.oe 0.57+/-0.07 l.O:t0.1 1.0+/-0.1
TABLE C-23 CONCENTRATIONS OF IODINE-131 IN MILK Results* in Units of pCi/1 STATION NO.
"JANUARY**
- FEBRUARY MARCH APRIL MAY JUNE
'*'****I*
SA-MLK-13E3
<0.1
<0.1
<0.07
<0.09
<0.07
<0.09
<0.1
<0.08
<0.07
<0.08
<0.07
<0.07 SA-MLK-2F4
<0.09
<0.09
<0.07
<O.l
<0.07
<0.08
<0.09
<0.08
<0.07
<0.08
<0.08
<0.07 SA-MLK-5F2
<0.1
<0.1
<0.08
<0.09
<0.06
<0.08 e
<0.1
<0.08
<0.09
<0.07
<0.09
<0.08 SA-MLK-14F1
<O.l
<0.1
<0.08.
<0.09
<0.07
<0.09
<0.1
<0.07
<0.07
<0.08
<0.08
<0.08 SA-MLK-15Fl
<O.l
<0.1
<0.08
<0.09
<0.07
<0.09
<0.1
<0.07
<0.07
<0.09
<0.09
<0.08 SA-MLK-361
<0.2
<0.1
<0.09
<0.1
<0.06
<0.07
<0.* 09
<0.07
<0.08
<0.07
<0.08
<0.07 N
STATION NO.
JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER
. SA-rt..K-13E3
<0.1
<0.07
<0.09
<0.1
<0.07
<0.08
<0.08
<0'.05
<0.07
<0.09
<0.07
<0.06 SA-MLK-2F4
<0.09
<0.07
<0.08
<0.-07
<0.08
<0.1
<0.07.
<0.04
<0.07
<0~08
<0.09
<0.07 SA-MLK-5F2
<0.09
<0.07
<0.09
<0.09
<0.08
<0.08
<0.1
<0.05'
<0.09
<0.1
<0.08
<0.07 SA-MLK-14F1
<O.l
<0.08
<0.09
<0.1
<0.09
<0.09
<0.1
<0.04
<0.08
<0.1
<0.1
<0.08 SA-MLK-15F1
<0.1
<0.08
<0.09
<0.2
<0.1
<0.09.
<0.08
<0.05
<0.09
<0.1
<O.l
<0.08 SA-MLK-361
<0.09
<0.08
<0.09
<0.07
<0.09
<0.1
<0.09
<0.04
<0.07
<0.08
<0.09
<0.07 1-131 results decay corrected. to sample stop date.
Sampling dates can be found on Table C-25.
TABLE C-24 CONCENTRATIONS OF GAfl*IA EMITTERS* AND STRONTIUM-89** AND -90 IN HILK Results in Units of pC1/1 +/- 2 sigma STATION NO.
NUCLIDE JANUARY***
FEBRUARY MARCH APRIL MAY JUNE SA-MLK-13E3 K-40.
1400;tl40.
2000t200 1500+/-150 1400+/-140 1500+/-150 1300+/-130 Cs-137
<1.2
<1.2
<1.4.
'l.5tl.2
- 1.8+/-1.2 1.4+/-1.0 Sr-89
<3.J
<5.2
. <3~1
<31 (1)
<11 (2)
<9.6 (2)
<l.O
<1.7 "4.6+/-1.4
<a.*9 (1)
- 2~5+/-0.8
<1.4
. 1.5+/-1.2
. 3.8+/-1.4
- 1.7+/-1.2
- 1.7+/-1.2 2.3+/-1.1 Sr-89
'~2.5..
<13 (2)
<4.8
<6.5 ~
<1.9
<12 (2)
Sr-90 0.6+/-0.5
- 2.0+/-0.9 "3.5+/-2.0 4.2+/-2.3
- 2.3+/-0.8 2.4+/-1.1 SA-rt..K-5F2 K-40 1500+/-150 1500+/-150 1300+/-130 1700+/-170 1300+/-130 1400+/-140 Cs-137
<1.2
- 1.5+/-1.1
. 1.4+/-0.9 1.5+/-1.0
. 3.8+/-1.1 6.4+/-1.3 Sr-89
<2.7
<9.0 4.1+/-3.1
<5.4
<14 (2) 2.7+/-2.5 S'r-90 0.6+/-Q.5
. 3.9+/-1.8
- &.3+/-2.1 6.8+/-2.0 6.6+/-1.l
<2.2 c.v STATION NO.
NUCLIDE JULY AUGUST SEPTEMBER OCTOBER****
NOVEMBER DECEMBER SA-MlK-13E3 K-40 1300+/-130 1500+/-150 1400+/-140 1500+/-150 1600+/-160 1400+/-140 Cs-137
<1.6 2.6+/-1.1 5.6+/-1.3
<1.4
<1.2 2.0:1:1.1 Sr-89
<3~8
<2.9
<2.1
<4.3 Sr-90
. 1. 7+/-1.2 6.1+/-1.0 4.4+/-0.8 4.2+/-1.5 SA-MLK-2F4 K-40 1400+/-140 1300+/-130 1400+/-140 1500+/-150 1400+/-140 1900+/-190 Cs-137 2.7+/-1.2
<1.4
<1.2 3.0+/-1.3 2.5+/-1.2
<1.2 Sr-89
<3.6
<2.6
<6.6 1.8+/-1.5 Sr-90
<1.8
- 2.6+/-0.9 2.8+/-1.5
- 1.1+/-0.9 SA-MLK-5F2 K-40 1500+/-150 1400+/-140 1400+/-140 1500+/-150 1400+/-140 1600+/-160 Cs-137 6.1+/-1.4 3.1+/-1.2 3.9+/-1.4
<1.4
<1.2
<1.2 Sr-00
~5.* 1
<2.8 2.0+/-1.4 Sr-90 5.4+/-1.6 5.6+/-1.0 4.1+/-0.8
- ~
- 1
- _1:~
L STATION r<<:J.
NUCLIDE SA-MLK-14Fl K-40 Cs-137 Sr-89 Sr-90 SA-MLK-15Fl K-40 Cs-137 Sr-89 Sr-90 SA-MLK-361 K-40 Cs*137 Sr-89 Sr-90 STATION r<<:I.
NUCLIDE SA-MLK-14Fl K-40 Cs-137 Sr-89 Sr-90 SA-MLK-15Fl K-40 Cs-137 Sr-89 Sr-90 SA-MLK-361 K-40 Cs-137 Sr-89 Sr-90 TABLE C-24 (cont.)
CONCENTRATIOtlS OF GAMMA BUTTERS* AND STRONTIUM-39** AND -90 m MILK Results in Units of pCi/l +/- 2 sigma JANUARY***
FEBRUARY ltARCH APRIL 1500+/-150 1600+/-160 1400+/-140 1400+/-140
<1.2
<1.2
<1.2
<1.4
<2.7
<9.8 (2)
<3.2
<4.8
<1.0 2.9:t0.8
- 2.9+/-1.3 2.7+/-1.7 1600+/-160 1600+/-160 1600+/-160 1400+/-140
<1.4.
<1.2
<1.4 2.1+/-1.3
<12 (2) 8.5+/-5.0
<3.4
<25 (2) 2.8+/-1.0
- 4.7+/-2.4
- 4.0+/-1.4.
. 3.0+/-1.2 1500+/-150 1400+/-140 1400+/-140 1300+/-130
<1.4 1.5+/-1.1
<1.4
<1.2
<2.4
<6.9
<43 (2) 3.0+/-2.8
<0.7 4.4+/-1.4
. 3.9+/-1.4 4.1+/-1.6 JULY AUGUST SEPTEMBER OClOBER****
1300+/-130 1400+/-140 1300+/-130 1600+/-160
<1.6
<1.4 2.6+/-1.4
<1.4
<3.5
<2.8
<4.4 2.0+/-1.1
- 3.6+/-0.9 2.7+/-1.5 1400+/-140 1400+/-140 1300+/-130 1300+/-130 1.6+/-1.1
<1.2 2.6+/-1.3
- 2.7+/-1.4
<6.0
<3.0
<2.8 2.9:t0.8 4.1+/-1.0 2.9+/-1.0 1500+/-150 1200+/-120 1100+/-110 1300+/-130 2.8+/-1.5
<1.4
<1.4 3.1+/-1.2
<4.2
<2.4 3.3+/-1.7
<3.4 3.6+/-1.4 5.2+/-0.9 2.9+/-1.0 2.9+/-1.2 All otlier ganma emitters searched for were <LLD; typical LLDs are givan 1n Table C-33.
Sr-89 results are corrected for dece,y to sample stop date.
Sampling dates can be found on Table C-25.
MAY JUHE 1400+/-140 1400+/-140 2.6+/-1.1 5.0+/-1.3 3.5+/-1.6 2.9+/-1.6 3.1+/-1.0 3.4+/-0.9 1200+/-120 1400+/-140 J.1+/-1.0 3.5+/-1.3 4.7+/-2.7
<2.7 3.0+/-1.5 2.7+/-1.0 1700+/-170 1400+/-140 4.4+/-1.3 4.0+/-1.2 4.9+/-2.l 4.2+/-2.3 4.9+/-1.3
.5.;3+/-1.5 r<<:IVEMBER DECEMBER 1500+/-150 1600+/-160
<1.4
<1.4
<2.5 3.-1+/-1.0 1600+/-160 1400+/-140
<1.4
<1.2 1300+/-130 1400+/-140
<1.4
<1.4
<5.2
<1.a*
3.4+/-1.9 3.7+/-0.7
- Strontium program was reduced after the third quarter. Station MLK-3Gl continues to be analyzed for Sr-39 and -90 on a monthly basis UI by RMC; in addition. one station a month is selected by PSE~G to be analyzed for Sr-89 and -90.
High MDL due to low chemical yield.
High Mil. due to long dece,y period.
e
- i.
TABLE C-25 SAr4PLING DATES FOR IULK SAf.WLES MONTH 13E3 2F4 5F2 14Fl 15Fl 361 i'
! I.
JANUARY 1-05-81 1-05-81 1-04-81 1-04-81 1-04-81 1-04-81 I:
to to to to to to 1-06-81 1-06-81 1-05-81 1-05-81 1-05-81 1-05-81 I I r 1 1-19-81 1-19-81 1-16-81 1-18-81 1-18-81 1-18-81
~ i to to to to to to I,
- ~ !
1-20-81 1-20-81 1-19-81 1-19-81 1-19-81 1-19-81 I*
r, FEBRUARY 2-02-81 2-02-81 1-31-31 2-01-81 2-01-81 2-01-81 e
I 'i.
to to to to to to I
1 2-03-81 2-03-81 2-02-81 2-02-81 2-02-81 2-02-31 I) 2-17-81 2-16-81 2-14-81 2-17-81 2-17-81 2-17-31
- ~.
to to to to to to 2-18-81 2-17-81 2-17-81 2-18-81 2-18-81 2-18-81 MARCH 3-02-81 3-02-81 3-02-81 3-01-81*
3-01-81 3-01-81 to to to to to to I**
3-03-81 3-03-81 3-03-81 3-02-81 3-02-81 3-02-81
(.
'I U'1 3-16-81 3-16-81 3-15-81 3-15-81 3-15-Bl 3-15-81 1!
to to to to to to 3-17-81 3-17-Bl 3-16-81 3-16-81 3-16-81 3-16-81
- i.
I;.
APRIL 4-06-81 4-05-81 4-06-81 4-06-81 4-05-81 4-06-81 to to to to to to
' ~
4-07-81 4-06-81 4-07-81 4-07-81 4-07-81 4-07-81
~i ~*
L 4-20-81 4-19-81 4-20-81 4-21-Bl 4-19-Bl 4-20-81 to to to to to to e
4-2'1-81 4-20-81 4-21-Bl 4-21-81 4-20-81 4-21-Bl I
- t. j MAY 5-04-81 5-03-81 5-04-81 5-05-81 5-03-31 5-04-31
~: '
to to to to to to 5-05-81 5-04-81 5-05-81 5-05-81 5-05-81 5-05-31 5-13-81 5-17-81 5-17-31 5-17-81 5-17-81 5-18-31 to to to to to to 5-19-81 5-18-81 5-18-81 5-18-81 5-13-81 5-19-31 JUNE -
6-01-81 5-31-81 5-31-81 5-31-81 5-31-81 6-01-81 to to to to to to
~.
6-02-81 6-01-31 6-02-81 6-01-81 6-01-81 6-02-81 i _
6-15-81 6-14-81 6-13-81 6-14-81 6*14-81 6-15-81 to to to to to to 6-16-81 6-15-81 6-15-81 6-15-81 6-15-81 6-16-31
TABLE C-25 (cont.)
SAMPLING DATES FOR MILK SPJ~PLES r<<>NTH 13E3 2F4 5F2 14Fl 15Fl 3Gl JULY 7-06-81 7-06-81 7-05-81 7-06-81 7-06-81 7-05-81 to to to to to to 7-07-81 7-07-81 7-06-81 7-07-81 7-07-81 7-06-81 7-20-81 7-20-81 7-18-81 7-20-81.
7-20-81 7-19-81 to to to to to to 7-21-81 7-21-81 7-20-81 7-21-81 7-21-81 7-20-81 AUGUST 8-03-81 8-03-81 8-03-81 8-03-81 8-03-81 8-02-81 to to to to to to 8-04-81 8-04-81 8-04-81 8-04-81 8-04-31 8-03-81 8-17-31 8-17-81 8-16-81 8-17-81
. 8-17-81 8-16-81 to to to to to to 8-18-81 B-18-81 8-17-81 B-18-81
&-18-81 8-17-81 SEPTEMBER 9-07-81 9-08-81 9-07-81 9-08-81
- 9-oa-81
. 9-07-81 to to to to to to 9-09-81 9-09-81.
9-08-81 9-09-81 9-09-81 9-08-81
. O"I 9-21-81 9-20-81 9-19-81 9-21-81 9-20-81 9-21-81 to to to to to to 9-22-81 9-21-81 9-21-81 9-22-81 9-21-81 9-22-81 OCTOBER 10-05-81 10-04-81 10-05-81 10-04-81 10-04-81 10-05-81
. to to to
- to to to 10-06-81 10-05-81 10-06-81 10-05-81 10-05-81 10-06-81 10-19-81 10-18-81 10-17-81
. 10-19-81 10-18-81 10-19-81 to*
to to to to to 10-20-81 10-19-81 10-19-81 10-20-81
- 10-19-81 10-20-81 NOVEltlER 11-01-81 11-01-81 10-31-81
. 11-01-81 11-01-81 10.:31-81 to to to to to to 11-02-81 11-02-81 11-02-81 11-02-81 11-02.;.01 11-02-.81 11-16-81 11-15-81 11-16-81 11-15-81 11-15-31 11-16-81 to to to to to to 11-17-81 11-16-81 11-17-81 11-16-81 11-16-81 11-17-81 DECEMBER 12-06-81 12-07-81 12-07-81 12-07-81 12-07-81 12-06-81 to to to to to to 12-08-81 12-08-81 12-07-31 12-08-31 12-08-81 12-07-81 12-14-81 12-13-81 12-13-81 12-13-81 12-13-81 12-14-31 to to to to to to 12-15-81 12-14-81 12-14-81 12-14-81 12-14-81 12-15-81
TABLE C-26 CONCENTRATIONS OF GAii°"' EMITTERS* IN EDIBLE FISH Results 1n Units of pC1/g(wet) +/- 2 sigma STATION SAMPLING K-40 NlHJER DATE SA-ESF-llAl 6-01-81 to 2.9+/-0.3 7-02-81 8-27-81 to
- 3.5+/-0.4 9-18-81 SA-ESF-12Cl 6-01-81 to
. 3.2+/-0.3 7-02-81 8-27-81 to 3.8+/-0.4 9-18-81 SA-ESF-7El 6-01-81 Cs-137
<0.008
<0.009
<0.009
<0.01 to 3.3+/-0.3 0.016:t0.009 1-02.;31 8-27-81 to 4.6+/-0.5
<0.009 9-18-81 All other ganma emitters searched for were <LLD; i;Ypical LLDs are given in Table C-33.
e e
r TABLE C-27 CONCENTRATIONS OF STRONTIUM-89* AND -90, AND TRITIUM IN EDIBLE FISH SAMPLES Bones Flesh (pCi/g(dry) +/- 2 sigma)
Aqueous Fraction (pCi/l +/- 2 sigma)
Organfc Fraction (pC1/l +/- 2 sigma)
STATION DATE Sr-89 Sr-90 H-3 Hi-3 SA-ESF-llAl 6-01-81 e
to
<0.2
<0.08 82+/-63 317+/-72 7-02-81.
8-27-81 to
<0.08
<0.05
<110
<112
!11-18-81
$A-ESF-12Cl 6-01-81 to
<0.09 0.04+/-0.03
<86
<112 co 7-02-81 8-27-81 to
<0.06
<0.04
<110
<112 9-18-81 SA-ESF-7El 6-01-81 to
<0.09 0.05+/-0.03
<86 156+/-70 7-02-81
.e 8-27-81 to
<0.07
<0.04 83+/-68 126+/-69 "9-18-81 Sr-89 results are corrected for decay to sa111>le stop date.
TABLE C-28 CONCENTRATIONS OF GArff\\ EMITIERS* IN BLUE CRAB SAHPLES Results in Units of pCi/g(wet) +/- 2 sigma STATION NUrtJER DATE SAMPLE TYPE K-40 SA-ECH-llAl 6-01-81 e
to Flesh 1.7+/-0.2 7-02-81 8-27-81 to Flesh
- 2.1+/-0~2 9-18-81 SA-ECH-12Cl 6-01-81 to Flesh
- 2.s:t0.3 7-02-81 8-27-81
\\.0 to Flesh 2.1+/-0.2 9-18-81 All other ganna emitters <lLDi typical LLDs are given 1n Table C-33.
TABLE C-29 CONCENTRATIONS OF STRONTIUM-89* AND' -90 AND TRITIUf~ IN BLUE CRAB SAMPLES STATION Sr-89 Sr-90 NUleER DATE SAMPLE pCi/g +/- 2 sigma pCi/g +/- 2 sigma SA-ECH-11Al 6-01-81 Flesh
<0.02
<0.007 to 7-02-81 Shell 0.8+/-0.2 0.94+/-0.09 8-27-81*
Flesh
<0.08
- 0.01+/-0.02 to 9-18-81 Shell
<0.1 0.24+/-0.04 SA-ECH-12Cl 6-01-81 Flesh
<0.01
.. 0.007+/-0.004 to
- ~
7-02-81 Shell
- 1.1+/-0.2
- 1.0+/-0.l 8-27-81 Flesh
<0.06 0.03+/-0.02 to 9-18-81 Shell
<0.08
- 0.20+/-0.04 Sr-89 results are corrected for decay to saq>le stop date.
Indicates tritium analysis not perfonned on shells.
H-3 (Edible Portion) pCi/l +/- 2 sigma
<86 123+/-68
<86
<110 e
- 1 I
- I
.I
- 1
TABLE C*:ll CONCENTRATIONS OF CWl4A EIUTTERS* AND STRONTIUM-89** AND *90 IN FOOD PRODUCTS Results fn Unf ts of pCf /g(wet) +/- 2 sf !JlliJ STATION I'<<>.
DATE SAfl>LE TYPE K-40 Sr-89 Sr-90 SA-FPV*21El 5-03-81 Asparagus 2.2+/-0.2
<0.01
<0.007 SA-FPV*2El 7-27-81 Peppers
- 2.0+/-0.2
<0.006
<0.003 SA-FPL*1F3 7-27-81 Cabbage
- 2.4+/-0.2
<0.02 0.015+/-0.006 SA-!FPV-5F1 7-27-81 TOllllltoes
- 2.8+/-0.3
<0.008 0.004+/-0.002 e
SA-IFPG-lG 1 7-27-81 Com
. 2.8+/-0.3.
<0.008 0.003+/-0.002 SA-FPV-161 7-27-81 Tomatoes
- 2.s+/-0.3
<0.006 0.004+/-0.002 SA-FPG-:lt4 7-27-81 Com 5.9+/-0.6
<0.008
<0.004 SA-FPV-:tt4 7-27-81 Cucunt>ers
- 1.s+/-0.2
<0.008
- o.oo3:t0.003 co....
SA-FPV*3H4 7-27-81 Peppers
- 1.1+/-0.2
<0.02
- o.013:t0.007 SA-FPV-:tt4 7-27-81 Tomatoes "3.1+/-0.3
<0.006
<0.003 SA-FPV-5Dl 7-28-81 Squash 1.5+/-0.2
<0.01 0.008+/-0.003 S"-'FPV-161 7-28-81 Peppers 2.0+/-0.2
. <0.009 0.004i0.002 SA--FPV-14F3 8-08-81 to Tollllltoes
- 2.1+/-0.2
<0.008
<0.004 8-10-81 SA~FPG-14F3 8-11-81 Com 2.1+/-0.2
<0.009
<0.004 e
All other ganma emf tters searched for were <LLD; typf cal LLDs are. given fn Table C-33.
Sr-89 results are corrected for decay to sa111>le stop date.
TABLE C-31 CONCENTRATIONS OF GAft-tA EMITIERS* AND STRONTIUf.f-89 AND -90** IN MEAT 1 GA14E, AND BOVINE THYROID Results in Units of pCi/g(wet) +/- 2 sigma
'I
- .1 STATION r<<>.
DATE SAMPLE TYPE K-40 Sr-89 Sr-90
- 1 pCi/g(dry)+/-2 sigma e
SA-GAM-3El 1-08-81 to Muskrat 2.4+/-0.2
<0.2 0.50+/-0.05 1-09-81 SA-l!Wl-llEl 3-05-81 to Muskrat 3.1+/-0.3
<0.9 0.5+/-0.3 3-06-81 CX>
N SA-FPB-3El 3-09-81 Beef 2.7+/-0.3 SA-THB-3El 3-09-81 Bovine Thyrui d
- 1.3+/-0.7 SA-FPB-3El 11-02-81 Beef 1.7+/-0.2 SA-THB-3El 11-02-81 Bovine ThYroid
<0.6 SA-FPB-14Fl.
12-08-81 Beef 1.7+/-0.2 e
SA-THB-14Fl 12-08-81 Bovine Thyroid
<1.1 All other gamna emitters searched for wer.e <LLD; typical LLDs are given in Table C-33.
Radiostrontium perfonned on muskrat only. Sr-89 results are corrected for decay to sarq>le stop date.
I CX>
w STATION NlJtBER SA-VGT-361 SA~VGT-2F4 SA-VGT-14Fl
- SA*VGT-13E3 SA* VGT-15 Fl SA-VGT-15Fl SA-FPG-3El SA-FPG-361 SA-FPG-15Fl TABLE C-32 CONCENTRATIONS OF GAt.f*IA EMITTERS* IN FODDER CROP SAMPLES DATE 8-01-81 to 8-31-81 9-08-81 9-08-81 9-21-81 9-21-81 10-05-81 10-14-81 11-17-81 11-30-81 Results in Units of pCi/g(dry) +/- 2 sigma SAMPLE TYPE Silage Green Chop Green Chop Green Chop Weed Chop Com Silage Soybeans Soybeans Soybeans Be-7
<1.2
<1.1
<0.4
<0.5 2.3+/-0.7
<1.3
<0.3
<0.5
<0.2 K-40 8.7+/-1.8 12+/-2 5.6+/-0.6 5.2+/-0.8 10+/-1 7.5+/-1.4 16+/-2 21+/-2 13+/-1 Cs-137
<0.1
<0.1
<0.05
<0.06
<0.08
<0.1 0.04+/-0.03
<0.05
<0.03 All other ga11111a emitters searched for were <LLD; t,ypical LLDs are given in Table C-33.
TABLE C-33 LLDs FOR GAMf4A SPECTROMETRY SURFACE AIR WELL/POTABLE WATER FISH SEDIMENT PARTICULATES PRECIPITATION WATER NUCLIDES (pCi/1)
(pe1/g-wet).
. (~C1/~~d~).
(lo-3pc1/m3)
(pC1/1)
(pC1/1)
Be-7 5.2 0.07 0.3 7.6 7.0 Na-22 o.8
- 0.009 0.6 0.6 K-40 11
- 1.2 7.8 7.8 Cr-51
- 5.3 0.06 0.4 7.6 5.9 5.8 Mn-54
- o.6 0.008
- 0.03 0.6 0.6 0.6 Co-57
- 0.02 0.3 1.0 Co-58 0.7 0.009
- 0.03 0.5 0.7 0.7 Fe-59 1.5 0.02 0.09 1.1 1.6 1.4 I;
Co-60 0.0 0.009 0.03 0.5 0.8 0.3 Zn-65 1.4 0.02
- 0.00 0.9 1.5 1.4 Zr-95
- 0.06 fl>-95 0.06 Zrft>-95 0.6 0.008 0.6 0~6 Mo-99 18
- 1.1 39 51 40 Ru-103 0.04 0.9 Ru-106 6.3 0.08
- 0.02 6.1 13 6.3
~. ~
Ag-llOlil 0.6 0.008 0.03 0.6 0.8 0.6 Sb-125 *
- 0.01 1.7 Te-129m 12
- 0.2 1.4 28 13 13 I-131 1.0 0.02 0.2 3.4 1.4 1.3
. Te-132 1.5 0.07 3.6 3.0
. I-133 Cs-134 0.6 0.008 0.03
- o.5 0.8 0.6 Cs-136 1.2 0.02 0.1 1.2 1.6 1.5 Cs-137 0.6 0.008 0.04 0.8 0.6 Ba-140 0.5 9.7 9.8 La-140 0.1 1.6 2.8 BaLa-140 1.0 0.02 1.3 1.2 Ce-141 0.07 1.0 Ce-144 1.6 0.03 0.2 3.2 1.6 Ra-226 1.1 0.01 1.1 1.2 1.2 Th-232 3.1 0.03 1.8 3.1 3.1
TABLE C-33, (eont.) *.
~
LLDs FOR GAt.f.tA SPECTROMETRY.
FOOD FODDER MILK PRODUCTS CROPS GAME SHELLFISH.
f<<IQ.IDES (pCi /l)
(pCi/g-wet).
. (pCi/g~dry)
( pCi I g-wet)
(pCi/g-wet)
Be-7 9.4 0.02 0.3 0.7 0.09 Na-22 1.3 0.003 0.03 0.008 0.01 K-40 Cr-51
- 15.1 0.02 0.2 0.06 0.1 e
Mn-54 1.0 0.003 0.03 0.008 0.01 Co-57 Co-58 1.1 0.003 0.03 0.008 0.01 Fe-59 3.7
- 0.007 0.09 0.02 0.02 Co-60 1.2 0.003 0.03 0.008 0.01 Zn-65 3.2 0.008 0.08 0.02 0.03 Zr-95 rt>-95 Zrrt>-95 1.2 0.003 0.03 0.008 0.009 Mo-99 130 0.08 0.9
- 0.2 1.9 Ru-103 CX>
Ru-106 8.0 0.03 0.3 0.00 0.1 (J"I Ag-llOm 1.0 0.003 0.03 0.008 0.01 Sb-125 Te-129m 19 0.06 0.5 0.2 0.2 1-131 2.3 0.004 0.06 0.01 0.03 Te-132 6.1 0.004 0.07 0.02 0.1 1-133 0.09 3.1 0*4 Cs-134 0.9 0.003 0.03 0.008 0.01 Cs-136 2.7
- 0.007 0.07 0.02 0.03 Cs-137 1.2 0.003 0.05 0.009 0.01 Ba-140 e
La-140 Bala-140 1.7 0.004 0.05 0.01 0.02 Ce-141 Ce-144 3.2 0.01 0.01 0.03 0.03 Ra-226 1.6 0.005
'0.06 0.01 0.02 Th-232 4.7 0.01 0.1 0.03 0.05 Indicates a* positive concentration was measured in all samples analyzed.
Indicates that no LLD was calculated for that nuclide in that media.
APPENDIX D SYNOPSIS OF ANALYTICAL PROCEDURES 87
GROSS ALPHA ANALYSIS OF SAMPLES Total Water (A0, Al)
A 250 m1 (A0) or one 1 (Al) aliquot of the sample is evaporated to dryne~s on a hot plate in a preweighed, 2 11 X 1/4" ringed planchet, allowed to cool, and re-weighed.
The planchet.is counted in a low-background, gas flow proportional counter. Self-absorption corrections are inade based on the measured sample weight and calculated thickness. The calibration standard used is. Pu-239. A 250 ml or one 1 sample of distilled water is evaporated in the same manner and used as a blank.
Total Salt Water (AA)
Alpha emitters are concentrated initially from a liter aliquot of water sample by coprecipitation with magnesium hydroxide. The precipitate is then dissolved in hydrochloric acid and titanium trichloride is added to the solution. The alpha emitters are coprecipitated by adding barium chloride and sulfuric acid to pre-cipitate barium sulfate. The precipitate is transferred to a tared stainless steel planchet and dried. The planchet is reweighed and counted in a low back-ground gas-flow proportional counter. Self-absorption corrections are made on the basis of the weight of the precipitate.
Calculations are made utilizing the following equations:
Result (pCi/l)
= ((S/T) - (B/t)) I (2.22 V E TF) 2 sigma error (pCi/l) = 2 ((S/T2) + (B/t2)) 112 I (2.22 VE TF) where:
s B
E T
t v TF
=
=
=
=
=
=
=
Gross counts of sample Counts of blank Fractional Pu-239 counting efficiency Number of minutes sample was counted Number of minutes blank was counted Sample aliquot size (liters)
Transmission factor (based on net weight of sample in counting planchet)
Calculation of lower limit of detection (LLD)
The detection limit is assumed to be exceeded when the counting result is different from the blank reading by at least 4.66 times the standard deviation of that back-ground.
LLD (pCi/l) = 4.66 (8112) I (2.22 VE TF t) 89
~--~*,_-
--*--.-;.,..* * "" ":"*- ~.,~ **-~-r* ***-
where:
B = Counts of blank E = Fractional Pu-239 counting efficiency t
= Number of.minutes blank was counted V = Volume of aliquot (liters)
TF = Transmission factor (based on net weight of sample in counting planchet)
Air Particulates (AD)
After a decay period of three to seven days, to allow f-0r the decay of short lived radium and thorium daughter products, the filters are counted in a gas-flow proportional counter. The alpha activity per unit volume is calculated from the volume of air filtered. An unused filter is used as a blank.
Calculations are made utilizing the following equations:
Result (pCi/m3) = ((S/T) - (B/t)) I (2.22 V E) 2.sigma error (pCi/m3) = 2 ((S/T2) + {B/t2))112 I {2.22 V E) where:
S = Gross counts of sample B = Countsofblank E = Fractional Pu-239 counting efficiency T = Number of minutes sample was counted t
= Nuni>er of minutes blank was counted V = Volume of aliquot (cubic meters)
Calculation of lower limit of detection (LLD)
The detection limit is assumed to be exceeded when the counting result is different from the blank reading by at least 4.66 times the standard deviation of that back-ground.
LLD (pCi/l) = 4.66 (B112) I (2.22 VE t) where:
B = Counts of blank E = Fractional Pu-239 counting efficiency t
= Nunt>er of minutes blank was counted V = Volume of aliquot (cubic meters) 90
> "" """" ~~~~~~~_;_~~--------__;--.....;.. __;.....;.. __________________ ~---
GROSS BETA ANALYSIS OF SAMPLES Total Water (B0, Bl)
A 250 ml (B~) or one 1 (Bl) aliquot is evaporated to dryness on a hot plate in a preweighed, 2" x 1/4", ringed planchet and reweighed. The planchet is then counted in a low background gas-flow proportional c~unter. Self-absorption corrections are made based on the measured residue weight and calculated thickness. The calibration standard used is Sr Y-90.
A 250 ml or one 1 sample of distil-led water is evapo-rated in the same manner and used as a blank.
calculations are made utilizing the following equations:
Result (pCi/l) = ((S/T) - (B/t)) I {2.22 VE TF) 2 sigma error (pCi/l) = 2 ((S/T2) + {B/t2))1/2 I (2.22 VE TF) where:
S = Gross counts of sample B = Counts of blank E = Fractional Sr-90-Y-90 counting efficiency T = Number of minutes sample was counted t
= Nunt>er of minutes blank was counted V = Volume of aliquot (liters)
TF = Transmission factor (based on net weight of sample in counting planchet) calculation of lower limit of detection (LLD)
The detection limit is assumed to be exceeded when the counting result for the saf11lle is different from the blank reading by at least 4.66 times the standard deviation of that background.
LLD {pCi/l) = 4.66 (8112) I (2.22 VE TF t) where:
B E
t v TF
=
=
=
Counts of blank Fractional Sr-90-Y-90 counting efficiency Number of minutes blank was counted Volume of aliquot (liters)
Transmission factor (based on net weight of sample in counting planchet}
Air Particulates (BD)
After a decay period of three to seven days, to allow for the decay of short lived radium and thorium daughter products, the filters are counted in a gas-flow proportional counter. The beta activity is calculated from the volume of ~ir filtered. An unused filter paper is used as a blank.
calculations are made utilizing the following equations:
Result (pC1/m3) = (S/T) - (B/t)) I (2.22 V E) 91
2 sigma error (pCi/m3) = 2 ((S/T2) + (B/t2))1/2 / (2.22 V E) where:
S = Gross counts of sample B = Counts of blank E = Fractional Sr-90-Y-90 counting efficiency T = Number of minutes sample was* counted t
= Number of minutes blank was counted V = Volume of sant>le (cubic meters)
Calculation of lower limit of detection (LLD)
The detection l i mi t is ass urned to be exceeded when the counting result for the sample is different from the blank reading by at least 4.66 times the standard deviation of that background.
LLD (pCi/m3) = 4.66 (8112) I (2.22 V ~ t) where:
B E
t v
=
=
=
=
Counts of blank Fractional Sr-90-Y-90 counting efficiency Number of minutes blank was counted Volume of sample (cubic meters) 92
GA~A SPECTROMETRY OF SAMPLES Water (Nl)
Four liters of sa~le is reduced to 100 ml and sealed in a standard container and counted with a Nal(Tl) detector coupled to a multi-channel pulse-height analyzer. The counting time is 50,000 seconds.
Milk (N7)
A 4 liter aliquot is dried at 175°C, ashed at 500°C until no carbon residue is present, compressed and sealed in a standard container, and then counted with a Nal(Tl) detector, coupled to a multi-channel pulse-height analyzer.
The counting time is 50,000 seconds.
Dried Solids (NS, GS)
A large quantity of the sample is dried at a low tel!1'erature, less than 100°C.
A 100 gram aliquot (or the total sample if less than 100 grams) is taken, compressed to unit densityj sealed in a standard container, and counted with a Nal{Tl) or Ge(Li) detector, coupled to a multi-channel pulse-height analyzer.
The counting time is 50,000 seconds.
Air Dried Solids {NA)
A large quantity of sample is air dried. A 100 gram aliquot {or the total sample if less than 100 grams) is taken, compressed to unit density, sealed in a standard container and counted with a Nal(Tl) detector, coupled to a multi-channel pulse-height analyzer.
The counting time is 50,000 seconds.
Air Particulate (GB)
All samples received for the month are mixed, compressed, and sealed in the standard container, and counted with the high resolution Ge(Li) detector, coupled to a multi-channel pulse-height analyzer.
Calculation of result and two sigma error The spectrum obtained is smoothed to eliminate spurious statistical noise.
Peaks are identified by changes in the slope of the gross spectrum. The net counting rate above the baseline is calculated. This counting rate is con-verted to activity in curie units, making allowance for counting efficiency and ganma ray abundance. A PDP-11 computer program was introduced for spectrum analysis~
Calculations are made utilizing the following equations:
Result (pCi/l, g or m3) s
((S/T) - {B/t)) I (2.22 V E F) 2 si~a error (pCi/l, g or m3) = 2 ((S/T2) + (B/t2))112 I (2.22 VE F) 93
where:
s B
T E v F
=
=
=
=
Sample counts in energy channels for peak being quantitated Background counts in energy channels for peak being..
quantitated Number of minutes safl1lle was counted Detector efficiency for energy of interest Sample aliquot size Fractional gamna abundance Calculation of lower limit of detection (LLD) for GB and GB LLD (pCi/l. g or m3) = 4.66 (6 s>1' 2 I (2.22 v E F T) where:
s T
E v F
=
Sample counts in energy channels for peak being quantitated Number of minutes sample was counted Detector efficiency for energy of interest Sample aliquot size Fractional garmia abundance Calculation of lower limit of detection (LLD) for Nl, N7, NS and NA LLD {pCi/l 1 g or m3) = 4.66 (.63 6 s)1/ 2 I (2.22 V E F T) where:
s T
E v F
=
=
=
Sample counts in energy channels for peak being quantitated Number of minutes sample was counted Detector efficiency for energy of interest Sample aliquot size Fractional garrma abundance 94
ANALYSIS OF WATER SAMPLES FOR POTASSIUM-40 BY AA (E~)
Sample Preparation An aliquot sample size of 100 ml is filtered. The concentration of potassium is determined spectrophotometrically on a Perkin Elmer tt>del 373 atomic absorption unit. The result obtained, in micrograms per milliliter, is multiplied by the specific activity of 0.12% for natural potassium to deter-mine the annunt of potassium-40 present in the sample.
The error reported is 10% of KCl are determined with each sample set.
Calculations are made using the following equations:
K-40 (pCi/l) = Cs D (C/S) K 103 LLD (pCi/l) = Cs D (.1/S) K 103 where:
Cs
= Concentration of Standard (µg K/ml)
C
= Sample reading S
= Standard reading D
= Dilution factor K
= Specific activity of K-40 per unit weight of potassium
=.852 pCi/mg 95
ANALYSIS OF SAMPLES FOR TRITIUM Water (H2)
A 15 ml aliquot of the safTl>le is vacuum distilled to eliminate dissolved_ gasses and non-volatile matter. The distillate is frozen in a trap cooled with a dry ice-isopropanol mixture. Eight (8) ml of the distillate are mixed with ten (10) ml of Insta-Gel liquid scintillation solut1on. The sample is then counted for tritium in a liquid scintillation counter. A sample of low tritium (<50 pCi/1) water is vacuum distilled as a blank and is counted with each batch of samples.
In the calculation of the result it is assumed that the condensated and original sample are of equivalent volumes. The volume change associated with the remJval of dissolved gases and non-volatile matter is not significant compared to the other errors in the analysis.
Calculations are made utilizing the following equations:
Result (pCi/l) = ((S/T) - (B/t)) I (2.22 VE) 2 sigma error (pCi/l) = 2 ((S/T2) + (B/t2)) 1/2 / (2.22 VE) where:
S = Total gross counts of sample B = Counts of blank E = Fractional H-3 counting efficiency T = Number of minutes sample was counted t
= Number of minutes blank was counted V = Aliquot volume (liters)
Gross counts of sample may be corrected for the blank activity. If the collection container is rinsed with distilled water and the rinse is added to the sample, the rinse plus sample and a separate aliquot of the distilled water are counted. The corrected gross counts foF the sample only are calculated using the following equa-tions:
s = ((s-b)v) I G s = (c(G+H)) I V b = (d(H)) I V v = ((G+H) V) I G where:
s = Gross counts of salT{lle G = Volume.of sample H = Volume of rinse s
= Volume corrected gross counts of sample plus rinse b = Volume corrected gross counts of rinse v = Corrected aliquot volume c = Uncorrected gross counts of sample plus rinse d = Uncorrected gross counts of rinse 96
Calculation of lower limit detection (LLD)
The detection limit is assumed to be exceeded when the counting res,4lt is different from the blank reading by at least 4.66 times the standard devi.ation of that background.
LLD (pCi/l) = 4.66 (B112) I (2.22 VE t}
- where:
B = Counts of blank E = Fractional H-3 counting efficiency t
= Number of minutes blank was counted V = Aliquot volume (liters)
Aqueous and Organic Fraction of Milk or Organic Solids (H3, H4, H9)
A carefully measured aliquot of a food product, such as milk or fish, is dried in a rotating vacuum flash evaporator. During the evaporation process, the evaporated water fraction is trapped out by a dry ice isopropanol mixture for coanting as in (a) below.
The dried residue is reserved for (b). The wet sample is analyzed as in (c).
- a. Aqueous H-3 in Food Products An eight (8) ml aliquot of the cold-trapped water is counted in a liquid scintillation counter in the same manner as surface water samples are counted.
- b. Organic Bound H-3 in Food Products The dried residue is combusted in an RMC designed oxidizer. The collected water - organic fraction is measured and vacuum distilled to renDve any impurities. Permanganate in KOH solution is added to rermve impurities which may cause quenching.
An eight (8) ml aliquot is counted in a liquid scintillation counter. If less than eight (8) ml are collected, the entire portion collected is carefully measured with a 10 ml pipette and then counted.
A sample of deep well water is counted as a blank.
- c.
Aqueous and organic Bound H-3 in Food Products A wet weight aliquot is combusted in an RMC designed oxidizer. The collected water fraction is measured and vacuum distilled to rermve any impurities. Per-manganate in KOH solution is added to rermve irJl)urities which may cause quenching.
An eight (8) ml aliquot is counted in a liquid scintillation counter. If less than eight (8) ml are collected, the entire portion collected is carefully measured with a 10 ml pipette and then counted. A sample of deep well water is counted as a blank.
Calculations are made utilizing the following equations:
Result (pCi/l) = ((S/T) - (B/t)) I (2.22 VE) of distil late 2 sigma error (pCi/l) = 2 ((S/T2) + (B/t2))1' 2*1 (2.22 VE) of distill ate 97
Result (pCi/g of freeze dried sample) = A (YI) 2 si!Jlla error (pCi/g of freeze dried sample) = C (YI)
Result (pCi/g or 1 of original sample) = A (YF) 2 sigma error (pCi/g or 1 of original sampl*e.)
= C (VF) where:
S = Gross counts of sample B = Counts of blank E = Fractional H-3 counting efficiency T = Number of minutes sample was counted t
= Number of minutes blank was counted V = Volume of distillate counted YI = Liters of water-organic recovered/ g of freeze dried sample YF = Liters of water recovered/ (1 or g) of sample aliquot taken A = Result in pCi/l of distillate C = 2 sigma error in pCi/l of distillate Calculation of lower limit detection (LLD)
The detection limit is assumed to be exceeded when the counting result is dif-ferent from the blank reading by at least 4.66 times the standard deviation of that background.
LLD (pCi/l) = 4.66 (B1/2) I (2.22 VE t)
LLD (pCi/g of freeze dried sample) = F (YI)
LLD (pCi/l or g) = F (VF) of original sample where:
B E
t v YI VF F
=
=
=
=
=
Counts of blank Fractional H-3 counting efficiency Number of minutes blank was counted Volume of distillate counted Liters pf water-organic recovered/g of freeze dried sample Liters of water recovered/Cl or g) Qf sample aliquot taken LLD in pCi/l of distillate 98
'----'-'--'-'--"'---'"...: : c**......,o.**---,-..-;=-------c **..--.,*=----------'--'-------"--'---~~~-=--~-'-----'"'"*---..*-~-~-~~------------
e ANALYSIS OF SAMPLES FOR IODINE-131 Milk or Water (10)
The initial stable iodide concentration in milk is detennined with'an iodide ion specific electrode. Thirty milligrams of stable iodide carrier is *then added to four (4) liters of milk. The iodide is removed from the milk by passage through ion-exchange resin. The fodide is eluted from the resin with sodium hypochlonite, and purified by a series of solvent extractions with the final extraction into a toluene phase. The toluene phase is mixe*d with a toluene-based liquid scintillation solution. The sample is then counted in a beta-gated gamna coincidence detector, shielded by six inches of steel. Distilled water is used as a blank. The yield is calculated from stable iodide recovery based on the recovered volume.
Calculations are made utilizing the following equations:
Result = ((S/T) - {B/t)) I {2.22 V E F Y)
{pCi/l) 2 sigma error = 2 ((S/T2) + (B/t2)) 112 / (2.22 V E FY)
(pCi/l)
= 4.66 {B112) I (2.22 V E F Y t)
{pCi/l) where:
S = Gross counts of sample in channels containing 1-131 peak B = Background counts in channels containing 1-131 peak T = Number of minutes sample was counted t
= Nuni>er of minutes background was counted E = Iodine-131 counting efficiency V = Sample aliquot size F = Fractional ganma abundance Y = Chemical yield of iodine Air Cartridges (11)
An iodine absorber composed of charcoal is emptied into an aluminum can (6 ems high by 8 ems in diameter) and counted with a NaI (Tl) detector, coupled to a multi-channel pulse-height analyzer.
Calculation of results and two sigma error Peaks are identified by changes in the slope of the spectrum. If peaks are iden-tified the spectrum obtained is snDothed to eliminate spurious statistical noise.
The presence of iodine-131 is identified by the presence of a 364 Kev peak.
The net counting rate above the baseline is calculated. This counting rate is con-verted to activity in curie units, making allowance for counting efficiency and gamma ray abundance. A PDP-11 computer program is used for spectrum analysis.
Results are corrected for decay from the sampling time to the middle of the counting period, using a half-life value for 1-131 of 8.06 days.
Calculations are made utilizing the following equations:
Result3 = ((S/T) - (B/t)) I (2.22 V E FY)
(pCi /m )
gg
2 si~ error = 2 ((S/T2) + (B/t2))112 I (2.22 V E F Y)
(pCi/m )
LLD 3 = 4.66 (B112) I (2.22 V E F Y t)
(pCi/m )
where: s
=
B
=
t
=
E
=
v
=
F
=
Gross counts of sample in channels containing I-131 peak Background counts in channels containing I-131 peak Number of minutes background was counted Iodine-131 counting efficiency Sample aliquot size Fractional gamma abundance 100
I
/
ANALYSIS OF SAMPLES FOR STRONTIUM-89 AND -90 Total Water (50, T~)
A two liter aliquot of sa"1>1e is used. Stable strontium carrier is *added to the liquid to facilitate chemical separation of Sr-89 and -90, and to determine the strontium recovery. Strontium concentration and purification is ultimately real-ized by at least two precipitations of strontium nitrate in concentrated nitric acid. Additional iron rare earth scavenging and barium chromate separations are performed to remove suspecte~ interfering nuclides. The purified strontium is c6nverted to a carbonate for weighing and counting. Soon after the separation, the sa!T1'le is counted in a low-background gas-flow proportional counter. After about 14 days, the SallfJle is recounted, then Sr-89 and -90 activities are calcu-lated on the basis of Y-90 ingrowth.and Sr-89 decay. A sample of distilled water is used as a blank.
Milk (S4, T4)
A one and half liter aliquot of milk is ashed to destroy organic material and then dissolved in concentrated mineral acid. Stable strontium is added to the dissolved ash to facilitate chemical separation of Sr-89 and -90, and to detennine the strontium recovery. Strontium concentrations and purification is ultimately realized by at least two precipitations of strontium nitrate in concentrated nitric acid. Additional iron rare earth scavenging and barium chromate separations are performed to remove suspected interfering nuclides. The purified strontium is converted to a carbonate for weighing and counting. Soon after the separation, the sample is counted in a low background gas-flow proportional counter. After about 14 days, the sample is recounted, then Sr-89 and -90 activities are calculated on the basis of Y-90 ingrowth and Sr-89 decay. A sample of distilled water is used as a blank.
Bones and Shells (SS, TS)
A large quantity of the sa~le is dried, ashed and a 2S g portion is then dissolved in concentrated acid. Stable strontium carrier is added to the dissolved sample to facilitate chemical separations of Sr-89 and -90, and to detennine the strontium recovery. Strontium concentration and purification is ultimately realized by at least two precipitations of strontium nitrate in concentrated nitric acid. Addi-tional iron rare earth hydroxide scavenging and barium chromate separations are per-formed to remove suspected interfering nuclides. The purified strontium is converted to a carbonate for weighing and counting. Soon after the separation, the sample is counted in a low-background gas-flow proportional counter. After about 14 days, the sa~le is recounted, then Sr-89 and -90 activities are calculated on the basis of Y-90 ingrowth and Sr-89 decay. A sample of distilled water is used as a blank.
Soil and Sediment (S6, T6)
A large quantity of sample is dried, and a 2S g portion is then leached with concen-trated HCl before drying. Stable strontium carrier is added to the sample to facili-tate isolation of the strontium and to detennine the strontium recovery. Strontium concentrations and purification is ultimately realized by at least two precipitations of strontium nitrate in concentrated nitric acid. Additional iron rare earth scavenging and barium chromate separations are performed to remove suspected interfering nuclides.
The purified strontium is converted to a carbonate for weighing and counting. Within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after the separation, the sat11lle is counted in a low-background gas-flow pro-portional counter. After about 14 days, the sample is recounted, then Sr-89 and -90 Wl
activities are calculated on the basis of Y-90 ingrowth and Sr-89 decay. A sample of distilled water is processed with each batch of samples._
Organic Solids {S8, TB)
A 250 g portion of the sample is ashed and then dissolved in concentrated acid.
Stable strontium carrier is added to the ~issolved sample to facilitate chemical separation of Sr-89 and -90, and to detennine the strontium recovery. Strontium concentration and purification is ultimately realized by at least-~~o precipitations of strontium nitrate in concentrated nitric acid. Additional r:are earth *iron hydrox-ide scavenging and barium chromate separations are perfonned to reroove suspected inter-fering nuclides. The purified strontium is converted to a carbonate for weighing and counting. Soon after the separation, the sample is counted in a low-background gas-flow proportional counter. After about 14 days, the san{>le is recounted, then Sr-89 and -90 activities are calculated on the basis of Y-90 ingrowth and Sr-89 decay. A sample of distilled water is used as a blank.
Air Particulates (SA, TA)
Stable strontium carrier is added to facilitate chemical isolation of Sr-89 and
-90 and for determination of the strontium recovery in the procedure.
Strontium concentrations and purification is ultimately realized by at least two precipitations of strontium nitrate in concentrated nitric acid. Additional hydrox-ide precipitations and barium chromate separations are performed.
The purified strontium is converted to a carbonate for weighing and counting.
Gross beta counts are made soon after the strontium isolation and again after a 7-14 day interval and Sr-90 and Sr-89 activities are calculated on the basis of appropriate Sr-89 decay and Y-90 ingrowth equations.
Calculations are made using the fol.lowing equations:
Result Sr-90 =3((Z(Sl-81)) - (S2-82)) I (2.22 KV E9 Y T)
(pCi/l, g or m )
2 sigma error 3r-90 = 2 (Z2(Sl+81) + S2+82) 112 / (2.22 (K2)1/ 2 V E9 YT)
(pCi/l, g or m)
MDL = (-9 -6(§ 82+Z(Sl-81)) 112 + 2.25 + z2(Sl+81))/(4.44 V E9 Y T)
{pCi/l, g or m )
Result Sr-89 =3{F{Sl-81) + H(S2-82)) I (2.22 V EB Y T exp (-.693t4/52.7))
{pCi/l, g or m) 2 sigma error ~r-89 = 2{F2(Sl+81) + H2{S2+82))112 I {2.22 V ES YT exp(-.693t4/52.7))
(pCi/1, g or m)
MDL = {F{X-83) + H (S2-82)) I {2.22 V EB Y T exp (-.693t4/52.7))
{pCi/l, g or m )
102
1 l
where:
Y-90(2) 51 52 Bl B2 tl t2 t3 t4 El E2 z R
H K
F c B x E9 EV EB T v v
= 5r-89 counts on first count
= Counts of Sr-90
= Counts of V-90 on first count
= Counts of V-90 on second (after equil.)
= Sr-89(1) + Sr-90 + V-90(1) + B(l)
= 5r-89(2) + Sr-90 + V-90(2) + B(2)
= Blank counts in first *Count
= Blank counts in second count
= Time in hours from separation time to Sl
= Time in days from separation time to S2
= Time in days from Sl to S2
= Time in days from sampling date to separation date
= 1 - exp (-.693tl/64 hours)
= 1 - exp (-.693t2/2.667 days)
= exp (-.693t3/52.7 days)
= E9/EV
= (1 + El/R)/K
= Z (El/R + 1) (E2/R)
= 1 -
(~/K) - Z (E~/KR) 2
= (-9 F Bl) - 9 H (S2+B2)+(F Bl) - 2 F H B2 S2+2 F H Bl B2 2
= 2 F H (S2-B2) i 2 F2 Bl - 9 F2
+ (H(S2-B2))
= ((82 - 4 F2 C) /Z - B) / (2 F2)
= Counting eff. of Sr-90 =.3590 -.7082 X (Wt. in g of strontium carbonate)
= Counting eff. of V-90
=.4380 -.1337 X O~t. in g of strontium carbonate)
= Counting eff. of Sr-89 =.4568 -.2060 X (Wt. in g of strontium carbonate)
= Number of minutes sample and blank were counted
= Viel d
= Sample aliquot size Calculation of minimum detectable levels (MDLs)
Due to the method of calculating the activity of Sr-90 in the presence of Sr-89, the form used in the NBS Handbook 80 for calculating minimum detectable activities is not applicable.
103
i ENVIRONMENTAL DOSIMETRY (00, Dl, 02)
Measurement Techniques Each dosimeter utilized is a capillary tube containing calcium sulfate. (Tm) powder as the thermoluminescent dosimeter (TLD) imterial. This was chosen primarily for its high light output, minimal thennally induced signal loss (fading), and lack of self-dosing. The energy response curve has been flattened by a complex multiple element energy compensation shield supplied by Panasonic Corporation, manufacturer of the TLD reader. The four dosimeters per station are sealed in a polyethylene bag to demonstrate integrity at time of measurement.
Visible through the bag are the sample placement instructions. One set of TLDs is pl aced in a 1 ead shield at RMC and represents a ze.ro dose. The TLDs are then taken and placed in the field stations; one field TLD set is placed in a field lead shield at station 18 and is used in calculating the in-transit dose.
Following the pre-designated exposure period the TLD is heated with hot gas and the luminescence measured with a TLD reader. Data are normalized to standard machine conditions by correcting machine settings to zero before readout.
Data are corrected for in-transit dose using a set of TLOs which is kept in a lead shield in the field and only exposed during transit.
Average dose per exposure period, and its error, are calculated.
The basic calibration is in mR exposure to a standard Cs-137 source. This is converted to absorbed dose in tissue by the factor : 0.955 rad/Roentgen and to dose equivalent by using a quality factor of 1.
Calculation of results and two sigma error gross TLD(i) = (TLD{i) - D0(i)) (CF (ins)) {CF(i)) 0.955 mrad/mRoentgen ITO= NET(site0) - {NET{RMC0) {D(sta) I D(RMC0)))
NET TLD(i) =gross TLD(i) - ITO AVG n
= ((sigma i=l NET TLD)/n)(D(STO) I D(EX))
ERROR (95% CL) = t(n-1) sigma NET TLD(i) In) (D(STD)/D(EX))
104
where:
- e ENVIRONMENTAL DOSIMETRY (cont.)
Gross TLD(i)
TLD(i)
NET TLD(i)
CF( ins)
ELS 00 (i)
CF(i)
ITO NET(site)0 NET(RMC)'4 D(sta)
D(RMC~)
AVG n
D(EX)
D(STD) t(n-1) sigma NET TLD(i)
ERROR
= Individual TLD reading corrected to standard instrument conditions
= Gross reading of dosimeter i
= Net dose obtained during exposure period i5 g§e field
= Correction factor of reader = (6.21~- (ELS- * )
= External light source
= Zero for dosimeter, i
= Calibration factor for dosimeter i
= In-Transit dose
=.Mean of n dosimeters in site lead shield
= Mean of n dosimeters in RMC lead shield
= Exposure period of station
= Exposure period of RMC~
= Mean exposure per standard exposure period at a given station
= Number of readings
= Days exposed
= Days in standard exposure period
= t-distribution (student) factor for 95% CL
= Standard deviation of n readings of NET TLD(i)
= The 95% confidence limit error of AVG 105
- e APPENDIX E
SUMMARY
OF INTERLABORATORY COMPARISONS 107
~
I
~
e
- e TABLE E-1 INTER-LABORATORY COMPARISONS GROSS ALPHA AND BETA IN WATER (pCi/liter) and AIR PARTICULATES (pCi/filter)
SAMPLE RMC EPA All Participants DATE RMC #
TYPE ANALYSIS
.*MEAN+/-s.d.
MEAN+/-s ~d
- MEAN+/-s.d.
Jan 43613 Water
- 0.
10+/-2 9+/-5 9+/-3 1981 a
40+/-3 44+/-5 44+/-6 March 53663 APT
- 0.
33+/-1 30+/-8 32+/-5 1981 a
74+/-2 50+/-5 56+/-11 March 54441 Water
- 0.
.26+/-3 25+/-6 24+/-6 1981 a
31+/-2 25+/-5 28+/-5 April 54841 Water
- 0.
64+/-7 91+/-23 76+/-24 1981 6
134+/-9 141+/-7 140+/-21 May 55883 Water
- 0.
25+/-2 21+/-5 19+/-5 1981 a
15+/-2 14+/-5 16+/-4 June 56994 APT
- 0.
30+/-2 28+/-7 32+/-6 1981 a
79+/-5 54+/-5 64+/-10 July 57789 Water
- 0.
19+/-3 22+/-6 18+/-5 1981 a
16+/-1 15+/-5 17+/-4 Sept 60388 Water
- 0.
48+/-4 33+/-8 28+/-8 1981 f3 26+/-1 28+/-5 25+/-6 Sept 60776 APT a
27+/-3 25+/-6 26+/-6 1981 a
63+/-7 51+/-5 61+/-10 Oct 62491 Water
- 0.
52+/-5 80+/-20 70+/-17 1981 f3 106+/-3 111+/-6 103+/-15 Nov 64277 Water
- 0.
24+/-2 21+/-5 20+/-5 1981 f3 21+/-1 23+/-5 23+/-5 109
SAMPLE DATE RMC #
TYPE Feb 44003 Water 1981 Apr 53660 Water 1981 June 56309 Water 1981 Aug 58155 Water 1981 Oct 61871 Water 1981 Dec 64936 Water 1981 TABLE E-2 INTER-LABORATORY COMPARISONS TRITIUM IN WATER pCi/liter RMC ANALYSIS
'MEAN+/-s.d.
H-3 1680+/-137 H-3 2727+/-6 H-3 2053+/-32 H-3 2693+/-40 H-3 2467+/-106 H-3 2637+/-90 110 EPA All Participants MEAN+/-s.d.
MEAN+/-s.d.
1760+/-341 1778+/-230 2710+/-355 2717+/-373 1950+/-344 1946+/-241 2630+/-354 2616+/-361 2210+/-348 2133+/-214 2700+/-355 2676+/-244
DATE Jan 1981 Jan 1981 March 1981 March 1981 Apr 1981 May 1981 May 1981 June 1981 July 1981 July 1981 Sept 1981 Sept 1981 Oct 1981 Oct 1981 Nov 1981 (1)
SAMPLE RMC #
TYPE 43229 Water 43514 Milk 44815 Food 53663 APT 54841 Water 54379 Water 55248 Milk 56994 APT 57331 Food 57812 Milk 59585 Water 60776 APT 62491 Water 62547 Milk 63205 Food TABLE E-3 INTER-LABORATORY COMPARISONS STRONTIUM-89 AND STRONTIUM-90( 1)
RMC ANALYSIS MEAN+/-s~d.
Sr-89 24+/-11 Sr-90 27+/-7 Sr-89
<8 Sr-90 22+/-3 Sr-89 74+/-13 Sr-90 32+/-2 Sr~90 16+/-2 Sr-89 32+/-6 Sr-90 29+/-5 Sr-89 51+/-2 Sr-90 26+/-10 Sr-89 9+/-2 Sr-90 9+/-1 Sr-90 18+/-2 Sr-89 36+/-14 Sr-90 23+/-1 Sr-89 20+/-7 Sr-90 16+/-0 Sr-89 21+/-5 Sr-90 6+/-2 Sr-90 16+/-1 Sr-89 24+/-7 Sr-90 9+/-6 Sr=89 26+/-2 Sr-90 17+/-2 Sr-89 31+/-6 Sr-90 21+/-2 EPA All Participants MEAN+/-s.d.
. MEAN+/-s~d.
16+/-5 15+/-5 34+/-2 32+/-5 0
29+/-37 20+/-3 19+/-3 47+/-5 43+/-18 29+/-2 27+/-8 18+/-1.5 17+/-3 38+/-5 34+/-9 28+/-1.5 26+/-7 36+/-5 32+/-10 22+/-1.5 22+/-6 25+/-5 22+/-6 11+/-1.5 10+/-3 19+/-2 19+/-3 44+/-5 44+/-9 31+/-2 29+/-3 25+/-5 24+/-6 17+/-2 16+/-2 23+/-5 22+/-3 11+/-2 11+/-2 16+/-2 17+/-3 21+/-5 22+/-6 14+/-2 13+/-3 23+/-5 22+/-5 18+/-2 18+/-3 38+/-5 35+/-6 23+/-2 23+/-4 Results reported in pCi /1 for water and milk, pCi/filter for air particulates, and pCi/kg for food.
111
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SAMPLE DATE RMC #
TYPE Apr 53750 Water 1981 Aug 58205 Water 1981 Dec 64544 Water 1981 TABLE E-4 INTER-LABORATORY COMPARISONS IODINE-131 IN WATER pCi/l iter RMC ANALYSIS MEAN+/-s~d.
I-131 31+/-3 I-131 66+/-5 I-131 64+/-3 112 EPA All Participants MEAN+/-s~d.
MEAN+/-s.d.
30+/-6 29+/-5 73+/-7 72+/-7 76+/-8 69+/-10
SAMPLE DATE RMC #
TYPE Jan 43514 Milk 1981 Feb 44441 Water 1981 March 44815 Food 1981 March 53663 APT 1981 April 54841 Water 1981 May 55248 Milk 1981 June 56246 Water 1981' June 56994 APT 1981 July 57331 Food 1981
-.:--::-~'- ---
TABLE E-5 INTER-LABORATORY COMPARISONS GAMMAllJ RMC ISOTOPE MEAN+/-s~d~
<203 (a)
Cs-137 42+/-3 Ba-140
<177 K
1647+/-0 Cr-51
<67 Co-60 25+/-1 Zn-65 89+/-1 Ru-106
<28 Cs-134 35+/-2 Cs-137 5+/-1 I-131 103+/-6 Cs-137 48+/-2 Ba-140
<51 K
<4 Cs-134 12+/-3 Cs-137 16+/-1 I-131 24+/-2 Cs-137 21+/-2 Ba-140
<26 K
1777+/-77 Cr-51
<39 Co-60 17+/-3 Zn-65
<6 Ru-106
<27 Cs-134 20+/-2 Cs-137 30+/-2 Cs-137 15+/-4 I-131 78+/-8 Cs-137 43+/-1 Ba-140 0
K 2739+/-68 113 EPA Al 1 Participants MEAN+/-s~d.
MEAN+/-s ~d.
26+/-10 26+/-6 43+/-9 42+/-7 0
4+/-5 1550+/-134 1529+/-155 0
49+/-11 25+/-5 25+/-4 85+/-5 89+/-11 0
50+/-43 36+/-5 33+/-5 4+/-5 5+/-2 119+/-12 123+/-13 53+/-5 53+/-6 0
0 2640+/-132 2749+/-311 14+/-5 16+/-4 0
0 10+/-5 10+/-3 15+/-5 15+/-3 26+/-6 27+/-7 22+/-5 23+/-3 0
0 1559+/-78 1563+/-104 0
0 17+/-5 17+/-3 0
0 15+/-5 12+/-9 21+/-5 20+/-3 31+/-5 31+/-5 16+/-5 20+/-5 82+/-8 87+/-15 45+/-5 46+/-6 0
0 2640+/-172 2819+/-323
) *
- ~
- DATE July 1981 Sept 1981 Oct 1981 Oct 1981 Oct 1981 Nov 1981 (1)
(a)
SAMPLE RMC #
TYPE 57812 Milk 60776 APT 62282 Water 62491 Water 62547 Milk 63205 Food TABLE E-5 (cont.)
INTER-LABORATORY COMPARISONS GAMMA OJ RMC ISOTOPE
- .MEAN+/-s ~d.
<8 Cs-137 31+/-1 Ba-140
<25 K
1136+/-49 Cs-137 18+/-3 Cr-51
<75 (a)
Co-60 25+/-2 Zn-65 25+/-2 Ru-106
<29 Cs-134 21+/-1 Cs-137 33+/-2 Co-60
<3 Cs-134 11+/-1 Cs-137 16+/-1 I-131 53+/-1 Cs-137 26+/-2 Ba-140
<17 K
1526+/-0 Co-60 26+/-2 Cs-137 27+/-1 Ba-140
<35 K
2113+/-0 EPA All Participants MEAN+/-s.d.
MEAN+/-s.d.
0 7+/-7 31+/-5 32+/-4 0
0 1600+/-80 1593+/-99 19+/-5 24+/-6 34+/-5 36+/-9 22+/-5 23+/-3 24+/-5 24+/-4 0
0 21+/-5 20+/-4 32+/-5 33+/-4 0
0 12+/-5 12+/-2 15+/-5 16+/-3 52+/-6 53+/-7 25+/-5 27+/-3 0
0 1530+/-77 1532+/-108 30+/-5 30+/-4 33+/-5 34+/-4 0
6+/-6 2730+/-137 2758+/-331 Results reported in pCi/liter for milk and water, pCi/sample for air particulates, and pCi/kilograms for food products except K which is reported in mg/liter for milk and mg/kilogram for food products.
Sa"'1le was not analyzed within one half-life resulting in large LLD due to a long decay period.
114 F
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r' APPENDIX F SYNOPSIS OF DAIRY & VEGETABLE GARDEN SURVEY 115
\\.
l APPENDIX F SYNOPSIS OF DAIRY & VEGETABLE GARDEN SURVEY A door-to-door survey of dairy farms within 5 miles of SNGS was perfonned in April and July. The results of the April s.u.rvey were as follows:
One dairy fann, located 4.9 miles from SNGS in the west sector was 1 ocated.
The results of the July survey were as follows:
No change from April survey.
Since a dairy fann was located within 5 miles of the site, the vegetable garden survey was perfonned to a distance of one mile.
No vegetable gardens were found in this area.
117