ML18092B555
| ML18092B555 | |
| Person / Time | |
|---|---|
| Site: | Salem, Hope Creek, 05000000 |
| Issue date: | 12/31/1986 |
| From: | PSE&G RESEARCH CORP. |
| To: | |
| Shared Package | |
| ML18092B554 | List: |
| References | |
| RTL-ENV-87-01, RTL-ENV-87-1, NUDOCS 8705070117 | |
| Download: ML18092B555 (169) | |
Text
{{#Wiki_filter:... ,.t~,, "('{.'~.!~f.:.~l.~. r*1.';_,. :'.~f*!~~~~~~t1F~~ .. ~ **:*y . _:-(~::-~-:-*~:._-.. . ,- ' .....,.."_;:~~'.:*~* . ;:* .
. ,,~-~".;~::.;.~~: .. ;,**r***.*.:*: ,_,,.~ --*.*_.. r.:
- -~,:..... . . *'***
........ Prepared Far
., . -~/:.S
RTL-ENV-"'87-01 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Fc.w Salem Generating Stat.icn. Unit i: Doc:l<et No. 50=272 Salem Generating Staticmo Unit 2: Docket No. 50-<:H,,1 Hope Creel< Generating Stat ion: Doc:l<et No. 50-354 I 1986 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT
..JANUARY 1 TO DECEMBER 31, 1986 PUBLIC SERVICE ELECTRIC ANO GAS COMPANY Sy
~SE&G RESEARCH CORPORATION
; RESEA~CH ANO TESTING LABORATOR~
. *-.j APRIL 1987 I
. *-*......,.---~..,.------ *--~- ----------..-~-----:*--*-****----*-- -----.--* *-:-. -.--.--- -** *-* .. ----. ------ . - - **--*---**--**------.---:-~..:~ ...~if---'*-*--*** .. *-*--*---.--***-.-* - *- - -*
TABLE OF CONTENTS
SUMMARY
o***** *0*111e1oocieo11e1e1c()CDeoc**g****C11E10***C1**0*0C ' 1' 1 INTRODUCTION. eC1eeeC1Geeeeee*eeeeeeGeeeee *'. 0 ****** Cl
- 2 THE PROGRAM ** **oc*C1*e*****oeeeec1>eo1:1t1* 3 Objectives. c o o o e o o E> o o o o o o o Cl e o o o o *
- o o o *
- c.
OOOCIOCCCICO 3 sample Collection. oeooo0ceGeoooeoe O.eOCCICI000CO 4 Data Interpretation. e e e e Cl o Cl Cl* e e 0 G e e Cl e D. O Cl e !I* O G Cl e Cl Cl Cl Cl 0 e Cl Cl 5 Quality Assurance Program. 6 Program Changes~ *** . '**
. *t ID !~ e e e 7 RESULTS AND DISCUSSION. efloeooo1D*eoo 7 Atmospherieo 0 0 0 0 D 0 e cc c 0 Cl) 0 0 0 0 0 0 0 0 0 c' 0 (!) 0 *11 o' 0 0 C> ~;o 0. e Cl 0 0.0 0 0 Cl 0 0 7 Direct Radiation *** OCODOCCIC8()0000000 10 Terrestrial ** " o e OG Cl 0 00 00 OC!IOGGOO 0 0 0 Cl 10 Aquatic ***** * * * * * *. * * * *
- o * * * *
- c *
- e ~* **
- 0 16 PROGRAM DEVIATIONS. e e Cl e e e e e G Cl G Cl e e e e e e e e e ,e e e e e e e e e e Cl e e ID 8 e e e Cl e 19 CONCLUSIONS ****** ************cioeoeeooocoe C1eeeOGCOGeC1eee 19 PROGRAM OVERVIEW. 0000CICIOOCICOCICI080000DOCI
- e* Cl o. c a o *
- e
- o o
- c o o c
- 21 REFERENCES. ooocaooooeeeoccooooocociao eaeooooocoeooeeoooo 36 APPENDIX A PROGRAM
SUMMARY
. () ... 'ci. 0 0 Cl c Cl 0 39 APPENDIX B SAMPLE DESIGNATION AND:LOCATIONS. 51 APPENDIX C DATA TABLES ********** Q 0 '* . '* CIOOOOOOOOCCCOCIOCIOCOOO 59 APPENDIX D SYNOPSIS OF ANALYTICAL'PROCEDURESo Cl Cl 0.0. Cl 0 0 cc 0 113
"' APPENDIX E
SUMMARY
OF USEPA ENVIRONMENTAL RADIOACTIVITY
" LABORATORY INTERCOMPARISON STUDIES PROGRAM RESULTS 0°0 Cl c Cl* 0 . 0 0. c G G. 0° 0 0 . :0 0 0 161 APPENDIX F SYNOPSIS OF LAND USE CENSUS. 0 0 0 o_o 0 0 0 0 0 0 0 0. 0 0 .-0 ... 171 *. 1 1
I I
', *1
~
LIST OF. FIGU.RES .. *.. FIGURE* NUMBER. . FIGURE DESCRIPTION.
~~~~~~~~..;;..;;;..;;..~;;;...;..~.=...:;:;.;.::.=...:;~.;.;;.....;_~~~~~~~-*
PAGE
~
- 1. Comparison of Average Concentrations of Beta Emitters in Precipitation and in Air Particulates,.
1973 through 1986.................................. 26 lA. Comparisbn of Average Concentrations of Beta Emitters in Precipitation and in Air Particulates, 1983 th~ough 1986 ********* ~........................ 27
- 2. Average Ambient Radiation* Levels from Quarterly TLDs in the Vicinity of Artificial Island, 1973 through 1~86 .......* ** . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 28 2A. Comparison of Ambient Radiation Levels of Off-Site Indicator Station~ vs. Cont~ol Stations, 1982 through 1986 *************************************** 29
- 3. Average Concentrations of Iodine-131 in Milk in the Vicinity of Artificial Island, May 1974 through December 1986 **********.** :.- *.*************** * *******. 30 ~
3A. Average Concentrations of Iodine-131 in Milk in the Vicinity of Artificial Island, 1983 througn 1986 ... 31
*.**; 4. Average Concentrations of Beta Emitters and Potassium-40 in the Delaware River in the Vicinity *.* . *' 6f Artificialjisland, 1973 through 1986 ****** ~ ***** 32 4A. Average Concen~rations of Beta Emitters and Potassium-40 in the Delaware River in the Vicinity of Artificial Island, 1983 through 1986 ************ 33
- s. Average Concentrations of Tritium in the Delaware River in the Vicinity of Artificial Island, 1973 through 1986* ..*.....*..*. *............*. *...*... :. ..... 34
- / ..
SA. Average Concentrations of Tritium in *the Delaware River in the Vicinity of Artificial Island, 1983
*.. ,.j through 1986 *************************** ~ ***********
1:1.
SUMMARY
During the per.iod from January l through December* 31, 1986;. the*. Research* and Testing Laboratory (RTL), PSE&G Research Cor.po-ration, has been responsible for the collection and analysis of all samples and the maintenance of sampling equipment connected with the Radiolog_ical Environmental Monitoring Program (llEMP'); at Artificial Island, Salem County, New Jersey. This program was designed to identify .and quantify concentra~ tions of radioactivity in various environmental media and ta quantify ambient radiation levels in therenvirons of Artificial Island. Due to the proximity of the Salem~and Hope Creek Gener-ating Stations a common REMP is beinci' co.hducted. Salem Gene.r-ating Station (SGS) Unit One became* crit:ic!al on December 11., 1976, thereby initiating the operational phase of the REBPo Data collected during the operaJ:,ion,al! phase served as a sourc:e.- of preoperational data for Salem Uqit ~wo and the Hope Creek Generating Station. Salem Unit Two achieved initial criticality on August 2, 1980 and the Hope Cre~k :G:enerating Station achieved initial criticality on June 28, 19:~6 ~ '! This report presents the results of thermoluminescent dosi~~t~i arid radiological analyses of environmental samples collected~d~iing 1986. A total of 4091 analyses were perf'ormed on 1615 environment.al samples during the period covered' by .this report.- Samples of air particulates, air iodine, surface, ground and drinking water, benthic organisms, sediment, milk, fish, crabs, vegeta-bles, game, fodder crops, meat, soi1,:* and precipitation were r: collected. Thermoluminescent dos~meter$ were* used to measure ambien~ radiation levels. Ambient radiation levels remained .at normal levels observed in previous years until May 9, 19~~ when radioactivity from the Chernobyl-4 reactor accident wa~ detected. According to reports provided to Western scientists at:the International Atomic Energy Agency conference on Chernc;>byl held in Vienna, Austria, it is now known that the accident occurred as a result of a
-~
poorly planned reactor experiment. Soviet plant personnel I deliberately took actions which blocked the plant's safeguard
. ' systems that would have automatically prevented the accidento
**: .. i This action resulted in a reactivity excursion accident in which the reactor became prompt c;ri.tical [ 24 I. The excursion resulted in a power escalation which resulted in fuel melting and finally
-, a steam explosion which prdp~lled fuel fragments, activation products and burning graphite into the environmente The intense heat of the graphite fire.provided a mechanism for the radio~
active fission products and activation products to_ become_. sufficiently buoyant to enter :the upper atmosphere [ 25].
'.*:~ Actions taken to fight the fire resulted in additional destruc~
tion of.the core which caused*airborne releases into the environment to fluctuated by several orders of magnitude for several days after the accident~
Estimates*: of projected :I-131 concentrations :i;n milk*. in the. town .... of Pr ipyat, . USSR. were .'reported*. as :high as 10 3, 700 ,*ooo pCi/L [ 25 l ~.
- The Soviets arid the Scandariavian countries.also.repcirted measur--
ing excessive concentrations of radioactivity in.soiis,, reindeer flesh, fish, wells, rainwater and goat milk.* .Since all releases from*our nuclear stations were within our technical -specifica-tions, the increases in radioactivity a~ measured in various environmental media in the vicinity of the Artificial Island were due to the accident at Chernobyl-4 and not to the operation of the Salem or Hope Creek. Generating Stations *. INTRODUCTION Artificial Island is the site of Salem and Hope Creek Generating Stations. The Salem -Generating Station (SGS) consists of two operating pressurized water nuclear power reactors. Salem Unit One has *a net rating of 1090 MWe (3338 MWt), and Salem Unit Two is rated at 1115 MWe (3411 MWt). The Hope Creek Generating Station (HCGS) is a boiling water nuclear power reactor which achieved initial criticality on June 28, 1986. The Hope Creek Unit has a* net rating of 1067 MWe (3293 MWt). Artificial .Island is a* man-made peninsula on the east bank of th Delaware River and was created by the deposition of hydraulic fill from dredging operations. It. is located in Lower Alloways Creek Township, Salem County, New Jersey *. The environment
- surrounding Artificial Island is characterized mainly by the Delaware River and Bay, extensive tidal marshlands, and low-lying meadowlands. 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 agriculture [7,8]. More specific informatfon
.on the demography, hydrology, meteorology, and land use of the area may be found *in the Environmental Beports [7,8], Environ-mental Statements [9,10], and the Updated Final Safety Analysis Report for SGS [11] and the Final Safety Analysis .Report for HCGS
.. [ 12]. /
Since 196a an off-site Radiological Environmental M6nitoring Program (REMP) has beeri conducted at the Artificial Island Site.
*Starting in December* 1972, more extensive radiological monitoring programs were. initiated. The operational REMP. was initiated in December 1976 when Salem Unit 1 achieved criticality. The
.. t. Research and Testing Laboratory (RTL), PSE&G Research Corpo-ration, a wholly-owned subsidiary of Public Service Electric and
. ~ .. *: . ~
.. *. Gas Company,. has been involved in the REMP since its inception
- The RTL is responsible for the collection of all radiological environmental samples, and, from 1973, through June, 1983, conducted a quality assurance program in which duplicates of a portion of those samples analyzed by the primary laboratory were also analyzed by the RTL. *
- 2
'-.~._..-...,."'."'-, ---*~-:**.---;--~ - : : : - - :- *. - : . : - - *~
... _,-~- ...
..... - . * - -- .. - .~*-::~-:-'-. -:~*-7""-~~--~---~~-~~.--:-: ~:---:*--~*-*.
.. - - - - - .- .- . "-;-"?- ------ ---** -*--;--* *--- -*--- -*-**
- From January1 1973, through. June, ,.1983 1.. Radiation Management
- Corporation (RMC) had primary responsib-ility. for _the analysis of all samples under the Artificial. Island REMP and the annual reporting of* results.
- RMC reports for the *the preopera tional phase from* 197 3 to 1976 and for *the operational phase from 1976 through 1982 are referenced in this report [l-3]. On July 1, 1983, the RTL assumed primary responsibility.for the analysis of all samples (except TLD's) arid the reporting of results.
Teledyne Isotopes (TI), Westwoo9, NJ, at that time was made responsible for third-party QA analyses and TLD's *. RTL reports for the operational phase from i983 to 1985 are refere~ced in this report [4~6].
' " t ;
This report summarizes the r.esu:lts from January l through December 31, 1986, for the* A;rtffi!cial Island Radiological Environmental Monitoring ~r~gram
- I: **
'1 THE PROGRAM t; r .t~
~ :-;
The operational phase of !th~ :;REMP was conducted in accordance with Section Sections 3/4~l~~and 6.9.1.10 of Appendix A to SGS Oper*ting Licenses DPR-7& and DPR-75 [14,15] and. Sections 3/4.12 and 6c9.l *. ~. of Appendix A to:HCGS Operating License NPF=57 [lSlo An overview of the program is provided in Table 1 (page 21). Radioanalytical data from samples collected under this program were compared with results from the preoperational phase. Differences between these periods were examined statistically, where applicable, to d~te~mine the effects, if any, of station operations. * *
- The REMP for the Artii~cial Island Site includes additional samples and analyses not specifically required by the Salem and Hope Creek Generating :Stations Technical Specifications. The summary tables in this r~port include these additional samples and analyses
- Objectives
. ., *. '
- l
' .; .~
i The objectives bf'.: th'e Operational Radiological* Environmental i Monitoring Program ~re:
! 1. To fulfill.~h~ obligations of the Radiological surveillance
_,' sections of the Technical Specifications for the Salem
. Generating"Station 1SGS) and the Hope Creek Generating
*. *j Station (HCGS).
- 2. To determine whether any significant increase occurs in the concentration'of radionuclides in critical pathways *
.. ~ I
. :. j
.******. . \'!'
- . j
~
'*1
*~--- *---~-;""'r~- ,---------**---~
... .. - . .. ,-.... c7 .. *--,..,..,*~~~~.;.;.,~.:- -- **-----..-- .. - _.... *----.----, ..... _ .*---.,:--*~~--- * ******-*r,***- -i-*-*
4. To determine-if SGS or HCGS has*~caused :an increase*in radidactive,inventory.of;long~lived radionuclides~. To detect any change .in ambient gamma.radiation.levels.
~he
- 5. To verify that SGS and HCGS operations have no detrimental effects on the health and safety of the public or on. the environment.
This report, as required by Section 6.9.1.10 of the Salem Technical Specifications, and Section 6.9.l.,6 of the Hope Creek Technical Specifications summarizes the findings of the 1986 REMP. Results of the four-year preoperational program which was conducted prior to the operation of any reactors on the Arti-ficial Island have been summarized for purposes of comparison with subsequent operational reports [2]. Sample Collection In order to meet the stated objectives, an appropriate opera-tional REMP .was developed." samples of var.ious media were selected to obtain data for the evaluation of the radiation dose to man and other organisms *. The selection of sample types was bas~d on: (1) established critical pathways for the transfer of radionuclides through the environment to man, and .(2) experience gained during the preoperat.ional phase. Sampling l.ocations were determined from site meteorology,* Delaware estuarine hydrology, local demography, and land uses~ Sampling locations were divided into two classes - indicator and control. Indicator statioris are those which are expected to manifest station effects, if any exist; control samples are collected at locations which are believed to be unaffected by station operations. Fluctuations in the le~els of radionuclides and direct radiation at indicator stations are evaluated with respect to analogous fluctuations at control. stations. Indicator and control station data.are also evaluated relative to preoper-ational data. Air particulates were 'collected on Schleicher-Schuell No. 25 glass fiber filters with low-volume air samplers. Iodine was collected from air by adsorption on TEDA-impregnated charcoal cartridges connected -in series after the air particulate filters. Air sample volumes were measured with calibrated dry-gas meters and were corrected to standard temperature and pressure. * . . . - : :**. ~
-~
Precipitation was collected in a. Wong Laboratory Automatic Precipitation Collector having a 95 square inch collection area. The collector is automatically covered during periods of* no precipi. ta ti on to exclude fallout resulting from dry. deposition *
- Samples were collected monthly and transferred to new polyethyle
- ' .1 4
bottles~ The collecto~~as rinsed~with distilled watet to ... include residual particulates-in the precipitation samples *
. Tritium results were corrected. f.or. the tritium. content *o*f the.
distilled water. Ambient radiation levels in the environs were measured with energy-compensated CaS04 (Dy) thermoluminescent dosimeters (TLD's) supplied and riead by Teledyne Isotopes. Packets for monthly and quarte~ly:exposure were placed on and around the Artificial Island Sit~ at various distances. Well water samples. were. collected monthly by PSE&G personnel and separate raw and ~~ea~ea potable water samples were composited daily by personnel.of~ the City of Salem water treatment plant.
*New two~gallon polyethy!lene containers were used .for all water samples. ;
I All estuarine sa,mples were collected by V. J. Schuler Associates f Inc. and delive~ed ~y PSE&G personnel. surface water samples were collected ~n!n~w containers which were rinsed twice with the sample medium p~i~rj t~ collection. Edible fish and crabs were taken by net, and~ f..rozen in sealed polyethylene containers. Benthos and sedim*it samples were taken with a bottom grab sampler. Milk samples were taken semi-monthly when cows were on pasture and monthly when cows were not grazing on open pasture. Samples were collected in hew polyethylene containers. Food products, fodder crops, game;~ and beef were sealed in new plastic bags or jarso All perishable samples were transported in ice chests, and no preservative$ wer~'added. Soil samples:.wh~ch *are collected once every three years were collected at several locations in New Jersey and Delaware. Appendix A describes and summarizes, in accordance with Section
- 6. 9. l ~ 10 of .the Salem TS and Section 6. 9 .1 *. 6
- of the Hope Creek TS, the enti~e*operational program as performed in 1986.
Appendix B.des~ribes the coding system which identifies sample
.' type and location. Table B-1 lists the sampling stations and the
., types of. samples collected at each station. These sampling 1 stations are indicated on maps B~l and B-2.
Data Inter~retation
*** ..... : Results. 0~*~11 analyses were grouped according to the analysis.
performed for each type of sample and are presented in the data tables : in :Appendix c. All results above the lower limit of detection (:LLD) are at a confidence level of +/- 2 sigma. This 1 represents: *the range of values into which 95% of repeated analyses of the same sample should fall. As defined in Regula-tory Guide:4.8, LLD is the smallest concentration of radioactive
*'" .J
- .**:Z
... -j
*j
. ..:~ .* .
l
-,....----;-***--;--*---*-- *--- -----.-~----**.:. --.-~.*.~r,f~
.. ..j--*-** *-* --*- -*---.*.*-*- *--.-*-**-*---.-*,-----.**---.- -- -- * --**--****.-**-**-.-- --*.**** .,. .. ______ ;-*---* -- --*---- .... - - - .- . I
I.
. material.* in *a sample that* will. yie-ld a' net count (above system*.
. backgrouIJ,dJ that wil,l. be detected* wi-.th 95% probabi*li°ty with only 5% probability of falsely concluding that a *blank observation represents a. "real signal". LLD i~ normally calculated as 4~66
*~
times one standard deviation of the background count or of the blank sample count as appropriate. The grouped data were averaged and standard deviations calculated in accordance with Appendix B of Reference 18. Thus, the 2 sigma deviation* of the averaged data represent sample and not analytical variability. When a group of d~ta was composed Of 50%* or more LLD values, averages were not calculated. Grab sampling is a useful and acceptable procedure for taking environmental samples of a medium in which the concentration of radionuclides i~ expected to vary slowly with time or where intermittent sampling is deemed sufficient to establish the radiological characteristic~ of the medium. 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 considered valid.
- Quality Assurance Program PSE&G Research Corporation, Research and Testing Laboratory (RTL), has a quality assurance program designed .to maximize confidence in the analytical procedures used. Approximately 20%
of the total analytical effort is spent on quality control, including process quality control, instrument quality control, interlaboratory cross-check analyses, and data review. The analytical methods utilized in this program are summarized in Appendix* D. The quality of the results obtained by the RTL is insured by the implementation of the Quality Assurance Program as described in . the Environmental Division Quality Assurance Plan [19,20] and the Environmental Division Procedures Manual [21]~. The internal
- quality control activity of the Laboratory includes the quality control of instrumentation, equipment and reagents; the use of reference standards in calibration, documentation of established procedures and computer programs, and analysis of duplicate and spiked samples. The external quality control activity is imple-mented through participation in the USEPA Laboratory Intercom-par ison Studies Prog*ram. These results are listed in Tables E-1 through E-5 in Appendix E
- I '*
'-.-----:_,,..,~-.,.---:-:----:-_--:--*.--, -~-.~-~~-
-~,,..,..-~---.-*""7""'~~-~~""'7~':~-..,..-;_. -*-:-.*----":"7.-**;*.*--...*--:**~-,.-----.*o---*-*-;- ..-*- *-- --
Program*changes* Location 2F4 from which milk~.fodder crops and soil were collected, terminated milk production in Sept~mber and was. replaced by location 2F7. No samples were missed due to this change. : RESULTS AND DISCUSSION The analy:ticai: results of the 1986 REMP samples are divided into categories ~a~ed on exposure pathways~ atmospheric, direct, terrestrt;al ~ .. ~nd aquatic. The analytical results for the 1986 REMP are *;summarized in Appendix A. The* data for individual sample~ ~r~*presented in Appendix Co This i~c~~~n discusses the data for samples colle~ted under the REMP. ;;ri:~:does not include the data from the quality assurance program ~~sc~ssed previously.
!: J. !! .
AtmosPheric
. Air Part!culates (Tables C-1, C-2, C-3)
The.* weekl:y air particulate samples were analyzed for gross alpha and gros$ beta. Quarterly composites of the weekly samples from each* station, were analyzed for specific gamma emitters and a
.single quarterly composite sample was analyzed for Sr-89 and sr~90. Total data recovery for the eight sampling stations du~in$ 1986 was 98.4 percent.
Concentrations were detected in 359 of the 416 weekly samples analy~ed for gross alpha emitters (Table C-1). Alpha concentra~ tions: ranged from 0.8 x io-3 to 22 x lo-3 pCi/m3 with the gr~n~ average for all stations being 2.6 x lo-3 pCi/m3. i Analysis of weekly air p~rticulate samples for gross beta (Table
..... --C=2) , indicated concentrations were detected in 410 of the 416
.";**samples ranging from 6.7 x io-3 to 370 x io~3 pCifm3, with
* ~he grand average for a11* stations being 41 x io-3 pCi/m3.
I Figure 1 indicates the relation between gross beta activity in
~ .' . ~ir particulates and precipitation for the preoperational and f'.*'.
f
- *~
operational periods, including the effects of atmospheric weapons
- .:.. .- .. *;: testing and the accident at the Chernobyl-4 nuclear power*
t! reactor.' Strontium~89 and sr-90 analyses are no longer required by the T*chnical Specifications for the Salem or Hope Creek Generating s.tat:ions. In order to maintain documentation of the ambient
*-. . 1l i r *
-* . -~---~-.---- ..! _,, --'-;:*.::-~-----~--- --*--------*-----**** --*-:---:*-----..--:-~ -~ ----~~--:-*--* - -..---- --- . *-~-*- *-* .. *- *-**- .---- **, _,______ --**-;- -------- **-- ... - . . . - --*--- *--- =--- .* ***-- - --.-- .*.-
levels of sr~a~ and .sr-90*in_the*air~surrounding tha stations,: . . strontium analyses are performed on.the -.lst quarterly: sarnpl~ from each location as a management* audit . sampl:e. : Strontium::-89 and
- Sr-90 was not detected in any of the e:l.ghtmorithly composited samples analyzed; LLD sensitivities ranged from <0*~3 x io-3 to
<2.0 x lo-3 pCi/m3 and from <0.2 x io-3 to <0.3 x lo-3 pCi/m3 for sr-89 and sr-90 respectively.
Results of gamma spectrometry indicated detectable levels o~ Be-7 in all of the 32 monthly composites, with a maximum of 110 x lo-3 pCi/m3. Berylium-7 is a naturally-occurring radionuclide attributed to cosmic ray activity in the atmosphere. During this reporting period detectable levels of Ru-103, Ru-106, cs-134, Cs-137, Ra-226, and Th-232 were noted in many of the locations sampled. Ruthenium-103 levels ranged from 7.5 x lo-3 to 9.2 x lo-3 pCi/m3. Ruthenium-106 levels ranged from 4.0 x lo-3 to 8.3 x lo-3 pCi/m3. Cesium-134 levels ranged from 8.4 x lo-3 to 10 x lo-~ pCi/m3. Cesium-137 levels ranged from 16 x lo-3 to 18 x lo-3 pCi/m3. In reviewing the data it is noted that Ru-103, Cs-134 and cs-137 levels increased significantly during the second quarter of 1986. The Ru-103; Cs-134 and cs-137 increased levels are not attribut-able to the operation of the Salem or Hope Cr~ek Generating
-" *. i Stations. Based on their respective effluent release reports, there were no releases of Ru-103, Cs-134 or Cs-137 during the second quarter (22,23]. The increased levels are attributable to the Chernobyl-4 reactor accident. since similar concentrations existed at indicator arid control station locations
- Radium-226 was also detected in one of the samples at a concen-tration of 1.2 x lo-3 pCi/m3, which is within the variations
*of the LLD sensitivities for the ~ther samples which.ranged from
<0.3 x lo-3 to <10 x lo-3 pCi/m3. Thorium-232 was detected
- in one of the samples at a concentration of 1.7 x la-3 pCi/m3.
.. : . ~
This value* is within the variations of the LLD sensitivities for the other samples which ranged from <l.l x l0-3 to <2.7 x lo-3 pCi/m3. Air Iodin&* (Table c-4)
. ;;-: ~
.,., cartridges for the adsorption of air*iodine were connected in
*series after each of the air particulate filters. The adsorption media in these cartridges is triethylenediamine (TEDA) impregnated charcoal.
Iodine-131 was below detectable levels for the first four months of the year until the week of May 5 when radioactive iodine
- originating from the Chernobyl-4 reactor accident was detected.
~ ..'
8 ., -.. . :~ . .. , . *-
I Iod.ine-131 was* detected at all locations during the three w.e::k<I.y* sampling periods starting on May 5 I l-986 ~nd. ending on May* '2:.7?, .. 1986. Elevated. levels p.ersisj:ed at. several locations du:ing the
- last. week. in May and. the . first* week in June. Levels as high as:.
'320 x lo-3 pCi/m3 were detected at two locations.* A value of :610 x io-3 pCi/m3 was measured in one of our management audit samples but was not used in calculating any of our av*ezra:.q-as be¢ause of the short sampling period. During the remainder: Q;f
'the year I-131 levels remained at levels below our LLD. The r.L.O sensitivities ranged from* <7. 7 x io-3 to <40 x io-3 pCi/u3: ..
The :increased I-131 levels are not, attributable to the ope*ra~t::iia11 i; ofi the Salem or Hope Creek Generating Stations. Based om th:eii.r respective effluent release reports, there was no significaint rel~ase of I~l31 during the second quarter [22,23]. All of the
~levated I-131 results are attributable to the Chernobyl-4
.teactor accident.
- ~
' r
~; r
* ; !:Pr~cipi tat ion (Tables c-6, C-7) i ::
- !iAlthough not required by the technical specifications, pre~:n.jpli-
,: tation samples were collected at location 2F2 in the town o*!
!Salem. Monthly samples were analyzed for gross alpha, gl'OS/$
*.beta, tritium, and gamma emitters. Gross alpha concentratic~s
- were detected in four of the. twelve samples analyzedo The
*results detected were 0.6, Oo9, 1.2 and 1.3 pCi/L. These ?"esults
- were within the* variation of the LLD sensitivities for the
' .remaining samples which ranged from <O. 3 to <l. 7 pCi/L. Beta activity was detected in all twelve monthly samples and ranged from 1.9 to 15 pCi/L, with an average of 5.5 pCi/L. Tritium Nas not detected in any of the twelve samples analyzed; LLD sensi-tivities ranged from <130 to <140 pCi/L.
Gamma analysis was performed on each of the monthly samples except for January, 1986 when there was insufficient precipita~ tion. Detectable levels of I~l31 and cs-137 were found in one sample during May 1986 at a concentration of 7.4 and 4.8 pCi/L
- -~..<*
.. respectivelyo The increase in I-131 and Cs=l37 levels was
-)1'
-~T:?~~~-*~ :
attributed to the Chernobyl-4 re~ctor accident since simila~
- , ,* .... levels of iodine and cesium were measured in precipitation
.* ;:-; .f: collected at the Research and Testing Laboratory location 3H3v
' ,~
- I I
located 110 miles away from the Salem and Hope Creek Stations& Otherwise levels of I~l31 and Cs-137 were below detectable I
. I I
levelsQ Levels of other gamma emitters were comparable to levels observed-in previous years. The presence of Be=7 was detected in each
'. ~
sample at concentrations ranging from 35 to 71 pCi/L. Radium-226
! . was detected in three samples at a concentration of 7.0~ ~.l and
. ' 4.8 pCi/L. These values are within the variations of the LLD sensitivities for the other samples which ranged- from <4.i to
**j *:
I l
'l*1 ""
~
.l
., .: *1 **.
<f:'.t~*~:JT--*-*~-----~------------~~*--*-.----------*- - . ----*;::--*--:~ ~.--*---.---- **:-----*:-* . -----*---.-*-- .. ...,, ------*- *--:**-- - --*.-- ... - .... -- --- . ------- -- ---.
<13 pCi/L.
- A slightly detectable leyel of. natural*ly~qccurring
- K-40 .was dete.cted in one 'sample ,a:-t *a* level df
- s~t pCi/L du;r.ing* t*he
- September ~ampling periotj. Hbwever, this .value wa~ ~ith~n the ..
variations of .the LLD sensitivities measured throughqut.the year. Thorium-232 was detected in orte sam~le ~u;ring th~ A~guit ~a~pling
- - .. period at a concentration of 7.5 pCi/L. This value is within the variations of the LLD sensitivities for the other samples which ranged from <7.2 to <21 pCi/L~ All other gamma emitters searched for were below the LLD.
Direct Radiation (Tables t-8, c-9) A total of 41 locations were monitored for direct radiation during 1986, including 6 on-site locations, 29 off-site locations within the 10 mile zone, and 6 control locations beyond 10 miles. Monthly and quarterly measurements were made at the 6 on-site stations and at 15 off-site indicator stations~ and 3 control. stations. An additional 14 quarterly measurements were taken at* schools and population centers with 3 additional controls beyond the 10 mile zone in Delaware. Fou*r readings for each TLD at each location were taken in order to obtain a more statistically valid result. The average dose
- rate for the 15 monthly off-site indicator Ttn*s was 5.8 milli-ra:ds per standard month, and the corresponding averaged control.
dose rate was 6.4.millirads per standard month. The average dose rate for the 29 quarterly off-site indicator TLD's was 5.1 millirads per standard month, and the averaged control rate was 5.6. For these measurements, the rad is considered equivalent to the rem, in accordance with 10CFR20.4. In Figure 2, the average radiation levels are plotted for the 13 year period through 1986. Figure 2A shows the* monthly averages of the off-sit~ indicator stations and the control stations for 1982 through 1986. Ambient radiation levels during 1986 were comparable to those obtained during 1985. I Terrestrial Milk (Tables C~lO, c-11, C-12) Milk samples were collected in accordance with the Salem and Hope Creek Technical Specifications at six local dairy farms. During this reporting period, one dairy operator terminated operations (location 2F4) and, as required by the SGS and HCGS Technical . Specification, a replacement location (lbcation 2F7) was found and added to.the surveillance program. Samples were collected semi-monthly* when cows were on pasture and monthly when cows w e r . ... not on pasture. . . . . . .
- Each sample was analyzed. for .I:""l31 and gamma emi t.ters. I.n. addi-tion, aithough not* sp.ecif ic~lly required by the SGS and. liCGS Technical* Specifications,*~ne sample from each location was analyzed for:: -Sr..;.89 and Sr-90 in order to maintain the data base developed *in prior years. All sr-89 results were below detect-*
able levels. Strontium-90 results were comparable at indicatar and control locations and averaged 2.1 pCi/L. Following the nuclear accident at the Chernobyl-4 reactor in the Soviet Onion,* iodine-131 levels increased significantly. Esti-mates of the quantity of I-131 released from the Chernobyl-4
.. reactor indicate that as much as 20% of the core inventory of
' I-131 could have been discharged (25]. Samples collected during the third week in May and analyzed for I-131 using an ion
' exchange resin method, ranged between 11 and 53 pCi/L with the highest result obtained at the control station location. The elevated levels persisted during June and the first week of July.
The mean of the indicator locations which had detectable levels of I-131 was 10 pCi/L while the mean at the control locations
;' : which had detectable concentrations of I-131 was 19 pCi/L.
Levels of I-131 iri milk did not return to normal levels until the
.. third week of July. All other samples collected during the year
*, indicated no discernible I-131 activity. Figure 3 and 3A shows 11 the average I-131 activity measured during this year compared to results obtained in.previous yearso Table c~10 lists the results and shows that sensitivities ranged from <Ogl to <0.8 pCi/t. ..
Gamma spectrometry showed detectable concentrations of naturally= occurring K-40 in all samples. The annual mean concentration measured at indicator locations averaged 1400 pCi/L, and the annual mean concentration measured at control locations averaged 1400 pCi/L~ Sodium-22 was detected in one sample in May at a concentration of 4.6 pCi/L. The Na-22 LLDs for all stations ranged from <l.O to <6.4 pCi/L. Manganese-54 was detected in only one sample at a l~vel of 2.9 pCi/L. The Mn-54 LLDs for all stations ranged from <0.7 to <4.9 pCi/L. Zinc-65 was detected in only one sample ~t a concentration of 11 pCi/L. Cesium-137 was detected in six samples at levels which ranged from 3.3 to 5.1 pCi/L. Since the cs~l37 LLDs for all stations ranged from
<2.3 to <5.l pCi/L the positive results are not considered as being significant. Levels as high as 14 pCi/L ~ere detected during the preoperational program [2]e Radium~226 was detected in four samples at concentrations comparable to levels observed
.... . during the preopecational program (2]
- Although not as sensitive as the ion exchange method, I-131 results were also obtained in the gamma scan and .the values *were
*>.*-*.: comparable to the results obtained using the anion exchange resin method. Iodine~l31 levels obtained from the gamma scan averaged 20 pCi/L at the indicator locations which had detectable levels and 36 pCi/L at the control locations. All other results searched for were below LLD.
Concentrations of. I-.131 in milk. in* the 2nd .. _quarter* .exceed~d .. the-* values in.Table.3~12~2 of *the SGS and~acGs~TechQical Specifica~
- tions. These concentrations are not . attributed* to_ the. op~ration.
of the Salem and Hope Creek Generating Stations *... Based up.on their respective effluent release reports, th~re was ~o signifi-cant release of I-131 during the 2nd quarter (22; 23]. Well Water (Tables c-14, C-15, c-16) Although wells in. the vicinity of the Salem and Hope Creek Generating Statiori are not anticipated to be affected by plant operations, water samples were collected monthly from two indi-cator wells and one control well. Each.sample was analyzed for gross alpha, gross beta, tritium, potassium-40 and gamma emitters. Quatterly composites were analyzed for.radiostrontium. Gross ~lpha concentrations from 0.6 to. 2.D pCi/L were de~ected in seven of the.indicator locations, with LLD sensitivities for the other analyses ranging f~om ~0.5 to <3.7 pCi/i. G~o~s beta activity was detected in all of the samples. The mean activity for the iridicator locatio~s wa~ 7.6 pCi/L with a range of 2.0 to ts pCi/L; mean activity for the control location was 7.4 pCi/L with a range of 2.5 to 9.5 pCi/L. PotassiiJ.m-40 in _each monthly
- sample was-determined by atomic absorption* spectroscopy *. *Mean .
activi~y for the indicator locations was *8.7 pCi/L with a range of 2.7 to 16 pci/L, and mean activity for the control location was 9.4* pCi/L with a range of 7.4 to 17 pCi/L.
- All tritium results were at LLD levels of <130 to <140 pci/L.. Neither Sr-89 nor sr~90 was dete_cted in any of the samples. The LLD sensi ti v-i ties for Sr-89 ranged from <0.4 to <11 pCi/L, and from <0.3 to
<0.6 pCi/L for sr-90.
Gamma spectrometry was performed on each sample. Potassium-40, Ra-226 and Th-232 were the orily gamma emitters detected.
*.-j Although not as sensitive-as atomic absorption, K-40 was detected by gamma scan in eight samples at lev*els ranging from 35 to 4 7
.pci/L. Radium-226 was detected in seventeen of the twenty four indicator locations and *eleven of the twelve control station
'***. ** lbcations at values which rang~d from a low 2.9 pci/L to a *high of 170 pCi/L~ The range of the Ra-226 values were higher than values observed in previous years. We believe that results are
-, higher due to a procedural change in which the samples are no
*longer boiled down to a 100 ml standard geometry. This change results in less radon daughters being removed from the sample.
Since Ra-226 is an alpha emitter, its identificatioh by gamma
-isotopic analysis is obtained by counting the Pb-214 gamma rays
' .. .~ from the daughter products. We believe that values currently being observed* are indicative of the concentrations which have
. always existed. Concentrations of Th-232 were d~tected in two
- ,.* indicator station samples a*t B. 4 and* 10 pCi/L*; *LLD values for the other thirty f_our samples. ranged. from <4. 6 *to <10 pCi/L.
12 -* + *:;::**,;
;-*. * *:-l
Potable Water. (Tables C"'."'17,
- C-18, c-19)
Both raw and treat~d water samples were collected from the Salem water treatrnenb.plant. Each consisted. of daily aliquots composited into a monthly sample. The* raw water source for this plant is Laurel Lake and adjacent wells. Each sample was analyzed for gross alpha, gross beta, K-40, tr.itium, and gamma emitters. Quarterly composites of raw and treated water were analyzed for sr-89, sr-90. Detectable alpha activity was noted in eleven water samples at concentrations ranging from 0.5 to 1.5 pCi/L; LLD sensitivities ranged from <0.5 to <2.4 pCi/L (raw), and from <0.5 to <l.9 pCi/L (treated). Beta activity was observed in all of the 24 monthly samples witp ranges of 2.0 to 13 pCi/L (raw), and 1.7 to 8.2 (treated), and averages of 3.6 pCi/L (raw) and 3.6 pCi/L (treated). Potassium-40 concentrations for raw and treated samples *were similar but lower than the gross beta activity in all cases. The K-40 average for the raw and treated samples was 1.6 and 2.0 pCi/L respectively. Tritium activity was observed in one of the twenty-four samples at a concentration of 150 pCi/L. strontium-89 was detected in one of the eight quarterly composite
- water samples at a concentration of 0.8 pCi/L; LLD sensitivities ranged from <0.5 to <l.6 pCi/L for Sr-89. Strontium-90 was not detected in any of the water samples and the LLDs ranged from
<0.4 to <l.O pCi/L for Sr-90. Gamma spectrometry detected Ru-103 in one sample at 2.6 pCi/L; Ra-226 in three samples at concentra~
tions ranging from 2.6 to 8.4 pCi/L; and Th-232 in three samples at concentrations ranging from 5.7 to 6.8 pCi/L. The LLDs ranged from <0.5 to <5.6 pCi/L for Ru-103; .from <3.7 to <5.8 pCi/L for Ra-226 and from <4.9 to <9.6 for Th-232. Food Products (Table C-20) Although vegetables in the region are not irrigated with water in which liquid plant effluents have been discharged, a variety of food products grown in the area for human consumption were sampled. These included sweet corn, peppers, asparagus, cabbage, and tomatoes *
.1 All samples contained naturally occurring K-40 at concentrations from 910 to 3400 pCi/kg~wet, with an average for all samples of 2100 pCi/kg-wet. Berylium-7 was detected in one sample at a concentration of 24 pCi/kg=wet. Iodine-131 was detected in one indicator location and one control location at levels of 33 and 62 pCi/kg-wet for samples.collected during May. The increased I-131 levels are not attributable to the operation of the Salem or Hope Creek Generating StationsG Based on their respective f:'
13 . - -~
---*-- ..... --* --.*-**-------- *--:.-~---~--:-;:-:~----; ..... --*---- - --- ---~----*-;-,,,**-*-- .....--- - -*. -- . --. -* --------- --*-** . -- *:-*- *-*-- *- ..,.... *..... ***.**--,.----.**.~ .---~-,.- ***-
.*.* ~
effluent releasereports;\:here were no significant release of I-131 during the second quarter [22,23] ... All of ~h~ elevated: I-131 results are attributable to the Chernobyl-4 reactor* accident. A trace of Cs-137 was detected in tomatoes from two control stations ~t 1.5 and 2.1 pCi/kg-wet. Since the LLD sensitivities ranged from <l.6 to <24 pCi/kg-wet, the detectable levels of Cs-137.are not considered as being significant. Concentrations of Ra-226 were detected in three samples ranging from 8.3 to 68 pCi/kg-wet. The two highest concentrations measured occurred at two different control locations at concentrations which were comparable. to *the LLD-values. The LLD values ranged from <1.8 to
<51 pCi/kg-wet. Thorium-232 was detected i~ one tomato sample at a concentration of s.s*pci/kg-wet~ The LLDs ranged from <5.5 to <110 pCi/kg-wet for a variety of food products collected during the reporting period.
Game (Table C-21) Since muskrats inhabit the marsh lands surrounding the-~ite, and since muskiatsare consumed by local inhabitants,*two muskrat
- samples were collected and analyzed for gamma emitters. Gamma scans of the. flesh indicated the presence of naturally-occurring K~40 in both. samples at concentrations of 2200 and 2400
.. i pCi/kg-wet
- Beef (Table C-21)
Although not required by the SGS or HCGS Technical Specifica-tions, beef sampies are collected, when* available, twice a year. The second semi-annual beef sample was not obtained. Farmers from
.whose animals the samples are normally obtained did* not slaughter
*from July through December 1986 *.
Analysis of the flesh for gamma emitters indicated the presence of naturally-occurring K-40 at concentrations of 2500 pCi/kg-wet, * .. *.. *: . and Cs-137 at 7.3 pCi/kg-wet
- Fodder Crops *(Table C-22)
*Samples of *crops normally used as cattle feed were collected at nine locations where these products may be a significant element in the food-chain pathway. Six of the locations are or ~ere mil sampling stations*.
- Samples collected .for *wet, gamma an*alysis
., .. *-J included barley, feed corn, corn silage and soybeans. - 14
Potassium=40. was detected in all of. the nine samples* at con*cen~ trations. ranging from 2300 to. 15000 pCi/kg-wet, wi_th an average:* af 7000 pCi/kg-wet. Berylium-7, from the atmosphere, was found .. in five of the samples at concentrations. ranging from 37D to 1400 pCi/kg-wet. Cesium-137 was detected in one of our control loca-tions at a concentration of 13 pCi/kg-wet. The LLDs for Cs-137 ranged from <17 to <54 pCi/kg=wet. Radium-226 and Th~232 wer::e detected in two different samples at a concentrations of 35 and 170 pCi/kg-wet. The LLDs for the Ra-226 ranged from <36 tQ <lGO pCi/kg-wet while the LLDs for Th-232 ranged from <59 to <l3U pCi/kg-wet.
- Soil (Table C-23)
Soil is sampled every three years at 16 locations, including two controls, and analyzed for Sr-90 and gamma emitters. Sanples are collected at each station in areas that have been relatively undisturbed since the last collection in order to determine any change in the radionuclide inventory of the area. The concentrations of sr-90 for the indicator stations ranged from 27 to 140 pCi/kg-dry with an average. of 91 pCi/kg~dry... The two control stations yielded results of 56 and 130 pCi/kq~dry with an average of 93 pCi/kg. Since the purpose of these samples is to determine if the operation of the nuclear stations is resulting in an increase in the inventory of long lived reactor produced radionuclides in the environment, the values obtained were compared to data reported in previous years. Averages for the indicator stations were 220 pCi/kg in 1977, 149 pCi/k~ in 1980, and 125 pCi/kg in 1983. Averages for the control stations were 430 pCi/kg in 1977, 195 pCi/kg, and 93 pCi/kg in 1983. The gradual decrease is perhaps attributable to the wash~out and decay of weapons testing fall-out from the l950's to the 1960 9 s. Gamma spectrometry of these samples showed detectable concentra-tions of the naturally occurring radionuclides (K~40, Ra-226, and_ Th-232) and the fission product Nb-95 and cs~l37. The Nb-95 concentrations found ranged from 34 to 63 pCi/kg with an ave~aqe of 48 pCi/kg. These results are comparable to measurements obtained during the preoperational studies in which levels* of Nb-95 of 90 pCi/kg were observed [2]. The cs-137 at the indicator stations ranged from 78 to 1500 pCi/kg with an average
. - -:~
of 393 pCi/kg. The two control stations were 210 and 690 pCi/kg
.. with an average of 450 pCi/kg. Averages for the indicator stations were 710 pCi/kg in 1977f 445 pCi/kg in 1980 and 440
. _]
-.. ! pCi/kg in 1983. Averages for the control stations were 620 pCi/kg in 1977, 650 pCi/kg in 1980 and 615 pCi/kg in 1983.
.,l
.. '
- 0
~ : .. i
- Aquatic surface Water ( Tabies
- c-24, c-25., c-26, C-27 ).
Surface water samples were collected morithly at five locations in the Delaware estuary. One location is at the outfall area, another is downstream from *the outfall area, and another is directly west of the outfall area at the mouth of the Appoquini-mink River. Two upstream locations are in the Delaware River and at the mouth of the Chesapeake and Delaware Canal, the latter being sampled when the flow is* from the Canal into the river. Station 12Cl, at the mouth of the Appoquinimink River, serves as the operational-control. All surface water samples were analyzed monthly for gross alpha and gross beta emitters, and gamma emitters. Quarterly composites were analyzed for tritium. Alpha concentrations were detected in 19 of the 48 indicator samples and in four of the twelve control samples, with concen-trations for all samples. ranging from 0. 7 to 12 pCi/L; LLD sensitivities which ranged from <0.6 to <4.7 pCi/L. Beta con-centrations for the indicator stations ranged from 2.4 to 130 pCi/L with an average of 51 pCi/L, and for the control statioti,
' from 7.5 to 81 pCi/L with an average of 45-pCi/L. *Nearly all of
"* the beta activity* was contributed by K-40, a natural component *
->'. *j::;*.
*of salt and brackish waters, as illustrated in Figure 4, which compares averaged gross beta and K-40 concentrations.
Tritium ~onceritrations for the indicate~ statio~s ranged from 130 to 270 pCi/L. The average of the eight indicator samples with detectable *1.evels of tritium was 160 pCi/L. Tritium was detected in one of the four control samples at 150 pCi/L. Levels for the years 1973 through 1986 are plotted in Figure 5. Gamma spectrometric analysis of surface. water samples -showed detectable concentrations of K-40 in 34 of the 48 samples. The average K-40 concentration at the indicator stations was 88
--{
pCi/L, .with a range of 33 to 160 pCi/L. Average K~4o concentra-tio~ at the control station, where detectable concentrations
*_were found in nine of the twelve samples, was 70 pCi/L with a range of 29 to 95 pCi/L. Radium-226 was detected in seven indicator station samples, with the*values ranging from 2.6 to 11 pCi/L, and one control station sample at 25 pCi/L. Radium-226 concentrations in this year's samples were higher than in _
j *_previous years due to procedural change in which water samples
' are no longer boiled down to a 100 ml standard geometry. This change results in less radon daughters being removed from the sample. Since Ra-226 is an alpha emitter, its identification by gamma isotopic.analysis is obtained by counting the Pb-214 daughter product. .concentrations of Th-232 in five indicator station samples were detected rangingfrom 5.3 to 9.3 pCi/L and one control sample at 9 .2 pCi/L.. LLD sensitivities for Th-232 ranged from <5.3 to <9.3 pCi/L.
16
Fish (Tables c~28, C~29) Edible species of *fish were collected semi-annually at thre.e locations and analyzed .for tritium and gamma .emitters (flesh~ and for sr-89 and sr-90 (bones). . Samples included channel catfis.hi, summer flounder, weakfish and bluefish. Gamma spectrometry of these samples indicated K-40 in all s.i~ samples at an average concentration of 3000 pCi/kg-wet with a range of 2700. to 3300 pCi/kg-wet. One of the six samples had detectable concentrations of Cs-137 with a value of 8.3 pCi/kg-wet. The LLD sensitivity for the other five samples
.~
ranged from <12 to <19 pCi/kg~wet. Radium-226 was detected in the second semi-annual sample at two locations, at concentrations of 33 and 41 pCi/kg-wet. Levels as high as 130 pCi/kg-wet ~ere observed during the preoperational period [2]. Thorium-232 WJas detected in the ~irst semi-annual sample from the control station at a concentration of 29 pCi/kg~wet. LLD sensitivities for Th~232 ranged from <31 to <61 pCi/kg-wet. s~rontium-89 was detected in one of the six bone samples, with a concentration of 330 pCi/kg-dry. The LLD sensitivities for the other six samples ranged from <40 to <75 pCi/kg-dry. Two of the four semi-annual indicator samples analyzed for sr-90 had detect-able concentrations of 34 and 240 pCi/kg~dcyf with an average of 137 pCi/kg~dry. The level seen at the control location fo~ the sample collected during the period from May 12 to May l~, 1986 was 1500 pCi/kg-dry. ~ review of station effluent release records does not indicate any significant quantity of Sr-89 or sr-90 being discharged during the first half of the year [231. Tritium analyses were performed on the aqueous fraction of the flesh portions* of these samples. None of the samples analyzed indicated any detectable concentrations of tritium. Blue Crab (Table C-30)
. *. *, . : .~
Blue crab samples were collected semi~annually at two locations, and the edible portions were analyzed for gamma emitters, sr-89
.. -~-
and.Sr~90, and tritium in the aqueous fraction.
***. )
_- .. The shells were also analyzed for Sr=89 and Sr-900
-*.'-~
Potassium-40 was detected in the flesh portion of all four samples. Potassium-40 levels ranged from 1700 to 2000 pCi/kg=wet with an average of 1800 pCi/kg-wet. Radium-226 was detected in two samples from the control location at concentrations of 19 and 20 pCi/kg-wet~ Strontium-89 was not detected in any of the four flesh samples; LLD sensitivities rariged from <28 to <46 pCi/kg-wet. One shell sample from the f i.rst semi-annual set had detectable levels of Sr-89 at 300 pCi/kg~dry; and LLD sensitivities ranging from <67 to <89 pCi/kg-dry. ~imiliar concentrations were observed during the preoperational program [2]. 17
*.*.j
*1
- ' --* 1
- J, -~-~--:---**------:------- ~----*-~*---- -;--*.----:--~-**-:*-:--*- *- -----... -------------* **--. -~*-* *.*----*** ----:- - -**-** ---*- ---------,, -*- .... *--.--- .-* - - - -- *.-.-**- - -- *- . --- -** . -*
- Strontium-90 was not . detected in any of the edible flesh portion$*'-*
of the blue crab samples. The*LLD.sensitiviti9s.:for these samples ranged from <18 to <24 pCi/kg~wet for *Sr-90. All four shell samples had detectable concentrations of.Sr-90 ranging from 150 to 490 pCi/kg-dry with an average of 340 pCi/kg-dry. - Tritium activity was not detected in the aqueous fraction of any of the edible flesh portion of the four blue crab samples collected. The LLD sensitivity achieved, in all cases was <50 pCi/kg-wet. Benthic Organisms and Sediment . (Tables c-31, C-32) Benthic organisms were separated from the bottom sediment and analyzed for gamma emitters. All gamma emitters searched for
*were <LLD sensitivities. It should be noted ~hat, due to the very small sample sizes for all samples, satisfactory gamma sensitivities could not be achieved.
Sediment samples of sufficient size were availabla to enable sensitivity requirements for both Sr-90 and gamma emitters to be
~~ I met. Levels of Sr-90 were* below LLD (<19 to <38 pCi/kg-dry)
- ' ~~-~'.:. *in all twelve samples. analyzed. Results of gamma spectrometry
- indicated the presence o~ naturally-occurring K-40, Ra-226, and
". Th-232 in all twelve samples with averages of 10000, 620, and 740 pCi/kg-dry res'pectively. Concentrations of the .gamma emitters, i
i Mn-54, co-58, co-60, cs-134 and Cs-137 were also detetted.
*Manganese-54 was detected in three. samples at an average concen-tration of 26 pCi/kg-dry with LLDs ranging from. <18 to <38 pCi/kg-dry. Concentrations of Co-58 were detected in four samples ranging from 31 to 80 pCi/kg-dry, with the average being 57 pCi/kg-dry. Cobalt-58 LLD sensitivities for the remaining four samples ranged from <23 to <38 pCi/kg-dry. .concentrations
*Of co-60 were detected in eight samples *ranging from 37 to 110 pCi/kg-dry, with the average being 72 pCi/kg-dry. Cobalt-60 LLD
.. ' . ~- ' sensitivities for .the remaining four samples ranged from <36 to
<48 pCi/kg-dry. Cesium-134 concentrations were detected. in four*
samples at levels ranging from 46 to .82 pCi/kg-dry, with LLDs ranging from <16 to <3~ pCi/kg-dry. _Cesium-137 concentrations in four samples ranged from 49* to 82 pCi/kg-dry: LLD sensitiv-ities ranged from <16 to <39 pCi/kg-dry.
*.._\
. I
. I
. 1
*.5
.-i
~ .* i
. : .i ~~{ lS*
- .:.j
PROGRAM DEVIATIONS Air particulate/iodine sampler location 252 for the week be,gim~ *.. > ning January 13, was operational for only 1.2 days out of a 7.d~Y. sampling week due to an instrument malfunction. Direct radiation measurement results from location 6Fl for Mai~~h are unavailable: TLDs were missing from the field location. Air particulate/iodine sampler location 5Dl for the week be~im ning May 12, was operational for only 2ol days out of a 1 da..y sampling week due to an_ instrument malfunction. Air particulate/iodine sampler location 16El for the week begin-ning May 27, was operational for only 0.6 days out of a 1 da~ sampling week due to ari instrument malfunctiono Iodine-131 results from location 3H3 for the week beginnin9 June 2, are unavailable due to a faulty sampling assemblye Milk gamma results from location 3Gl for the September 22-23~ sample are unavailable due to loss of sample during prepara.tian .. Air particulate/iodine. sampler location. 252 for the week begia-ning November 24, was operational for only Oo2 days out of a 1. day sampling week due to an instrument malfunctiono Air particulate/iodine sampler location 3H3 for the week begin= ning December l, was operational for only 2.0 days out of a 7! day sampling week due to an instrument malfunction. Air particulate/iodine sampler location SDl for the week begin-ning December 15, was operational for only 0.3 days out of a 7 day sampling week due to an instrument malfunction.
., .1 CONCLUSIONS The Radiological Environmental Monitoring Program for Artificial
' j
-. ; Island was conducted during 1986 in accordance with the SGS and HCGS Technical Specifications. The objectives of the program
- .j were met during this periodc The data collected assists in demonstrating that SGS Units One and Two and HCGS were operated in compliance with Technical Specifications.
J The ability of the program to detect radionuclides released from
*. the accident at the Chernobyl-4 reactor, has demonstrated tbat the program being conducted is effective in sensing small.
increases in radiation levels. It is evident that air, milk, water, food products and soil surrounding the Chernobyl power reactor complex were seriously contaminated as a result of the
- 0 19
;---~--***-*-- ** *.--*- **-:**-* **.,.--*,.--*- -*-*: ~, *-.-*--* -*.,*---*~--****--* *~ .. ,.,..* ,** 7""-;*-;-:-"T:--*o *, .-----*,.- -.--.**** ._ __ , *-*-
accident *.. However~ radiation levels measured.in the United* States due.*to the accident were not affected in*terms of public, health and safety. Ambient radiation le~els as measured .in our program were relatively low, averaging 5.1.mrad/std. month. Although ambient radiation levels remained normal, our surveil-* lance programs were sufficiently sensitive to detect radio-nuclides in the environment which were discharged from the damaged Chernobyl~4 reactor. The concentrations measured and provided in this report although higher than normal were not excessive. In fact, with the exception of I-131 in milk, none of the concentration found exceeded the reporting levels estab-lish~d by the USNRC. The reporting levels establlshed in the Technical Specifications applies only to abnormal environmental measurements caused by the licensed power reactor. None of the I-131 detected in milk was due to the o*peration of the Salem or Hope Creek reactors. The operation of SGS Units One and Two and HCGS had no significant effect on the radiological character-istics of the environs of Artificial Island.
*~'
. . ~ .:
20
- . -~ ~ .~
. -- :~:::~~-r:=---~*~*-~-v:--_-:-.:*-;:~:;;.::-*-::--::-~-~,---.-.*.----:--:*--.-~-.-~--~*-:*--:-.-:-.::_--:- ...--_-_--......... -.-.. --~....-~----.--~-~,.---:-*- *-- ------.... --::-*-:--.--* .. -,..-.:;*-::.---~ -7**-*-~--<' ;:-
., '-:~ *'.
*1
.~ _:*.:. .... 'r ~: .* .,: * ***>
.. :.: ... ; ~: . '" . . . ~ * *£*_ ":. :. '. _._ ... . -~*****-* .-.
l i
*1 .1 I
TABLE l 1986 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM S!A'.l!IOll CODE COLLECTION MED!Uli INDICATOR CONTROL FREQUENCY TYPE/FREQUENCY* OF ANALYSIS I. ATMOSPHERIC ENVIRONMENT
- a. Air Particulate 2S2 501 l6El lFl 3H3 Weekly Gross alpha/weekly 5Sl lODl 2F2 Gross beta/weekly Sr-89 & Sr-90/first quarterly**
Gamma scan/quarterly
- b. Air Iodine 2S2 SDl 16El lFl 3H3 Weekly Iodine-131/weekly
!\'\) 5Sl 1001 2F2 Ii--'
*i
*.*1 c. Precipitation 2F2 ll!onthly Gross alpha/monthly Gross beta/monthly Tritium/monthly 1 Gamma scan/monthly i
- u. DIRECT RADIATION
- a. Thermoluminescent 2S2 501 2El lFl 3Gl :nu Monthly & Gamma dose/monthly Dosimeters 5Sl lODl 3El :?F2 3H3 Quarterly Gamma dose/quarterly 5S2 HDl 13El 2F6 7Sl 16El 5Fl lOSl 6Fl HS]. 7F2 llFl 13F4 I I
... .- .. _ *-*~- **-*-. .. .
~ .
l
..:i
; TABLE 1 (cont'd)
.*,\
J .i 1986 ARTIFICIAL. ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
*1
*I
..:] MEDIUM ST!T!QH INDICATOR CODE CONTROL COLLECTION
¥R~QUENCY TYPE/FREQUENCY* OF ANALYSIS
. ~:1
.~:* .
.~:; :::*--~.
. J j
.* . <1 ~- Thermoluminescent 4D2 ~El 2F5 1G3 . :, Qii_arterly Gamma dose/quarterly
.. ] Dosimeters (cont'd) 11E2 3F2 lOGl
.J .12El 3F3 16.Gl
- i 10F2
.l iI 12Fl
'I 13F2 I 13F3 I
*'I 14F2
. .I
. :1 15F3
..~
*.1 j
~
16F2
;! l\)
.i.
- 1. III. TERRESTRIAL ENVIRONMENT
- a. Hilk 13E3 2F4 3Gl Monthly Iodine-131/monthly 2F7*** (animals not Gamma scan/monthly
~F2 on pasture) 11F3 Semi-monthly Iodine-131/semi-monthly 14Fl (animals on Gamma scan/semi-monthly on pasture) Sr-89 & Sr-90/July, first
- collection** .
- b. Well Water 2s3 5Dl 3El Monthly Gross alpha/m~ntnly Gr-.oss peta/monthly Potassium-40/monthly Tritium/monthly Gamma scan/monthly Sr--89 & Sr--90/quar-ter-ly
-*~ *. .'.. *,..;_...;_.. __ _
TABLE ]. (cont'd) 1986 ARTU'ICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM S'.£~'.l!IQH CODE COLLECTION HEDIUH INDICATOR CONTROL FREQUENCY TYPE/FREQUENCY* OF ANALYSIS Cc Potable Water 2F3 Monthly Gross alpha/monthly (Raw & 'Treated) <<composited Gross beta/monthly daily) Potassium-40/monthly Tritium/monthly Gamma scan/monthly Sr-89 & Sr-90/quarterly
~. Yegetables 2El 1F3 lGl 3H5 Annually Gamma scan/on collection
!l\'ll 3EJ\. 4Fl 2Gl (at harvest)
~ 5Fl 14F3
@. Game 4Cl U.Dl Semi- Gamma scan/9n collection
'j (Muskrat) annually
- f. !Beef 3El Semi- Gamma scan/on collection annually 9* Fodder crops 3El 2F7 3Gl Annually Gamma scan/on collection l3E31 5F2 11F3 14Fl
I-
.'i
............ *- .. - ... - ,._. -~-- ---*--.
I
.-<1 l
j i
.j TABLE 1 (col)t'd) i I
i 1986 ~RTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM _-:1
- .:.1
.I COLLECTION
- STATION CODE
.. 1
. MEDIUM INDICATOR CONTROL FREQUENCY TYPE/FREQUENCY* OF ANALYSIS J I h *. Soil 6Sl 5Dl 2El lFl 3Gl 3H3 Collected Sr-90/on collection
.. .. j lODl 16El 2Fl from each Gamma scan/on collection
- I
\I 2F2 location 2F4 once every I
1 2F7 *.* liiree years. I ~~:-* . 5Fl
- 1 5F2
- J1 11F3
*. 'I l 14Fl I
l\) I
- l. IV. AQUATIC ENVIRONMENT.
.l
;[ a *. surface Water llAl 7El 1F2 l2Cl Monthly Gr_oss alpha/monthly
**1 16Fl. Gross beta/monthly
*j Gamma scan/monthly
*1 Tritium/quarterly i
~
*1 l
- b. Edible Fish llAl 7El_ 12Cl Semi- Tritium (flesh) annually. Aqueous fraction/on collection Sr~89 & Sr-90 (bones)/on ~ollection
*1 Gamma scan (flesh)/on collection J
.~
1
- c. Blue Crabs llAl 12Cl Semi- Ttitium (flesh)/on collection 1
I annually Sr-89 & Sr-90 (shell)/on collection Sr-89 & Sr-90 (flesh)/on collection I! Gamma scan (flesh)/on collection I I
TABLE l (cont 0 d) 1986 ARTIFICIAL ISLAND RADIOLOGICA~ ENVIRONMENTAL MONITORING PROGRAM si~irnu CODE COLLECTION HEDIUH INDICATOR COlilTROL FREQUENCY TYPE/FREQUENCY* OF ANALYSIS dl. Benthic Organisms llAl '1El 16Fl 12Cl Semi- Gamma scan/on collection annually
- e. Sediment :UAl '1'El l6Fl 12Cl Semi- sr~9o/on collection 15Al annually Gamma scan/on collection l6Al
~ l* Q Except for TLDs. the quarterly analysis is performed on a composite of individual samples collected during the quarter.
&c Management audit analyses, not required by Technical Specifications or by specific commitments to local officials. &cc Station 2F7 replaced station 2F4 (terminated milk production) on September 1 0 1986.
I
.. l FIGURE 1 COMPARISON OF AVERAGE CONCENTRATIONS OF BETA EMITTERS IN PRECIPITATION ANO AIR PARTICULATES 1973 THROUGH 1986 LE GENO 500 AIR 1E-3 pC1/mHH3 e o RAIN pCi/L
+------+
I I I I I
' 100 . + ... L ., ******************* * ***
I I I I I I t I I I
+
50 ,*. *\. : * ** 1, *********************
"it, 11 I I I I I I I I I
I
.Jl'i- / ' I I \I I 11',..¥
+ 11 11 I I
I I I
~ .f- I I I I I
+\
I I I I t. I'+ I I
\ \
- t I
ID 10 ** "/i_ **** L. I \ I
**********'****I***
I I
* *. * * .. * * * .\. * * * ... * * * * * * * * *
- i * * * * * *. * . I. * * *
- 4.I*. * * * * *. * *. * * * * * * * * .. * * * * * * .N.
.... I\ I I .l,
-l-I ~ I ~ .L \ I \ ..-
..L
+ I I o r, 1
+~l .......... \~/ . \..................... A. .~.\:.\t .
1 'i I ,1 .Y' 5 f. .....t.. . .. " ..... " " " .. .~ .. .. . " ... +... \ ...
\ I' I I I
~ I t-+ ,' I I 11 "\" ")'. ;\" I I I I mID ~ ID ~ i Iii + \ .,....J. E+
nu I .... \ I ', I~; ~ . ~ iii j!! + \I I v i~! I -~ID l m sa c1i ,.. 1~:1-+--t--ti-+--t-ti-+-+-t-++-tl-+--t-11-+--t-11-+--+-11-+-+-t-+-+-1-+-+-1-+-+-+-+-+-+-+-+-+-+-+-+-+-+--+--4-+-+-l-+-+-l-+-~~
+
l 1234123412341234123412341234 4123412341234123412341234
~973 1974 1975 i976 1977 1978 ~979 i 1981 1982 t983 ~ss4 1985 1986
I
,
- l- . . -...... *', ,.,.,. . . . . . . . L. *" " * * * "* ...... " ***
FIGURE iA COMPAAISION OF AVERAGE CONCENTRATIONS OF BETA EMITTERS IN PAECIPITATION AND IN AIR PARTICULATES ftOOo--~~~~~~~~~~~~~~~~~~~~~~~~~~~~~._.~~~~~~~-. 1983 THROUGH 1986 LEGEND 500 AXA 1E-3 pCi/mNM3 e e RAIN pC:l/L
+-- - - - -+
i. 100 0 0 oOOO 0.0 0 0 00 0 00 0 O o o 0 0 o 0 0 o 00 0 o o O o oO o o 00 o o O O O o o o oO o o o Oo 00 O O O o 0 0 0 oo oo o O o o o o o o o o o o o o o o o o o o o o o o o o o o o o o o o o o o 0 o o o oo o o o o o o o o oo 0 0 0 0 0 50 ***************************************************************************..******.***** '** ******* *.*. 10 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . y. . . .,. . . . . . . + 8\ t 5 ******************~****************************** ..................../1. ....................... .!. .\.,/.\ t
\\ ' ~ ~ +. 'ti..
'8
+
+.-+I I' I
I
. i< 8 "'
I 'B 'f f +
\ l
~
;it..._...>\ Ki . \ "Ji iC ~
6 16 81 f i\
/ I I T
-4 i .{. \ \
I 0 ' I' -.- \ I I I' I 6
\ 0 \ 8 T \ ~ I 8 s, " I ~ I 0 \I\
\ 6 -\-* 8 I I \ '+ ~ I \ / I f' ,+- \ O iii
~ \I~ D
'a 'a
¥ I
i no* B + +I I \ V
~ IB S
..J
~
~ .\t oD 80
\
\ I f il!
I 1JfMAMJJASDNDJFMAMJJASONDJFMAMJJASONDJrMAMJJA5PNP
~se3 488"4 ~~~!!! tsee
FIGURE 2 AVERAGE AMBIENT RADIATION LEVELS FROM QUARTERLY TLDS IN THE VICINITY OF ARTIFICIAL ISLAND 1973 THROUGH 1986 LEGEND ALL STATIONS s--~~~~~~~~~~~~~~~~~~~~~~~~~~~~~-o o 9. CONTROL STATIONS
..... - - - - -+
*1
-.: 1 1
II L:
~ 1--~~~~~~~~~-,--~~~~~~~~~~~~~~~~~~~~~~~~~~~ 7
*1 i c
.J 0
;; E n 6-+-~-,--~~~~.--~~~~~~~~~---t-H~r-~-t+~~~~--1r--1----,,r-"'<rtr.-.-r_._~,.----t--+-6
~
IO
'E Ill
~ 5-1-~--r'---t-it-t-~"T-;,--"'"'"t--rlR--W----W~----t>t-it't-~~-R-~t--~f-\+t-~---~~~~~---it--~-r-,t---'r 5 E
*. i
- -~
4 3 3 . i
- 2 2 112341234123412341234123412341234123412341234123412341234
~973 tS74 !9715 :f.978 1977 1978 1979 1 . 1 9 8 1 1982 1983 1984 19BB 1988
FIGURE 2A
~OMPAA,SON OF AMBIENT RADIATION LEVELS OF OFF-SITE INDICATOR STATIONS VS. CONTROL STATIONS 1982 THROUGH 1986 iO--~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~--~~~~~~~~.- .c .µ c
0 E n
..,i II) 'U)
E I> L E I I :
---4 2
JFMAMJJASONDJFMAMJJASONDJFMAMJJASONDJFMAMJJASDNOJFMAMJJASOHD-irse ~~~~ 1sa~ ssas i~a6 ' 1 I
..' ' !j ' .*.c,* ... ' . -- .- -
- r*)
....~.-.* \ . '*~-*. .. ___ ....,.. .. - .. --* - ... -.. -
. -. _ . *r ."-'-"""-';._.,__c"'*'---;-.,_,..__
~~--
-~ ~ . -- . . . -
,)
- --~ ~ ........ .
. *n I!
... 1 j
I 1
*I l'
l FIGURI: 3 l I AVERAGE CONCENTRATIONS OF IODINE-131 IN MILK I IN THE VICINITY OF ARTIFICIAL ISLAND
**1 1974 THROUGH 1986
/1 30
. *~
'j 28 28
*:j . ' 26 26
*..i
.*.1
*j 24 24 1
.{ 22 22 l 20 ................................ , ...................................................................
' . *********************** 20 .
- 1 l 18 r::
~
18
.. ~1 _J 16 g---
H 16 .* **1 'u
..-1 1<1.
i~
~ a. 14 14
.. i
*1 12 12
*\. 1*: ,,;
. 10 ............................ ****************************** ~-***********-************************** ......... ~.1!...... . 10
.~}
I m m m m ~ i m ~ ~~ a i~ ~~ ~~~~ !~~IP ~ I. 8
. i t*
fN !!t::f: X ~llJa~ ii!
\
..~ i*,
~di ~ -i:J. ~.!. ~
D 6 wJ. za sa wd. uLJ. zasa t- uias.. u 6 I
. i
.* 1
*I 4
\ \
4 2
.,1 O~'f-.111-.lfl-il-'t'-""f&-'!l-lf'~~~-i-ll~olfL-~-t-J~ut'-~ll-'t'-""f&-'f--l+l....~ut'-.lflo-ll~~~-'P-'~~.~~Jtl-l~~!F-4~~ ,*,*! l 123412341234 1234 1234123412 . 2 3 4 12 3 4 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 '
0 f97~ ~9715 is7~ ili77 . 1978 197$ f.S~n ~ i982 i983 ~StM £fiHU5 1988
FIGURE 3A AVERAGE CONCENTRATIONS OF IODINE-131 IN MILK
'j, IN THE VICINITY OF ARTIFICIAL ISLAND I
1983 THROUGH 1986 30 --~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~30 28 28 26 . 26 24 24 22 22 20 *****. .*. . . . . . . . . . . . . .. * ............ .. ...... .. . . . . .* . . . .. . . . . . . . . . . . *. . . . . . . . . . . . . . . .. . . . ... . . . . . .. . .. .. . . . . . . . . . . . . . .. . . .. 20 iB 18
<<:ill l!-.il ....! 16 16
'u
.-II I
a i4 14
! 12 12
. I i
- 11) .... ...... .. ... ..... .. ...... . .. ..... ....... ... .. . . .. . ... . .. ........ ... ... . .. . . . . .. . . . .. . .. . . . . ...... . . . ... E............ . "' 10 B
. l8 IO e
B B "Ir c 6 m
~ iii a:
ID 111 6
~ u J, ffi WN 4 :r u
- s J.
% Cl 4 2 2 I.
o _ D I J f MA M J J A S 0 N D J F M A MJ J AS 0 ~ g J f MA MJ J AS DN P ~ f MA MJ J A ~ g NP
~sas a.s&4 i~i'I~ taae .
.,. .*...~...~--.... ;: . :_. :~*'*~ ........ ~.
- J r ' L -* .... _., '*** - - ,,_*_
i - **
'* ~: - .. . ... ... * . . . . *1 I
j
*I **---*-*'.
i l
.j i
*.I
'1
'.'I *FIGURE 4 --*-. ***
- i AVERAGE CONCENTRATIONS OF BETA EMITTl::RS --&*- K-40 IN
.j 1
i THE DEL. RIVER IN THE VICINITY OF ARTIFICIAL ISL. I 1973 THROUGH 1986 I
.* .1 I
LEGEND _*j "I 500 GROSS BETA
- I e o
.;I POTASSIUM-40 I +----- . :.1;
- ~
.,I i
100 50 _J
'u rl a.
10 ........... ****************** ..................................................................................... . 5 ...,........................ -~ ................. **********~ ................................ ****************fl***
~ mi m ~ ~ i~ iei
~~
~!
si~iil~.. U il t
*a ;a S 1--.to-fo-'"*-4__+-t_ _~_ _+-+__t-+_ _t--+--+-ii-+--f-l~-t-1--+-1--+-+-+-t-t--t-t--+--+-ll--+--+-il--+--+--tf-+--t-l-i-+-1--+-+~
! 12341234123412341234123412341234123412341234123412341234 i'
i;! If Q.. 11lo1 497$ 1974 t975 ~978 1977 1978 i97B 1 1981 1982 1983 ~Be4 ~988 1988 1,
.. -.. ' . -*~ ....,:. **-**~ ..
FIGURE "4A AVERABE CONCENTAATXONS OF BETA EMXTTERS Q K-40 XN THE DEL. RIVER IN THE VICINITY OF ARTIFICIAL ISL. 1983 THROUGH 1986 LEGEND 500 GROSS BETA e e PIJTASSXUM-40
+------+
soo
~ 50 i ~ _J
+
'ua.
rl I
- i
.j iO ,........................... '....................... .. ..... ........ *,* .... . I
\I 5 ............................................ ~ ........ ................................................ *-;..;*** ~-............... .
.i i !i i II JFMAMJJASONDJFMANJJA~ONOJFMAHJJASONDJF~AMJJASOND t'aas fi&a.c gs~~ tsae i I.
.f . . * *-* * . . .,....... -*
' I
- _.,* .' ' * ' **** ~ ,,~_.~ ~****-. ~~.,
** .. ... .* _..L, .. .
~~-
>l
.. *I
.*:1*1-
. **1
. :4 _
.. PIGURE B .
.* ****_1 AVERAGE .. CO~f;f:~TRATIONE; . Qf_ ..'!"~ITIUM IN THE ... -1*
. . *1 DELAWARE . RIVER IN THE. VICJ:NITY- . . **oF*-:;ART:.I.F:CCl:AL . .. ISL
- 1973 THROU.(;H ~:986*:**-- c--------.._. .*-*-**-*
. . ,.-..-.- --~~-** - - - - -
I 10000 _ _ _ _ _...._________________________ ~_
- 1
-- *** r * * ~ *
*1 5000 ********** .-************ ***.*********** *************** ***** **.*******-********* -*.*****.*********************** , ****..*.*********
1000 ****************************************************************************. *********************** ....................... .
~-j 51)0 ********************.* *******************************************************.**.*********.*********.******** , ***************
*.j
...J
'a.
(J
*:: ::::: :: :::::::: :: :: :: :::::::*.; :: ::: *::: .... ,: :. ::::: .. :::;1 .:* *: :. ::::: ::: ..:* *::* ::::: ::::. ::::::. ::*. ::*:*z:.~ *:
m
- m i m m ~ - - i m l .i I i~ -* 1r~f 1~ I! ~ -
ii' 6 . ~ s
;! ~'
~* ~*
' 11 11~
. . '\
' *~t
- j
. . *i 12341234123412341234123412341234123412341234123412341234 Ul73 !B74' ta7a iB7B tB77 tS78 tB7S t teat 1982 1983 UH14 1988 1988
. *1. *- __ ....... -* - . - . . -~
l
*i I
I
! AVERAGE CONCENTRATIONS OF TRITIUM IN THE FIGURE BA DELAWARE R,IVEA IN THE VICINITY OF ARTIFICIAL ISL.
1983 THROUGH 1986 5000 ****** ****************************************** ........................................................................... . AOOC * * * * * * * * * * * * * * * * * * * * ** ** ** * ************************************************************************************************* 500 ** ******** ** * ... * * * ** ........ ***** *** * . * . *** * * ** * *** * *** * * ***** ** ** * * *****. * *******************************.*.********** 100 .****..... : .********.**.*******.......**..*....*.*. *............................................... *.* * . . * * . . . . ..........**.. 50 ~
******************************************** ******* ..................... .'.****.********************* *-;.;*** ~- .***.**.*****..
;1
~
Jl IF ft.fi A li4 J J A S 0 N D J F MA MJ J A S 0 N D JI f 114 A M J J A S 0 H D J f MA MJ
*I ~I J AS 0 ND i'.B83 !'!98~ ~lil-~ UJB~
[l] REFERENCES. Radiation Management Corporation.. "Artific.:ial Island Radiological. Environmental* Monitoring l?rogram - Annual Reports 1973 through 1962" *. [2] Radiation Management corporation. "Artificial Island Radiological. Environmental Monito~ing l?rogram - Preoperation summary - 1973 through 1976".* RMC-TR-77_;.03 ,; 1978. [3] Radiation Management:corporation. "Artificial Island Radiological Environmental Monitoring l?rogram - Deceml:Jer ll to Deceml:Jer 31, 1976". RMC-TR-77-02, i97.7. ; .
\ ! l
[4] PSE&G Research:Cqrpora~ion, Research and Testing LaJ:>oratory.
"Artificial Island Radiological Environmental Monitoring l?rogram - 1983 Annual Report*~:. ; R'+'L-ENV-84-0l, 1984.
*; ; :r
[5] PSE&G Researc~ Corporation, Research and Testing LaJ:>oratory *.
"Artificial Iialand* Radiological Environmental Monitoring l?rogram - 1984 Annual Report:*!. ; ~TL-ENV-85-0l, 1985.
- Ii : *1* * .
I ' [6] PSE&G Research ¢orporation, Research and Testing LaJ:>oratory.
"Artificial Island Radiological.. Environmental Monitoring Program - 1985 Annual. Report"~ ~TL-ENV-86-0l, *1986 *
..' ~ .
[7] Public service Ele_ctric and Gas company. "Environmental Report, Operating License* Stage -* Sal.em Nuclear Generating Station Units l and 2". 197le': "
- . [8] Public Service Electric and*Gas Company. "Environmental Report, Operating *.License Stage - Hope creek Generating Station. 1983.
[9] United state~' Atomic Energy commission. "Final Environmental Statement - Salem Nuclear Generating Station, Units l and 2 11
- Docket No. 50-272 and 50-311. 1973~
[10] . United State~ Atomic Energy commission. "Final Environmental Statement - Hope creek' Generating
. Station, Docket.No. 50-354. 1983.
[ll] Public Servi,ce Electric and Gas. Company. "Updated Final. Safety Analysis. Report - Salem Nuclear Generating Station, Units l and 2". 1982 *
.. -*.. ) . . '
,.: [12] Public Service Electric and Gas Company. "Final Safety Analysis Report Hope*creek Generating Station. 1984. *
[13] Pubiic :Service Electric and Gas Company. "Salem Nuclear Generating Stat+/-od Unit l - Technical. Specifications", AppendiX A to Operating License No. DPR-70, 1976, sections 3/4.12 and 6.9.l.lO (Amendment 59
~:~),.,:
' ~
..... --; - --***.,;:-I"','
. -~ .
REFERENCES. {cont id) .. [14] Public Service Electric and Gas Company. "Salem Nuclear Generating Station Unit 2 - Technical Specifications", Appendix *A t_o Operating License No. DPR-75, 1981, Sections 3/4.12 and 6.9.lolO (Amendment 28
£~).
[15] PUblic Service Electric and Gas company. "Hope creek Generating Station Unit l - Technical Specifications", Appendix A to Facility Operating License No. NPF-57, 1986, Sections 3/4.12 and 6.9.1.10. [16] Pu.blic Service Electric and Gas company. "Offsite Dose calculation Manual~ - Hope creek Generating Station. [17] PUblic:: service Electric and Gas Company. "Offsite Dose calculation Manual" - Salem Generating Station. [18] u. s. Environmental Protection Agency. "Prescribed Procedures for Measurement of Radioactivity in Drinking Water. 11 EPA-600/4-80-032, August, 1980. [19] PSE&G Research corporation, Research and.Testing Laboratory. "Environ-mental Division Quality Assurance Manual." September, 1980. [20] PSES!G Research corporation, Research and Testing Lanoratory. ~Environ= mental Division Quality Assurance Plan.n (supereedes Quality Assurance Manual)f January6 1987. [21] PSE&G Research corporationu Research and Testinq Laboratory. ~Environ= mental Division Procedures Manual." February, 1981. [22] PUblic Service Electric and Gas Company. "Radioactive Effluent Release Reports, RERR-l and RERR Hope creek Generating Station. 1986. [23] PUblic Service Electric and Gas Company. "Radioactive Effluent Release Reports, RERR-20 an~ RERR Salem Generating Station. 1986. [24] Nuclear Newso "Chernobyl: The Soviet Reporte" October 1986. [25] The Heal.th Physics Society Newsletter. "Preliminary Dose Assessment of the Chernobyl Accident. Part II.~ January 1987 * . . *.I
** J ....
...... 1
.-~
- . :, i APPENDIX A PROGRAM
SUMMARY
. . . ."" . ~ .
. I
. ,,,."':"_._ -*----.--:-, --*--*. *- .___,. *-;- * --*- ---- *--. *-~ ...... -- *-* . ----- .... -*- .. , -- **- **;* -.. r*--- -*---*-- ---** -.-*-******.--: -::- -* - ----*. ----- .,.... -- ---- -***---<--*-*-:* .... -** -- .*-* .. ... . .. -* ********--* --- - -- . -* ..
\. ,;:'. .. ' . .. .. . .. . '
~
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SALEM GENERATING STATION DOCKET NOS. 50-27Z/-3H HOPE CREEK GENERATING STATION DOCKET NO. 60-364 SALEM COUNTY, NEW JERSEY JANUARY 1, !986 to DECEMBER 31, 1986 ANALYSIS AN!li LOWER NUMBER Of
~EDIUM OR PATHWAY TOTAL NUMBER UNIT Of Al I IUDICAIOB IOC!IXOUS IOC!IIOU WIIU UI6UESI ~E!U COUIHOI 1llC!IIOU NON ROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED
<<UNIT Of MEASUREMENT) PERFORMED (HO)* (RANGE) !HSTANC*E AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Air Part iculi!hs Aiphm 416 0.8 Z.8 (311/364) zsz 0.4 ml NNE 3.1 (46152) Z.8 (48/62) 0 00-3 pCt/m3) (0.8-Z2) (0.9-22) (1.0-20)
Beh '316 41 (369/364) 2S2 0.4 mi NNE 46 (li0/62) 42 (61162) 0 (6.7-370) ( 9. 4-360) (11-330) Sr-89! 8 0.3 <UD <HD <LLD 0 oj:b II-" Sr-90 s 0.2 <Lrn ~no <LLD 0 . Gillmla Be-7 3Z 77 (28/28} !iDl 3.li mi E 91 (4/0 76 (4/4) 0 (60-110) (80-110) (64-90) Ru-1031 :ilZ 0.1 8.6 p12a) !iDl 3.6 mi E 9.2 014) 7.6 (114) 0 (7 .6-9.2~ {9.Z) (7 .6) lllu-106 32 1.6 6.6 (3/28) lFl 6.8 mi U 8.3 (114) 4.0 (114) 0 (4.0-8.:ll) (8.3) ( 4 .0) CsHM 312 0.31 9. 3 (7 /28) lfl 6.8 ml N 10 010 9. z (1/4) 0 (8.4-10) (10) ( 9. 2) 2fZ 8.7 mi NNE 10 (114) ( 10)
<<:s-137 312 0.3 17 (7 /28) zsz 0.4 mi NNE 18 (114) 17 (114} 0 (16-18) (18) ( 11) lliDl 3.6 ml E aa ( u~)
OR)
!lili-Z26 32 0.3 1. 2 ( 11211) If l 6.8 mi N l.2 0/4) <LLP 0
( 1.2) {1,2) Jh-232 28 a.! l. 7 0120 lf l 6.8 mi N !.7 01.i) <LLP 0 ( 1. 7) ( l. 7)
~. '
..::* J ' _,., ..... ,. '* 1.: ' J::_ ..
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SALEM GENERATING STATION DOCKET Nos: 60-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 60-354 SALEM COUNTY, NEW JERSEY JANUARY 1, 1986 to DECEMBER 31, 1986 ANALYSIS AND LOWER . NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL IUDIC:AIOH I llC:AIIllU5 lllC:AIIllU WIIU Ul6UESI' MEAU C:DUUDf I DC:6IIDU NONROUTINE SAMPLED . OF ANALYSES DETECTION MEAN*f NAME MEAN MEAN REPORTED
. (UNIT OF MEASUREMENT) PERFORMED . (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Atr lodtne I-131 416 7.7 160 (27/364) 16El 4.1 ml NNW 190 (3/62) 170 (4/61)
(10- 3 pCt/m3) (26.:.320) (70-300) (64-320) '.;.
. Preclpttatlon Alpha 12 0.3 1.0 (4/12) 2F2 8.7 mt NNE 1.0 (4112) No Control 0 (pCi/L) (0.6-1.3) (0 .6-1. 3) Locatton Beta . I .12 1.6 6.6 (11/12) 2F2 8.7 mi NNE 6.6 (11/12) No Control 0 (1.9-16) (1.9-16) Location
--- - * -H ,. . 12 130. <LLD <LLD No Control 0
. ., *location
.," Gamn~
. i. Be-7 li -47 (11/.H) ** *.zn....8.7 mL.HNE 47 (11/11) No Control Q
\ (3~-71) ... -- -.... '* .::: : : ~ * ( 35-71) . Location
*1 K-40 11 26 69 (1/ll)c - *.,,::.*._ _,_ ~F_z*a~TmTNNE .. ., - 69.. (1111) No Control
*.i 00
._ 0
' (69) ** . - ... ,, ..*:..*o.c::.~~---.*,... o . . . . * (69) iocatfori 1-131 11 1.6 7.4 (1/11) 2F2 8*.1~mi NNE 7:*f(l*/U*)-- - *. No.Contr.q\ .. 0
( 7. 4) -{-7.4) . . Location .. , Cs-137 11 0.8 4.8 (1/11) 2F2 8.7.mi NNE . 4.8 (1/11) No Control 0 (4.8) (4.8) Location Ra-226 11
- 4.2 6.6 (jJ1i) 2F2 8.) mi NNE li.6 (3/11) No Control 0 (4.8-7.0) (4.8-7.0) Location Th-232 11 7.2 7.6 (1/11) 2F2 8.7 mi NNE 7.5 (1/11) No Control 0 (7.5) (7.5) Location J
. j
~*
***~ ' ; ....*,* ..
ARTifICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SALEM GENERATING STATION DOCKET NOS. 60-UZ/-311 HOPE CREEK GENERATING STATION DOCKET NO. 60-364 SALEM COUNTY, NEW JERSEY JANUARY 1, ,1986 to DECEMBER 31, 1986 ANALYSIS AND LOWER NUMBER Of MEDIUM OR IPAiHWAY TOTAL NUMBER UNIT OF 611 IUDIC6IQH IOC6IIOUS IOC6IlOU ~lIU Ul6UESI HE6U COUIBOI iQC6IIOU NONROUHNE SAMPLED Of ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED
<<UNIT OF MEASUREMENT) PERFORMED (HD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Direct Rild1iltton Gillllllil 287 6.9 (Z61IZ61) 7Sl 0.1 mt SE 6.9 (lZ/12) 6.4 (36/36) ' .0 (mrad/std. month) Dose (monthlll) (3.8 - 1.7) (6.9-7.1) ( 6.1_-1.6)
Gilllllla 164 6. 0 (140/140) 751 0 .1 mt SE 6.0 (4/4) 6.6 (Z4/Z4) 0 Dose (qtr]lf. b (3.4-6.1) (Ii .6-6 .6) (4. 9-6.4) ~ ir'1 l)Ulk 1-131 122 0.1 10 ( 16/ 103) 3Gl 17 mi NE 19 (3119) 19 (3/19) 0 (111Ct/L) (O.Z-47) (0.3-li3) (0.3-63) Sr-89 7 0.8 <LLD <HD <LLD 0 Sr-90 7 z.o (6/6) 6FZ 1.0 mt E 3.0 (lll) Z.1 (111) ii (l.Z-3.0) (3.0) (Z. 7) Sillmlil Na-ZZ lZ! 1.0 4.6 (11102) 6FZ 7.o mi E 4.6 (!/20) <LLD 0 (4.6) .*...... (4.6) K-40 121 1400 ( 102/ lOZ) ** /- :=:. - 2F4 6.3 mi NNE 1400( 13113) 1300 ( 19/19) 0 (lZOO-l!iOO) '* (1300-1600) ( 1100-1400) Mn-54 121 0.7 2.9 (lllOZb 13E3 4.9 mi W z. 9 ( 1120) <LLD 0 (Z.9) (z. 9) Zn-61i 12ll 1.8 11 (11102) llf3 6.3 mi SW 11 (1/ZO) <LLD 0 ( U) (U) Il-Ul !Zll 0.6 20 (8/102) 31H 17 ml NE 3~ (2./19) ~P. (Z/~f)) 0 (3.8~49) (7,4,,66) (7.4~6§)
<<:s-U7 U~ll 'Z.3 4 .1 (li/aOZ) fiU 7.o mi E 4.fi UW)) ~HP @
(l.3~1i.l) (:il.9-t:i. 0 Ra-226 RZil 6. l 6.6 (31102) 14fl 5.5 mi WNW 5 .s (zr20 > 6.5 (1119) 0 (4.4-7.3) (4.~-1'.3) (5.5)
/. ,. \,';
*::.... .. , *.: . .:. ~-. ~-. ,,._. ~;,:,..,: .:,._;,~ .~ .... -~ -~, . . .::... -~: .. *' ..
.ARTIFICIAL iSLAND RADIOLOGICAL ENVIRONMENTAL MONITORING* PROGRAM
SUMMARY
SALEM GENERATING STATION DOCKET NOS. 60-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 60-364 . SAL~M COUNTY, NEW JERSEY .JANUARY 1, 1986 to DECEMBER 31, 1986 ANALYSIS AND *LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF All INDICATOR \OCAllONS IOCATION WITH HIGHEST MEAN CONTROi IOCATION NONROUHNE SAMPLED OF ANALYSES. DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUR~MENTS Wel 1 Water Alpha 36 0.6 1.2. (~/24) 2S3 700 ft NNE 1.2. (4112) <LLD 0 (pC 1/L) (0.6-2.0) (0. 7-1. 7) Beta 36 1.0*** 7.6 (24/Z4) 6Dl 3.6 mi E 10 (lZ/lZ) 7.4 ( 12/12) 0 (2.0-16) (Z.0-l!i) (Z.!i-9.li) K-40 36 8. 7 (24/24) liDl 3.6 mi E 13 (12112) 9.4 (12/12) 0 (2.7-16) (8.8-16) (7 .4-17) H-3 36 130 <LLD . <LLD <LLD ii Sr-89 12 0.4 <LLD <LLD. <LLD *o '* Sr-90 12 0.3 '<LLD <LLD <LLD -* 0 GaRJna K-40 36 21. 42 (4/24) liDl 3.6 mi E 42 (4/lZ) <LLD . p .**_J-. (36-47) .* (36-47)
~a-:22~ **'- 36 3.3 Z9 (17124) 3El 4.1 mi NE 69 (11112) 69 ( 11112) . 0 ";j':. (3.3-96) (2.9-170) (Z.9-170)
- ,. 'J" Tti-z3z- 36 4.6 .9.Z (2/Z4) 601 3.6 mi E 9.Z (2/lZ) <LLD 0
. 1 - : - (8. 4-10)
I j (8.4-10) l ... -. *.- *..- ... _j j Potable Water Alpha 24 0.6 o.8 <11/.?H ZF--3 -8.0 .11),i NNE * -- *
- f t - ..
0.8 ( 11_/24) No Control 0 Raw-Treated (0.6-1.6) ..:...-_ -- :. .! -*----~ ** ;..- ~
.*-**-- ... (iL6:.:t. 6) *Local ion .
__ (pCi/L) Beta Z4 1.0*** 3.6 (~4/24) 2F3 8.0 mi NNE .3.6._(24/24) No Control 0
** ,_P"*** *** * *
(1.7-13). l~.:7-13) [a canon K-40 24 1.8 (24124) 2F3 8.0 mi NNE 1.8 {i4i24) No Contra l * -- 0 (1.3-4.9) (l.3-4.9) Location
- H-3 24 130 l!iO ( 1/24)
( l!iO) 2F3 8.0 mi NNE 1.!iO ( l / 24) ( 150) No Control Location 0
AR!XF!CIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SALEM GENERATING STATION DOCKET NOS. 60-2721-311 HOPE CREEK GENERATING STATION DOCKET NO. 60-364 SAllEM COUNTY, NEW JERSEY JANUARY 1, 1986 to DECEMBER 31, 1986 ANAa.YSIS AND lOWEI! NUMBER OF
~EDIUN OH PATHWAY TOTAL NUMBEl.l UMH Of ~II IUDICAIDR !DC!IIDUS I OCAII!lU kiIIU. Ul6UE51 l:IEAU COIHROI I OCAIIOU NONROUHNE SAMPlfl> OF ANAIL lfSES . DEJIECHON MEANH NAME MEAN MEAN REPORTED
<<UNIT Of MEASUREMENT) PE!lfORNED {U.D)"' (RANGE) DXSTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Pot~ble Water cont'd Sr-89 ~ 0 .6 o.e (1/8) 2f3 8.0 mi NNE 0.6 (118) No Control 0 hw-Tuahdl (0.8) (0.8) locatton (pCW.) Sr-90 8 <<) .4 <LLD <LUI No Control 0 location Gillll!llill
~ on l<-40 Z4 zz Z6 (2124) 2F3 8.0 mi NNE 26 (2124) No Control 0 (Z6-Z6) (26-26) location Ru-103 24 <<1.6 Z.6 (1124) Zf3 8.0 mi NNE 2.6 (1124) No Control 0 (Z.6) .. (2.6) locatlorn
. .*-. ~ -
lhl-226 24 SJ. 7 6.9 (3/Z4) 2f3 8.0 ml NNE 6.9 {3124) No Control 0 (Z.6-8.4) (2.6-8.4) location Th-232 24 . 4.9 6.1 (3/24) 2f3 8.0 mi NNE 6.A (3/24) No Control 0 (6.7-6.8) (6.7-6.8) Loe at fon fruit &Vegetabie$ Ganma {pC I/kg-wet) Be-7 20 H 24 (1/12} 4fl 6.1 mi ENE 24 ( 112) <LLD 0 ( 24) (24) l<-40 20 z100 (1ZI 12) 2Gl 12 mi NNE 3400 (111) 2100 (8/8) 0 ( 910-2600) (3400) (1600-3400) I-i31 20 2.3 33 (1112) 2Gl 12 ml NNE 62 (AH) 62 ( 118) 0 (33) (62) (62) Cs-U7 20 A.6 <LLD 3H6 26 ml NE 2.1 (1!4) 1.8 (218) 0 ( 2 .1) (l.6-2.1) Ra-226 20 l.8 8.3 (1112) AGl 10.3 mi N 68 (1/3) 63 (218) 0 (8.3) (68~ (58-68) Ho-2?:? :w ~.IS B.8 P.tfi.2~ ~t'.\f~ 5.4 mi WNW t?"B {L/2i~ t.UO 0 (Vq 1\ &. rl~ ;
**.-~;;~ ..._'.... --~~~~~;'::~: -~ ':_:....~ /*:*. *.*
-,.::.~::* ~*~..'..*--~: . ..;. :. ... ...:...::*..
." . - ---*~ **-*
. I l I
.j
>1
.*.1
.,i I
.I ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
. i i :
I
*i SALEM GENERATING.STATION DOCKET NOS. 60-272/-311
.I DOCKET NO. 60-364
.j HOPE CREEK GENERATING STATION i
SALEM COUNTY, NEW JERSEY JANUARY 1; 1986 to DECEMBER 31, 1986 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF All IUDICAIOB IOCAIIOUS IOCAIIOU ~IIU UI6UESI MEAU COUIBOI IOCAIIOU NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED l (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS
.l '.
*I
..i, Ganmil Game
. . . J.
i (pCi/kg-wet) K.:.40 2 2400 ( 1/1) 4Cl 2.8 mi ENE 2400 ( 1/1) 2200 ( 1/1) o*. j (2400) ( 2400) ( 2200)
".j
- i i
.I Beef Gilnmil
'*:l
*1
~ (pC i /kg-wet) K-40 1 2600 (.1/1) 3El 4.1 mi NE 2600 (1/1) No Control 0
. i ( 2600) Lociltion i (2600)
! Cs-137 1 7.3 (111) 3El 4.lmiNE 7.3 (111) No Control 0 (7.3) (7.3) Lociltion Fodder Crops Ganma
( pC I /kg-wet) Be-7 9 140 880 (4/7) 14Fl 6.6 mi WNW 1400 (Ill) 1100 (l/Z) 0 (370-1400) (1400) ( 1100) K-40 9 6600 (717) 3El 4.lmiNE 16000 (1/1) 8600 (212) .0 (2300-16000) ( 16000) (3000-14000)
. -. .;*~1- Cs-137 '*~ 17 <LLD 361 17 mi NE 13 (1/2) 13 (1/Z) 0
. < -- (13) (13)
*,1,.*
J Ra-226 9 36 36 (117) 2F7 5. 7 mi NNE 36 (1/1) <LLD 0
.*.; (36) (35)
<LLD Th-232 9 69 170* ('lt7) 14fl 5.6 mi WNW - 170 (111) ()
( 170) ( 170)
-* * '* ,.~---- ..-::r*: *..~ - **_,: :.*.*
~
1
,i * - .. . .
.::-*:. *- !. !._* __ ~:.:...:-.. '.,: .. *-. : * * .
ro *** * *
* ~ >* *' * ..;. ' ,,' * '
- ~ '
,* * - ' * * * "* * : ' '* *** * * " " " * '* *c*>
* **~<,. ';,. \ j ~ '** .. ,
AR1If ICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
SALEN GENERATING STATION DOCKET NOS. li0-27Z/-3U HOPE CREEK GENERATING STATION DOCKET NO. 60-364 SALEM COUNTY, NEW JERSEY JANUARY 1, 1986 to DECEMBER 31, 1986 ANALYSIS AND LOWER NUMBER Of MEDIUM OR PATHWAY TOTAL NUMBER UNIT OF AIL IUDI&AIOH LO&AIIOU5 IO&AIIOU ~IIU UIGUESI MEAU &OUIHOI IOCAIIOU NONROUTUIE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN . REPOUEO (UNIT Of MEASUREMENT) PERFORMED (LLD)* (RANGq DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMfNTS 1 Soil Sr-90 16 2Z 91 (13114) Zfl 6.0 mt NNE 140 (Rli) 93 (Z/Z) 'o (pCi/kg-dry) (Z7-140) (140) (66-130).
. '\
Gillmli8 7800 (14/H) .*.* 11F3 6.3 ml SW . '*0* l'(-40 ll.6 13000 011) 8600 (Z/Z) ( lZ00-13000) :~*- ( UOOO) ( 7900-9200) l)(!:h Nb-96 16 4.li 48 (Z/14) ZF7 6.7 mi NNE 63 (111) <LLD 0*
~ (34-63) (63)
Cs-U1 X6 390 ( 14/R4) lfl 6.8 mt N lliOO (111) 460 (2/Z) 0 (78-UiOO} (1600) (210-690) lllin-226 16 680 (14/n-0 16El 4.1 mi NNW 1000 UH) 810 (2/2) 0 (260-1000) ( 1000) ( 770-860) Hf3 6.3 mi SW 1000 (111) (1000)
'H'h-232 16 710 (14/14) 16El 4.1 ml NNW 1200 ( 111) 800 (212) 0 (ZJ0-1200) ( 1200) (780-810) i Surface Water Alpha 60 0.6 3.1 ( 19/48) lfZ 7.1 mi N 6.6 (3112) 3.li (4112) 0 (pC i IL) (0.7-12) (2.6-12) ( 1. 8-8. 3)
Beh 611 3.8*** 61 (48/48) 7El 4.6 ml SE 76 (12112) 46 ( 12/12) 0 (2.4-130) (16-130) (7.li-81) H-3 zo !30 160 (8/16) UAl 0.2 ml SW 210 (214) 160 (1/4) 0 ( 130-270) ( ili0-270) ( 160)
'* :. ~
1'- ~.......C.*._,_.::__ , __ ,; .... - * ~ ~..... . ........ *'- *- .. : :'. : :*_,._ .. *- : .. * ...... ... . . . - - ........ ..
*i
*1
.*j
\
. :j
'.'l
.*1 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
n
;1 I SALEM GENERATING STATION DOCKET NOS. 60-272/-311 I HOPE CREEK GENERATIN.G STATION DOCKET NO. 60-364 II
. *i SALEM COUNTY, NEW JERSEY JANUARY*l, 1986 to DECEMBER 31, 1986
'/'*
,j
'i
. 'l MEDIUM OR PATHWAY ANALYSIS AND LOWER TOTAL NUMBER LIMIT OF Al I IUDICAIOH IOCAIIOUS IOCAIIOU WIIU UI6UESI YEAU COUUOI IOCAIIOU NUMBER OF NON ROUTINE SAMPLED MEAN** NAME MEAN l (UNIT OF MEASUREMENT) PERFORMED Of ANALYSES DETECTION (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) MEAN (RANGE) REPORTED MEASUREMENTS
*-1 I . ~ . :*
*:i
-.i l Surface Water cont'd. Ganma K-40 60 24 88 (34/48)
(33-160) 7El 4.6 m1 SE 100 (lZ/12)' (66-160) 70 (9/12) (29-96) 0
*I
- l Ra-226 60 3.3 6.6 (7148) l2Cl 2.6mi WSW 26 (1/12) 26 (1112) 0 I ( 2.6-11) (26) (26)
'~~ Th-232 60 4.9 7.4 (6/48) 12Cl 2.6 m1 WSW 9.2 (1/12)
- .".j ~ 9.2 (1112) 0
<<>> (6.3-9.3) (9. 2) (9.2) '-.1 *.i
- j
.\
.j Edible Fhh Sr-89 6 40 <LLD 12Cl 2.6 m1 WSW 330 (1/2) 330 (1/Z) 0 I
I ( pC 1/kg-dr y) (bones) Sr-90 6 24 140 (214) 12Cl 2.6 mi WSW (330) 1600 (112) (330) 1600 (1/2) 0 1 I (bones) (34-240) ( 1600) ( 1600) (pC1/kg-wet) H-3 6 60 <LLD <LLD <LLD 0 (aqueous) Ganma K-40 6 3000 (4/4) llAl 0.2 mi SW 3000 (Z/2) 3000 (212) *O
'.i (2700-3300) ( 2700-3300) ( 2700-3300)
*l 12Cl 2.6 mi WSW 3000 (2/2)
*I
.*'.j (2700-3300)
. .. ~~ . Cs-137 6 12 8.3 (1/4) llAl 0.2 m1 SW 8.3 (1/2) <LLD 0 I (8. 3) (8. 3) Ra-226 6 20 37 (2/4) llAl 0.2 mi SW 41 (1/2) <LLD 0
~;-
(33-41) . ( 41)
*:. - -_ -. Th--2 ._ 6 31 <LLD 12Cl 2.6 mi WSW 29 (1/2) 29 (112) 0
- 1 (29) (29)
'I
I l j ARTIFICIAL ISLAND RADIOLOGICAL ENViRONNfNTAl MONITORING PROGRAM
SUMMARY
*1 SALEM GENERATING STATION DOCKET NOS. 60-272/-3Rl HOPE CREEK GENERATING STATION DOCKET NO. 60-364 SA~EM COUNTY, NEW JERSEY JANUARY l, 1986 .to DECEMBER 31, 1986 ANALYSES AND LOWER NUMBER OF MED!UN OR PATHWAY . TOVAL illlUNBER UD@!T OF ALI IUOICATOR IOCAIIOUS !OCATIOU WITH HIGHEST HEAM CONTROi IOCATIOU NONROUTXNE SAMPLED OF AAALYSES DETECTION MEAN*>!! NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) '.~*~RSTANCE AND DIRECTION (RANGE~ (RANGE) MEASU.REMENTS
- . '~ -
Blue Cubs Sr-8~ .fl 67 300 (l/Z) 11Al 0.2 m1 SW 300 ( H2) <LLD 0 {pC I/kg-dry) (shei]h) (300) (300) Sr-90 4 260 (212) 12Cl 2.6 ml WSW 400 (212) 400 (212) : o*
<<sheH:s) (160-380) (320-i&90) ( 320-490)
<<l>C i/kg-weit) H-3 4 60 <HD <LLD <LLD 0 1)(11. (aqueous) w Sr-89 ~ 28 <LLD 'LLD <LLD 0 (flesh)
Sr-90 4 18 <LLD <LLD <LLD 0 (f1HDll>> Ganma
!C-40 . l& 1800 (212) llAl 0.2 ml SW 1800 (212) 1800 (212) 0
( 1700-2000) ( 1700-2000) ( 1700-2000) 12Cl 2.6 mi WSW 1800 (212) ( 1700-2000) Ra-226 4 28 . <LLD 12Cl 2.6 mi WSW 20 (212) 20 (212~ 0 (19-20) (19-20) Benth1c Organ1sms G11nm11 8 <LLD <LLD <LLD 0 (pCHkg-dry) . i
.r I i
. I
;)
*\
i ARTIFICIAL ISLAND RADl_OLQGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
. I
.;*,l SALEN GENERATING STATION DOCKET NOS, 60-272/-311
**1 HOPE CREEK GENERATING STATION DOCKET NO, 60-364
- 1 J
l SALEM COUNTY, NEW JERSEY JANUARY 1, 1986 to DECEMBER 31, 1986
, I
*.I
.I
.j i ANALYSIS AND LOWER NUMBER OF
..*i, MEDIUM OR PATHWAY . TOTAL NUMBER LIMIT OF ALL IUDICAIDB IDCAIIDUS IDC6IIDU ~IIU UIGUESI YEAU CDUIBDI IDCAIIDU NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED
*J *J
- ,[ (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS
.I ' -~
.j i Sediment Sr-90 lZ 19 <LLD <LLD <LLD 0 I
I (pC1/k9-dry) Gillllllil i K-40 lZ 9600 (10/10) 16Fl 6.9 mi NNW 16000 (212) 16000. (212) 0
- .J l' (3600-16000) (16000-16000) (14000-16000)
*1 Mn-64 12 18 26 (3/10) llAl 0.2 ml SW 27 (212) <LLD 0
.,\
'J (JI (24-29) (26-29) 0
,,j Co-68 12 23 67 (4110) 16Al 0.3 mi NW 80 (1/2) <LLD 0
<1 (31-80) (80)
'i Co-60 lZ 36 72 (8/10) llAl 0.2 mi SW 100 (212) <LLD 0
; *l (37-11_0) (92-110)
I
**:.; C5-134 12 16 61 (3/10) 16Al 0.7 mi NNW 82 (1/Z) 60 ( 112) 0
,i (46-82) (82) (60)
.*1 "1. Cs-137 12 16 61 (3/10) llAl 0.2 ml SW 82 (1/2) 20 (1/2) 0 1I (49-82) (82) (20)
I
*I
. Ril-2Z6 12 610 (10110)
(330-810) 16Al O. 7 mi NNW 780 (212) (760-810) 700 (212). (670-840) 0 ..
' i Th-232 12 720 ( 10/10)
- 16Fl 6,9 mi NNW 970 (212) 880 (212) 0 (300-1000) ( 940-1000) (870-880)
. *.. l ' LLD listed is the lowe5t calculated LLD during the reporting period .
**Mean calculated using values above LLD only. Fraction of meaGurement* Above LLD are in parentheses.
~** Typical LLD value.
- ..J
.. ~ .
'j
APPENDIX 8 SAMPLE DESIGNATION ANO LOCATIONS
~ -r 51
----~-~ ----._.-.-...-*---------,,,****-,.**-------~---:-------* *--.---.._.---...,.....,..---.-----~---,:--:-*----*-~ *-:--**-----~---.-------- -- **--
APPENDIX B SAMPLE DESIGNATION.*: . The PSE&G Research.Corporation identifies samples by a three part code. The first two letters are the power station identification code, in this cas.e
' SA".
9 The next three letters are for tl'l.e media sampled. AIO = Air Iodine IDM = Immersion Dose (TLD) APT = Air Particulates MLI< = Milk ECH = Hard Shell Blue Crab PWR = Potal:lle Water (Raw) ESB = Benthic organisms PWT = Potable Water (Treated) ESF = EdilJle Fish
- RWA = Rain Water ESS = Sediment SOL = Soil FPB = Beef SWA = surface Water FPL = Green Leafy Vegetacles VGT = Fodder crops (Various)
FPV = Vegetables (Various) WWA = Well Water GAM = Game The last four symbols are a location code based on direction and distance from the site. Of these, the first two represent each of tl'l.e 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 numbered in a clock-w~e: directioru i.e. 2=NNEP 3=NE, 4=ENE~ etc;. The next digit . is a letter Q which represents the radial distance from the plant~
- s = on-site location E = 4~5 Dci.les off-site A = 0~1 DU.les off-site F = 5-10 miles Off=site
.B = l-2 miles off-site G = io~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., l,2,3, *** For example, the designation SA-WWA-SDl would indi.cate a sampie in the SGS program (SA), consisting of well water (WWA), whi.ch had been collected in sector number 5, centered at 90' (due east) with respe<;t. to the reactor site at a radial distance of 3 to 4 miles off-site, (therefore, radial, distance* D). The number l indicates that this is sampling station #l in that particular sector *
- '?
. I
.-J
.. _ --------------. -*-* ._---- --*-**---.~------.,. ----- - -
SAMPLING LOCA'rIONS
. All 1986. sampling location's and specific. information about the individual locations are given in Table B-l. Maps B-l and B-2 show the locations of sampling stations with respect to the site.
TABLE B-1 STATION CODE STATION LOCATION SAMPLE TYPES 2S2 o.4 mi. NNE of vent. AIO,APT,IDM 2S3 700 ft. NNE of vent; fresh water holding tank WWA SSl 1.0 mi. E of vent; site access road AIO,APT,IDM 6Sl 0.2 mi. ESE of vent; observation .building area SOL 6S2 0.2 mi. ESE of vent; observation bµilding IDM 7Sl 0.12 mi. SE of vent; station personnel gate IDM lOSl 0.14 mi. SSW of vent; site shoreline IDM llSl 0.09 mi. SW of vent; site shoreline IDM' ll.Al 0.2 mi. SW of vent; outfall area ECH,ESB,ESJ", ESS,SWA lSAl 0.3 mi. NW of vent; cooling tower blowdown ESS discharge line outfall l6Al 0.7 mi. NNW of vent; south storm drain ESS discharge line
.-, ' 4Cl 2.a mi. ENE of vent GAM 12Cl 2. 5 mi. WSW of vent; west bank of Delaware l:U ver ECH,ESB,ESF, ESS,SWA 4D2 3.7 mi. ENE of vent; Alloway Creek Neck Road IDM 5Dl 3.5 mi. E of vent; local farm AIO,APT,IDK, SOL,WWA lODl 3. 9 mi.. SSW of vent; Taylor's Bridge Spur AIO,APT,IDJ!,SOL llDl 3.S.mi. SW Of vent GAM l4Dl 3.4 mi. WNW of vent;. Bay View, Delaware IDM J 54
.. J l
.**-t~.-...-_-.-:-:-_-.-~~------.--.:-*--*:-:*;*:-~~-::-::-~:*-::-:--:::--~~--.-.. - ..-.~::-;---~=-:-~--....,-7"-*~~:---:--~-.,...-:...-~-- -~--.':--:~---~;;-:----;._-:----~.;~ -.---~-- - - ";--*.*--*--~---- '":~-- :***~-,.-*-.;-*:-
- STATION CODE TABLE STATION LOCATION s~1 (cont'd}
.SAMPLE TYPES 2El 4.4 mi. NNE of vent; local farm FPV,IDM,SOL 3El 4.l mio NE of vent; loca.1 farm FPB,FPV,IDM, VGT,WWA 7El 4.5 mi. SE of vent; l mi. W of Mad Horse creek ESB,ESF,ESS,SWA 9El 4.2 mi. S of vent IDM llE2 SoO mi. SW of vent IDM 12El 4*4 mi. WSW of vent; Thomas Landing IDM 13El 4.2 mi. W of vent; Diehl House Lab IDM l3E3 4.9 mi. W of vent; local farm Mr..K,VGT 16El 4ol mi. NNW of vent; Port Penn AIO,APT,IDM,SOL lFl s.a mi. H of vent; fort ~lfsborq AIO,APT,IDM,SOL lF2 7ol mi.. N of vent; midpoint of Delaware River SWA 1F3 5o9 mi. N of vent~ local farm FPL,FPV 2Fl 5.0 mi" NNE of vent; local farm SOL 2F2 807 mi. NNE of vent; Salem SUbstation AIO,APT,IDM, RWA,SOL 2F3 800 mi. NNE of vent; Sal.em Water Company PWR,PWT 2F4 6.3 mi. NNE of vent; local farm MLK,SOL 2F5 7.4 mi.. NNE of vent; Salem High School !DH 2F6 7o3 mi. NNE of vent; Southern Training Center IDM 2F7 5o7 m.i,. NNE of vent~ local farm ML&'.,SOL,VGT 3F2 5.l mi. NE of vent; Hancocks Bridge Municipal IDM Bui.ldinq 3F3 8.6 mi.. NE of vent; Quinton Township School IDM 4Fl Sol mi. ENE of vent; local. farm FPL,FPV 5Fl 605 mi. E of vent FPV,IDM,sor..
5F2
*------*--**-----***-~--.-. ---.;-*---**~-.--. -----.~---"'7""---~------..--- *-:-----~- --.-. *---,- :------~ -*--.--'--*. -*-- - ... -. -**.**: ******----- ---.. . . --.- -- - . ~ ----*-- ---* -
STATION CODE TAELE B-1 .(cont'd) STATION LOCATION SAMPLE TYPES 6Fl 6.4 mi. ESE of vent; Stow Neck Road IDM 7F2 9.1 mi. SE of vent; Bayside, New Jersey IDM lOF2 5.8 mi. SSW of vent IDM llFl 6.2 mi. SW of vent; Taylor's Bridge Delaware IDM llF3 5.3 mi. SW of vent; Townsend, Delaware MI.I<, SOL ,.VGT l2Fl 9.4 mi. WSW of vent; Townsend Elementary School IDM l3F2 6.5 mi. W of vent; Odessa, Delaware IDM
.13F3 9.3 m+/-. w of vent; Redding Middle School, IDM Middletown, Delaware 13F4 9.8 mi. w of vent; Middletown, Delaware IDM 14Fl 5.5 mi. WNW of vent; local farm MLK,SOL,VGT 14F2 14F3 15F3 6.6 mi. WNW of vent; Boyds corner 5.4 ..mi. WNW Of vent; local farl!l 5.4 mi. NW of vent IDM FPV IDM 16Fl 6.9 mi. NNW of vent; C&D canal ESB,ESS,SWA 16F2 8.1 mi. NNW of vent; Delaware City PUblic School IDM lGl 10.3 mi. N of vent; local farm FPV
- I 1G3 19 mi. N of vent; Wilmington, Delaware IDM 2Gl 12 mi. NNE of vent; Mannington Township, NJ FPV
. J
.--! 3G1 17 mi. NE of vent; local farm IDM,MLK,SOL,VGT lOGl 12 mi. SSW of vent; Smyrna, Delaware IDM 16Gl 15 mi. NNW of vent; Greater Wilmington Airport IDM
-3H1 32 mi. NE of vent; National Park, New Jersey IDM 3H3 110 mi. NE of vent; Research and Testing AIO,APT,IDM,SOL Laboratory 3HS 25 mi. NE of vent; local farm FPL ,FPV --*'*
--*--~
.* :1
*, 56
AJUIFICJAL l.SLA~~OCATIONS . ON SITE. SA MPl ING
\
.j Cl
. _*: 1
- -~ 57
. 'l
. ~-
. -* -~~ ----
MAP S-2 0FF-SITE SAMPLING LOCATIONS ARTIFICIAL ISLAH D 58
APPENDIX C DATA TABLES
. i i; .I i
l i .. I _._.,...--------.---.-.-------*---***'"<--- ---*----:.-------- -------*----.----- -. ___________ !. *. - - -,---- - .. ; - - - - - - - * . - - - - - - * - * - - .. - - - - - - - --- -- --- --***--* --~ --- --.-*- -- *****-* - * - .* .,. *** - -* * - * : -
- DATA TABLES Appendix c presents the analY.tical results <Jf. the 1986 Artificial Island Radiological Environmental Monitoring Program for the period of January l to December 31, 1986 *.
TABLE OF CONTENTS TABLE NO. TABLE DESCRIPTION PAGE ATMOSPHERIC ENVIRONMENT AIR PARTICULATES 1986 Concentrations Of Gross Alpha Emitters ******************** 64 c-2 1986 concentrations of Gross Beta Emitters.c:1****o*o*cio******oo* 66 C-3 1986 Concentrations of Strontium-89 and Strontiwn-90 and Gamma Emitters in Quarterly Composites *******************.* 68 AIR IODINE C-4 1986 Concentrations of Iodine~l3l ************* ~ **************** '10 DATES C-5 1986 Sampling Dates for Air Samples **************************** PRECIPITATION C-6 1986 concentrations of Gross Alpha and Gross Beta Emitters and Tritium ** Cl * * * * * *
- Clo.., e Cl. Cl * *
- Cl. c *
- o . Cl. e * * * *
- Q e *** o **** " *** o o 77 1986 concentrations of Gamma 11:mitters *******************.******* '18 DIRECT RADIATION TBERMCLUMINESCEN'r DOSIMETERS 1986 Quarterly TLD Results *** Cl Cl o Cl Q c '° o = Cl o
- c o G:I
- c * "
- o
- c. c Cl
- Cl* Cl o Cl o o " c 79
* °:-j
... I
*; 1986 Monthly TLD Results 0
- Cl 0 0 0 0 0 0 0 0 _o Cl 0 C) Cl g C> Q 0 0 c 0 °0 Cl e
- 0 0 Cl 0 e S!J .o G 0 Cl 0 0 so_
.. ' . ~
..- i
. i
*.*.1
**i 1
i 61
- .------.--*----- ~------*** -~ - - - --*-- - - .--~--- .--r-*- *-------~ ~~---:-*-- .~----~.-*----~...-~ -- ---- -- ~*----- - - - .-* .. ~-*** ****- ~ ... *****- ~ --;- -, **--*. w , - ....... - - - - - * **-
TABLE NO. OA'l'A 'l'ABLES ' (cont 1. c1. ) TA5LE DESCRIPTION PAGE
'l'ERRES'l'RIAL ENVIRONMENT MILK C-10 1986 concentrations of Iodine-131 **************.**************** 82 C-ll 1986 Concentrations of Strontium-89 and Strontium-90 *********** 83 c-12 1986 Concentrations of Gamma Emitters ************************** 84 C-13 1986 Sampling Oates for Milk Samples *************************** 88 WELL WATER C-14 1986 concentrations of Gross Alpha and Gross Beta Emitters; Potassium-40 and Tritium.................................. 90 C-15 1986 concentrations of Gamma Emitters **************************
- c-16 1986 Concentrations of Strontiwn-89 and Strontiwn-90 in.
Quarterly *composites.~************************************ 94-POTABLE WA'l'ER C-17 1986 concentrations of Gross Alpha and Gross Beta Emitters; _ Potassium-40 and-Tritiwn.................................. 95 C-18 1986 Concentrations of Gamma Emitters ************************** 96 C-19 1986 Concentrations of Strontium-89 and Strontiwn-90 in Qua.i:-terly composites ..**.... *-* .....*..*...........*........ 97 FOOD PRODUCTS* C"."20 1986 concentrations of Gamma Emitters in VegetalJles ************
- 98 c-21 1986 Concentrations of Gamma Emitters in Game and Meat ********* 99
.~
- . ~
FODDER CROPS c-22 1986 concentrations of Gamma. Emitters *********.**********.******* 100 62
DATA TABLES . ( cont. ' ¢i. ) .. TABLE NO. TABLE DESCRIPTION * *PAGE SOIL C-23 1986 Concentrations of Strontium-90 and Gamma Emitters ********* lOl AQUATIC ENVIRONMENT SURFACE WATER C-24 1986 concentrations of Gross Alpha Emitters ******************** 102 C-25 1986 Concentrations of Gross*aeta Emitters ***** ~*************** 103 C-26 1986 Concentrations of Gamma Emitters ************************** 104 C-27 1986 concentrations of Tritium in Quarterly Composites ******* :. lO;i EDIBLE FISH C-28 1986 Concentrations of Strontium~89 and strontium-90 and Tritium. o . o o . o o . o o e e o o o o a o a o o o o o o o o" ~. o o o . o o . Clo o o o . o . o o o o o 106 c~29 1986 Concentrations of Gamma Emitters ******************.******** 107 BLUE CRABS C-30 1986 concentrations of Strontium-89 and Strontium-90: Gamma Emitters and Tritium. o El * * * * * * * * * *a o * *
- o o * *
- o * * * * * . 0. e o 108 BENTHIC ORGANISMS
.i C~3J. 1986 Concentrations of Gamma Emitters ************************** 109 I
SEDIMENT C-32 1986 Concentrations of Strontium~90 and Gamma. Emitterso**O****o 110
-:...l SPECIAL TAE!LES i
LLDs C-33 1986 PSE&G Research corporation LLDs for Gamma Spectrometry **** 111
**.1 l
1.
- ')\>j 63
- .:*1
. --.-~..,. . --.-.---~-----;-------...... -- ~.~-:-------:- :---------.--.- --,.._,.,---- -------~-.- --:---*-----*-.-:~----------*-- *-*- ,. -,~*- --.- ....... - ---, ..,_, - ,.,-: **:-'"":"""* ,... -~- - --.-* -- -- ---*---* *---** -* ---
. .. .. . ~ ..
....' . .. :... ...:.._~:.
_, -~ ..* **- .:~-:...,.~,. ,:...~ *. -- ~----*-**-~**:;,.,!_;...*......... ,._,_,-... ; _: ..
.:i, *.
- .... *-:~-J *.
I i TABLE C-1 j 1986 CONCENTRATIONS OF GROSS ALPHA EMITTERS IN AIR PARTICULATES 1 I Results in Unit5 of 10- 3 pCt/m3 :t i sigma I
.1 1
STATION ID
**1 MONTH* SA-APT-2S2 SA-APT-651 SA-APT-601** SA-APT-1001 SA-APT-16El SA~APT-lfl SA-APT-ZFZ SA-APT-3HJ AVERAGE
.] 1.7:t0.9 2.2t0.8 1. 7+/-1.1 2.6:tl. l l.8:t0.8 1. 8+/-0. 8 2. l:t0.9 3.l:tl.1 2. l:tl.O j JANUARY i 1.8tl.O 1.8t0.9 2.l:tl.1 1.9:t0.9 2.0:t0.8 ( 1.0 2.4tl.O 1. 7t0.8 1.8+/-0.8
*1 <4.0 (1) l.4:t0.6 2.0tl .0 1.3+/-0.8 1.7t0.7 1. 7:t0.8 1.8+/-0. 7 3. 2:tl.O 1. 9+/- 1. 3
>j"' 1. 4:t0. 7 1.9t0.8 <0.9 l.6t0.9 l.6t0.8 1. 6+/-0. 8 1. 3t0. 7 l.4t0. 7 1.5+/-0.6 I
- 2. 8tl. 0 ?.4:t0.8 <0.9 1.9:t0.9 1. 7+/-0.9 2.0:t0.9 2.0:t0.8 1.8tl.O l.'9fl. 1
*.:*1 "i
I FEBRUARY ( 1.0 l.3:t0.9 3.Jtl.6 1.3:t0.8 2.0:t0.9 1. 7+/-0.8 l.9:t0.9 <0.9 1.7+/-1.5
*1 l 2.0:t0.8 2.9:t0.8 1. l:t0.8 2.6:t0.9 2.6:t0.8 2.2:t0.9 2.0:t0.7 2. l:tO. 7 2;2:i:1. l "I. *~ l.3:t0.8 l.6:t0.9 ( 1.0 l.6:t0.9 2.6:t0.9 1.6+/-0.8 1. 7+/-0.8 1. O:tO. 6 1.5tLO*
l 2.4:t0.9 l.9:t0.8 1.6:tl.O 1.6+/-0.8 2.3:t0.9 1. 9:t0. 9 l.9:t0.8 2.4t0.8 2.0+/-0.7
' * .. i
..1 MARCH 2.7+/-1.0 2.3:t0.8. 2.6:tl. 3 2.6:to:8 3.0:t0.9 2.4:t0.8 2.6:t0.8 2.4+/-0.8 2.6+/-0.4
~j 0) 1.2:t0.8 <0.9:* . <1.0 <1.1 <0.8 <0.9 <0.9 1. l:tO. 7 1.0t0.3
.j 2.4:t0.8 2. 2:t0. 9-: . <1.0 2.8:tl.O 3.0:tl.O 2.0:t0.8 2.2:t0.8 2. l:tO. 8 2:211.2
&fl.
- i. l.'8:t0.8 0.8:t0.6 1.3:tl.O 2.4:t0.9 2.3:t0.8 2.6:t0.9 1.6+/-0.li 2.3:t0.8 1. 9.i). 2 i APRIL 2.2:t0.8 2. l:t0.8 <1.0 l.3:t0.8. l.2:t0.8 1. l:tO. 7 l.6:t0. 7 1. 3:t0. 7 1. 5+/-0. 9 1*
j 0.9:t0.7 l.l:t0.7 <1.0 <0.8 l. l:t0.6 1.4:t0.7 l.6t0. 7 l.O:t0.6 1. l:til. 6 1* i l.8:t0.8 **t.J:tO. 7 1.8:tl.3 1.6:t0.9 1. 7+/-0. 8 2.0:t0.8 ( 1. 3 2. l:tO .8 1. 7:i:0.6
'*1 2.0:t0.8 l.3:t0. 7 . l.7:tl.l l.O:tO. 7 2.0:t0.8 1.6+/-0.8 2.2:t0.8 1. l:tO. 7 Lfii1L9
- l MAY 2.2:t0.8 3. 3:tl.O 1. 8:tl. ~ 3.0:tl.O 3. 2:tl.O 2.3:t0.8 2.8:t0.9 1. 9:t0. 7 2.611.2
! . 22:t2 ll:t2 2l:t2 10:t2
<0.8
<3.0 (1) 19:t2 9.9:tl.6 21:t2 8.9:tl.6 19+/-2 12:t2 20:t2 10+/-2 20:t2 9.8:tl.6
. 18114.
10+/-? :.
.! 7 .4tl.3 6;8:tl.2 '* 3.0:tl.4. 6.6:tl.3 6.6tl.1 5.3+/-1.1 7. ltl. 3 4.7:tl.O 5. 7+/-2.8
- 7. 2:tl.6 6.2:tl.6 2.6:tl.8 6.2:tl.~ <9.2 (1) 6.8+/-1.4 7 .4:tl.6 7 .4:tl.6 6.1+/-3.4 JUNE 12:t2 9.3:tl.6 <2.0 10:t2 8.2:tl.4 9,'Z:tl.6 9.6:tl.6 8.7+/-1.4 8;6+/-ui 2.0:t0.8 1.3+/-0. 7 ( 1.0 0.9:t0.7 1. 7:tO. e l.6:t0.B 1.910.8 1.6:t0. 7 1. !110. 8 2.8:tl.O 3.0:tl.O 2. l:tl.2 2.0:tl.O 2.2:t0.8 2.3:tl.O 2.4+/-0.9 2.4+/-0.9 2'.410.1 2.6:t0.9 <0.8 1. 4:tl. 1 l.9:t0.B 1. 2:t0. 7 l.8t0.8 1.h0.8 2.2:1;1>.8 Lhi.l
- -*. - *-****-* ---~-*~ *--* ,_
.. ____** ~~.
- .~ *.. ~ :.:. **---*-*:. :..., ..':* _,_._: ~~.:*; .. .:... ..... :*~.'.' ..... ; ..-;'-... .
IABlE C-R (cont'd) 1986 CONCENTRATIONS Of GROSS ALPHA EMITTERS IN AIR PARTICULATES Results in Units of 10- 3 pC1/m3 t 2 sigma S!AHOM ID MONTH* SA-APT-252 SA-APT-liSl SA-APT-501** SA-APT-1001 SA-APT-16El SA-APT-lfl SA-APi-2f2 SA-APT-3H3 AVERAGE JULY R.2:1:0.1 A.h0.6 <2.0 2.2t0.9 2.4+/-0.8 2.4t0.9 2. l:tll. 8 1. 3t0. 7 1. 8+/-1. l i.8t0.9 2.0t0.8 <2.0 2.2t0.9 A.8:1:0.8 2.2:1:0.9 2.8:1:0.9 2.6t0.9 2.210.1
~i.z <A.2 2.3:1:1.4 1.6:1:0.9 1.7t0.9 1.ltO .8. 1.8:1:1.0 l.6tli.9 l. 6t0. 8
<!. i L4t0.8 <1.0 2.h0.9 2.8ti.O <1.1 1.3t0.9 ( 1.1 1.6+/-1. 6 AUGUST 1.6:1:0.9 n.2:1:0.8 <1.0 1.0t0.8 1.0t0.8 1.8t0.8 1.9tl.O 1. 7t!J.8 l.4t0.8 Z.6:1:LO 1.9+/-0.9 <2.0 1.8:1:0,9 2.6:1:0.9 <1.1 i.8:1:0.9 2.0tll.9 2.0t0.9 3.8:1:1.0 3.8:1:0.9 <1.0 4.0tl.O 4.6:1:1.0 4.4:1:1.0 2.6:1:0.8 1.6:1:0.8 3.2t2.6 2 .6t1.1 1. 2+/-0.8 <2.0 2.6t0.9 2.2+/-0.9 1.8+/-0.9 1. 7+/-0. 9 3.0:1:1.0 2.ltl.l 1.0:1:0.7 <O. 9 1. 9tl. l 2.0t0.8 3.6+/-0.9 1.4t0. 7 R.6:1:0.8 1.2:1:0.8 l.7t1.7 SEPTEMBER 1.4t0.9 R.2t0.8 <2.0 1.4+/-0.9 1.9+/-1.0 1. 2+/-0 .8 1. 7t0. 9 1.6+/-0.9 1. 6+/-0 .6 all 2.4t0.8 3.0t0.8 1.9+/-1.2 3.1:1:0.9 2.9t0.8 2.7':1:0.8 3.2:1:0.8 2.4:1:0.8 2Jt0.9 IClll 2.0t0.8 1.6:1:0.8 l. 9tl. 6 1.6:1:0.8 1.6:1:0.8 1. 7t0.9 1.7:1:0.8 1.6:1:0.8 1. 710.3 L7t0.8 L9t0.8 2.2tl.3 2.0t0.8 1.2+/-0.~ 2.0t0.8 1. 2+/-0. 7 2.0t0.8 1.8t0.8 OCfOBER <1. 2 <1.1 <1.0 <1.3 <l. 2 <1.1 ( 1.2 ( 1.2 1.lt0.7 0.8t0.6 <1.0 1. 7:!:0. 7 1.6:1:0.6 1.6:1:0. 7 1.6:1:0. 7 1.8t0.8 1.4t0. 7 2.0:1:0.9 2.0t0.8 ( 1.0 i.7t0.8 2.0t0.9 1.4t0.8 l. 2t0. 7 1.6:1:0.8 1. 6t0. 8 2.3:1:1.0 2.4t0.9 3.3+/-1.6 1.8:1:0.8 1.9t0.8 1. 7t0 .8 1. 9:1:1.0 1.9t0.9 2.2tl.O l.2t0. 7 1.4t0.8 2.8+/-1. 6 1.2+/-0.8 2. ltO. 9 1.5t0.8 <0.8 2. lt0.8 1.6+/-1..3 NOVEMBER 3.7:1:1.l 3.lt0.9 l.8+/-1. 2 3.b0.9 4.0tl.O 4.!tl.l 3.6:1:1. l 3.2tl.O 3.3tl.4 I 1.7tll.9 1.2+/-0.8 2.2:1:1.3 1.1:1:0.8 L4t0.8 1.6+/-0.8 1.6+/-0.8 1.6t0.8 1.5t0 .'7 L9t0.9 2.6t0.9 <l.0 1.8+/-0.9 1.8t0.8 2.7tl.0 1.2:1:0.8 2.4:1:1.0 l. 9tl. 2
<29 (1) i.8t0.9 3.7+/-1.7 2.h0.8 2.2:1:0.8 1. 8t0. 9 2.0t0.9 2.6t0.9 2.3+/-1:.3 DECEMBER L2t0.9 1.-tt0.8 2.0tl.2 <1.0 1.6:1:0.8 ( 1.0 <1.0 <3.6 (1) 1. 3:1:0. 7 2.9:1:!..0 2.7+/-1.0 2.0tl.3 2.2t0.9 2.4t0.9 2.0t0.9 2. l:tO. 8 2.6t0.9 2.410.7 2.1:1:1.0 2. lt0.9 <20 (l) 2.6:1:1.0 R.9t0.8 1.910.8 1.8:1:0.9 2.6:1:0.9 2.lt0. 7 2.0:1:0.a 2.Zt0.9 '*,
- 2. ltl.3 2.4:1:0.9 2.610.8 1. 2+/-0. 7 L4t0.8 . 1.010. 7 1.811.}
AVERAGE 2.9:1:7. l Z.6:t6.-t 1. 8:1:1. 4 2.7:t6.9 Z.8:1:6.0 2.6t6.1 Z.7t6.Z 2.h6.l Grand AveragQ l.6t6.9 v Sampl1n~ dates can be found ~n Table C-6. vv Results by Teledyne isotopes. (A) High iLD due to 1ow samp~e vo~ume. Result not included ijn any a111arage5.
II
**-- .. -_...'.... -*~ ,--* _,. . .'..,~.*~; . :; .. .;~--
',I'
".;.:., **:*~* ... :_.:...:' -'*-" :.. ..:* ~**, .~. "
. ~
. *' :~ :..
-* ****' .. :-.~~'_:,
... :.. ; '. . - . ; '.) .. .. _.**,,::. ,,.:: .. .:... *_ .. *-* --- ..,.,,......, .... **'
l
. '\
I I i TABLE C-2. 1986 CONCENTRATIONS OF GROSS BETA EMITTERS IN AIR PARTICULATES Re~ults 1n Units of 10- 3 pC1/m3 :t 2 sigma
.I STATION ID i
I MONTH** SA-APT-ZSZ SA-APT-6Sl SA-APT-501** SA-APT-1001 SA-APT-16El SA-APT-lfl SA-APT-ZFZ SA-APT-3H3 AVERAGE
.I I
! 25t3 3Z:t3 28:t3 26t3 28t3 32t3 28+/-5
*I JANUA~Y Z6:t3 Z7:t3 I 29:t3 27:t3 26t3 28:t3 27:t2 14tZ 27:t3 Z5:t3 26+/-9
.*j 32:t12 (1) l9:t2 20+/-3 2Zt3 20:t2 20t3 22t2 28t3 . 22t6
. ' 2l:t3 20+/-2 22t3 24:t3 22:t3 17t2 19:t2 18:t2 20+/-5 29+/-3 28+/-3 29t3 29:t3 30+/-3 32t3 29:t3 24+/-3 29+/-4
.i.I
. !! FEBRUARY 17tZ 15+/-3 19t3 19+/-3 '18t2 16t2 14t2 13t2 16+/-4
*I 30t3 32+/-3 29t3 36t3 30:t2 33t3 32:t2 27t2 31+/-6
*.1 16:t3 14+/-3 17t3 18t3 17t3 16+/-3 13t2 15+/-2 16t3 1 24:t3 24:t3 22+/-3 24t3 24:t3 2~+/-3 i 28t3 24+/-3 23:t3
. MARCH Z5t3 Z2:t2 24:t3 26+/-3 22tZ 25t3 26t3 20t2 24+/-4 13:tZ 13t2 17t2 16t3 13tZ 16tZ 15tZ 17tZ 15+/-3 I ()) 24tZ Z4t3 21+/-3 24t3 2Zt3 22t2 2lt2 19tZ 22+/-4 ()) 20t2 21t2 24t2 22+/-3 l 23:t? ~3tZ ZO:t3 24+/-3 23:t2 i
*1 . APRIL 16:t2 13t2 17t3 lO:tZ 12:t2 16t2 13t2 12t2 14+/-6
.~i 9.4+/-2.3 7.6t2.2 10+/-2 9.0:t2.3 8.6tZ.O 8.0t2.3 8.0t2.2 llt2 8.9t2.3 19+/-3 22+/-3 ZO:t3 18+/-2 12t3 20t2 18t6
*1 j 19:t2 24t3 16:t2 2l:t2 23t3 2lt3 2l:t2 19+/-2 . 21t3 16t2 2lt5
*:.1 20+/-3 22t2 23+/-3 MAY
- 23+/-3 Z4t3 23+/-3 26:t3 24+/-3 23+/-3
.i 350:t8 . 340+/-8 20t3 330+/-8 370:t8 350+/-8 340+/-8 330t8 300+/-230
.;*;" 270+/-7 260t7 170tl0 (1) 260+/-7 240+/-7 270t7 260t7 260t7 260t22'
.: I
*1J 170+/-6 180t6 140+/-10 180t6 160+/-6 180+/-6 180+/-6 130+/-6 160+/-40
**: 170+/-6 160+/-6 140t10 170:t7 200+/-27 (1) 160+/-6 160+/-6 190t7 160+/-34 I
JUNE 200t6 180:t6 160tl0 190t6 160+/-6 190+/-6 180+/-6 170+/-6 180+/-29 3lt3 26t3 . 27t3 30+/-3 29t3 35t3 26t3 31t3 -29t6 . 32t3 34+/-3 28+/-3 34t3 34+/-3 30+/-3 36t3 37+/-3 .33+/-6 27t3 6.7tl.9 26+/-3 24:t3 25t3 24+/-3 23+/-3 . 24t3 :z211~
.I
.i
*' ~
.i
_., .*..... * * .'I
- t I*
'. {'
- . ~ . **:.... ~.* ..-~.* ..~..' ..... -* ... . *1 *.:~~ **L. *- . ..... __ , :: :*...,*' ..... : * *-*- ~-. ~ ::. .t:".. **:
TABLE C-2 (cont'd) 1986 CONCENTRATIONS OF GROSS BETA.EMITTERS IN AIR PARTICULATES Results in Un~t~ of 10-3 pCt/m3 :t Z sigma STATIOff ID MONTH* SA-AP1"-2SZ SA-APT-liSl SA-APT-liDl** SA-APT-1001 SA-APT-16El SA-APJ-lfl SA-APT-ZFZ SA-APT-3H3 AVERAGE JULY Z9:t3 24t3 Z7:t3 3lt3 31+/-3 Z4:t3 24+/-3 Zli:t3 Z7:t6 30+/-3 26+/-3 20+/-3 30+/-3 28+/-3 30:t3 31+/-3 Z7:t3 Z8:t7 26:1:3 24*31 27t3 24+/-3 24+/-3 Z4:t3 27+/-3 24:1:3 25:t3 21::1:3 24t3 26+/-3 26+/-3 26:t3 2Zt3 22+/-3 Z4:t3 Z4t4* AUGUST 22+/-3 2Z:t3 ZZt3 2l:t3l 24+/-3 20tZ 23+/-3 19+/-3 22+/-3 36+/-3 33t3 30:t4 32t3! 33+/-3 3Z:t3 3h3 28:t3 32+/-4 28t3 26:1:2 21+/-3 24:t3 Z6:t3 28+/-3 27+/-3 2Zt3 25:t5 20t3 "!6:t3 24+/-3 20:1:3 ZO:t3 ZO:t3 18+/-3 19:t3 ZO:t5 23tZ 22:t2 23+/-3 22:t2 24:t2 26+/-2 24+/-3 24:t3 Z3t2 SEPJEMBU 26:t3 26:t3 28+/-4 26t3 26:t3 28:t3 26:t3 Z6:t3 Z6:t2 30:t3 3Zt3 30t3 30:t3 32:t3 29:t3 26:t3 28:t3 30:t4
©ii 22t3 20:tZ Z6t3 24+/-3 2h2 Z4:t3 23+/-3 19:tZ 22+/-5
~
28ii:3 :ll1:t3 Z4:t3 28t31 28+/-3 27+/-3 28:t3 36:t3 Z9:t1 OCiOBER *21:t3! ll8t2 19:t3 18+/-3 19:t3 19:tZ Hl:t3 ZZ:t3 19+/-3 19:t2 20:tZ lli:tZ 20:1:2 20:tZ 18+/-2 2C:tZ ZO:i:Z 19+/-4 26:t3 Z7:t3 25+/-4 26:t3 26+/-3 26:t3 21i:t3 20+/-3 26:t4 39:t3 40t3 38:t4 36:t3 34+/-3 38:t3 38:t3' 38*3 38+/-4 24+/-31 22:t3 26:t3 21:t3 23:t3 . 24:t3 23:t3 2613 23+/-3 NOVEMBU ll7:t31 lli:tZ 16:1:3 !4:t2 16:t:Z 16:t2 i6:t2 20:t3 1614 22+/-3 24:t3 26:t3 26:1:3 2Z:t2 24+/-3 23+/-3 24:t3 24:t3 28:t3 27:t3 26:t3 28:t3 Z6:t2 28+/-3 26+/-3 32:t3 28+/-4
<90 (Z) 29+/-3 36:t4 23+/-2 26:t3 26:t3 30+/-3 27:t3 28:t:8
- DECEMBER 20:t3l 2l:t2 23:t3 18:tZ 19:tZ 20:tZ 22+/-3 16:t7 (1) 20:t3 29:1:31 Z9:t3 30:t4 28:t3 29+/-3 Z6t3 Z7:t3 26:t3 28+/-3 31i:t3 36:t3 99:t49 ( 1) 36+/-3 32:t3 33:t3 33+/-3 Z9:t3 33+/-6 i 26+/-2 28+/-3 27:t3 29:1:3 25:t2 27tl 29.t3 Z6:t] Z7:t3 AVERAGE 45:tR30 otZ:t120 3!:1:60 44:!:130 40:U20 43:030 4b!20 4hUO 6rilo4 A11eril!Je 4hlio
~ Samp]tng dates can be found In iab1e C-6.
~c Result$ by ieledyne isotopes.
~1! Due to low sample 1101ume, resuit not tncluded in any 1verage1.
2 High LLD due to 1ow samp1e ~oUu!ll@. Result not tnc~ude~ tn any ~~erages.
,. * '**---**~*~"~*- ~-'* - "' '~- *** ' ' * ' ' " r ** "** .,..
TABLE C-3 . 1986 CONCENTRATIONS Of STRONTIUM-89* ANO STRONTIUM-90 AND GAMMA EMITTERS** IN QUARTERLY COMPOSITES Of AIR PARTICULATES Results In Units of 10- 3 pCl/m3 +/- 2 sigma STATION IO COLLECTION PERIOD Sr-89*** Sr-90*** Be-7 Ru-103 Ru-106 Cs-134 Cs-137 Ra-226 Th-232 SA-APT-2S2 12-30-85 to 03-31-86 <0.4 <0.3 64+/-5 <0.4 <3.1 <0.6 <0.6 ( 1.0 <Z.2 03-31-86 to 06-30-86 96+/-7 8.8+/-0.8 <7.7 9.8+/-0.9 18+/-1 <1.8 <2.6 06-30-86 to 09-29-86 89+/-6 <0.5 <4.4 <0.6 <0.4 <l.O <l. 7 09-29-86 to 12-29-86 66+/-6 <0.6 <5.9 <0.5 <0.7 <l.2 <2.7 SA-APT-6Sl 12-30-86 to 03-31-86 <0.4 <0.2 66+/-5 ' <0.3 <4 .1 <0.6* <0.4 ( 1.1 ( l. 9 03-31-86 to 06-30-86 *- ..: 77:tli 7.8+/-0.6 4.0:tZ. l 9.3+/-0.8 17+/-1 <l. 3 ( 1.6 06-30-86 to 09-29-86 88:tli <0.3 <4.3 <O .Ii <0.4 <0.3 ( i .2 09-29-86 to J2-29-86 66:tli <0.3 <6.3 <0.6 <0.6 <1.0 <2.1 m O> SA-APT-601 (1) 12-30-85 to 03-31-86 <2.0 <0.3 86+/-8 <0.8 <6.0 <0.6 <0.6 <9.0 (2) 03-31-86 to 06-30-86 110+/-12 9.2+/-1.3 <7.0 8.4+/-1.1 18+/-2 <10 (2) 06-30-86 to 09-29-86 89+/-11 <1.0 <8.0 <l.O ( 1.0 <10 (2) 09-29-86 to 12-29-86 - 80+/-6 <0.6 <3.0 '<0.3 <0.4 <6.0 (2) SA-APT-1001 12-31-86 to 04-01-86 <0.4 <0.3 71+/-5 <0.4 <4.7 <0.6 <0.3 ( 1.0 <2.3 04-01-86 to 07-01-86 88+/-6 8.7+/-0.7 <7.0 9.ilt0.9 17+/-1 ( 1.6 <2;4 07-01-86 to 09-30-86 76:tli <0.6 <4.3 <0.6 <0.4 ( 1.0 ( 1. 2 09-30-86 to 12-30-86 60+/-4 <0.6 <2.7 <0.5 <0.4 <0.7 ( 1.6
*i
.'1
.,' !! .. *** /: .
. .... . . .. .... **- - '. .... ~ ... .:, .....
I TABLE C-3 (cont'd)* 1986 CONCENTRATIONS Of STRONTIUM-89* AND STRONTIUM-90 AND GAMMA EMITTERS** IN QUARTERLY COMPOSITES OF AIR PARTICULATES Results In Units of 10- 3 pCl/m3 :1: 2 sigma STATION ID COLLECTION PEMIOD Sr-89*** Sr-90*** Be-7 Ru-103 Ru-106 Cs-134 Cs-137 Ra-226 lh-232 SA-APT-16El 12-31-86 to 041-01-86 <I!. 41 <0.3 64:1:4 <0.4 <3.9 <0.4 <0.4 ( 1.0 (I. 6 l 04-01-86 to 07-01-86 83:1:!5 1.6:1:0.6 4.2:1:2.1 8.411:0.8 16tl ( 1.4 '( i .6 1 01-01-86 to 09-30-86 83tli <0.3 <4.2 <0.6 <0.4 <0.'11 *< 1.1 J J 09-30-86 to 12-30-86 64t4 (0,3 <2.6 <0.4 <0.4 <0.6 <1. l I I l l SA-APT-lfl .! 12-30-86 to 03-31-86 <0.6 <0.3 66:1:6 <<C. n <4.6 <0.6 <0.6 l.Zt0.6 <2.2 03-31-86 to 06-30-86 86:1:6 8.8+/-!1. 7 8.3t3.3 lOtl 17tl ( 1.4 <2.3 06-30-86 to 09-29-86 79:1:6 <<0.4 <4.6 <0.6 <0.5 <0.9 1. 7+/-1.0 09-29-86 to 12-H-186 64tE <0.2 <3.6 <0.6 <0.4 <0.8 <l. 3 Cll co SA-APT.:.2f2 .., AZ-30-85 to 03-31-86 <G.3 <0.2 63:11:~ <<lli.3l <Z.8 <0.6 <0.3 <0.3 <L2 03~31-86 to 06-30-86 80:1:6 9.0tG.8 <7.2 lOti Htl <1.1 <2.3 06-30-86 to 09-29-86 78t6 <0.6 <3.0 <0.6 <0.4 <1. R <2.2 09-29-86 to iZ-29-86 6h6 <<0.6 ( 1.6 <0.4 <0.4 <L 1 <LB SA-AP1f-3H3
'Contiro])
12 6 to 03-31-86 <O.:ll <0.2 64t4 <0.31 <3.9 <0.4 <0.4 <0.9 (l, l 03-31-86 to 06-30-86 83t6 7.6t<<l.li 4.0tl.9 9.2:1:0.7 17tl <0.3 ( 1.1 06-30-86 to '09-29-86
- 90t7 <0.1 <7.6 (0,6 (0,6 <1. R <2.1 09-29-86 to lZ-29-86 64+/-6 ((),6 <6.8 (0,3 (0,6 ( 1.3 ( 1. 9 AVERAGE 76tU u Sr-89 results are corrected for decay to &le stop dmts.
=* AJl ot~er ganma emitters searched for were <LLD; typlc~I llDs ar~ given In Table C-33.
aaa Management audit anaUyses, ~ot required by Techolca~ specAflcilijons or by specific conmitments to Joe al off ic iii Iii. (1) Results by Veledyne Isotopes.
<<Z) Not analyzed by Te]edyne isoto~es.
r--*~-'- . . '--*'. . -* *--.. * - -* * . . . . ... *.* I
~1 l; .
l*_i.
*1
,j TABLE C:-4
*.1
.! I 1986 CONCENTRATIONS OF IODINE-131* IN FILTERED AIR Results 1n Units of 10- 3 pCt/m3 t Z sjgma STATION ID
*MONTH** SA-AIO-ZSZ SA-AI0-651 SA-AI0-6Dl*** SA-AIO-lODl SA-AI0-16El SA-AIO-lfl SA-AIO-ZFZ SA-AI0-3H3 AVERAGE JANUARY <19 <16 <ZO <33 <ZZ ( 9.3 <Z4 <16
<14 <Z6 <20 <14 <17 ( 8.0 <14 <13
<140 (1) <13 <20 <23 <18 <22 <17 <22 I <17 <23 <20 <27 <18 <16 <17 <16
*1 I <16 <16 <10 <11 <26 <16 <22 <29 i
.1 I
FEBRUARY <Zl <Z4 <20 <23 <18 <21 <19 <16 I <19 <10 <10 <11 <14 ' <17 <11 <16
*J <16 <41 <30 <13 <28 <30 <21 <13 I <16 <Z4 <10 <28 <20 <18 <14 <17
- j
.\
i 0 MARCH <Z6
. <16
<19
<Zl
<17
<14
<30
<10
<20
<14
<26
<17
<14
<20
<19
<19
<16
<19
<ZZ
<18
( 11
<U
<18
<18
.1
.J ( 13 <16 <10 <13 <12 <16 <20 <16 j
APRIL <18 < 8.7 <40 <19 <22 <18 <26 <20
.! <16 <20' <20 <21 <16 <18 <17 <14 i! <19
<16
<30
( 9.9
<30
<40
<18
( 16
<Zl
<13
<17
<23
<39
<13
<12
<16 j
1 MAY <20 <16 <40 <16 <26 <20 <26 <22
- I
! 310t34 310t32 280t60 310t29 300t32 320t36 270t32 320t32 300t37 **! 230t30 180t28 610t220 (2) 180t28 190t29 220t28 220t28 230t30 210t46 oj 8ltl4 66t16 73t16 60tl7 70t18 76t16 73tl8 65t16 69tl7 1
I 48tZO <32 <60 46t20 <390 (1) 42t23 62t22 64t20 48t20
!i
*, JUNE 26tll 33t13 <30 <28 <28 32tl6 <30 (3)
J <16 <22 <40 <29 <19 <18 <20 <16 .. .-
.. j <17 <22 <20 <14 ( 8.9 <28 <21 <19 .
( 17 <14 <30 <14 <18 <14 <22 <20 I
- ,1
..... j
lABlf C-4 (cont'd) 1986 CONCENTRATIONS Of IODINE-131* IN FILTERED AIR Re5ults in Units of 10- 3 pCi/m3 +/- 2 sigma SJAHOU rn lllONJH** SA-Al0-2S2 SA-AR0-551 SA-AI0-501*** SA-AI0-1001 SA-Al0-16El SA-AIO-lfl SA-AI0-2f2 SA-AI0-3H3 AVERAGE JULY <24 <A4 <20 <26 <20 <19 <26 <l8
<22 <U <30 <16 <21 <18 <20 <16
<20 <!4 <20 <22 <19 <16 <30 <17
<19 <!2 <20 <1l <13 <20 <16 <20 AUGUST ( 9.4 <H <30 ( 9.9 <28 <14 <18 <15
<26 <n9 <20 <22 <23 <12 <21 <15
<14 <Il6 <20 <30 ( 8.0 <21 <lO . <24
<U <18 <30 <19 <lJ <23 <!6 <18
<16 <12 <20 <14 <13 <20 <iii <16 SEPTEMBER <22 <24 <30 <21 <27 <23 <17 <20
< 9.1 ( 7.7 <20 <26 <16 <19 <21 <22
..;ii <26 <24 <20 <H If-'
<25 <33 ( 11 <12
<18 <32 <20 <14 <25 <13 <22 <19 OCIOBER <20 <10 <20 <36 <20 <21 <11 <17
<R4 <H <10 <14 ( 9.0 <16 <22 <18
<23 <H <30 <22 <31 <33 <26 <19
<18 <A9 <20 <H ( 8.6 <20 <30 <20
<16 < 9.6 <20 <26 <14 <12 ( 8.5 <18 NOVEMBER <20 <Ali <20 ( 19 <15 <20 <24 <15
<21 <28 <10 <21 ( 17 <17 <231 <26
<!9 <Ui <30 <21 <H <16 <14 <18
< lOOO (1} <17 <10 <19 <21 <28 <25 <21 DECEMBER ( 9.2 <18 <20 < 8.1 * <12 <13 <19 ( 120 0)
<22 <16 <10 <19 <16 <21 <22 <18
<20 <H ( 1000 ( 1) <20 <R3 <16 ( 1. 9 ( 17
<23 <2! <10 <29 <AB <29 ( 36 <30
~ I-131 results are corrected for decay to sample stop date.
** Sampling date$ ~an be ffound ~~ Table C-6.
*** Results by Te]edyne Isotopes.
ll) High LLD due to lo~ sample volume.
- 2) High uncertainty due to low samp]e volume. Result not included i~ any averages.
~3) No results due to faul~y sampiing assembly.
.. :~ ...... ~.. _* ... ~:.:.:....:..~~~ ... '_.: ._ *...:..:.. .. _ ' .. * **--" ****- "' ... , ; '. * .,.., * *: o >' '**~
- M,o/ ... i - . *"*' ... .. .. *.... :.:. *. "***-*** . , ..
I.
*I
- )
i
.,l
*l i'
i TABLE C-6 1986 SAMPLING DATES FOR AIR SAMPLES j I l. 1* STATION ID MONTH zsz 6Sl 601 1001 16El lfl ZFZ 3H3
- 1 JANUARY lZ-30-86 lZ-30-86 lZ-30-86 JZ-31:-86 lZ-31-86 lZ-30-86 lZ-30-86 12-30-86 "i to to to to to to to
! to 01-06:...86 J
I Ql-06-86 01-06-86 01-06-86 01-06-86 01-06-86 01-06-86 01-06-86 ii 01-06-86 to 01-06-86 to 01-06-86 to 01-06-86 to 01-06-86 to 01-06-86 to 01-06-86 to
. 01-06-86 to I
01-13-86 01-13-86 01-13-86 01-14-86 01-14-86 01-13-86 01-13-86 01-13-86
.i
! 01-13-86 01-13-86 01-13-86 01-14-86 01-14-86 01-13-86 01-13-86 01-13-86 to to to to to to to to
*.] 01-14-86* 01-Z0-86 01-Z0-86 01-Zl-86 01-21-86 01-20-86 01-20-86 01-20-86 I
.J 1 01-20-86 01-20-86 01-20-86 01-Zl-86 Ol-Zl-86 01-20-86 01-20-86 01-20-86 to to to to to to to to II 01-27-86 01-27-86 01-27-86 01-28-86 01-28-86 01-27-86 01-27-86 01-27-86
. *. *1
' 01-27-86 01-27-86 .
. *) 01-27-86 01-27-86 01-27-86 01-28-86 01-28-86 01-27-86
..;z to to to to to to
.j to to r
(\) 02-03-86 02-03-86 02-03-86 02-03-86 02-03-86 OZ-03-86 02-03-86 02-01-86*
.* .i FEBRUARY 02-03-86 OZ-03-86 OZ-03-86 02-03-86 02-03-86 02-03-86 02-03-86 02-03-86
.i to to to to to to to to
..I., OZ-10-86 02-10-86 OZ-10-86 OZ-11-86 02-11-86 OZ-10-86 02-10-86 02-10-86
*, J
. *,I l !>2-10-86 02-10-86 02-10-86 OZ-11-~6 02-11-86 02-10-86 02-10-86 02..:10-86 to to to to to to to to .*
.1 ,I 02-18-86 02-18-86 02-18-86 OZ-19-86 02-19-86 02-18-86 02-18-86 02-18-86
.I OZ-18-86 OZ-18-86 02-18-86 OZ-19-~6 02-19-86 02-18-86 02-18-86 02-18-86
'.I to to to to to th ; . ( ..
to to
. :I 02-24-86 02-24-86 02-24-86 02-26-~6 02-25-86 02-24-86 02-24-86 02-24-86 j
.. ~ . 02-25-86 02-24-86 02-24-86 02-24-86 I 02-24-86 02-24-86 02-24-86 02-26-86
*:i to to to
- to to to to to
.~J 03-03-86 03-03-86 03-03-86 03-03-86 "03-03-86 03-03-86 03-03-86 03-03-86
.;j 03-03-86 03-03-86 03-03-86 03-03-86 03-03-86 03-03-86 03-03-86 MARCH 03-03-86 ta* *
.. 1 to to to to to to to
*;;'J
*1 03-10-86 03-10-86 03-10-86 03-11-86 03-11-86 03-10-86 03-10-86 03-10-86
- -:*" :; 03-10-86 03-10-86 03-10-86 03-11-86 03-11-86 03-10-86 03-10-86 03-10~86
., .l to to to to to
.i to .to to
- ,I 03-17-86 03-17-86 03-17-86 _03-1. 03-18-86 03-17-86 03-17-86 OJ:.. lJ-86
*1
.j
,*.,.~.:~ ... ~....:..:--...:, . .. .:.::.::..::~ .. *...: .~:.::.., ~ ... ~: ~,:.. .* ~ .:i. ....*.-....:.......~.*~- *. *~*;..,,_.. ~ . ~- <.** J ,. .* "" .*.* ( " ... :... , ; ..... '
iI I I. TABLE C-6 (cont'd) 1986 SAMPLING DATES FOR AIR SAMPLES STATION ID MON!H 252 651 6Dl 1001 16El lf! 2F2 3H3 MA!ICH 03-17-86 03-U-86 03-17-86 H-nll-86 03-18-86 03-17--86 03-17-86 03-17-86 to to to to to to to to
@3-24-86 03-24-86 03-24-86 03-25-86 03-26-86 03-24-86 03-24-86 03-24-86 03-24-86 03-24"-86 03-24-86 03-26-86 03-26-86 03-24-86 03-2'4-86 03-24.-86 to to to h to to to to 03-3R-86 031-31-86 03-31-86 04-01-86* 04-01-86 03-31-86 03-31-86 03-31-86 APIUL <<>3-:U-86 03-31-86 03-31-86 04-01-86 04-01-86 03-31-86 03-31:-86 03-31-:86 to to to to to to to to 04-07-86 04-01'-86 04-07-86 04-01-86 04-07-86 04-01'-86 04-07-86 04-07-86 04-07-86 04-07-86 04-07-86 0~-0?-86 04-07-86 <<>4-0?-86 04-07-86' 04-07-86 Q:.o to to to to to to to o4-a4-86 ID4-!C-86 04-14-86 04-16-86 04-16-86 04-14-86 04-14-86 04-14-86
~ 04-14-86 04-14-86 04-14-86 04-16-1116 04-16-86 04-14-86 04-14-86 04-14-86
~ to to to to to to to to 04-21-86 04-21-86 04-21-86 04-U-86 04-21-86 04-21-86 04-18-86* 04-21-86 04-U-86 04-21-86 04-21-86 04-21-86 04-21-86 04-21-86 04-21-86 04-2*i-86 to to to
- to to to to to 04-28-86 04-28-86 04-28-86 04-29-86 04-29-86 04-2!1-86 04-28-86 04-28-86 MAY 04-28-86 04-28-86 04-28-86 04-29-86 04-29-86 04-28-86 04-28-86 04-28-86 to ta to to to to to to Oli-06-86 Oli-05-86 06-06-86 06-0li-86 06-06-86 06-06-86 06-06-86 06-06-86 06-06-86 l!lli-06-86 06-06-86 Oli-06-86 06-0!i-86 06-06-86 O!i-O!i-86 O!i-06-86 to to to to to to to to Oli-12-86 06-12-86 06-12-86 06-12-86 06-12-86 Ol:i-12-86 06-12-86 05-12-86
\
.~ i 06-12-86 Olii-ll2-86 O!i-12-86 06-12-86 O!i-12-86 06-12-86 06-12-86 06-12-86 to to to to to to to to 06-19-86 06-19-86 06-14-86* 06-19-86 O!i-19-86 06-19-86 06-19-86 06-19-86
' 06-19-86 06-19-86 O!i-19~86 Oli-H-86 06-19-86 Oli-19-86 06-19-ij6 06-19-Bfi to to to to to t.9 t9 tq Oli-27-86 06-27-86 06-27-86 Oli-27-86 Oli-U-86 Ofi-i1-116 Q§-U,.11~ O!i-27-'~g Oli-Z7-86 06-Z?-86 06-U-86 Oti~U~96 C16-n-e6 (lij,.iHlfi o~-n~a~ Qij-27:-ij~
to to to ~o to to to to I 06-02-86 06-0Z-86 06-02-86 06-02-86 06-28-86* 06-02-86 06-02-86 06-02-86 1
**::_; _,L_.:~~-::..:.;: .. ~ =.! **:.&.:.. . . h .... *........... --*-~--:~-.:_:, .. ;... ... - **.,. ....:...J.-'..*.- -,.~.r::,,, ,;, .... ***.!; **- ** ' ..... ,. *****~- **- .. , .. ****-** . *-- ... *-* .....
l j I
\.
II
.i j TABLE C-6 (cont'd)
I
- 1
.j 1986 SAMPLING OAT~S FOR AIR SAMPLES I
1* j STATION ID MONTH 252 65~ 601 1001 16El lfl 2F2 3H3 JUNE 06-02-86 06-02-86 06-02-86 06-02-86 06-03-86 06-02-86 06-02-86 06-02-86 i" to to to to to to
. 06-09-86 to to r.
*1 06-09-86 06-09-86 06-09-86 06-09-86 06-09-86 06-09-86 06-09-86
)
06-09-86 06-09-86 06-09-86 06-09-~6 06-09-86 06-09-86 06-09-86. 06-09-86 1 to to to to to to to to - I 06-16-86 06-16-86 06-16-86 06-16-86 06-16-86 06-16-86 06-16-86 06-16-86 I J i 06-16-86 06-16-86 06-16-86 06-16-86 06-16-86 06-16-86 06-16-86 06-16-86
' to to to to to to to to i 06-23-86 06-23-86 06-23-86 06-23-86 06-23-86 06-23-86 06-23-86 06-23-86 i
'.j 06-23-86 06-23-86 06-23-86 0~-23-86 06-23-86 06-23-86 06-23-86 06-23-86
! to to to to to to . to to II
. -~
..,, JULY 06-30-86 06-30-86 06-30-86 06-30-86 06-30-86 06-30-86 07-01-86 07-01-86 07-01-86 07-01-86 06-30-86 06-30-86 06-30-86 06-30-86 '
06-30-86 06-30-86 I
.t ~ to to to to to to to to . . -3 07-07-86 07-07-86. 07-07-86 07-07-86 07-07-86 07-07-86 07-07-86 07-07-86 I
j 07-07-86 07-07-86 07-07-86 07-07-86 07-07-86 07-07-86 07-07-86 07-07-86 j to to to to to to to to
**I 07-14-86 07-16-86 07-16-86 07-16-86 07-16-86 07-14-86 07-16-86 07-14-86
.j 07-14-86 07-16-86. 07-16-86 07-16-86 07-16-86 07-14-86 07-16-86 07-14-86
'1I to to to to to . to to *to
.. , 07-21-86 07-21-86 07-21-86 07-21-86 07-21-86 07-21-86 07-21-86 07-21-86 i
i 07-21-86 07-21-86 07-21-86 07-21-86 07-21-86 07-21-86 07-21-86 07-21-86 1I to to to to to to to to l 07-28-86 07-28-86 07-28-86 07-29-86 07-29-86 07-28-86 07-28-86 07-28-86
.*Ij AUGUST 07-28-86 07-28-86 07-28-86 07-29-86 07-29-86 07-28-86 07-28-86 07-28-86
.. i' to
- to to to to to to to
. *~
08-04-86 08-04-86 08-04-86 08-04-86 08-04-86 08-04-86 08-04-86 08-04-86.
.I 08-04-86 08-04-86 08-04-86 08-04-86 08-04-86 08--04-86 08-04-86 08-04-86
~j_, to to to to to to to to 1
08-11-86 08-11-:86 08-11-86 08-12-86 08-12-86 08-11-86 08-11-86 08-11-86
~ ..t 08-11-86 08-11-86 08-11-~6 08-12-86 08-12-86*'* 08-11-86 08-11-86 .... i
- ' .. *.**1 to to to to to to to
***\
. ...:1 08-19-86 08-19-86 08-19-86 08-19-86 08-19-86 08-19-86 08-18-86
*<1!
*..,j
;,j
;, ',J*
*-** .. ~~. ~~-* *~*- *,~ ..... *~**. ~......**..::.. ..; ;. *.......* *:.' ...
TABLE C-6 (cont'd) 1986 SAMPLING DATES fOR AIR SAMPLES S'H"ATION ID flCOtHH 252. 6Sl 6Dl lODl l6El lfl 2.fZ 3H3 AUGUST 08-19-86 08:..19-86 08-19-86 08-H-86 08-19-86 08-19-86 08-19-86 08-18-86 to to to to to to to to 08-2.6-86 08-26-86 08-26-86 08-26-86 08-26-86 08-26-86 08-26-86 08-2.6-86 08-2.ii-86 08-26-86 08-2.6-86 08-26-86 08-2.6-86 08-26-86. 08-2.6-86 08-2.6-86 Q:o to to to to to to to 09-02-86 09-02-86 09-02-86 09-03-86 09-03-86 09-02-86 09-02-86 09-02.-86 SEPTEMBER 09-02-86 09-()2-86 09-0Z-86 09-03-86 09-03-86 09-02.-86 09-02.-86 . 09-02.-86 to to to to to to to to 09-08-86 09-08-86 09-08-86 0~-08-86 09-08-86 09-08-86 09-08-86 09-08-86 09-08-86 09-08-86 09-08-86 09-08-86 09-08-86 09-08-86 09-08-86 09-08-86 to to to to to to to to 09-16-86 09-16-86 09-16-86 09-16-86 09-16-86 09-16-86 09-16-86 09-1~-86
~
09-16-86 09-16-86 09-16-86 09-16-86 09-16-86 09-16-86 09-16-86 09-16-86 IO!I to to to to to to to to 09-22-86 09-22-86 09-2.2-86 <<19-22-86 09-2.2.-86 09-22-86 09-22.-86 09-2.2.-86 09-22-86 09-22-86 09-22.1-86 09-22-86 09-2.2.-86 09-2.Z-86 09-22.-86 09-22.-86 to to to to to to to to 09-29-86 09-29-86 09-29-86 09-30-86 09-30-86 09-29-86 09-29-86 . 09-2.9-86 OCTOBER 09-29-86 09-29-86 09-2.9-86 09-30-86 09-30-86 09-29-86 09-2.9-86 09-29-86 to to to to to to to to 10-06-86 l0-06-86 10-06-86 i0-06-86 10-06-86 10-06-86 10-06-86 10-06-86 10-06-86 no-06-86 10-06-86 10-06-86 10-06-86 10-06-86 10-06-86 10-06-86 to to to to to to to to 10-14-86 10-14-86 10-14-86 10-16-86 10-16-86 10-14-86 10-14-86 10-14-86 10-14-86 . 10-14-86 10-14-86 10-16-86 10-16-86 10-14-86 . 10-14-86 10-14-86 to .to to to to to lo t'o 10-20-86 10-20-86 10-20-86 !0-20-Si> 10-20-86 A0-20-116 10-20-96 lO-i0-.1i6 Uh?0~86 tO-tlHl6 HH!!l-8!> U!-Z0-86 10-Z0-86 10-20-86 10-Z0-86 10-20-86
!I to to ~Q to to to to to
- ~
l0~2Mti to=-n=s6 H)-U:-@li ll)-2~-86 10-28-86 10-27-86 10-27-86 10-27-86 RG-27-86 Ull-27-86 i0-27-86 10-28-86 10-28-86 10-27-86 10-27-86 10-27-86 to to to to to to to to 11-03-86 U-031-86 11-03-86 H-03-86 11-03'-86 11-03-86 11-03-86 11-03-86
I
.j j
*I
*1 I TABLE C-6 (cont'd) l 1986 SAMPLING DATES FOR AIR SAMPLES J
- j STATION ID
~j I MONTH 252 651 6Dl ~ODl 16El lfl 2F2 3H3 l --1
- 11-03-86 11-03-86 11-03-86 11-03-86 11-03-86 11-03-86 11-03-86 11-03-86 NOVEMBER
- \ to to to to to to to to 11-10-86 11-10-86 11-10-86 11-10-86 11-10-86 11-10-86 11-10-86 11-10-'86
. :*J1
**. 11-10-86 11-10-86 11-~0-86 11-10-86 . 11-10-86 11-:10-86 11-10-86 11-10-86 . *-1 to to to to to to to to *.:1 11-17-86 11-17-86 11-17-86 11-17-86
- 11-17-86 11-17-86 11-17-86 11-17-86 11-17-86 11-17-86 11-17-86 11-17-86 11-17-86 11-17-86 11-17-86 11-17-86 J *' to to to to to to to to
;'i . 11-24-86 11-24-86 11-24-86 11-24-86 11-24-86 11-24-86 11-24-86 11-24-86 11-24-86 11-24-86 11-24-86 11-24-86 11-24-86 11-24-86 11-24-86 11-24-86 Ii to 11-24:..86*
to 12-01-86 to 12-01-86 to 12-02-86 to 12-02-86 to 12-01-86 to 12-01-86 to 12-01-86 I DECEMBER 12-01-86 12-01-86 12-01-86 12-02-86 12-02-86 12-01-86 12-01-86 12-01-86 I
- l. to to to to to to to to 12-08-86. 12-08-86 12-08-86 12-09-86 12-09-86 12-08-86 12-08-86 12-03-86*
1 12-08-86 12-08-86 12-08-86 12-09-86 12-09-86 12-08-86 12-08-86 12-08-86 to to to to to to to to
- 12-16-86 12-16-86 12-16-86 12-16-86 12-16-86 12-16-86 12-15-86 Il 12-16-86 12-16-86 12-16-86 12-16-86 12-Ui-86 12:..16-86 12-16-86 12-16-86 12-16-86
. -~
i to to to to to to to to *
*. :j 12-22-86 12-22-86 12-16-86* 12-22-86 12-22-86 12-22-86 12-22-86 12-22-86
"{ 12-22-86 12-22-86 12-22-86 12-22-86 12-22-86 12-22-86 12-22-86 12-22-86 I to to to to to to to to l 12-29-86 12-29-86 12-29-86 12-30-86 lZ-30-86 12-29-86 12-29-86 12-29-86
*Reduced sampling period due to instrument malfunction.
** Start date was delayed by one day due to instrument malfunction at time of startup.
This required replacement of the air sampler.
. -~j I
- 1986 CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMITTERS, AND TRITIUM IN PRECIPITATION TABLE C-6 STATION ID: SA-RWA-2F2 Results in Units of pCi/L +/- 2 sigma COLLECTION PERIOD ALPHA BETA TRI TI OM 12-31-85 to 01-27-86 <l. 6 <l.6 <140 01-27-86 to 02-25-86 <1.5 1.9+/-1.2 <130 02-25-86 to 03-31-86 <l. 6 4.4+/-1.4 <140 03-31-86 to 04-28-86 <0.3 3.7+/-0.8 <140 04-28-86 to 06-03~86 <0.3 lStl <140 06~03-86 to 07-01-86 1.J+/-Oo7 8.4:H.O <140 07-01=86 to 01~29*-86 <l.l 3.8:!::0.8 <140 07~29-86 to 09-03-86 1. 2:t:l.l 12+/-1 <130 09-03-86 to 09-30-86 0.9+/-0.5 3.8+/-0.8 <140 09-30-86 to 10-27-86 <l. 2 2.2+/-0.6 <140 10-27-86 to 12-01-86 0.6+/-0.6 3.5+/-0.7 <140
... 12-01-86 to 12-29~86 <l. 7 l.9:!::0.6 <130
.' . ~
.. *' **t .i AVERAGE 5.2+/-8.6
*.**I w * ** '
.. . .:.. ~
' ._. ;: *.. *' ~
.. : . -~ I
; * 'i
- .'. ;;.::! 77
.. * -~ '
. f
.* !-----~-~---
.. **- .. -*~ ----;--.. --...-.,--;-*............-, o*-~--- ...... --.----.-------*-****~**-***--..--,*--.**----*** *-*-------- .. *----**- ---*- **-;- ....... - ---.,.- - --*-- --- .. - *-**.------- - . .. I
TABLE-C-7.
- 1986 CONCENTRATIONS OF GAMMA EMITTERS* IN PRECIPITATION
~
STATION ID: SA-RWA-2F2 Results.in Units of pCi/L +/- 2 sigma. COLLECTION PERIOD Be-7 K-40 I-131 cs-137 Ra-226 Th-232 12-31-85 to 01.-27-860 Ol-27-86 to 02-25-86 35+/-12 <39 <2.4 <2.4 7.0+/-3.0 <7.2 02-25-86 to 03-31-86 71+/-21 <57 <4.7 " <2.9 <6.7 <12 03-31-86 to 04-28-86 64+/-15 <32 <2.6 <2.0 <4.6 <8.0 04-28-86 to 06-03-86 41+/-23 <81 7.4+/-3.5 4.8+/-3.0 <13 <21 06-03-86 to 07-01-86 54+/-13 <40 <3.4 <3.2 <6.4" <11 07-01-86 to 07-29-86 52+/-14 <42 <4.8 <3.2 <6.4: <ll 07-29-86 to 09-03-86 42+/-10 <25" <l.6 <0.8 <4.2 7.5+/-4.l 09-03-86 to 09-30-86 35+/-14 59+/-25 <3.8 <3.7 <7.7 ~14 09-30-86 to 10-27-86 36+/-12 <40 <3.4 <2.6 5.1+/-2.4 <ll 10-27-86 to 12-01-86 43+/-12 <41 <l.5 <2.l 4.8+/-2.7 <7.6 12-01-86 to 12-29-86 42+/-13 <29 <4.8 <2.0 <4.8 <7.4 AVERAGE 47+/-24
- All other gamma emitters searched for were <LLDJ typical LLDs are given in Tal:>le C-33.
I **Not analyzed.due to insufficient pre~ipitation during sampling period. " i 78
-~~~ ___.._ . _ .
. '. ~ . . ....... .
- TABLE c~e 1986 DIRECT RADIATION MEASUREMENTS - QUARTERLY TLD :RESUL'.l'.S .
.Rasul.ts in mrad/standard month*
(.Resul.ts by Teledyne Isotopes) JANUARY APRIL JULY OCTOBER STATION ID to to to to AVERAGE MARCH JUNE SEPTEMBER DECEMBER SA-IOM-2S2 5.3+/-0.3 4.4+/-0.2 5.2.:1:0.3 4.7+/-0.6 4.9+/-0.8 SA-IOM~5Sl S.l:!:0.2 4.0+/-0.3 4.9:t0.3 4.2:t:0.3 4.6:tl..l SA-IOM~6S2 5.3:!:0.3 4.3+/-0.2 5.4:t:0.2 4.6:!:0.3 4.9:t.l.l SA-IDM-7Sl 6.6+/-0.7 5.6+/-0.S 6.2+/-0.4 5.6:t:0.5 6.0+/-1..0 SA-IOM-lOSl s.a+/-o.5 5.0:t0.3 4.8:t0.2 5.1+/-0.3 5.2+/-0.9 SA-IOM llSl00 5.0+/-0.2 S.2:t:0.3 5.2:t0.3 4.7+/-0.3 5.o:to.s SA-IOM 402 00 5.0:1:0.2 4.9+/-0.4 6.7:t:l.8 5.1+/-0.5 5 .6:t;l..6 SA-IDM-501 5.5+/-0.2 4.6:1:0.l 5 .4::!:0.3 4.6+/-0.3 5.0:l:l..O SA-IOM-1001 5.4+/-0.4 5.0+/-0.3 5.7+/-0.5 4.8+/-0.4 5.2:!;0.8 SA-IDM-1401 5.4+/-0.6 4.5:1:0.2 5.5+/-0.3 4.9:1:0. 7 5.1:.1:0.9 SA-IDM-2El 5.6:.1:0~5 4.2:1:0.5 5.5+/-0.4 4.7+/-0.5 S.O:.l:l.3 SA-IOM-3El 5 .2:.1:0 .4 4.4+/-0.2 5.3+/-0.3 4.5+/-0.5 4~8:.1:0 .9 SA-IDM-9El 6.3+/-0.8 5.4+/-0.3 6.2:.1:0.5 5.7+/-0.9 5.9+/-0.8 SA-IDM-11E2 5.9+/-0.6 5.2:1:0.7 6.3+/-0.5 5.5+/-0.7 5.7+/-1.0 SA- IDM-l2El 5.7+/-0.5 4.8+/-0.3 6.0+/-0.4 5.4+/-0.8 5.5:t:J..O SA-IDM-13El 4.9+/-0.l 4.2+/-0.2 5.0:1:0.3 4. 3:t:O .4 4.6+/-0.8 SA-IDM-16El 5.5+/-0.2 4.8+/-0.5 5.6+/-0.3 5.0+/-0.5 5.2:!:0.8 SA-IOM-lFl 5.4:.l:0.5 4.3:1:0.4 5 .5:.1:0 .4 5~0+/-0.5 5. O:.l:l..l SA-IOM 2F2 00 4.5:1:0.7 3.6+/-0.3 4.4:1:0.3 3.7+/-0.3 4.0+/-0.9 SA-IDM-2F5 5.4+/-0.l 4.6:1:0.2 5.4+/-0.4 4.8+/-0.5 s.o+/-o.a SA-IOM-2F6 5.1+/-0.2 4.4+/-0.4 5.4:1::0.4 4.8:t0.2 4.9+/-0.8 SA-IOM-3F2 5.Sil.2 4.2:1:0.3 4.9:!:0.2 4.1:1:0.3 4. 7+/-1..2 SA-IOM-3F3 5.0+/-0.2 4.3:t:0.2 s.o:to.2 4.3:t:0.3 4.6:1:0o7 SA-IOM-5Fl 5.2:t:0.7 4.3:!:0.5 5.l+/-0.3 4.6:!:0.S 4.8:1:008 SA-IDM-6Fl 4.7+/-0.3 3 .6:1:0.,l 4.6:1:0.2 3.8:!:0.3 4.2+/-1.l SA-IOM-7F2 4.6:t0o2 3.4:1:0o2 4.3:1:0.2 3.5:1:0.1 4.0:Uo2 SA-IOM-10F2 5.7:1:0.5 5.1+/-0.4 5.9:1:0.3 5.l.+/-0.5 5.4:1:0.8 SA-IOM-llFl 5.0:1:0.5 5.2:1:0.4 5.8:1:0.5 5.3:!:0.6 5.5+/-0.6 SA-IDM-12Fl 5.7:!:0.3 4.7+/-0.3 5.7+/-0.l 4o9:!:0.4 5.2:!:1.0 SA-IDM-13F2 5.3+/-0.4 4.6+/-0.4 5.4:1:0.3 4.8+/-0.4 5.0:1:0.a SA-IDM-13F3 5.7+/-0.4 4.8+/-0.3 5.7:1:0.4 5.0:!:0.5 5.3:!:0.9 SA-IOM-13F4 5.7:1:0.2 4e6:1:0.S 5.6:1:0.3 4.9:1:0.5 5.2:1::J..l SA-IOM-14F2 5.3:1:0.l 4o5:1:0.4 5.5+/-0.4 5.1:1:0.1 S.l:!:0.9 SA-IOM-l5F3 6.0:1:0.5 .5.2:1:0.2 6.3:1:0.4 5.4:1:0.4 5~7:1:1.0 SA-IDM-16F2 5.2:1:0.1 4.3:1:0.2 5.4:1:0.3 4.S:t:0.4 4.9:!:1.0 SA-IOM-lG3 ~C~ 5.8:!:0.4 5.5:1:0.8 6.4:1:0.4 5.7:1:0.4 5.8:!:0.8 SA-IOM-3GJ. C 5.8:!:0.4 4.9:1:0.3 5.8:1:0.3 5.1:1:0.6 5.4:!:0.9 SA-IDM-lOGl ~ C~ 6.l:!:0.6 s.1:1:0.s 5.9:t:O.S 5.3:t0.5 5.6:1:1.0 SA-IDM-16Gl C 6.l.+/-0.6 S.3:1:0.5 6.3:1:0.6 S.8+/-0.7 5.9+/-0.9 SA-IOM~3Hl ~C~ 6.0+/-0.5 5.0+/-0.3 5.0+/-0.2 5o2:!:0.5 S.5:t:l.O SA-IDM-3H3 C 5.9:!:0.S s.o:t:o.2 5.9:1:0.3 5.2:1:0.s 5.5:1:0.9 AVERAGE 5.s:ta.9 4.6il.O 5.5:!:1.l 4.9:!:1.l
- . ~-
Grand Average 5.l:!::l.3 ~ ..
~ The standard month (C) Control station
= 30.4 da.ys *
- 79
\
-----***,-- --.---*-.*--o-r,~~-~--*-~-;--*-.::;*-::'--~ *~~7*-~~":-~*-- -.--:.,.-**-*-.*- - . - .* °'**-~,-: *-~** ..* -- **- *-* - -- - . *-** ...... -- .. ***.--------~---*-*--**,.--... -
' ..I -* ---*-*-**-*~--- ---- .... ~ .
TABLE C-9 1986 DIRECT RADIATION MEASUREMENTS - MONTHLY TLO RESULTS Results in mrad/standard month* (Results by Teledyne Isotopes) STATION ID ' JANUARY FEBRUARY MARCH APRIL MAY JUNE SA-IDM-2S2 5.3+/-0.3 6.6+/-0.l 5.2+/-0.4 6.6+/-1.2 6.7+/-0.8 5.6+/-0.5 SA-IDM-5Sl 5.2+/-0.4 5.9+/-0.l 4.5+/-0.2 6.2+/-0.7 5.9+/-0.6 5.0+/-1.2 SA-IDM-6S2 5.6+/-0.4 6.4+/-0.4 4.9+/-0.5 6.8+/-0.5 6.3+/-0.4 5.9+/-0.5 SA-IDM-7Sl 6.5+/-0.6 7.5+/-0.7 6.0+/-0.7 7.7+/-0.6 7.3+/-0.6 7.0+/-0.9 SA-IDM-lOSl 5.9+/-0.6 6.8+/-0.2 5.4+/-0.5 7.4+/-0.7 6.9+/-0.6 6.4+/-0.7 SA-IDM-llSl 5.2+/-0.4 6.1+/-0.3 4.7+/-0.2 6.9+/-0.4 7. 7+/-1.0 6.0+/-0.9 SA-IDM-501 5.5+/-0.5 6.1+/-0.l 5.0+/-0.5 6.6+/-0.8 6.1+/-0.4 5.8+/-0.6 SA- IDM-1001 5.7+/-0.5 6.6+/-0.3 5.3+/-0.4 7.2+/-0.6 6.9+/-0.6 6.7+/-0.7 SA-IDM-1401 5.6+/-0.4 6.6+/-0.4 5. 5+/-1. 3 6.9+/-0.5 6.9+/-0.7 6.2+/-0.7 SA-IDM-2El 5.5+/-0.3 6.2+/-0.4 4.9+/-0.5 6.6+/-0.6 6 .7+/-1.0 5.6+/-0.6 SA-IDM-3El 5.5+/-0.5 6.1+/-0.3 4.7+/-0.1 6.5+/-0.5 6.4+/-0.6 5.2+/-0.8
.' 6.2+/-0.2 4.7+/-0.3 6.5+/-0.4 5.8+/-0.7 5.9+/-0.7 SA-IDM-13El 5.3+/-0.8 Q) SA-IDM-16El 5.6+/-0.6 6.7+/-0.6 5.0+/-0.2 7.0+/-0.4 6.8+/-0.7 6.3+/-0.9 0 SA-IDM-lFl 5.7+/-0.3 6.4+/-0.6 5.1+/-0.3 6.9+/-0.6 6.5+/-0.6 6.3+/-0.8 SA-IDM-2F2 4.8+/-0.4 5.8+/-0.3 4.1+/-0.2 6.0+/-0.5 5.4+/-0.3 5.0+/-0.4 SA-IDM-2F6 5.9+/-0.6 6.6+/-0.5 5.0+/-0.6 6.8+/-0.6 5.9+/-0.5 6.0+/-0.9 SA-IDM-5Fl 5.5+/-0.6 5.9+/-0.3 4.6+/-0.3 6.5+/-0.5 6.1+/-0.4 5.6+/-0.7 SA-IDM-6Fl 5.0+/-0.3 5.7+/-0.1 (1) 5 .* 9+/-0.4 5.4+/-0.3 5.0+/-0.3 SA-IDM-7F2 4.3+/-0.3 5.4+/-0.3 3.8+/-0.3 5.5+/-0.7 5.1+/-0.4 4.5+/-0.7 SA- IDM- llFl 5.8+/-0.4 7 .0+/-1.0 5.5+/-0.5 7.4+/-0.6 7.1+/-0.9 6.5+/-0.6 SA-IDM-13F4 5.8+/-0.6 6.9+/-0.7 4.9+/-0.3 7.0+/-0.5 6.6+/-0.6 6.2+/-0.4 SA-IDM-3Gl (C) 5.5+/-0.2 6.3+/-1.0 5.3+/-0.4 7.4+/-1.5 6.8+/-0.8 6.1+/-0.4 SA-IDM-381 (C) 5.9+/-0.2 6.8+/-0.3 5.3+/-0.4 7.2+/-0.4 6.7+/-0.7 6.3+/-0.8 SA-IDM-383 (C) 6.3+/-0.6 7.4+/-0.4 5.6+/-0.3 7.6+/-0.6 7.3+/-0.6 6.6+/-1.0 AVERAGE 5.5+/-0.9 6.4+/-1.0 5. 0+/-1.0 6.8+/-1.1 6.5+/-1. 3 5.9+/-1. 2 I:
__-:_ **~--~L-."~ . :*,_ . . -. . ~e:.:. -* - ~:':*. I . . - .
"p , **
~ '*. '
i 1 l TABLE C-9 (COBlt 9 d)
- .*1 1986 DIRECT RADIATION MEASUREMENTS - MONTHLY TLD RESULTS l Results in mrad/standard month*
(Results by Teledyne Isotopes) STATION ID JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER AVERAGE SA-IDH-282 -. 5.9+/-0.3 5.7+/-0.5 5.3+/-0.5 5.4+/-0.3 4.9+/-0.4 '7.1+/-0. 7 5.8+/-1.4
*1 SA-IDH-5Sl 5.5+/-0.4 5.9+/-0.7 4.9+/-0.7 5.3+/-0.3 4.6+/-0.3 6.2+/-0.5 5.4+/-1.2 *I SA-IDH-6S2 6~1+/-0.5 6.1+/-0.4 5.5+/-0~4 5.7+/-0.4 4.9+/-0.5 6.6+/-0.6 5.9+/-L2 SA-IDM-7Sl 7.0+/-0.8 6.9+/-0.4 6.6+/-0.8 6.5+/-0.9 5.9+/-0.7 7.7+/-1.0 6.9+/-1.2, 1l SA- IDH-lOSl 6.5+/-0.6 6.5+/-0.4 5.7+/-0.5 6.4+/-0.6 5.5+/-0.3 7.6+/-0.9 6 .4+/-1.4 I I
SA- IDM-llSl 6.4+/-0.6 6.1+/-0.5 5.0+/-0.2 5.4+/-0.3 5.0+/-0.l 6.9+/-0.9 5.9+/-1.8 i' SA-IDM-5Dl 6.2+/-0.5 6.0+/-0.7 5.5+/-0.5 5.5+/-0.5 4.8+/-0.4 6.5+/-0.6 5.8+/-1.l SA- IDH-lODl 5. 7+/-1.l 6.3+/-0.5 5.8+/-0.4 6.1+/-0.5 5.3+/-0.4 6.9+/-0.6 6.2+/-1.3 SA- IDH-1401 6.8+/-0.l 6.2+/-0.3 5.7+/-0.5 6.0+/-0.8 5.2+/-0.4 6.9+/-0.6 6.2+/-1.2 SA-IDM-2El 6.0+/-0.7 6.0+/-0.3 5.5+/-0.3 5.6+/-0.5 4.9+/-0.6 6.5+/-0.9 5.8+/-1.2 SA-IDH-3El 6.0+/-0.4 5.9+/-0.5 5.1+/-0.3 5.5+/-0.3 4:8+/-0.4 6.3+/-0.5 5.?+/-1.2 SA-IDM-13El 5.9+/-0.4 5.9+/-0.4 5.2+/-0.6 5.7+/-0.4 4.8+/-0.5 6.6+/-0.6 5. 7+/-1.2
~ SA-IDM-16El 6.4+/-0.5 6.1+/-0.4 5.8+/-0.6 5.9+/-0.5 5.1+/-0.4 7.1+/-0.7 6.1+/-1.4 l}-<l
_SA- IDM-lFl 6.3+/-0.5 6.2+/-0.3 5.5+/-0.3 5.9+/-0.5 5.1+/-0.5 6.7+/-0.4 6.0+/-1.2 SA-IDM-2F2 ~-4+/-0.4 5.3+/-0.2 4.7+/-0.2 4.8+/-0.2 4.2+/-0.2 5.9+/-0.3 5.1+/-1.2 SA-IDH-2F6 6.0+/-0.6 6.1+/-0.3 5.6+/-0.3 5.6+/-0.3 5.0+/-0.5 1.-uo.6 6.o'+/-L3
'! SA-IDM-5Fl 6.1+/-0.3 5.9+/-0.2 5.5+/-0.3 5.6+/-0.4 5.0+/-0.3 6.4+/-0.6 5. 7+/-1.l SA-IDM-6Fl 5.6+/-0.3 5.3+/-0.2 4.8+/-0.3 5.0+/-0.3 4.3+/-0.2 6.1+/-0.5 5. 3+/-1.0 SA-IDM-7F2 5.0+/-0.3 4.9+/-0.l 4.2+/-0.2 4.6+/-0.3 3.8+/-0.2 5.5+/-0.6 4.7+/-1.2 SA-IDM-llFl 6. 8+/-1. 0 6.7+/-0.4 6.2+/-0.8 6.2+/-0.5 5.6+/-0.5 7.2+/-0.8 6-5+/-1. 3 SA- IDM-13F4 6.5+/-0.4 6.1+/-0.2 5.7+/-0.4 6.0+/-0.5 5.3+/-0.4 6.9+/-0.5 6.2+/-1. 3 SA-IDM-3Gl (C) 6.7+/-0.5 6.6+/-0.7 6.1+/-0.4 6.3+/-1. 3 5.1+/-0.3 7.2+/-0.3 6. 3+/-1.4 SA-IDM-3Hl (C} 6.7+/-0.9 6.7+/-0.4 5.6+/-0.6 6.0+/-0.5 5.4+/-0.2 7_.2+/-0.5 6.3+/-1.3 '
SA-IPM-383 (C) 6.9+/-0.5 6.9+/-0.4 6.3+/-0.8 6.5+/-0.3 5.9+/-0.4 7.4+/-0.6 6. 7+/-L 3 AVERAGE 6.2+/-1.0 f).1+/-1.0 5.5:1:1.l 5.7+/-1.0 5.0+/-1.0 6.8+/-1.l Grand Av~rng~ ~rQ!l.6 Ill The standard month * .3o.4 daye.
<<c> Control station U) TLD missing from field Jocat!on.
.. :~ *_ :*. :.:- - ..*..... .:... -**~ ,_ ~. ..
*'\ . - -- . J .
TABLE C-11 1986 CONCENTRATI0NS OF STRONTIUM-89* ANrr STRONTIUM-90 IN' MILK** Results in Units of pCi/L +/- 2 sigma STATION ID COLLECTION PERIOD Sr-89 sr-90 SA=MLK;,.,13E3 07/06-07/86 <0.9 1.9+/-0.3 SA~MLK~2F4 07/06~07/86 <0.8 l.St0.3 SA~MLK-2F7 08/03-04/86 <l.5 2.4+/-0.6 SA-MLK-5F2 07/05-07/86 <l.l 3.0+/-0.4 SA-MLK-llF3 07/07-08/86 <0.8 1.7+/-0.3 SA-MLK-l4Fl 07/06-07/86 <0.8 1.2+/-0.3 SA~MLR~3Gl 07/07=08/86 <0.9 2.7+/-0.3 {Control) AVERAGE :ic1:1::1.2
- sr-89 results are corrected for decay to midpoint of collection period.
** Management audit analyses, not required by Technical Specifications or by specific commitments to local officials.
- .-~- '*
-~ i
*1
~ *.. .:. ~ *1 i
.. ':.::*::':'.l 83
...i
. '~
___ .,.. __ . __, ___ ., _____ ~- ---- ... ~ ------*-* --.-...-;--v----*---------*** -*-- -.-,.......... -... -.**-*.---*-~:---:--*-**--**7--*<-*:-*--*-..---*-* ,- ----- --*-*-*--*.......
TABLE C-lZ 1986 CONCENTRATIONS OF GAMMA EMITTERS* IN. MILK' Results in Units of pCi/L :1: Z sigma .* STATION ID** NUCLIDE JANUARY FEBRUARY MARCH MONTHLY MONTHLY MONTHLY SA-MLK-13E3 Na-ZZ <3.4 <3.9 <4.0 K-40 1400:1:75 1400:1:79 1400:1:98 Mn-54 <Z.5 <3.4 <4.0 Zn-65 <1.Z <1.7 <10 I-131 <3.0 <Z.5 <4.7 Cs-137 <Z.7 <Z.8 <4.9 Ra-ZZ6 <5.9 <1.Z <9.4 SA-MLK-ZF4 (1) Na-ZZ <3.7 <5.6 <3.4 K-40 1400+/-74 . 1400+/-98 1400:1:76 Mn-54 <Z.5 <4.1 <Z.3 Zn-65 <5.9 <6.3 <6.9 I-131 <3.0 <3.8 <3.0 Cs-137 <Z.9 <4.6 <Z.7 Ra-ZZ6 <5.5 <7.4 <5.9 SA-MLK-ZF7 (2) Na-ZZ K-40 Mn-54 Zn-65 I-131 Cs-137 Ra-ZZ6 SA-MLK-5FZ Na-2Z <3.5 <2.Z K-40 1300+/-72 1300+/-81 1300:1:82
'Mn-64 <2.5 <3.3 <Z.7 Zn-66 <5.9 <9.1 <1.8 I-131 <3.Z <3.8 <0.6 Cs-137 <2.9 <2.9 <3.6 Ra-Z26 <6.2 <1.7 <5.9 SA-MLK-11F3 Na-22 <4.6 <4.5 <3.6 K-40 1300:1:90 1300:!:82 1300+/-74 Mn-54 <3.2 <Z.O <Z.3 Zn-65 <8.7 <7.3 <5.9 I-131- <3.3 <0.6 <3.3 Cs-137 <3.3 <3.7 <Z.9 Ra-226 <6.6 <6.8 <6.Z SA-MLK-14Fl Na-22 <Z.4 <3.6 <3.5 K-40 1300+/-81 1400+/-77 1400:t77 Mn-54 <3.8 <2.6 <3.Z Zn-66 <9.1 <6.9 <1.8 I-131 <4.7 <3.l <4.7 Cs-137 <3.9 <Z.6 <3.7 Ra-Z26 <6.1 <S.6 <7.9 SA-MLK-361 Na-Z2 <4.Z <6.Z* <4.9 (Control) K-40 1300+/-92 1300:t9Z 1400:1:92 Mn-64 <3.Z <3.S <3.Z Zn-65 <8.7 <8.7 <8.Z .;.* I-131 <3.1 <3.4 <3.6
- ,:*:j Cs-137 <3.3 <3.5 <3.3 0 Ra-226 <7.0 <7.0 <6.6
.-( AVERAGE K-40 1300+/-100 1400+/-110 1400:1:100 84
- ---- -----------.--,- -- *-....,--..,*-~.7*-:-*-,-~----------~.--:--**-*-****-*-**-*-*r'.*~---~-~~----~-.,,.--..v.-,-~-*- ......-*-*-*-------- *----;--*.--,~---*: * -*---- * ** *- *--~-***-* * * '* *.
TABLE C-12 (cont'd.) 1986 CONCENTRATIONS OF GAMMA EMITTERS* IN MILK
- Results in Units of pCIJL ~ 2 sigm~
STATION ID"'"' NUCLIDE APRIL MAY JUNE SEMI-MONTHLY SEMI-MONTHLY SEJfI-MONTHL Y SA-MLK-l3E3 Na-ZZ <4.9 <4.5 <4.6 <4.Z <4.9 <4. 5 . K-40 1400:100 1400+/-83 1300+/-76 1300+/-77 1300.:1:92 1400+/-79 Mn-54 <4.9 z. 9+/-1. 7 <2.8 <1.8 <3.IJ <1.4 Zn-65 <8.6 <7.4 <9.7 <7.3 <9.5 <8.3 I-131 <0.8 '<1. 9 <3. 9 13+/-Z 3.S:tZ.3 <4.4 Cs-137 <4.S <3.6 <3.6 <3.4 <l.6 <4.Z Ra-ZZ6 <8.6 <7.0 <7.4 <S.O <7.0 <6.Z. SA-MLK-Zf4 Na-ZZ <6.Z <4.4 <4.8 <4.6 <3.1 <4.6 K-40 1400:1:99 1400+/-77 1400:1:99 1400+/-92 1400+/-77 1400:1:93 Mn-54 <3.8 <LB <4.4 <3.5 <Z.5 <3.l
. Zn-65 <11 <6.9 <8.8 <8.7 <6..6 <8;z I-131. <Z.3 <3.4 <3.5 3Z.t3 <l.5 <4.0 Cs-137 <4.Z <4.2 <3.0 <3.8 ~.z. g <3.6 Ra-2Z6 <9.Z <8.3 <7.9 <7.0 <5.9 <6.Z SA-MLK-ZF7 Na-2Z K-40 Mn-54 Zn-65 I-131 Cs-137 Ra-Z26 SA-MLK-6FZ Na-ZZ <2.8 <4.5 <4.0 4.6:1:2.3 d .* 6 <3.6 K-40 1ZOO:t74 1300:1:96 1300+/-74 13Cl0:1:76 1200:s:94 1300:t7Z Mn-54 <2.9 <3.8 <Z.9 <3.S <4!.Q <2.3 Zn-65 <7.D <U <6.4 <6.2 <l*.a <6.7 I-131 * <3.D <3.7 <3.Z 49:!:4 7.M.T <3.4 C:s-137 <3.0 <4.7 <3.7 <3.6 5.W.4* 3.9:1.6 Ra-2Z6 <7.6 <6.6 <7.7 <7.7 <3* .0i <6.Z SA-MLK- l1F3 Na-2Z <1.D <4.9 <4.8 <4.1 <t.3- <3. l K-40 1400+/-77 1400:t9Z 1400:t97 1300+/-83 1ZOO:t:75* 1300:1:82 Mn-54 <Z.3 <3.1 <4.6 <1. 9 <l.3 <3.l Zn-65 <9.1 <8.7 <9.2 11:1:6 <3,7 <8.l I-131 <3.9 <3.7 <3.5 24+/-3 <4.Z <3.0 Cs-137 <2.3 <3.Z <4.3 <3.8 <l.8, <3.3 Ra-ZZ6 <6.3 <7.4 <7.8 <6.7 <1.L <7.l SA-MLK-14F1 Na-2Z <3.8 <5.1 <1.2 <1.6 <l.7 <4.9 K-40 1300+/-94 1300:t96 1300+/-83 1300:1:95 140G.t76- 1:400:t97 Mn-54 <1.1 <3.6 <2.8 <3.8 <Z.l'.t <3.9 Zn-611 <6.7 <5.0 <4,7 <5.4 <1.Z (, lCI I-131. <4.4 <3.2 <2,8 26:!:4 4. 7~:1:.!Jl <4.9
.. Cs-137 <Z.G <3.1 <3.8 . <4.1 3.hl.T <4.l
- ..... Ra-226 <8.1 <8.8 7.3:!:4.3 <7,9 4.4:t.Z. 8< <.8.2
,',"> ::! SA-MLK-3Gl Na-ZZ <4.8 <3.5 <4.8 <5.5 <4.7: <4.8 (Control) K-40 140Cl:!:93 1400:1:74 140Cl:1:82 14C!O:t97 1300:!:&1. ll.4ll0:1:93
- Mn-54 <3.5 <2.6 <2.9 <3.l <C.Z* <3.7
-. *:; Zn-65 <8.i <6.7 <4.8 <11 <8~&. <.i,4
. . ' :~ X-131. <4,1 <3.4 <4.0 65:t5 7.4t-.L& ,3,3
~
Cs-137 <-3.8 <Z.9 <Z.7 <4.2 <4.l ,3,9
,; Ra-ZZ.6 <7.7 !i.!i:tZ.9 <7,Q <!LB di.i t6.6
.. AVERAGE IC-40 1400:1:170 1400:d00 1400:1:110 1.300:1:100 1:.100:18@ Jl4".CtO:i:100
", .-~
.: .~: .;' ;' ..
i { '-.;.J.";1
.. .*' .~";
- -... :* rt .
-~*--,*--~..-.,-...-.~-~:---,---*-*--* **-*-**** ---:*r--~- * --**--:"'~*--*-.---_--;***-:-.- ----..*--*- -;-**-- ..-:-* -.- -.-** ----.:******* ,": ***~ -. -**- *.** ,. ** .. --* *
~ TABLE C-lZ (Cont'd;) 1986 CONCENTRATIONS* OF GAMMA .EMITTERS* IN. MILK Results in Units of*pCi/L :1: Z sigma STATION ID** NUCLIDE JULY AUGUST SEPTEMBER SEMI-MONTHLY SEMI-MONTHLY SEMI-MONTHLY SA-MLK-13E3 Na-ZZ <3.5 <5.0 <4.9 <3.0 <Z.1 <3.3 K-40 1400:1:75 1500+/-97 1400+/-96 1400:1:85 1400:1:78 1400:1:96 Mn-54 <Z.6 <3.8 <Z.8 <0.8 <0.7 <4.4 Zn-65 <5.4 <11 <8.0 <Z.1 <3.6 <9.7 I-131 <3.6 <3.3 <4.0 <Z.9 <3.1 <Z.8 Cs-137 <Z.7 <4.5 <3.9 <4.0 . 3. 7+/-Z.O <4.0 Ra-226 <5.9 <8.4 <6.6 <6.0 <8.8 <8.4 SA-MLK-ZF4 Na-ZZ <4.8 <3.7 <Z.9 <5.4 K-40 1300:1:92 1400+/-75. 1400+/-96 1500:1:96 Mn-54 <3.0 <Z.5 <4.1 <3.0 Zn-65 <9.5 <5.9 <9.0 <9.7 I-131 <4.0 <3.4 <0.7 <3.8 Cs-137 <3.8 <3.0 <4.5 <3.3 Ra-2Z6 <7.0 <5.5 <8.0 <7.0 SA-MLK-ZF7 Na-ZZ <3.7 <3.5 <4.5 <Z.6 K-40 1400:1:74 1300+/-73 1400+/-78 1400:!:78 Mn-54 <Z.6 <Z.5 <Z.6 <4.3 Zn-65 <6.7 <6.9 <8.1 <3.5 I-131 Cs-137 Ra-2Z6 - --
<3.Z
<3.Z 5.l:t:Z.8
<3.Z
<Z.7
<5.5
<3.Z
<3.2
<8.1
<Z.3
<3.7
*<8.7.
SA-MLK-5F2 Na-22 <3.9 <4.9 <6.4 <3.Z <1.6 <3.9 K-40 1300:1:77 1300:t:92 .1300:1:95 .1300:1:72. 1ZOO:t91 1ZOO:t7 Mn-54 <0.7 <3.1 <3.9 <Z.Z <2.0 <LG Zn-65 <5.5 <8.2 <7.3 <6.4 <lZ <Z.l I-131 <4.1 <3.4 <4.3 <3.Z <Z.3 <4.6 Cs-137 <4.7 <3.9 <3.8 <Z.9 <5.1 <3.8 Ra-226 <7.1 <7.0 <7.Z <5.9 <7.3 <7.7 SA-MLK- llF 3 Na-22 <6.3 <3.Z <6.0 <5.0 <5.9 <4.4 K-40 1500:1:98 1300:1:78 .1400+/-98 1500+/-100 1300:1:96 1300:1:93 Mn-54 <3.6 <3.1 <Z.9 <3.Z <3.3 <3.1 Zn-65 <14 <9.5 <4.7 <9.0 <8.Z <8.5 I-131 <4.6 <0.6 <4.5 <4.7 <0.8 <3.8 cs..:137 <4.8 <4.0 <3.0 <3.7 <4.4 <3.6 Ra-226 <6.8 <7.3 <8.3 <8.Z <8.Z <6.6 SA-MLK-14Fl Na-22 <5.5 <4.8 <4.1 <3.9 <3.5 <3.3 IC-40 1400:1:80 1400:1:97 1400:1:77 1400+/-78 1400+/-75 1300:1:82 Mn-54 <3.3* <1.8 <3.1 <1.7 <Z.3 <3.1 Zn-65 <9.4 <11 <1.8 <9.3 <6.4 <8.8 I-131 <Z.l <3.7 <3.7 <4.4 <3.Z <3.6 Cs-137 <3.6 <4.0 <3.7 <Z.9 <2.7 <3.7 Ra.:226 <8.0 <7.5 <6.3 <8. 7 ' <6.Z <6.9. SA-MLK-3Gl Na-22 <3.9* <Z.9 <4.6 <4.5 <3.9 (3) (Control) IC-40 1300:1:73 1400:1:84 1300+/-83 1100:1:86 1300:1:92
**' Mn-54 <Z.5 <2.4 <Z.Z <3.2 <3.5
~
Zn-65 <6.9 <8.6 <6.3 <7.7 <9.0 I-131 <3.0 <3.7 <3.3 <3.3 <3.7 Cs-137 <Z.9 <3.Z <3.7 <3.8 <3.5
* *,! Ra-226 <5.5 <7.5 <5.8 <6.6 <7.0 AVERAGE K-40 1400:1:160 1400:1:150 1400:1:100 1400:t:Z80 1300:1:160 1300:!:170
.~ 86
.---- ----*-- - . -;---:- .. *~---,--*** -----*- *- *- *--, -, __ --*-- -*- -**
... 'J TABLE C-lZ (cont'd.)
1986 CONCENTRATIONS OF GAMMA EMITTERS.* .IN MlLK'
- Results in Units of pCi/L % Z sigma
*.r*' ;_ ,**
. . . --**----~>-'; ...*. ~ *. :. **.. ** -.1 ** ~- ;. ** ** , * .' * * . *. * ** * **.*****
. TABLE C-13
- 1986 SAMPLING DATES FOR MILK SAMPLES STATION ID MONTH 13E3 ZF4 6FZ llf3 14Fl 361 JANUARY 01-06-86 01-06-86 01-04-86 01-06-86 01-06-86 01-06-86 to
- to to to to to 01-07-~6 01-06-86 01-06-86 01-07-86 01-06-86 01-07*-86 FEBRUARY OZ-03-86 OZ-OZ-86 OZ-01-86 OZ-03-86 OZ-OZ-86 OZ-03-86 to to to to to to .
OZ-04-8~
- OZ-03-86 OZ-03-86 OZ-04-86 OZ-03-86 OZ-04-86 MARCH 03-03-86 03-03-86 03-01-86 03-03-86 03-0Z-86 03-03-86 to to to to to . to .
03-04-86 03-04-86 03-03-86 03-04-86 03-03-86 03-04-86 APRIL 04..,07-86 04-07-86 04-06-86 04-06-86 04-07-86 04-06-8"6 to to to to to to 04-08-86 04-08-86 04-07-86 04-07-86 0*4-08-86 04-07-86 O>
<<>> 04-ZZ-86 04-Zl-86 04-Z0-86 04-Z0-86 04-Zl-86 04..:zo~a6 to to to to to to 04-ZZ-86 04-ZZ-86 04-Zl-86 04-Zl-86 04-ZZ-86 04-Zl-86 MAY 06-06-86 06-06-86 06-04-86 06-04-86 06-06-86 06-04-86 to to to to to to 06-06-86 05-06-86 06-05-86 0~-05-86 06-06-86 05-06-86 06-19-86 06-19.:.86 06-18-86 05-19-86 05-19-86 05-18-86 to to to to to to 06-Z0-86 06-Z0-86 06-19-86 05-19-86 05-Z0-86 05-19-'86 JUNE 06-08-86 06-08-86 06-07-86 06-09-86 06-08-86 06-09-86 to to to to to to ~ .
06-09-86 06-09-86 06-09-86 06-10-86 06-09-86 06-10-86 06-ZZ-86 06-ZZ-86 06-Zl-86 06-Z3-86 06-ZZ-86 06-Z3-'86 to to to to to to 06-Z3-86 06-Z3-86 06-Z3-86 06-Z4-86 06-Z3-86 06-24-86
*JULY 07-06-86 07-06-86 07-05-86 07-07-86 07-06-86 07-07-86 to to to to to to 07-07-86 07-07-86 07-07-86 07-08-86 07-07-86 07-08-86 01-'Zl-86 07-20-86 *7-19-86 07-Zl-86 07-20-86 07-21-86 to to to to to to 07-ZZ-86 07-21-86 7-21-86 07-22-36 07-21-86 07-ZZ-86
*j**'**-"*-<<'.!.~cc.:.:_.:o:_ -- - -- . -*--*** .. '......~.*--****-*~.:*:.* ,::~ .. *1 1
I 1 TABlE°C-13 (co~t'd) 198~ SAMPLING DATE$ IF.OM MILK SAMPLES STATION IO MONTH R3U 2f4* fifZ 11f3 14f l 361
*i "1 AUGUST H-0~-86 08-03-86 08-03-86 08-02-86 08-04-86 08-04-86 08-03-86 ) to to to to to to to 08-IH!-86 08-04-86 . 08-04-86 08-04-86 08-06-86 08-0fi-8,6 08-04-86
- 1
'J I 'i 08-R9-86 08-19-86 08-19-86 08-18-86 OB-18-86 08-18-86 08-'-19-86
.I to to to to to to to 08-20-86 08-Z0-86 08-20-86 08-19-86 08-19-86 08-19-86 08-20-86 SEPTEMBER 09-08-86 09-08-86 09-07-86 09-0)-86 09-07-86 09-08-86.
to to to to to to
*,I 09-09-86 09-09-86 09-08-86 09-08-86 09-08-86 09-09-86 09-U-86 09-22-86 09-Zl-86 09-21-86 09-21-86 09-22-86 *I.! h1 (to to to to to 09-23-86 O!ll-U-8(i 09-22-86 <<19-22-86 09-22-86 09-23-86 i1~
OCTOBER Ul-06-86 !0-06-86 10-06-86 !O-Oli-86 10-05-86 10-06-86 j to (to to to to to . RO-<<H'-86 A0-0}'-86 10-06-86 10-06-86 10-'-06-86 10-07-86 Uli-20-86 10-20-86 10-19-86 10-19-86 10-19-86 . 10-20-86 to to to to to to 10-21-86 10-2fi-86 10-20-86 10-20-86 10-20-86 10-21-86 NOVEMBU RHJJZ-86 H-09-86 11-01-86 U-02-86 11-02-86 11-0i-86 to fto to to to to
- lll-O:lH!6 H-10-86 11-0Z-86 11-03-86 11-03-86 11-03-86 U-H-86 U-H-86 11-16-86 11-16-86 11-16-86 ll-l7-'86 tl:o to to to to to U-iS-86 U-ll.8-86 U-17-86 11-17-86 11-17-86 11-18-86 i DIECEMBU RZ-O'Jl-86 iZ-07-86 12-06-86 12-08-86 12-08-86 12-07'-86 i fto to to to to to l AZ-08-86 lZ-08-86 lZ-08-86 12-09-86 12-09-86 12-08.:.86 j
"' Stat 1011 SA-MLK-21F4! termh!al:111tdl mHk production on September~ A, R986.
"'"'Station SA-MlK-2f7 replaced stal:ton SA-MLK-2f4 on September i, R986.
.. ~ - -' *-**-'-- *- ;_ -.; .. - . ~.. - ---':': -
TABLE C-14 1986 CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMITTERS, POTASSIUM-40 AND TRITIUM IN WELL WATER Results in Units of pCi/L +/- 2 sigma STATION ID RADIOACTIVITY 01-13-86 02-10-86 03-10-86 04-14-86 05-12-86 06-16-86 SA-WWA-2S3 Alpha <2.2 <l. 2 <l.6 <1.1 <l.O(l) <0.5 Beta 3.3+/-0.8 5.8+/-0.9 3.6+/-0.8 3.2+/-0.7 5.4+/-0.9 2.5+/-0.7 K-40 3.0+/-0.3 6.9+/-0.7 4.2+/-0.4 3.6+/-0.4 5.9+/-0.6 2.9+/-0.3 H-3 <130 <130 <140 <140 <130 <140 SA-WWA-5Dl
<O Alpha <3.7 <l. 4 <1.9 <0.8 <0.7 0 0.9+/-0.5 Beta 13+/-1 13+/-1 13+/-1 12+/-1 13+/-1 2.0+/-0.6 K-40 8.8+/-0.9 13+/-1 15+/-2 15+/-2 14+/-1 12+/-1 H-3 <130 <140 <150 <140 <130 <130 SA-WWA-3El (control)
Alpha <2.9 <l. 4 <1.9 <0.9 <0.8 <0.8 Beta 8.5+/-1.0 9.5+/-1.1 8.1+/-1.0 8.8+/-1.1 8.4+/-1.0 2.5+/-0.6 K-40 17+/-2 9.3+/-0.9 9.6+/-1.0 9.9+/-1.0 9.1+/-0.9 7.6+/-0.8 H-3 <130 <140 <140 <140 <L~O <140 AVERAGE Alpha
' Beta 8.3+/-9.7 9.4+/-7.2 8.2+/-9.4 8.0+/-8.9 8.9+/-7.6 2.3+/-0.6 **:' K-40 9.6+/-14 9.7+/-6.1 9.6+/-11 9.5+/-11 9.7+/-8.2 7.5+/-9.l H-3
. ~ I .
TABLE C-14 <<cont~d) 198~ CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMITTERS, POTASSIUM-40 AND TRITIUM IN WELL WATER Results in Units of pCi/L +/- 2 sigma STATION ID RADIOACTIVITY 07-14-86 08-11-86 09-15-66 10-14-86 11-10-86 12-15-86 AVERAGE SA...:wwA-2S3 Alpha 1.7+/-1.3 1. 6+/-1. 2 0.9+/-0.6 0.7+/-0.5 <1.3 . <l. 9 Beta 8.6+/-Ll 6.5+/-1.0 2.5+/-0.6 7.3+/-1.0 3.6+/-0.8 3.8+/-0.8 4.7+/-4.0 K-40 7.J+/-0.7 8.0+/-0.8 4.7+/-0.5 3.2+/-0.3 -2.9+/-0.3 2.7+/-0.3 4.6+/-3.8 H-3 <130 <140 <140 <140 <140 <130 SA-WWA-5Dl U!J l}..,j) Alpha <l.5 2.0+/-1.2 0.6+/-0.5 <0.5 <l.4 <l. 9 . -- Beta 13+/-1 12+/-1 3.8+/-0.7 4.9+/-0.8 12+/-1 15+/-1 10+/-9 K-40 13+/-1 16+/-2 12+/-1 12+/-1 !2+/-1 11+/-1 13+/-4 H-3 <130 <130 <140 <140 <140 <130 SA-WWA-3El
<<control)
Alpha <1.5 <l.2 <0.5 <0.5 <1.5 <2.0 Beta 8.5+/-1.l 8.8+/-1.l 5.3+/-0.S J.5+/-0.7 8.6+/-1.0 8.6+/-1.l 7.4+/-4.6 K-40 8.5+/-0.8 11+/-1 8.1+/-0.8 8.2+/-0.8 7.7+/-0.8 7.4+/-0.7 9.4+/-5.2 H-3 <130 <130 <140 <140 <140 I <130 AVERAGE Alpha 1.6+/-0.8 0.7+/-0.4 Beta HUS 9.1+/-5.5 3.9+/-2.8 s. 2+/-3. 0* 8.1+/-8.4 9.1+/-11 7.6+/-7.7 K-40 9.6+/-6.0 12+/-8 8.3+/-7.3 7.8+/-8.8 7.5+/-9.l 7.0+/-B.3 9.0+/-8.0 iH-3 (].) Station SA-WWA-2SJ was collected on 05-13-86.
... .. _.:. "-~ .. ;~ ~ ....... .... -~-~*
I TABLE C-15 1986 CON~ENTRATIONS OF GAMMA EMITTERS* IN WELL WATER I Results in Units of pCi/L +/- 2 sigma STATION .ID NUCLIDE 01-13-86 02-10-86 03-10-86 *04-14-86 05-12-86 06-16-86 SA-WWA-283 K-:40 <27 <28 <26 <27 <23 (1) <32 Ra-226 3.3+/-1.9 15+/-3 6.0+/-3.l <5.2 <3.3 7.4+/-2.9 Th-232 <6.6 <1.1 <4.6 <7.1 <5.3 <6.8 SA-WWA-5Dl K,.-40 <38 <.34 35+/-15 <33 <26 <40
<<O Ra-226 <4.0 15+/-3 59+/-5 42+/-4 <4.0 44+/-4 t.)
Th-232 <7.1 <6.1 <8.0 <7.9 <7.1 8.4+/-4.8 SA-WWA-3El (control) K-40 * <23 <38 <45 <42 <41 ~ <31 Ra-226 2.9+/-1.5 21+/-3 110+/-7 71+/-5 <4.6 63+/-5 Th-232 <5.8 <7.1 <9.9 <10 <8.7 <8.2 AVERAGE K-40 Ra-226 3.4+/-1.l 17+/-7 58+/-100 39+/-66 38+/-56 Th-232
' .: . ' - ~
. :.. *~-. ;: ..:~ :....,'.:...:...._. *-*" '.: .... ---- TABLE C-15 (cont'd) 1986 CONCENTRATIONS OF GAMMA EMITTERS* IN WELL WATER Results in Units of pCi/L +/- 2 sigma STATION J[ Dl NUCLIDE 07-14-86 08-11-86 09-15-86 10-14-86 11-10-86 12-15-86 AVERAGE SA-WWA-2S3 K-40 <23 <27 <30 <21 <27 <30 .. ~* Ra-226 15+/-2 <4.8 <4.4 <3.7 9.6+/-2.6 8.4+/-2.9 7.2+/-8.3 Th-232 <5. 3l <7.0 <6.3 <5.3 <5.2 <6.7 SA-WWA-5Dl K-40 <29 <29 <26 41+/-15 47+/-16 44+/-17
<IJi Ra-226 50+/-4 29+/-4 lO+/-J 66+/-5 21+/-3 96+/-6 37+/-56
~
Th-232 <7.l <7.l 10+/-4 <7.5 <7.1 <8.4 SA-WWA-3El (Control) . *'* K-40 <30 <39 <39 <32 <23 <33 Ra-226 97+/-6 11+/-3 11+/-4 170+/-7 28+/-3 68+/-5 55+/-100 Th-232 <8.0 <7.7 <B. e~ <6.1 <5.3 <8.0 AVERAGE lK-40 Ra-226 54+/-82 15+/-25 8.5+/-7.l 80+/-168 20+/-18 57+/-89 33+/-77 Th-232
- All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-33.
U) Station SA-WWA-2S3 was* collected on 05-13-86~
" ~
- .. ~* *~ "*' ,: .. ~ ~* ...
TABLE C-16 1986 CONCENTRATIONS OF STRONTIUM-89* AND STRONTIUM-90 IN QUARTERLY COMPOSITES OF WELL WATER Results in Units of pCi/L +/- 2 sigma 01-13-86 14-86 07,..14-86
.. 10-14-86 STATION ID to to *to to NUCLIDE 03-10-86 06-16-86 09-15-86 12"-15-86
- /
SA-WWA-283 Sr-89 <0.4 <11 (1) <0.6 .<0. 9 Sr-90 <0.3 <0.5 <0.4 <0.6
~
SA-WWA-5Dl Sr-89 <0.5 <8~oU> <0.5 <0.7 Sr-90 <0.4 <0.4 <0.4 <0.5
\ SA-WWA-3El i
i (Control) Sr-89 <0.6 <9.o(U <0.5 .<0.8 Sr-90 <0.5 <0.4 <0.4 <0.5
~ Sr-89 results are corrected for decay to sample stop date.
(1) High LLD due to extended period between collection and analysis .
. ~ ... _, ........ *.: :" .:.: ..... ,*, '.., ' ........ . ' ' ' . . . ,. .'. ..~*- ~ ..
TABLE C-17 1986 CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMITTERS 0 POTASSIUM-40 AND TRITIUM IN RAW AND TREATED POTABLE WATER STATION !Dg SA-PWR/T-2F3 Results in Units of pCi/L +/- 2 sigma RADIOACT!VXTY JANUARY FEBRUARY HARC!l! APRIL MAY JUNE Alpha {Raw) <2.4 0.7+/-0.5 0.1:1:0.5 <0.5 0.5:t0.4 <1.0 (Treated) <l.9 0.6+/-0.5 <0.6 0.8+/-0.5 0.6:t0.5 <1.4 Beta (Raw) 2.2+/-0.6 3.7+/-0.8 2.4+/-0.6 2.2+/-0.6 2.l:t0.6 2.4+/-0.7 (Treated) 2.4+/-0.7 2.6+/-0.7' 2.3+/-0.6 3.0+/-0.7 2.2+/-0.6 2.1+/-0.7 "JK-40 (Raw) 1.4+/-0. l 1. 7+/-0.2 1.4+/-0.l 2.0+/-0.2 1.3+/-0.l 1.4+/-0.l {Treated) 2.uo.~ l. 7+/-0. 2 l.4+/-0.l 2.0+/-0.2 l.~:i:O. 2 1.5+/-0.2 ilCI m H-3 (Raw) <140 <140 <140 <130 150+/-80 <140 (Treated!) <140 <140 <140 <140 <130 <130
- 1 I RADIOACTIVIT'lf JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER AVERAGE Alpha (Raw) 0.7+/-0.5 1.0+/-0.8 <0.6 <l.3 <2.0 1. 5+/-1.0 (Treated) 1.1+/-0.1 0.9:t0.6 <0.5 <l.3 <l.1 <0.9 Beta (Raw) 2.* 0+/-0.6 3.1+/-0.7 13+/-1 2.8+/-0.p 3.2+/-0.7 4.5+/-0.8 3.6+/-6.l (Treated) l . 7+/-0.6 8.2+/-1.0 5.1+/-0.8 6.5+/-0.9 2.8+/-0.? 3.8+/-0.? 3.6+/-4.0 JK-40 (Raw) l.3+/-0.l l. 3+/-0. l 1.3+/-0.l 1. 5+/-0 .1 l. ?+/-0.2 2.6+/-0.3 l.6+/-0.8 (Treated) l.3+/-0.l 1.3+/-0.l 1.3+/-0.l 4.9+/-0.5 1.6+/-0.2 2.3+/-0.2 2.0+/-2.0 H-3 (Raw} <130 <140' <140 <140 <130 <130 (Treated) <130 <140 <140 <140 <140 <130
')
T~BLE ~8 I 1986 CONCENTRATIONS OF GAMMA EMITTERS* IN RAW AND TREATED POTABLE WATER Results in Units of pCi/L +/- 2 sigma 01-01-86. 02-01-86 03-01-86 04-01-86 05-01-86 06-01-86 STATION ID to to to to to to NUCLIDE 01-31-86 02-28~86 03-31-86 04-30-86 05-31-86 06-30-86 SA-PWR-2F3 K-40 <22 <40 <23 <22 <27 ~44 Ru-103 <l. 7. <l. 5 <1.4 <4.6 <3. 3 <2 *. 1 Ra-226 2.6:tl.4 <5.0 <3.7 <3.7 <4.0 <5.1
'l'h-232 <5.8 <8.1 <4.9 <5.8 <7.1 <9.1 SA-PWT-2F3 '
K-40 <36 <29 <28 <26 <37 <26 Ru-103 <2.2 <l. 9 <0.9 <5.6 <1. 9 2.6:tl.3 Ra-226 <4.4 '<4.2 <4.0 <4.4 <5.3 <4.6. co Th-232 <6.6 5.7:t3.4 <7.3 <7.1 <7.2 <1.1 CJ) 07-01-66 06-01-66 09-01-86 10-01-86 11-01-66 12-01-86 STATION ID to to. to to to to NUCLIDE 07-31-86 06-31-86 09-30-86 10-31-86 11-30-86 12-31-86 SA-PWR;_2F3 K-40 <29 <23 <27 25+/-13 <37 25+/-14' Ru-103 <2.2 <l. 4 <1. 7 <2.1 <l. 8 <1. 9 Ra-226 <4.4 <3.7 . <4. 2 6.4+/-2.4 <4.3 <4. 4 .
'l'h-232 <7.5 <5.8 <6.0 <7.1 <6.1 5.8+/-3.3 SA-PWT-2F3 K-40 <22 <29 <41 <22 <40 <22 Ru-103 <2.0 <l. l <l. 2 <l. 7 <0.5 <1. 6 '. .*
Ra-226 <3. 7 <4.5 <4. 8 6.6+/-1.6 <5.8 <3. 7 .
'l'h-232 <4.~ 6.8:t3.6 <9.6. <5.3 <9.5 . < 5. 3
*-other gamma emitters searched for were <LLD1 typical LLDs are given in Ta~le C-33.
- *'1 i.:
..:~ .. , ~.......... :. .~~::);:~*.<<.:.,:.;::...:::.~~ - ~ *"- . .- .- ...... ,:, ',', ... :;, ~~**~* ...
j
*1 I
*J l
j TABLE C-19 1986 CONCENTRATIONS OF STRONTIUM-89* AND STRONTIUM-90 IN QUARTERLY COMPOSITES OF POTABLE WATER Results in Units of pCi/L +/- 2 sigma 1
., 01-01-86 04-0ll-86 07-01-86 10-01-86
. STATION ID to to to to NUCLIDE 03-31-86 dll6-30-86 09-30-66 12-31...:.86 SA-PWR-2F3 (Raw)
Sr-89 <l. 6 <0.8 0.8+/-~L3 <l 00 Sr-90 <l.0 <0.5 <0.6 <0.8
<<O ' ~ ->\!!
. 'i SA-PWT-2FJ
<<Treated) sr-89 <0.8 <0 7.
0 <0.5 <O .*a Sr-90 <0.5 <0.5 <0.4 <0.6 i
- . l
- Sr-89 results are corrected for decay to sample stop date.
1*
,.... . *1 * .r... : ..
. *~**** :~ . *. .. ~- "*~ -.
TABLE C-20 1986 CONCENTRATIONS OF GAMMA EMITTERS* IN VEGETABLES Results in.Units of pCt/kg (wet) +/- 2 sigma COLLECTION STATION ID OATE(S) SAMPLE TYPE Be-7 K-40 I-131 Cs-137 Ra-226 Th-232 SA-FPV-2El 06/14-16/86 Asparagus <110 2300+/-310 33+/-13 <21 <47 < 94 SA-FPV-3El 07-30-86 Tomatoes < 12 2300+/-64 < 2.3 < 1.6 < 1.8 < 5.7 SA-FPV-3El 07-30-86 Corn <130 2400+/-310 < 4.0 <12 <36 < 55 SA..:FPL-lf3 "07-29-86 Cabbage ( 27 2200+/-93 < 3.1 ( 3.8 ( 7.9 < 13 SA-FPV-1F3 07-29-86 Peppers ( 82 .1800+/-300 <25 <14 <61 < 83 SA-FPV-lf3 07-29-86 Tomatoes ( !6 2200+/-63 < 3.3 ( 2.2 ( 3.6 (
- 7. ~
SA-FPL-4Fl 07-29..:86 Cabbage 24+/-16 2300+/-99 < 3.9 < 3.7 8.3+/-3.6 ( 15 SA-FPV-4Fl 07-30-86 Tomatoes < 17 2600+/-74 < 4.0 < 2.2 < 3.9 ( 6.7 SA-FPV-6Fl 07-29-86 Peppers <130 1800+/-270 <24 <11 <37 ( 61 co SA-FPV-14F3 07-28-86 Tomatoes < 17 1700+/-53 < 3.7 < 2.0 < 3.7 8.8+/-4.7 Q) SA-FPV-14F3 07-28-86 Corn <160 2300+/-260 ( 3.8 < 3.2 <33 ( 63 SA-FPV-14F3 07-30-86 Peppers <130 910+/-230 <22 <18 <36 <67
*SA-FPV-lGl (C) 07-28-86 Tomatoes < 11 1600+/-62 < 3.3 1.6+/-0.8 < 2.9 ( 6.1 SA-FPV*lGl (C) 07-28-86 Corn <140 2200+/-290 - <20 <18 <40 < 78 SA-FPV-161 (C) 07-28-86 Peppers <190 1700+/-280 < 3.8 <24 68+/-34 ( 110
- SA-f PV-2Gl (C) 06-13-86 Asparagus ( 28 3400+/-340 62+/-20 <23 <61 < 95 SA-FPV-3H6 (C) 07-28-86 Tomatoes ( 14 1600+/-62 < 3.2 2.1+/-0. 9 < 2.9 ( 5.5 SA-FPV-3H6 (C) 07-28-86 Corn <170 2700+/-350 <22 <22 58+/-26 < 95 SA-FPL-3H5 ( c) 07-28-86 Cabbage < 40 1900+/-120 < 5.2 < 4.7 <10 < 21 SA-FPV-:3H6 ( c) 07-29-86 *Peppers <130 1600+/-260 <20 <21 <44 < 70 AVERAGE 2100+/-1100 11 other gamma emitters ~earched for were <LLD; typical in Table C-33.
ntrol Stat ion
. - t TABLE C-21 1986 CONCENTRATIONS OF GAMMA EMITTERS* IN GAME AND MEAT Results in Units of pCi/kg (wet) +/- 2 sigma COLLECTION STATION ID DATE(S) SAMPLE TYPE K-40 Cs-137 SA=GAM~llDl 01/11=13/86 Muskrat 2200+/-:170 <9o9 (Control)
SA~GAM-4Cl 01~12-86 Muskrat 2400+/-220 <15 SA-FPB-3El 02-24-86 Beef 2500+/-180 7.3+/-4.6 AVERAGE Muskrat 2300+/-280 Beef 2500+/-180
- All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-33.
**i
*J
-. i
* :. _*...*'*; ...~ *; *1!
- ..:>-1
~.--- . . -- __ ,_ - --:-*-**-c;:----~- ----*-:;*--.. - -:-***:*- ..- ---~-----~------ -*-. *-*** -- *----.----* ---. .--* ****--***-* .. * .. -:- -* ---* ----- ** *,"r- ---:--***-,: * ,_ __ -~*
TA~LE C-22 1986 CONCENTRATIONS OF GAMMA ~HITTERS* IN FODDER CROPS Results in Units of pCi/kg (wet) +/- 2 sigma COLLECTION STATION ID DATE(S) ~AMPLE lrYPE Be-'7 K-40 Cs-137 Ra-226 Th-232 SA-VGT-3E~ 10-13-86 soybeans <160 15000+/-590 <25 <39 <88 SA-VGT-13E3 09/01-05/86 Silage 1000+/-190 3600+/-510 <28 <67 <120 SA-VGT-2F'7 09/03-08/86 Silage 370+/-90 2600+/-280 <17 35+/-17 <63 SA-VGT-5F2 09-14-86 Silage <250 2300+/-470 <28 <76 <130 0 0 SA-VGT-5F2 11-01-86 soybeans <150 15000+/-610 <21 <38 <11 SA-VGT-llF3 09-01-86 Silage '740+/-180 4000+/-430 <19 <51 <76 SA-VGT-14Fl 09-15-86 Silage 1400+/-260 3400+/-520 <54 <100 170+/-100 SA-VGT-3Gl (C) 09-08-86 Silage 11Q0+/-240 3000+/-550 <41 <83 <130 SA-VGT-3Gl (C) 11-01-86 Soybeans <140* 14000+/-480 13+/-7 <36 <59 AVERAGE 590+/-960 7000+/-12000
- All other gamma emitters searched for were *<LLD; typical LLDs are given in Table C-33.
(C) control station
* .~. . I
.j
~
..,*.*-= *-*- --* ... ***~-*--"* .. ,., .......... ..:.:.:. ,..........: .. ..... ,
**! I i
I 1. I J ... TABLE C-23 "i
.I 1
1986 CONCENTRATIONS OF STRONT!UH-90 AND GAMMA EMITTERS* IN SOIL
*J .)
Results in Units of pCi/lltg {dry.) +/- 2 sigma j 1I COLLECTION STATION ID DATE Sr-90 IK-40 Nb-95 Cs-131' Ra-226 Th-232
*SA-SOL-6Sl 01-30-86 27+/-10 9200+/-450 34+/-19 100+/-19 490+/-40 620+/-72 SA-SOL-5Dl 07-30-86 120+/-14 5200+/-340 <22 350+/-23 510+/-37 550+/-64 SA-SOL-lODl 07-30-86 110+/-14 8300:1:420 <29 370+/-24 800+/-41 840+/-70 SA-SOL-2El 07-29-86 110+/-13 7300+/-400 <12 380+/-27 700+/-45 720+/-14 SA-SOL-16El 07-30-86 110+/-14 12000+/-410 <27 260+/-18 1000+/-40 1200+/-68 SA-SOL-lFl 07-30-86 120+/-13 3600+/-240 <15 1500+/-35 260+/-24 270+/-35 SA-SOL-2Fl 07-29-86 140+/-15 9100+/-430 <24 330+/-25 870+/-47 840+/-77 SA-SOL-2F2 07-29-86 <22 5500+/-380 <22 110+/-16 380+/-36 340+/-60 SA-SOL-2F4 07-29-86 55+/-10 7400+/-400 <28 370+/-24 770+/-40 730+/-67 SA-SOL-2F? 07-30-86 87+/-13 8300+/-420 63+/-22 330+/-26 890+/-50 890:t~l SA-SOL-5Fl 07-29-86 97+/-14 5100+/-270 <18 800+/-26 340+/-26 410+/-41 SA-SOL-5F2 07-29-86 77+/-12 3200+/-330 <22 290+/-24 480+/-38 410+/-59 SA-SOL-llF3 07-30:-86 43+/-12 13000+/-560 < 4.5 78+/-19 1000+/-51 1100+/-98 .. I '
SA-SOL-14Fl 07-30-86 87+/-14 12000+/-500 <19 230+/-25 960+/-48 1000+/-82 SA-SOL-3Gl ~C) 01-29-86 56+/-11 7900+/-450 <15 210+/-22 770+/-46 780+/-82 SA-SOL-3H3 (C) 07-28-86 130+/-15 9200+/-440 <26 690+/-31 850+/-46 810+/-76 AVERAGE 87+/-74 7900+/-5800 400+/-700 690+/-490 720+/-540
- All other gamma emitters searched for were <LLDa typical LLDs are given in Table C-33.
(c) Control station
** l',, **>***~*-'***
1* TABLE C-;-24 1985 CONCENTRATIONS OF GROSS ALPHA ~HITTERS IN SURFACE WATER Results in Units of pCi/L +/- 2 sigma STATION ID 01-20-86 02-03-86 03-03-86 04-08-86 05-05-86 06-09-86 SA-SWA-llAl <2.0 8.3+/-4.2 2.6+/-1.6 5.2+/-4.0 <4.0 . 2.0+/-1.4 SA-SWA-12Cl <l. '1 <4. '1 <l.2 8.3+/-2.5 1.8+/-1.3 <l.4 (Control) SA-SWA-'1El <2.0 3.6+/-2.6 1.2+/-0.9 <3.8 <l.4 <l.2 SA-SWA-1F2 <l.8 5.0+/-3.l <l.l 12+/-3 <1.6 <l.3 SA-SWA-16Fl <3.'1 4.4+/-2.9 <Ll <4.1 <1.5 <l.2 0 l\) AVERAGE 5.2+/-3.6 6.7+/-6.9 STATION ID 0'1-11-86 08-04-86 09-08-86 10-07-86 11-03-86 12-08-86* AVERAGE SA-SWA-llAl 1.6+/-1.2 1.8+/-1.0 <0.8 <0.8 <1.8 1.2+/-0.9 2.7+/-4.4 SA-SWA-12Cl 2.2+/-1.6 1.8+/-1.0 <l.6 <0.6 <1.9 <1.l (Control) SA-SWA-7El 1.6+/-1.2 1.3+/-1.0 1.1+/-0. '1 1.2+/-0.8 <l. '1 <1.1 SA-SWA-1F2 <l.5 2 .6+/-1. l <0.8 <0.8. <1.8 <l. 2 SA-SWA-16Fl <1.6 1. 5+/-1.0 0~'1+/-0.5 <0.9 <2.0 <1.1 AVERAGE l. 7+/-0.6 1.8+/-1.0
~
*=*.* - ..
*.~ >>. **, .. ;** '_.
- ..~.*.. .:.~.. :. . ' * * . *-* -* *****" .......... ., ... ~ ....... -*~ ** ~<-** .... *"
- j 1
I
'j
_i
)
TABLE C-25* ii 1986 CONCENTRATIONS OF GROSS BETA EMITTERS IN SURFACE WATER I
-1 Results in Units of. pCi/L +/- 2 sigma STATION :m 01-20-86 02-03-86 03-03-86 04-08-86 05-05-86 06-09-86 SA-SWA-llAl 181+/-8 21+/-4 12+/-1 32+/-4 24+/-4 24+/-4 SA-SWA-12Cl BU::8 17+/-3 1 .5+/-1.l 17+/-3 36+/-5 33+/-5 (Control)
SA-SWA-7El 92+/-9 51+/-6 16+/-2 50+/-6 63+/-7 42+/-6 I SA-SWA-1F2 39+/-5 fi.0+/-2.4 2.4+/-0.'7 10+/-2 9.2+/-2.? 22+/-4 SA-SWA-16Fl 50+/-6 8.1+/-2.6 3.8+/-0.8 13+/-3 11+/-3 25+/-4 II-"' 0
~ AVERAGE 69+/-46 22+/-37 a.Jui 24+/-33 29+/-44 29+/-16
- ~
i STATION ID 07-11-86 08-04-86 09-08-86 10-07-86 11-03-86 12-08-86 AVERAGE SA-SWA-llAl 89:t9 96+/-9 130+/-12 77+/-8 120+/-11 14+/-3 60+/-86 SA-SWA-12Cl 68+/-8 69+/-7 76:t8 59+/-7 72+/-8 9.8+/-2.7 '45+/-56 (control) SA-SWA-7El 110+/-12 120+/-11 130+/-12 110+/-11 100+/-11 3_0+/-4 76+/-77 SA-SWA-1F2 42+/-6 38+/-5 85+/-9 45+/-6 51+/-6 6.4+/-2.4 30+/-50 SA-SWA-16Fl 48+/-6 66+/-7 75+/-8 56+/-6 87+/-8 11+/-3 38+/-58 AVERAGE 1U5? '18+/-62 99+/-57 69+/-51 86+/-53 14+/-18. Girand Average 50+/-73 0
TABLE C-Z6 1986 CONCENTRATIONS OF GAMMA EMITTERS* IN SURFACE WATER Results tn Untts of pCi/L t Z sigma STATION ID NUCLIDE Ol-Z0-86 OZ-03-86 03-03-86 04-08-86 05-05-86 06-09-86 SA-SWA- llAl K-40 80tZ6 <41 80+/-19 33t18 43t19 64:tZO Ra-2Z6 <4.6 <4.4 <4.4 <4.9 <4.4 <3.7 Th-232 <7.6 <6.6 6.Z:t3.7 8.8+/-4.0 <8.4 5.3t2.8 SA-SWA-12Cl . K-40 86tZO
- Z9:t17 41t18 <29 46tZ3 <43 (Control) Ra-Z26 <6.2 <3.7 <3.7 <4.8 <4.6 <4.7 Th-232 <6.8 <6.8 <6.3 <6.4 9.2:1:4.3 <7.6 SA-SWA-7El K-40 90+/-27 84tl8 67tZ1 73+/-26 87tZO 83t22 Ra-226 <4.4 <6.6 <4.6 <6.0 <4.6 <4.4 Th-232 <8.1 <8.6 <8.3 <6.5 <6.2 <7.1 SA-SWA-lFZ K-40 67t19 <39 <24 <3Z <35 <Z7 Ra-226 <4.4 <4.4 <3.3 <3.9 5.4:tZ.9 <3.3 Th-232 <6.6 <9.0 <4.9 <7.6 <1.4 <6 ..3 SA-SWA-16Fl K-40 61+/-2Z <Z7 <Z6 <41 <26 <30 Ra-Z26 <4.2 <4.0 ll:t3 <6.1 <4.3 <4.9 T~-232 <6.9 <7.1 <6.2 <8.2 <5.7 <7.7
..... AVERAGE K-40 76:t32 48+/-50 47:1:47 0 ~
STATION ID NUCLIDE 07-11-86 08-04-86 09-08-86 10-07-86 11-03-86 lZ-08-86 AVERAGE SA-SWA-llAl K-40 1ZO:t24 110tZ6 140+/-26 140:tZ3 lZOt23 <3Z 84:t83 Ra-226 <4.6 <4.8 <4.l <4.4 <4.9 <4.6 Th-232 <7.8 <7.5 7.6:1:4.4 <8.0 <7.4 <7.5 SA-SWA-12Cl K-40 73+/-26 92+/-21 79:1:26 95+/-20 9l:t23 <43 62:t52 (Control) Ra-226 <6.3 <4.5 <4.3 25+/-3 <4.6 <6.1 Th-232 <8.6 <6.4 <8.9 <6.8 <6.8 <1.8 SA-SWA-7El K-40 l40:t21 lOO:tZ6 160+/-24 130+/-27 140+/-31 66+/-17 102+/-64 Ra-2Z6 . 2.9:tl. 7 <4.4 <4.6 <5.5 . <6 .1 <4.4 lh-232 <6.3 <6.2 <7.6 <8.5 <9.0 <7.1 SA-SWA-1F2 K-40 44t2Z 49+/-17 86:1:Z6 95:t20 61tZO <24 Ra-226 <4.0 8.4+/-2.0 <4.8 <5.7 <4.6 Z.6:tl.6 Th-232 <7.6 <6.8 <7.2 <7.5 <6.9 <6.3 ,. SA-SWA-16Fl K-40 68:1:19 63:tZ3 lOOtZl 60+/-18 94+/-27 <27 Ra-226 <4.9 <4.0 <4.4 3.3:tl. 7 5.2:t2.8 <4.5 Th-232 <6.3 <7.5 <6.4 <5;8 9.3:t4.8 <6.5 AVERAGE K-40 89+/-79 81+/-56 110+/-71 100:t64 100+/-60 e Grand Average K-40 69:t72
- other ganlna emitters searched for were <LLD; typical LlDs a . n in Table C-33.
.~:.:..:, * .:.**** ~:.. 1 **** * .~. * -**
~~.. '
...........:.:*,:* ..... _.\/ ******
.1
- I I
I TABLE C-27 *I 1986 CONCENTRATIONS OF TRITIUM IN QUARTERLY COMPOSITES OF SURFACE WATER Results in Units of pCi/L +/- 2 sigma 01-20-86 04-08-86 07-11-86 10-07-86 STATION ID to to to to AVERAGE 1!)3J-03-86 06-09-86 09-08-86 12-08-86 SA-SWA-llAl 150+/-80 <140 270+/-90 <140 ll-" SA-SWA-l2Cl 150+/-80 <130 <140 <130 a <<control>>
<<im SA-SWA-7El l3CU80 <140 140+/-90 <140 SA-SWA-lF2 <130 <130 170+/-80 <140 SA-SWA-l6Fl 140+/-80 <130 160+/-80 140+/-80 140+/-25 AVERAGE 140+/-20 180+/-110
,,, . ..:*." .. .. - . ~:... *' ...'* ..:..... ~. *, *,
I! I i i
.i TABLE C-28 1986 CONCENTRATIONS OF STRONTIUM-89* AND STRONTIUM-90 AND TRITIUM IN EDIBLE FISH r: \:. 'l'RITIUM (FLESH)**
I STRONTIUM (BONES) AQUEOUS FRACTION pCi/kg (dry) +/- 2 sigma pCi/kg (wet) +/- 2 sigma i STATION ID COLLECTION PERIOD sr-89 Sr-90 H-3 I I iI I I SA-ESF-llAl 05-05-86 to 05-13-86 <70 240+/-17 <50
,' l . I . 10-08-86 to 10-08-86 <48 <29 <50 I
I
- 1 SA-ESF-12Cl 05-12-86 to 05-19-86 330+/-100 1500+/-64 i
<50
~
a (Control) 10-08-86 to 10-08-86 <75 <44 <50 m SA-ESF-7El 05-06-86 to 05-07-86 <65 34+/-13 <50 10-09-86 to 10-09-86 <40 <24 <50
.I I
*J t Sr-89 results are coriected for decay to sample stop date.
** Tritium results by Controls for Environmental Poilution, Inc *
' *- . ._, __ ...;~-~::~- - -~- ...... *'-.. ;_,
I I I TABLE C-29
. j
' 1966 CONCENTRATIONS OF GAMMA EMITTERS* IN EDIBLE FISH
. i 1
*1 Results in Units of pCi/kg (wet) +/- 2 sigma STATION ID COLLECTION PERIOD K-40 Cs-137 Ra-226 Th-232 SA-ESF-llAl 05-05-86 to 05-13-86 2nHll+/-l80 8.3+/-4.5 <20 <31.
10-08-86 to 10-08-86 3300+/-290 <19 41+/-19 <*61 SA-ESF-12Cl 05-12-86 to 05-19-86 2700+/-230 <12 <24 29+/-18 (Control~ 10-08-86 to 10-08-86 33CHU240 <16 <34 <59 II-" 0 19
~
SA-ESF-7El 05-06-86 to 05-07-86 2800+/-230 <12 <24 <47 10-09-86 to 10-09-86 3000+/-240 <14 33+/-17 <53 AVERAGE 3000+/-560
- All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-33.
.i -r ... : ._ , 1
./
.11
*, TABLE C-30 I
Ii 1986 CONCENTRATIONS OF STRONTIUH-89* AND .STRONTIUM-90, GAMMA EMITTERS** AND TRITIUM IN BLUE CRABS Results in Units of. pCi/kg (wet) +/- 2 sigma COLLECTION AQUEOUS FRACTION STATION Ill PERIOD SAMPLE Sr-89 Sr-90 . K-40 Ra-226 H-3*** e
- SA-ECH-llAl 06/05-06/86 Flesh <28 <18 1700+/-210 <30 <50 Shell (1) 300+/-32 150+/-24 (2) (2) . (2) 10/08-09/86 Flesh <46 <24 2000+/-210 <28 <50 Shell (1) <67 380+/-19 (2) (2) (2)
Q--1 0 SA-ECH-12Cl 06/05".""06/86 Flesh <29 <19 2000+/-160 19+/-9 <50 (Control) Shell (1) <11 490+/-26 (2) (2) (2)
.10/08-09/86 Flesh <44 <24 .1700+/-150 20+/-9 <50 Shell (1) <89 ~20+/-24 (2) (2) (2)
AVERAGE Flesh 1800+/-350 Shell. 340+/-280
- sr-89 results are corrected for decay to sample stop date.
** All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-33.
*** Tritium results by Controls for Environmental Pollution, Inc. .I Strontium results in units of pCi/kg (dry).
ma and tritium analyses not required *.
. I TABLE C~31 1986 CONCENTRATIONS OF GAMMA EMITTERS* IN BENTHIC ORGANISMS . . *.
Results in Units of pCi/kg (dry) COLLECTION GAMMA STATION ID DATE* ACTIVITY SA=ESB=llAl 06~05=86 <LLD 10=14=86 <LLD SA-ESB~l2Cl 06-05-86 <LLD (Control) 10-14-86 <LLD SA-ESB-7El 06-05-86 <LLD 10-14~86 <LLD SA=ESB~l6Fl 06=05=86 <LLD io*.;.,14=86 <LLD
- All gamma emitters searched fo-r were <LLD: typical LLDs are given in Table c-33.
~ *. i e . j ***) .. **i
- . . . J
I'.** '*:!.* *.*..,.. I. I~. I _....... :,:.~ .~.:.. ;~~.:'.l..:.c*' .. .. ... ..*--** ..... -**-** .... 1c~ i I II
...,\1 . I i
i l TABLE C-3Z
*1 1986 CONCENTRATIONS OF STRONTIUM-90 AND ~AMMA EMITTERS* IN SEDIMENT**
I j Results in Units of pC1/kg (dry) t 2 sigma
.-1.
\i l
iI. STATION ID l DATE Sr-90 K-40** Mn-64 Co-68 Co-60 Cs-134 Cs-137 Ra-2Z6 Th-232 I
*1 i SA-ESS-JJAJ
'** 1 j 06-06-86 <19 3600t410 Z9+/-16 <3Z 9Zt17 <34 <ZS 330+/-44 360:t8Z*
.I 10-14-86 <Z1 8600+/-430 26+/-14 38*17 110t23 <22 82t19 . 760+/-46 980+/-.83 *i I
56-ESS-1561 06-06-86 . <20 7800t610 <34' <33 97tZ2 <44 <36 390+/-1i0 440+/-92 I 10-14-86 <Z~ 6800t360 <18 80t16 37tll <16 <22 400t33 300+/-57 I
. I' S6-ESS-J661
.f <Z4 <35 <38 06-06-86 4300t460 80tZ6 82+/-27 <16 810+/-62 iJOO:tliO
........ 10-14-86 <38 6000t400 Z4tl3 '79t18 49t21 <21 <29 760+/-46 780:t76 q
S6-ESS-IZC1
*1 (Control) 06-06-86 <21 16000t830 <34 . <37 <48 60+/-24 <35 670+/-63 880+/-110 10-14-86 <26 14000t640 <23 <23 <36 <20 20t1Z 840+/-42 870+/-74 56-ESS-ZEl i
' 06-06-86 <20 16000t660 <26 <27 37t19 46+/-18 49t16 690t44 770+/-80
.I
- 10-14-86 <30 l3000t660 <29 31tl6 78t26 <21 6lt15 690+/-42 720+/-78
- 1 "i S6-ESS-16Fl 06-0b-86 <28 16000t830 <38 <37 <48 66+/-26 <39 680+/-66 940+/- 110 10-14-86 <29 16000t670 <33 <36 <44 <24 <26 680t47 1000+/-91 AVERAGE 10000t9900 63t63 620+/-330 740+/-490
- All other ganma emitters searched for were <LLD; typical LLDs are given in Table C-33.
Sediment samples which iriclude*benthic organisms constitute t thos sample.
_c'!
......... -* - ;...... ~**4**-~*-*** --*
I TABLE C-33 1986 fSE&G RESEARCH CORPORAT!OM LLDs FOR GAMMA SPECTROMETRY AIR WATER FOOD PRODUCTS MEAT AND PARTICULATES ALL TYPES HILK AND FODDER CROPS GAME JMUCLIDES <<!0- 3pCi/m3 ) _ (pCi/L) h>Ci/L) (pCi/k.g-wet) (pCi/kg-wet) I GEOMETRls 13 Filters 3.5 Liter 3.5 Liter lOOml 400ml lOOml 400ml
*l.i l
- 1
. -*~ Jae-7 3. 0 14 14 e.o 120 37 92 1
I Ma-22 0.54" i.a l.B 1.2 15 5.3 11 . *i JK-40 e.o 32 "' II<
*
- If!
Cr-51 2.18 12 12 9.5 140 45 107
*1 Hn-54 0.38 1.4 1.4 1.0 14 4.4 10
-i Co-58 0.39 1.6 1.6 0.99 15 4.5 11 Fe-59 0.83 3.2 3.2 2.4 32 10 *- 24 Co-60 0.46 2.0 2.0 1.1 16 5.0 11 Zn-65 0.86 3.3 3.3 2.0 31 9.0 22 Hb-95 0.43 1.7 1.7 l.l 16 5.0 12 0--0 ll-' zr-95 o.n 3.0 3.0 2.0 2a a.a 21 ll-' ZrMb-95 0.71 3.0 3.0 2.0 28 8.a 21
~
_,; Ho-99 12 20 20 51 1300 370 2400 Ru-103 0.39 1.4 1.4 1.0 16 4.9 12 Ru-106 4.0 14 14 10 130 42 98 Ag-llOm 0.67 1.5 1.5 1.6 14 7.2 11 Sb-125 0.90 4.1 4.1 2.6 39 12 27 Te-129m 14 63 63 40 620 183 480 J[-131 0.46 1.8 1.8 1.7 30 9.0 30 Te-132 0.89 2.1 2.1 3.9 99 26 170 Cs-134 l0.51 1.7 l.7 1.3 13 5.7 9.3 Cs-136 0.49 1.9 1.9 1.3 22 6.4 20 Cs-137 0.35 l.7 1.7 1.0 17 4.4 12
- ' !Ba-140 l.6 6.2 6.2 5.0 82 25 71 La-140 0.73 2.3 2.3 2.2 32 11 28 JBaLa-140 1.6 6.2 6.2 5.0 82 25 71 .~ Ce-141 0.42 2.4 2.4 1.2 19 5.6 15 Ce-144 l.4 10 10 4.1 79 18 57 Ra-226 0.86 4.0 4.0 2.2 32 10 23 Th-232 1.1 6.8 6.8 3.8 54 17 40
TABLE C~33 (cont'd) 1986 PSE&G RESEARCH CORPORATION LLDs FOR GAMMA SPECTROMETRY SEDIMENT AIR FISH SHELLFISH AND SOIL IODINE NU CL IDES (pCl/kg-wet) (pCi/kg-wet) (pCi/kg-dry) NUCL IDES (lo- 3 pci/m3 ) GEOMETRY: lOOml 400ml lOOml 400ml lOOml lOOml Be-'1 3'1 92 142 85 120 I-131 15 Na-22 5.3 11 21 10 14 I-132 26 K-40 * * * *
- I-133 39 Cr-51 45 10'1 1'10 91 150 I-135 1.2 Hn-5~ 4.4 10 1'7 10 13 Co-58 4.5 11 18 10 14 Fe-59 10 24 41 22 36 Co-60 5.0 11 19 11 15 zn-155 9.0 22 35 22 25 Hb-95 5.0 12 19 10 15
&-' zr-95
~
8.B 21 35 20 26 l\) ZrNb-95 8.8 21 35 20 26 Ho-99 3'70 2400 1200 530 13000 RU-103 4.9 12 19 11 14 RU-106 42 98 160 9'7 120 Ag-llOm 1.2 11 28 10 '19 Sb-125 12 2'1 46 2'1 28 Te-129m 183 480 '720 430 600 I-131 9.0 30 33 18 52 Te-132 26 1'10 85 49 650 Cs-134 5. '1 9.3 22 9 12 Cs-136 6.4 20 24 14 31 Cs-13'7 4.4 12 1'7 12 12 Ba-140 25 ' '71 94 51 105 La-140 11 28' 41 20 52 BaLa-140 25 '71 94 51 105 Ce-141 5.6 15 22 13 1'7 Ce-144 18 5'7 '73 56 55 Ra-226 10 23 40 23 230 1'7 40 69 40 48 cates a positive.concentration was measured in a . . p l e s analyzed.
APPENDIX D SYNOPSIS OF ANALYTICAL PROCEDURES
- I ll~
. . ,.....---~---.:----*-* ~- ----:.---:-* -:---:-*----- ........ ~.- *--- *-:-.;: -. :--;**--:-*:-* -- --- '--. **.* .,.. ~---.--*-.,--, - ---7.. --~ :::- -!:"* - ~--..-~.- -* : * * . ~ r:-- : . -- --.--- ... . ..
1-SYNOPSIS OF .. ANALYTICAL PROCEDURES . Appendix D presents a synopsis of the .analyti.c.al procedures utilized by various laboratories for analyzing. the 1986
- Artificial Island Radiological Environmental Monitoring Program samples.
TABLE OF CONTENTS LAB* PROCEDURE DESCRIPTION PAGE GROSS ALPHA PSE&G Analysis of Air Particulates ******************** 117 TI Analysis of Air Particulates ******************** 119 PSE&G Analysis of Water ** 0 0 0 Cl Cl 0. 0. Cl 0 e e Cl GI Cl 0 0 e Q c I) e I) e 0 fl Cl> Cl 120 GROSS BETA PSE&G Analysis of Air Particulates .***.*************.* 122 TI Analysis of Air Particulates ******** : *********** 124 PSE&G Analysis of W a t e r o * * *
- c o e c e o o o C l e o c i o o o e o o G C l
- C C O O C I 125 POTASSIUM~40 PSE&G Analysis of Water o Clo. o o Clo o e o * ., o o o o e o Cl Q o o o c e o" Iii o ~Cl 126 TRITIUM PSE&G Analysis of Water ******************************* 127 CEP Analysis of Aqueous Fraction of Fish and crab *** 128 IODINE-131 PSE&G Analysis of Filtered Air ************************ 129 TI Analysis of Filtered Air ************************ 130 PSE&G Analysis of Raw Milk ********************.******** 131 STRONTIUM-89 AND STRONTIUM~90 PSE&G Analysis of Air Particulates *********** e******** 132 TI Analysis of Air Particulates **********.********** - .l.35 PSE&G Analysis of Raw Milk **************************** 137 PSE&G Analysis of Water 0 Q Q Q G 0 0 e 0 0 0 e 0 Q 0 t> 0 Cl E> 0 Cl Cl c 0 g 0" Cl ID Q 0 140 PSE&G Analysis of Vegetation, Meat and Aquatic Samples 143 PSE&:G Analysis of Bone and Shell ********************** 146 PSE&G Analysis of Soil and Sediment ******************* 149
. ' PSE&G Analysis of Samples for Stable Strontium ******** 152 115
.- ; :*.~-::~
' .~ ".\!
. .. ~
-:-----------..,,.. ,.... --~ . . . :--:t**,-.*-;*--:-*-*--- . -~~"' -*-:*--..-- -~-.------~- **-:* .- . -;-*----: . .---*,**.---.-. -----* *- ... *- -- ... - -- .... --***-~;-- -*- .. - --- -- . -- - . ***-*:-* ...... **-- *--
SYNOPSIS OF ANALYTICAL PROCEDURES (cdnt'd) TABLE OF CONTENTS L.AB* PROCEDURE DESCRIPTION PAGE GAMMA SPE::::TROMETRY PSE&G Analysis of Air Particulates ***************.***. 154 TI Analysis of Air Particulates ******************** 155 PSE&G Analysis of Raw Milk * *
- e *
- o * * * * * * * * * * *
- e * * *
- u * *
- 156 PSE&G Analysis of Water *************** " ******.******* c
- 157 PSE&G Analysis of Solids (combined procedures) ******** 158 ENVIRONMENTAL DOSIMETRY TI Analysis of Thermoluminescent Dosimeters .*****.. 160
- PSE&G - PSE&G_Research Corporation TI - Teledyne Isotopes CEP - Controls for Environmental Pollution, Inc *
' .* ~
. --. *. ~
.. -~
- "-] 116
**-,--- - -;-* - ***--*-*-----,.-- *:-;-** ..-~-* -......--7.~---**--**.*:-~ *-:*-- * .,.---,;:---""';"*~**-~--*7.~*---.---;---r- *--:-.,.... - - - . - .- * ---* - - * *- <---- ..,*.~* *--:*-~* -~ ~--,;- --,----* *---- ***--: --** *-.- . -** ** - *- . -*.* *
- SYNOPSIS OF.. PSE&G. RESEARCH CORl?ORA'l'ION PROCEDURE GROSS ALPHA.ANALYSIS OF AIR PARTICULATE SAMl?LES After a1low:i.ng at least a three~day (extendi.ng from the sample stop date to the sample count time) period for the short-lived radionuclides to decay out, air particulate samples are counted for gross alpha activity on a low back~
ground gas proportiona1 counter. Along with a set of air particulate samples, a clean air. filter is in:luded as a blank with an Am-241 air filter geometry a1pha counting standard. The specific a1pha activity is computed on the basis of total corrected air flow sampled during the collection period. This corrected air flow takes into*account the air ~ressure correction due to the vacuum being drawn, the correct.ion factor of the temperature-corrected gas meter as well as the gas meter efficiency itself. caiculation of Gross Alpha Activity: Air flow is corrected first by using the following equations: P = (B-V)/29.92 P = Pressure correction factor B = Time-averaged barometric pressure during sampling period, ivHq . V = Time-averaged vacuum during sampling period, "Hg 29.92 = Standard atmospheric pressure at 32°Fu "Hg V = F~P~0.946*0.0283 E F = Uncorrected air flow, ft 3 o.946 = Temperature correction factor from 60°F to 32°F 0.0283 = CUlJic meters per cUlJic foot E = Gas meter efficiency (= % efficiency/100) v "" corrected air flow, m3 p = Pressure correction factor Usinq these corrected a.:!.r flows. the gross alpha activity is computed as follows~ Result (pCi/m3 ) ~ (G--B)/T
*1
( 2 a22) *(E)$1 (V~ G = Sample gross counts B = Background counts (from blank filter)
'l' = Count time of sample and blank, minso E = Fractiona1 Am-241 counting efficiency V = corrected air flow of sample, m3 2.22 = No. of dpm per pCi 117
. .. ...~
.-::~::-*--.....**-:-* ....*:***- :~.,*-----":'"""-* *-.--- --*~-
l
.. I 2-sigma error (pCi/m 3 ) = (l.96*(G+B)l/ 2 )~A (G-B)
A = Gross alpha activity, pCi/m 3 G = Sample gross counts
=
B Background counts (from blank filter) caiculation of lower limit of detection: A sample activity is assumed to be LLD if the sample net count is less than 4.66 times the standard deviation of the count on the blank. LLD(pCi/m3 ) = 4.66
- ca) 1 / 2
{2~22)*(E)*(V)*(T) B = Background counts (from blank filter) E = Fractional Am-241 counting efficiency v = corrected air flow of sample, m3 T. = Count time of blank, mins. 118
- SYNOPSIS OF TELEDYNE ISOTOPES **PROCEDURE ANALYSIS OF AIR !?ARTICULATE FILTEHS.FOR GROSS ALPHA AND-BETA The air filter is first stored for 2 to 5 days from date of receipt to allow for decay' of the radon-thoron daughters. It is then placed in a stainless steel planchet which has been coated in the center with ruJ:lber cement. The filter is then counted for.beta activity and suosequently repeat counted for alpha activity (at a different voltage setting) in a Beckman-Sharp Wide Beta II automatic alpha-beta counter.
Gross alpha and beta activity (pCi/m3 ) are computed as follows: A = {G/T ~B) % qm~((G/T +B)/T)l/2 (2.22*V>11Y*D*E) (2o22*V'*Y*D*E) Where G = Total. sample counts B = Background counts per minute T = Sample count time, mins. 2.22 = dpm/pCi v = Sample volume, m3 Y = Chemical yield (Y = 1 in this case) D = Decay factor from collection to count date (D =1 in this case) E = Counter efficiency crm ::a* MUl.tiples of ccmntinq error. If the net activity (G/T -B) is equal to or less than the counting error, then the activity is considered to be the minimum detectable level, or MDL. where MDL = 3*(2*B/T)l/2 (2o22*V*Y*D*E) Varia.l:lles are as previously defined
SYNOPSIS OF:PSE&G-RESEARCH CORPORATION l?ROCEI;JURE GROSS ALPHA ANALYSIS OF WATE~ SAMPLES - The sample is thoroughly miXed. Then, a 250ml portion.of sample and an equal volume of deionized water blank are acidified with dilute sulfuric acid. Barium carrier is added and the sample heated to 50°C in order to help pre-cipitate barium sulfate. Maintaining the same temperature for the remainder of the procedure, iron carrier is then introduced. After a 30 minute equili-bration period, the sample is neutralized with dilute ammonium hydroxide to precipitate ferric hydroxide. The mixed precipitates are then-filtered onto a membrane filter, dried under -an infrared heat lamp, weighed and mounted on a stainless steel planchete The sample is then alpha-counted for lOO minutes on a low background gas proportional counter, along With a U-238 source of the same geometry. The blank is treated in the same manner as the sample. Water samples found to be excessively turbid due to the presence of suspended organic material require pretreatment of this material for the purpose of keeping the final sample thickness to a minimum. This is accomplished by filtering a measured aliquot of the sample (while the filtrate is set aside) and ashing the collected residue in a crucible. A blank of the same volume is handled in the same manner. Whatever leftover sample residue remains,after the ashing,is dissolved in concentrated nitric acid and passed through a hardened fast filter paper and combined with the sample- filtrate. The combined sampl is then neutralized with dilute ammonium hydr'oXide. From this point, both sample and-blank are acidified with dilute sulfuric acid. Barium carrier is added and the sample is heated to so 0 c in order to help.precipitate barium sulfate. Maintaining the same temperature for the remainder of the procedure, iron carrier is then introduced. After a 30 minute equilibration period, the sample is neutralized with dilute ammonium hydroXide to precipitate ferric hydroXide. The miXed precipitates are then filtered onto a membrane filter, dried under an infrared heat lamp, weighed and mounted.on a stainless steel planchet. The sample is then alpha-counted for the appropriate time on a low - background gas proportional counter,- along with a U-238 source of the same geometry. The blank is treated in the same manner as the sample. calculation of Gross Alpha Activity: Result (pCi/L) = (G-B)/T (2.22)*(E)*(V)*(S) G = Sample gross counts B = Background counts (from blank sample) T = count time of sample and blank E. = Fractional counting efficiency from U-238 source
- .. ** v = Sample volume, liters s = Normalized efficiency regression equation as a function of thick-ness 2.22 = No. of dpm per pCi 120
2~sigma. error. (pCi/L)- = (l.96*(G+B)l/?)1iA ** * * (G-B) A= Gross alpha activity, pCi/L G = Sample gross counts .. B = Background counts (from blank sample)
.-.'} :
... ' ~
..* .. -:--,- ~,- .* - -*- *-.:***--,.. -.*****-**'7"-*-**," , ___ _ -** *_--.. ~--:---.,.---- ......... ,__ .... - ..--- ****--* - .
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE GROSS BETA ANALYSIS OF AIR PARTICULATE SAMPLES . After allowing at least a three-day (extending from the sample stop date to the sample count time) period for the short-lived radionuclides to decay out, air particulate samples are counted for gross beta activity on a low back-ground gas proportiona1 counter. Along with a set of air particulate samples, a clean air filter is included as a blank with an sr-90 air filter geometry
.beta counting standard.
The gross beta activity is computed on the basis of tota1 corrected air flow sampled during the collection period. This corrected air flow takes into account the air pressure correction due to the vacuum being drawn, the correction factor of the temperature-corrected gas meter as well as the gas meter efficiency itself. calculation of Gross Beta Activity: Air flow is corrected first by using the* following equations: p = (B-V)/29.92 p = Pressure. correction factor B = Time-averaged barometric
.. pressure durinq samplinq period * *
"Hg v = Time-averaged vacuum during sampling period, "Hg 29 *.92 = Standard atmospheric pressure at 32°F, "Hg V = F*P*0.946*0.0283 E F = Uncorrected air flow, ft 3 0.946 = Temperature correction factor from 60°F to 32°F 0.0283 = CUbic meters per cubic foot E = Gas meter efficiency (= %
efficiency/100) v = corrected air flow, m3 p = Pressure correction factor Using these corrected air flows, the gross beta.activity is computed as follows: Result (pCi/m3 ) = (G-B)/T ( 2
- 22 ) * ( E) * ( V )" G = Sample gross counts B = Background counts (from blank
- filter)
T =Count time.of sample and blank, mins. E = Fractiona1 Sr-90 counting efficiency
- v =corrected air flow of sample, m 2.22 = No. of dpm per pCi
- j
.i
' 122
- 2-sigma. error (pCi/m3 ) = (l.96,..(G+B)l/2)*A (G-8)
A = Gross beta activity, pCi/m 3 G = Sample gross counts B = Background counts (from blank filter)
- ca.J..culation of lower limit of detectiong A sample activity is assumed to be LLD if the sample net count is less than
. i 4.66 times the standard deviation of the count on the blank.
LLD(pCi/m3) = 4.66 "' (B)l/2 (2.22)*(E)*(V)*(T} B = Background counts (from blank filter) E = Fractional Sr-90 counting efficiency v = Corrected air flow of sample, m3 T = count time Of blank, mins. i_
- 1
. ,j
SYNOPSIS OF TELEDYNE I.SOTOPES PROCEDURE* . .._,_ **--* ~ _,__ -* .. ANALYSIS OF AIR PARTICULATE*. FILTERS* FOR *GROSS ALPHA .AN:El BETA* --- The ai.r filter is .first stored for 2 to 5 days from date of receipt to allow. for decay of the radon-thoron daughters. It is then placed in a stainless steel planchet which has been coated in the center with rUbber cement. The filter is then counted for beta activity and subsequently repeat counted for
- alpha activity (at a different voltage setting) in a Beckman-Sharp Wide Beta II autQmatic alpha-beta counter.
Gross alpha and beta activity (pCi/m3 ) are computed as follows: A= (G/T -B) +/- ~m*((G/T +B)/T)l/2 (2.22*V*Y*D*E) (2.22*V*Y*D*E) Where G = Total sample counts B =Background counts per.minute T = Sample count time, mins. 2.22 = dpm/pCi V = Sample volume, m3 Y = Chemical yield (Y = l in this case) D = Decay factor from collection to count date (D =l in this case) E = Counter efficiency
~m = Multiples of counting error If the net activity (G/T -B) is equal to or less t.han the counting error, then the activity is considered to be the minimum detectable level, or MDL.
where MDL = 3*(2*B/T)l/2 (2.22*V*Y*D*E) Variables are as previ~usly defined 124 .. , ' I .* * . F *
-~---*-.-**-*--*----;'*-*--*--.-- ~-----~~- :7-**-*-~,.:-*:----~--.,.-.-~* -~ ----..--------.~
1*.* SYNOPSIS OF PSE&G RESEARCH CORl?OaATION PROCEDURE GROSS BETA ANALYSIS OF WATER SAMPLES The sample is m.iXed thoroughly. Then, a l.O liter portion is removed from the potal:!le, rain or well water container and 250ml taken from each surface water. A deionized water blank is prepared for each di.fferent volume of sample (e.g. l.O liter blank for l.O liter samples and 2SOml for 250ml samples). All samples and blanks are then evaporated on a hotplate until the volume approaches 20 to 25ml. At that point, the samples and blanks are transferred to tared stainless steel ribbed planchets and evaporated to dryness under an infrared heat lamp. They are sUJ:lsequentlY cooled in a desiccator, weighed and counted on a low background gas proportiona.1 counter along with an sr~90 source of the same geometry. calculation of Gross Beta Activity~ Result {pCi/L) = (G-B)/T (2.22)*{E)*V)*(S) G = Sample gross counts B = Background counts (from blank sample) T = Count time of sample and. blank E. :.:;, Fractional counting efficiency
. * . <'*from sr~9o source v ~ Sample volume, liters S ~ NormaL.ized efficiency regression equation as a function of thick=
ness 2.22 = Noe of dpm per pCi 2-sigma error {pCi/L) = (l.96*(G+B)l/2)*A (G--B) A = Gross beta activity, pCi/L G = Sample qross counts B ~ Background counts (from blank
.... -:-; sample)
. . ~
- -~
-~{*'.jt'.-~-~ _>[
. **.r* -: .:
125 _._.-' l
._. ..,....~.,...~:;- .-.~-:- :-:-*-=-~-=- *:--- -.,--* ***-*** - - , .. ---**,****---* *-* --
SYNOPSIS OF l?SE&G RESEARCH CORPORATIO
N. PROCEDURE
ANALYSIS OF WATER FOR .POTASSIUM 40 A 60 ml aliquot of water sample (with the exception of rain water) received by the Research and Testing Lal:loratory is first acidified to pH <2 With con-centrated nitric acid and then analyzed. for potassiwn by the following Atomic Absorption Spectrophotometry method: potassiwn standards of known concentra-tion (similar to that of the unknowns) are first prepared. An aliquot of each sample and standard is pipetted into stoppered flasks. In addition, a duplicate sample, ERA standard and blank water sample are likewise pipetted into their respective flasks. A solution consisting of 4% sodiwn is diluted 1:1 with water and then added to all the flasks. Depending on the AA instrument used, a calibration curve is prepared from the standards after which the samples are ~hen run. If the al:lsorbance of any sample is higher than the upper standard used, the sample is then either diluted and re-run, the burner head turned 90°, a more concentrated standard added to the calibration curve or a less sensitive wavelength used. Tne results, reported in parts per million (ppm), are converted to pCi/L by means of a computer program. Calculation of K-40 Activity: K-40 Activity (pCi/L) = 0.85*C 0.85 = Proportionality constant for converting ppm to pCi/L c = Potassium concentration, ppm
. ~
' 126
--------*~* ----;---**- ----:---- - -.-:-*~--:--- ~:--.:------:**-*-:r---:-.,--:--=-;-:-;-**-**.--~----.- .----*:--.** ..
- ----~--.-*--::;---.~: --,---..~*~7*:*-- *-*--***-~ --.-~---~ ...
SYNOPSIS . OF' PSE&G RESEARCH CORPORATION . PROCEDURE .* ANALYSIS OF WATER FOR TRITIUM ApproXj.mately SOml of raw sample is mixed with sodium hydroxide and potassium permanganate and is distilled under vacuum" Eight mi of distilled sample is mixed with lOml of Instagel liquid scintillation solution, and placed in the liquid scintillation spectrometer for counting. An internal standard is prepared by miXinq Sml of sample, lOml of Instagel, and o.lml of a standard with known activity. The efficiency is determined from this. Also prepared is a blank consisting of Sml of distilled low~tritiated water and lOml of Instagel, to be used for a background determination. This is done for each pair of samples to be countedc Activity is computed as follows: A (pCi/L) = (G-B)*(lOOO) 2.22*(E)*(V)*(T) A = Activity B = Background count of sample G = Gross count of sample E = Counting Efficiency v = Aliquot vol.ume (ml,) I T = count. time (min)
*'" 2o22 - DPM/pCi .
1000 = Number of m.l per L Efficiency (E) is computed as followsg E = (N)*(D)
.A' N = Net CPM of spiked sample D = Decay factor of spike A' = DPM of spike N is determined as follows:
N = C~(G/T)
- ....... C = CPM of spiked sample G = Gross counts of sample
.~
T = Count time (m.in) The associated error is expressed at 95%-confidence l.imit,.as followsg l.96*(G/T2 +B/T 2 ) 1 /2 ~(l000) 2.222 (V) * (E)
- . J
*i Samples are designated LLD if the activity is less than the following value:
LLD (pCi/L) == (4o66)*(B) 112.,ciooo) 2.22*(V)*(E)fl(T)
SYNOPSIS OF CONTROLS FOR ENVIRONMENTAL .POLLUT.ION, INC., PROCEDURE TRITIUM ANALYSIS OF AQUEOUS FRACTION OF BIOLOGICAL MATERIALS An aliqtlot of fish or cral:J flesh is placed in a round bottom flask, along with 200ml of benzene, and the water removed via azeotropic distillation. Three milliliters of the extracted water is then mixed with aquasol cocktail (NEF-934 Aquasol cocktail, manufactured by New England Nuclear corporation). The resultant miXture is comprised of 19 percent sample in a clear gel-type aquasol and provides a tritium counting efficiency of approXimately 30 percent, when counted on a Beckman r..s~100 Liquid Scintillation Spectrometer. The efficiency of the counting system is determined by placing 6 tritium standards (certified by NBS) before each set of water samples to be counted. The counting efficiency is determined from these standards which are equal in activity but vary in the amount of quenching. All samples are counted for 500 minutes each.
. ' -. -~-- :"j
. ~ . ~
I
. *. ~
- ;_**. :)
-~
- . ,'*. *1 128"
._, )
-------~-~~~~------.-----~---~--:--:-*,.........,-.-:----:.---.-*--:--:-***-*--------~-->'--:----:--*:-:-*:::--:~- "":*---:-*""'-"-"7'-.~.-- '""*--:*-~-~:-------- ... ---- ---. --..,. **-* .... , .....
SYNOPSIS OF PSE&G RESEARCH CORPOAA'l'ION'
- PROCEDURE *.
GAMMA ANALYSIS OF AIR IOD!NE ApproXiJnately 30om3 of air is drawn through a SOml
- b_ed of triethylenediamine (TEDA)=impreqnated charcoal granules at a rate which closely corresponds to the :breathing rate of an adult male. The contents of the exposed air iodine cartridge are emptied into an aluminum sample can containing SOml of fresh TEDA-impregnated charcoal. The can is hermetically sealed and then counted on a gamma detector.
ca1culation of Gamma Activity~ The followinq are the ca.l.culations performed for the gamma activitYr 2 sigma 00 error and LLD: Result (pCi/m 3 ) = N*D =R (2.22}*(E)*(A)*(T)*(V) N = Net counts under photopeak D = Decay correction factor Atl.*EXP(At2) l.-EXP( 00 ~tl)
' . Acquisition live time
._*i tl. ~
~: : ..~:.-. t2 = Elapsed time from sample collection to start of acquisition
~ = 0.693/nuclide half life E = Detector efficiency A = Gamma al:>undance factor (no. of photons per disintegration)
T = Acquisition live time, mins. v = Sample volume, m3 2o22 ~ No. of dpm per pCi 2~sigma error (pCi/m3 ) = 1.9S*(GC+Bc) 112 *R N Ge = Gross counts BC ~ Background COW'ltS All other varia.Dles are as defined earlier. The LLD (pe1/m~) = 4.ss~cac) 1 12 ~o (2.22)~(E)~(A)*(T)*(V) i l
*I SYNOPSIS OF TELEDYNE ISOTOPES PROCEDURE ANALYSIS OF CHARCOAL. FILTERS FOR. I(JDINE-131 Charcoal car~ridges are analyzed for I-131 using a lithiwn-drifted germanium detector interfaced With a 2048 channel pulse height analyzer calibrated at l.O Kev per channel. Teledyne Isotopes employs one of three possible data acquisition and computation systems. The first, a Data General NOVA mini-computer, in series with the pulse height analyzer, calculates* the number of
.counts (and the standard deviation) in the peak region by performing a linearly-interpolated background subtraction. If no peak is observed, then only tne background is used (along with sample volume, collection date and length of count) to.determine the detection lilni.t. The activity or MDL of each nuclide is computed on an IBM 360. This semi-automatic system is in contrast with the other two data acquisition* and computation systems, namely, a Tracor Northern TN-11 and a Nuclear Data 6620, which perform all the above computations automatically. All resultant spectra are stored on magnetic tape.
.*,*\
*1
- ~
.i 130
.*_***.*1
***---- ------...---..,..--*--*--.*------.. - - --........---,-..*--..--~ ----.--- - - . - -.-7*--.--- --; ;-- -;--:.--'7 ........_-:-:-:-.:-- -*-**----~...,.--- --:-- - * ----*.~ .. --------~-~--:---:-*" --*-~~-~.--- ~--*-: - -~* _-* * - - * - - - - ---
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE ... ANALYSIS OF RAW MILK FOR IODINE-l3l Stable iodine carrier is equil.:U:lra.ted in a 4~J.iter volume of raw milk before two separate SOml batches of anion exchange resin are*introduced to extract iodine. After each batch has been stirred in the milk for an appropriate timef both are then transferred to an aluminum sample can where the resins are rinsed with demineralized water several times and any leftover rinsewater removed with an aspirator stick. The can is hermetically sea:led and then counted on a qamma. detector. C!a.lcUl.ation of I~l3l Activity: I~l3l Results (pCi/L) = (G->B)/T*(l.OS)x(H) (2.22)*(E)*(V)*(Y) G = Sample gross counts B = Background counts (from blank sample)
'I' = count time of sample and blank E = Eo*EXP{-A.*M) = efficiency equation where Ea ~ countinq efficiency at zero sample thickness A. = Self~cwsorption coefficient M = sample thickness, mg/cm2 v :.:: Sample volume, liters y = Chemical recovery =
R
~--
Rl+R2 where R = mq of I- recovered Rl = mq of I- carrier. added R2 = mq of intrinsic staole I- measured in sample
. ~~,_.;
l.05 = Correction factor for protein~
- -~ bound iodine H ~ J/(l-K)*EXP(L) = correction factor for I-131 decay during count.i.nq period J = (Oc693/8.0S)~(R/l440)
=
R count time, minutes l440 = Noc of minutes per day 8c05 = Hal,f~life Of I=l3lf days K "" EXP(~J) L = (0~693/8.0S)*N N = Elapsed ti.me (days) from mid= point of collection period to beginning of count time * . ~- *. : '
SYNOPSIS OF PSE&G .RESEARCH CORPOBATION~-PROCEDURE . BADIOSTRONTIUM* .ANALYSIS OF AIR FILTERS The air filters are placed in a sma1l beaker and just enough fuming nitric acid is added to cover t~e filters. A blank, composed of the same number of clean air filters, is prepared in the same way. Stable strontium carrier is then introduced into each sample and several fuming nitric acid leachings are carried out to remove the radiostrontium from the filter media. once this is done, the resultant nitrates are dissolved in distilled water and the filter residue is filtered out. Radioactive interferences are stripped out by coprecipitation on ferric hydroXide (yttrium strip) followed by a barium chromate strip. The strontium* is precipitated as a carbonate, which is dried and weighed. The samples and b~ank are then counted on a low background gas proportional counter and, again, at least 14 days later. The basis for this two count method is-that sr-90 and sr-89 are both unknown quantities requiring two simultaneous equations to solve for them. . calculation of sr-90 Activity:
- sr-90 Results (pCi/m3 ) = N4/R (2.22)*(E)*(E(l5)/E')*(S6)*(V)*(U)
= W2 where SS = A + B*M + C:11M~ (This is the general form of the norma1ized Sr-90 efficiency regression equation for one particular gas proportional counter, where A, B ~d Care regression coefficients.)
M = Thickness density of strontium carbonate precipitate, mg/cm2
- E(l5)/E' = Ratio of sr-90 efficiency at thickness value of l5mg/cm2 to sr-90 counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples)
E = sr-90 counting standard efficiency v = sample quantity (m3) u = Chemical yield
., N4 = (N2 Fl*Nl)/W1 = net counts due to sr-90 only i
1
- *\
*1 Il = l - EXP ((-0.693/2.667)*tl)
I2 = l - EXP ((-0.693/2.667)*t2) tl = Elapsed time from Y-90 strip to first count
. *: . ,.. j 132
.. j
- - - - * ---*-* - ~--- --*--- ----_~.. *-....--*-----**-~-~-; -:-- *. .-.---'"-~*--::"':' . ,:--~~-"--::--*-;---- - -- --~... -~*--:-:--=*~---~-:* -* :--~--.,---- .,.- ---- *------, ... -* - - - -- - - - *:- ....... - ..... - *. --
t2 = Elapsed tJ.me from. Y-90 strip* to second count*** - 2.667 = Half-life of Y-90, days R1 =D + E*M + F*M2 (This is the general. form of the regression equation for Y-90 effwy/sr-90 eff'Y ratio for one particular gas proportionaJ. counter, where D, E and F are regression coefficients.) N2 =X - Y, where X and Y are recount gross counts and background counts, respectively Nl = Xl ~ Ylu where Xl and Yl are initi.a.l gross counts and background counts, respectively 2.22 = No. of dpm per pCi Fl= EXP ((-0.693/2.667)*t2) i R = Count time of sample and blank Using the same variable definitions as above, the 2-sigma error for sr-90 (pCi/m3 ) = Again, keeping the same variable definitions, the LLD for sr-90 (pCi/m3) =
+ (Xl+Yl1*Flj l/:2 Wl .
ca.J.culation of sr-89 Activity: sr-89 Results (pCi/m3 ) = N6/R
. (2.22)*(E)*(E(l5)/E')*(S7)*(V)*(U)*(F9)
S7 ~ G + H*M + I*M2 ('rh.is is the general. form of the normalized sr~89 efficiency regression equation for one particular gas proportional
*1 counter where G, Hand I are regression coefficients.)
N6 = Nl - N7*(l + Rl*Il) H'1 = (N2 ~ Fl*Nl)/Wl (This represents ec:runts due to Sr=90) E(l5)/Ew = Ratio of sr-89 efficiency at thickness value of l5mq/cm2 to sr countinq standard efficiency run at the time of instrument cal.;U:)ration (This standard is run with each group of environmental stront.iwn samples).
---..---.-~*- .--------,--:-*-*....---..------*- :-'..,.........,:--.-0*~**.-.*-:;- -*.....,-.-**-**--~-----------~~ .. -------..-,......-~~-*-- *.-;--o- **-~:-""..,_ **. ,-. -::---:-*:--.--**-****--. *--**** *-----: ~':'"*---*-~* ..* , "n ---* - * - ... - - * - ** ** - - - - ....
F9 =EXP _((-0.693/S0.5)~t) t =Elapsed time from midpoint of collection.period.to time of recount for milk samples only. For all other samples, this represents the elapsed time from sample stop date to time of recount. 50.5 = Half-life of Sr-89, days All other quantities are as previously defined. The 2-sigma error for sr-89 (pCi/m3 ) = 2* (sa2+s92)2 ~W3 (Nl - N7*(l+Rl*Il)) S9 = (Xl+Yl).1 / 2 All other variables are as previously defined. Keeping the same variable definitions, the LLD for sr-89 (pCi/m3 ) = 4.66*(sa2 +s9 2 ) 1 12
*. ~:
*--* *.;*i
. i
- .: *. j 134
*** t
*-.; i
-----.----~ ... - - - - - - - _ _ _ _ ..,.....:. _ _* -
** ----.---~.-- - - * --~---------*-:";"".,- ---*- ___ _,, _ _ _ _,_"""7 - ----- - - -----_:." ~ ** - **..-- - --- -- - - -*----- - -* -* -- - - -~. - -
SYNOPSIS OF *TELEDYNE *ISOTOPES PROCEDURE.* ANALYSIS OF COMPOSITED AIR PARTICULATE FILTERS FOR RADIOSTRONTIUM The composited air filters are leached with concentrated nitric acid, with
*heating, in the presence of strontiwn carriero After adding deionized water, the sample is gravity filtered through a paper filter and the filtrate diluted further with additional deionized water, cefore ceing split into two equal parts. One part is put aside for gross alpha analysis. and the other part evaporated on a hotplate to a small volume. The sample is transferred to a centrifuge tu.be and fuming nitric acid added to form the strontium nitrate precipitate. After centrifuging and pouring off the supernate, the precipi=
tate is dissolved in deionized water and an iron scavenge performed. This marks the ~eginning of the Y~9o ingrowth period. centrifuging and discarding the precipitate, standardized yttr1Wl1 carrier is added to the supernate and the sample is set aside for 5 to 7 days. After this period, the sample is alkalinized with ammonium hydroXide and heated in a hot water oath to form
*yttrium hydroxide. After cooling, the sample is centrifuged and the supernate saved for Sr-89 determination. The precipitate is dissolved with dilute nitric and hydrochloric acids, and the yttrium precipitated as oxalate using saturated ammonium oxalate solution. The yttrium oxalate is mounted on a .
tared paper filter, oven dried, weighed and counted on a gas proportional counter. 'l'he sample is then recounted the fol1owing day to confirm the decay of Y-900 The superna.te, saved for sr-89 determination. is treated with saturated sodium car~onate solution to precipitate strontiwn carbonate which is filtered on a tared qlass fil:ler filter, oven-dried and likewise counted 200 minutes on a gas proportional. counter. These samples, however, are covered with an aomq/cm2 aluminum al:>sorber to stop the sr~90 beta emissions, thus allowing the Sr-89 betas to be counted aloneo The sr-89 activity (pCi/m3 ) is computed as follows: A = (G/T-Bc-Ba) +/- ~m*((G/T+Bc+Ba)/T)l/2 (2.22*V*Y*D*E) (2.22*V*Y*D*E) If the net activity (G/T -a) is less than or equal to the 2a: counting error, the activity is considered MDL
.! where MDL = 2*(2:eB/T)l/2 (2.22*V*Y:eD:sE) where G = Total. sample counts
'r = sample count time, mins
- Be =Background rate of counter,-cpm
..* Ba = Backqround addition from Sr-90 and ingrowth of Y~90 2o22 = dpm/pCi
*. v = sample volume, m3 y = Chemical yield of strontium D = sr~89 decay factor from midpoint of collection period to counting date.
E = sr-89 counting efficiency with 80 mq/cm2 alW!Unum absorber a:m = MUl.tiples of counting error
. I . 'i
The sr-90 activity (pCi/m3 ) .is computed as.* fol.lows; A = (G/T-B) +/-. ~m*((G/T+B)/T) 1 / 2 (2.22*V*Y*D*E) (2.22*V*Y*D*E) Y = Chemica1 yieJ.d of the mount or sample counted D = Decay factor from the colJ.ection to the counting date E = counter efficiency AJ.1 other variabJ.es are as previousJ.y defined. If the net activity (G/T-B) is less* than or equa1 to the 2~ counting error, the activity is considered MDL
. j where MDL = 2*(2*B/T) 1 /2 (2.22*V*Yi*Y 2*I*D*&)
~ : _;
.. ____ :_~--- - 136
-----~ -- ---------~---- -----=- -~*- -....---..--,,_-.-,....,--~-- - - -----:,.--------"<'"' --_--:--:,.........- ------~-- -**- ----- .,......,,__, -c------**-.----*.~-
SYNOPSIS OF PSE&G. RESEARCH CORPORATION PROCEDURE *. RADIOSTRONTIUM ANALYSIS.OF*RAW MILK StalJle strontiwn carrier is first introduced into.a nti.lk sample and into a distilled water sample of equal volume to be used as a blank. The sample(s) and blank are passed through cation resin columns which adsorb strontium, calcium, magnesium and other cations. These cations are then e1uted off with a TRIS-buffered 4N sodi~ chloride solution into a beaker and precipitated as carbonates. The carbonates are converted to nitrates with 6N nitric acid and, by aqidifying further to an* overall concentration of 70% nitric acid, strontium is forced out of solution somewhat ahead of calcium. Barium chromate precipitation is then performed to remove any traces of radium and rad.iobarium.e Strontium recrystallization is carried out to remove residual calcium which may have been coprecipitated with the initial strontium precip~ itation. Another recrystallization removes ingrown Y=90, marking the time of the yttrium strip * . The strontiwn is precipitated as its carbonate, filtered, dried and weighe~ to determine strontium recovery. The samples and blank are then counted on a low background gas proportional. counter and, again, at least 14 days later. The basis for this two-count method is that sr-90 and sr-89 are both unknown quantities requiring two simultaneous equations to solve for them. caiculation of 0 Sr~9o Activity: Sr-90 Results (pCi/L) = N4/R (2o22)*(E)*(E(l5)/E 9 )~(S6)*(V)li(U) where SS =A + B*M + C*M2 (This is the qenera1 form of the norma1ized Sr-90 efficiency regression equation for one particular gas proportional counter, where A, Band care regression coefficients.) M = Thickness density of strontium carbonate precipitate, mg/cm2 E(lS)/E' = Ratio of sr-90 efficiency at thickness va.l.ue of l5mg/cm2 to Sr-90 countinq standard efficienc:y run at the time of instrument cal.illration (This standard is run with each group of environmental strontium samples)
- E = sr~90 countinq standard efficiency
.l v .,, Sample quantity (liters) u "" Chemical yiel.d N4 "':! (N2 ~ FlsaNl)/Wl = net counts due t.o Sr=90 onl.y Wl,
"" ((l + R11iI2) ~ (1 + R1*Il}liFl)
Il,
"" l~ EXP ((=Oo693/2o667)*'t:l}
I I.
- - * ... **-* - * -----~.---: --:--*-:--,------.~~--,* ~*-----~-------. .. -~..,._-o";"..--;-T--*--,*:- **-* ,. ---~***.**-*-:- -;-*--:-* -----;
_.. ~
"j I2 = 1 - EXP {(-0.693/2.667)*t2) tl = Elapsed time.from Y-90 strip to first count*
t2 = Elapsed time from Y-90 strip to second count 2.667 = Half-life of Y-90, days Rl = D + E*M + F*M2 (This is the general form of the regression equation for Y-90 eff'y/sr-90 eff'Y ratio for one particular gas proportional counter, where D, E and F are regression coefficients.) H2 = X - Y, *where X and Y are recount gross counts and back~ound counts, respect~vely Hl = Xl - Yl, where Xl and Yl are initial gross counts and background counts, respe~tively 2.22 = Ho. of dpm per pCi Fl= EXP ((-0.693/2.667)*t2) R .:. count time of sample and blank Using the same variable definitions as above, the 2-sigma error for Sr-90 (.pCi/L) = 2* lix:u.l + (XJ+Y1}*F12]l/2* (Wl*W2). Lwi2 Wl J (H2-Fl*Nl) Again, keeping the same variable definitions, the LLD for sr-90 (pCi/L) = 4.66* ~ + (Xl+Yla*n 2J l/2 Lwi wi J calculation of sr-89 Activity: sr-89 Results (pCi/L) = N6/R (2.22)*(E)*(E(l5)/E')*(S7)*(V)*(U)*(F9)
= W3 S7 =G+ H*M + I*M2 (This is. the general form of the normalized sr-89 efficiency regression equation for one particular gas proportional counter where G, Hand I are regression coefficients.)
NS = Nl - N7*(l + Rl*Il) N7 = (N2 - Fl*Nl)/Wl (This represents counts due to Sr-90) 138
---...---*---:------.-'""'*--- * - - - - : - - - - . . . - - - - * - - * - * * - - -;-'~~-~-.---:----~. *---.-.-----:--. *-*---- :-~~---:--:-.,.*---:- "'7";"-:-:- ... - ---:-*.....-........-----_ -----~-- *~ --* *- .,-. -.--*-*: . **-- --~,---.--:- -.- ****.--* --- - . . ------ *- *-*. -
E(lS)/Ew = Rat:ro of.Sr;..99 effic.iencyat thickness va.J.ue of lSmq/cm2 to sr-90 counting standard ef.ficiency run *at the time ~.of instrument calibration (This standard is.run with.each grqup of environmental strontiwn samples) .*. t = Elapsed t.ilne from midpoint of collection period to time of recount for milk samples only. For all other samples, this represents the elapsed t.ilne from sample stop date to time of recount. All other quantities are as previously defined. The 2-sigma error for sr~eg (pCi/L) = 2* (sa2+s92)1/2 *W3 (Nl - N7*(l+Rl*Il)) sa =f<x+Yl + <xi+n~*Fl ~ l/2 Lw1 2 w1 J S9 = {Xl+Yl)l/2
. All.other varial:Jles are as previously definedQ i
' ..~
SYNOPSIS OF P.SE&G RESEARCH' CORPORATION* *PROCEDURE_*:.:*;.... - RADIOSTBONTIUMANALYSIS OF WATER Stal:>le strontium carrier is introduced into a water sample and into a distilled water sample of the same volume which is used as a blank. The sample(s) and blank arethen made alkaline and heated to near boiling"before precipitating the carbonates. The carbonates are converted to nitrates by fuming nit~ic acid recrystallization which acts to purify the sample of most of the calcium. Radioactive interferences are stripped out by coprecipita-tion on ferric.hydroxide (yttrium strip) followed by a barilim chromate strip. The strontium is precipitated as a carbonate before being dried and weighed. The samples and blank are then counted on a low background gas proportional counter and, again, at least 14 days later. The basis for this two count. method is that sr-90 and sr-89 are both unknown quantities requiring two simultaneous equations to solve for them. Since surface waters , _as well as some drinking water samples , have bee*n found to contain significant amounts of siaJ:>le strontium, a separate aliquot from each sample is a.!alyzed for stal:>le strontium. These results are used in correcting the chemical recovery of strontium to its true value. Calculation of sr-90 Activity: Sr-90 Results (pCi/L) = N4/R (2.22)*(E)*(E(lS)/E')*(S6)*(V)*(U)
- = W2 where SS =A + B*M + C*M2 (.This is the general form of the normalized sr-90 efficiency regression equation for one particular gas proportional counter, where A, Band care regression coefficients.)
M = Thickness density of strontium carbonate precipitate, mg/cm2 E(lS)/E' = Ratio of sr-90 efficiency at thickness value of 1Smg/cm2 to Sr-90 counting standard efficiency run at the time of instrume.nt calibration (This standard is run with each group of* environmental
. j' strontium samples)
.. E = sr-90 counting standard efficiency
.. j
~-:.
v = Sample quantity (liters)
.. j u = Chemical yield N4 = (N2 - Fl*Nl)/Wl = net counts due to Sr-90 only Wl = ((l + Rl*I2) - (l + Rl*Il)*Fl)
. ::~::J .*.*
- 1 Il = l - EXP ((-0.693/2.667)*tl) 140*
.. ,.')
i
-~~~-.--**~---~--*------~--.--~---.-,---~,-.-.:-*--*--.*--,-."""*:-~:---..-.*-*::--:-:_.*-:-*--*-*":'"r---:--.-*-----*-;**-*~v**-~*:-:""'-*"*-:**~,-*-.**-***-:*:-*;******-*-*
I2 =l - EXP ((-0~693/2.667)*t2) tl =Elapsed time*from Y-90 strip to first count t2 = Elapsed time from Y-90 strip to second count 2.667 = Half-life of Y-90, days R1 = D + E*M + F*M2 (This is the general form of the regression equation for Y-90 eff'y/Sr-90 eff 'Y ratio for one particular gas
- proportional counter, where D, E and F are regression c:oeffic.ients.)
N2 =X - Y, where X and Y are recount gross counts and background counts, respectively Nl = Xl - Yl, where Xl and Yl are initial gross counts and background counts, respectively 2.22 = No. of dpm per pCi Fl= EXP ((-0.693/2.667)*t2) R = count time of sample and :blank Using the same variable definitions as anovef the 2=sigma. error for sr-90 (pCi/L) = 2~ r~ + CX1+Yl~*F11l/2 1i (Wl*W2) LWl Wl (N2-Fl*Nl) Again, keeping the same variable definitions, the LLD for Sr-90 (pCi/L) = 4.66*[<x+Yl t (Xl+Yl~*Fl] l/2 Wl 2 Wl caJ.culation of sr-89 Activityg sr~eg ResuJ.ts (pCi/L) = N6/R
- , (2.22)*(E)*(E(l5)/E')*(S7)~(v)~(U)*(F9)
= W3 S7 = G + R1iM + I*M2 (This is the general form of the normalized sr~89 efficiency regression equation for one particular gas proportional counter wn.ere Gf H and I are regression coefficients * .)
N6 = Nl - N7*(l + Rl*Il) N7 = (N2 = Fl*Nl)/Wl (This represents counts due to Sr=90) 141
-*---* --.- ,, **-*--:----*-- *----*- --:-*---.*----~ ...-- -----. --.--.---.---~~-..,...-._,.... *- ---*.-*- *--~...--*- --
E(lS)/E' =Ratio of sr-89 efficien~y at* thickness valu~ of l5mq/cm2 to sr-90 count.inq standard efficiency run at the time*of i.ns-trument calibration (This standard is. run.with each qroup of environmental strontiuin samp~es)
- F9 = EXl? ((-0.693/50.S)*t) t = Elapsed time from midpoint of collection period to time of recount for milk samples only. For all other samples, this represents the elapsed. time from sample stop date to time of recount.
so~s = Half-life of. sr-89, days All other quantities are as previously defined. The 2-sigma error for sr-89 (pCi/L) = 2* (sa2+592yl/2 *W3 (Nl - N7*(l+Rl*Il)) sa =Rx+;) + cx1+na*r1j l/2 Lw1 wi S9 = (Xl+Yl) 1 / 2 All other variables are* as previously defined. Keeping the same variable defini.tions, the LLD for sr-89 (pCi/L) = 4.ss*(sa 2+s9 2 ) 112
. I
.t
- '_ .* 142
----------- ~-~-~----,-~--- ... ----~-----~---- - - - - - ---,..~------ .. - -~- --~--- ----~ - .-- - * ----- -- **. ..,.. - ~ -* **.---**~ ---.- -._::--.." .** *.*=-. r-****-:---**-.
SYNOPSIS OF PSE&G RESEARCH CORPORATION*: l?ROCEDURE - RADIOSTRONTIUM ANALYSIS OF VEGETATION, MEAT AND AQUATIC SAMPLES The samples are weighed (recorded as "wet" weight) as received, .before .being placed in an oven to dry at l00°Cc At the completion of the drying period, samples are again. weighed (recorded as "dry" weight) and then pulverized. A measured amount {quantity dependent on desired sensitivity) of the pulverized sample is first charred over a Bunsen .burner and then ashed in a muffle - furnacec The ash is fused with 40g sodium carbonate, along with 20mg strontium carrier, at 90o 0 c for 1/2 hour. After removal from the f~rnace, the melt is cooled, pulverized and added to 500ml distilled water and heated to near boiling for 30 minutes, with stirtingc The sample is filtered (filtrate discarded) and the carbonates on the filter dissolved with lgl nitric acid (HNa 3 ). The resultant nitrates are heated to dryness and are dissolved in 20ml di,stilled water before adding 60m.J. fuming HN0 3 o After calcium removal with anhydrous acetone, radioactive interferences are stripped out by coprecipitation on ferric hydroXide followed by. coprecipitation on barium chromate. *The strontium is precipitated as its carbonate, which is dried and weighed. The samples are then counted on a low background gas proportional counter and, again, at least 14 days later. The basis for this two-count method is that ~r-90 and sr-89 are .both unknown quantities requiring two simultaneous equations to solve for them *
- caicuiation of sr-90 Activity:
Sr=90 ResUl.ts (pCi/kq wet) =
= W2
( 2 e 22 ) "' ( E) "' ( E ( 15 ) /E: i N4/R
) .... (SS ) "' ( V ) * ( u.)
where SS =A + B*M + C*M2 (This is the general form of the normalized sr-90 efficiency regression equation for one particular gas proportional counter, where A, Band care regression coefficients.) M = Thickness density of strontiwn carbonate precipitate, mg/cm2 E(l~)/Ev = Ratio of sr~9o efficiency at tlti.ckness va.J.ue of l5mg/cm2 to. sr~9a counting standard efficiency run at the time of instrument Cal.illration ('rhiS Standard is run With each g'I'OUp Of environmental strontiwn samples) E = sr-90 countinq standard efficiency V = Sample quantity (kq wet) u = Chemical yield N4 = (H2 Fl"'Hl)/Wl. = net counts due to sr~9o only
-*-- ---~---*- ~ *-*- - -------.-*--*--*------........----:---.,.-.-:-- **-:-*-***--,-;7"--'"':'"':" -~.-- .. -* . --.----- *- - - - - .-* - *- -.------****. - - ..*. --- ----- - .*.
Il = l -*EXE' ((-0.693/2.667)*'!:1) I2 = l - EXE' ((-0.693/2.667)*t2) tl = Elapsed time from Y-90 strip to first count t2 = Elapsed time from Y-90 strip to second count 2.667 = Ha1f-life of Y-90, days Rl = D + E*M + F*M2 (This is the genera1 form of the regression equation for Y-90 eff'y/Sr-90 eff'Y ratio for one particular gas proportiona1 counter, where D, E and F are regression coefficients.) N2 =X - Y, where X and Y are recount gross counts and background counts, respectively' Nl = Xl - Yl, where Xl and Yl are initia.J. gross counts and background counts, respectively 2.22 = No. of dpm per pCi Fl = EXP ((-0.693/2.667)*t2) R = count time of sample and blank
-~ Using the same varial:lle definitions as above,
*' the 2-siqma error for Sr-90 (pCi/kg wet) =
2*r~ + (X1+Y1~*F111/2* (W1*W2l Lw1 w1 (N2-Fl*Nl) Again, keeping the same variable definitions, the LLD for Sr-90 (pCi/kq wet) = 4.66* ~~;> + (Xl+Y1l*F121 l/2 calculation of sr~99 Activity: Sr-99 Resul.ts (pCi/kq wet) = N6/R
;:*! (2.22)*(E)*(E(l5)/E')*(S7)*(V)*(U}*(F9}
.~
= W3 S7 = G + H*M + I*M2 (This is. the genera1 form of the normaJ.ized Sr-89 efficiency regression equation for one particular qas proportional counter where G, Hand I are regression coeff:Lcients.}
N6 = Nl - N7*(1 + Rl*Il)
. ~
- = ***:
144
~--' - - _______ + _ _ _r -,.--------~-.-~-r.*..,__,....__~,.-,-,---. -------~--*-*---;**.-* -******---..-.,....*--*-:----,....---,--~---."""": -*"":-.-:~--" -,...-.~*,...._,***** ** ****.-- -~*-.**-~~; *- --..~-* -**-:; . e-:** ;- -*t~-
-N7 = (N2 - Fl:s.Nl)/Wl (This represents counts.due to Sr=90)
E(lS)/E' = Ratio of sr-89 efficiency at thickness *value of l5rng/crn2 to sr-90 counting standard efficiency run. at the.time* of instrument caJ..il'.>ration (This standard is run with each group of environmental strontium samples) F9 =EXP ((-0.693/50.S)*t) t = Elapsed time from midpoint of collection period to time of recount for milk samples only. For all other samples,_ this represents the elapsed time from sample stop date to time of recount. so.s = Half-life of sr-89, days A1l other quantities ~e as previously defined. The 2-sigma error for sr-89 (pCi/kg wet) = 2~ (sa 2 +s9 2 ll/2 1lW3 (Nl - N7*(l+Rl*Il)) SS =li.x.+/-..tl_ + (XJ+/-yJ~*FJJ l/2
~ Wl S9 = (Xl+Yl)l/2 Keeping the same variaJJle definitions, the LLD for sr-89 (pCi/kg wet) =
4.ss~csa 2 +s9 2 > 1 1 2
/
* * * - " *r*-* **--;-**--.--* *-* .... - - - --~--.,***. -
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE.* RADIOSTRONTIUM. ANALYSIS OF. BONE AND SHELL The bone or shell is first physically separated from the rest of the sample* before being broken up and boiled in 6N sodiwn hydroXide (NaOH) solution for a brief time to digest remaining flesh/collagen material adhering to the sample. After multiple rinses with distilled water, the bone/shell is then oven dried and pulverized. An aliquot of the sample is removed, weighed and ashed in a muffle furnace. Then, in the presence of strontiwn carrier and cesiwn holdl:lack carrier, the radiostrontium is leached out of the ash by boiling in diluted nitric acid, after which the sample is filtered. The sample is then treated with concentrated (70%) nitric acid and boiled
*. ~
until strontiwn nitrate crystallizes out. The strontiwn nitrate is freed of calcium by repeated fwning nitric acid recrystallizations*. From this point on, any radiological impurities are removed by coprecipitation with ferric hydroXide followed by coprecipitation with bariwn chromate. The strontium is precipitated as strontiwn carbonate, which is dried, weighed, then beta.- counted on a low background gas proportional counter. A second count is performed at least 14 days later. The basis for this two-count method is that Sr-90 and Sr-89 are both unknown quantities requiring two simultaneous equations to solve for them. caJ.cuJ.ation of sr-90 Activity: - . sr-90 Results (pCi/kg dry) = N4/R
~.
(2.22)*(E)*(E(l5)/E')*(S6)*(V)*(U)
= W2 where S6 =A + B*M + C*M2 (This is the general form of the normalized sr-90 efficiency regression equation for one particular gas proportional counter, where A, Band care regression coefficients.)
M = Thickness density of strontium carbonate precipitate, mg/cm2
- .i E(lS)/E' = Ratio of sr-90 efficienC:y at thickness val.ue of l5mg/cm2 to sr-90 counting standard efficiency run at the time of instrwnent Calibration (This' standard is run with each group of environmental -. t strontiwn samples)
E = sr-90 counting standard efficiency V = Sample quantity (kg dry)
*~: !
u = Chemical yield N4 = (N2 - Fl*Nl)/W1 = net counts due to sr-90 only
-*- -* ." ~-~'--
- Wl IJ.
= ((l + Rl*I2) ~ (l + Rl*Il)*Fl)
= l - EXP ((-0.693/2.667)*tl)
I2 = l - EXP ((-0.693/2.667)*t2) tJ. = Elapsed time from Y-90 strip to first count t2 = Elapsed time from Y-90 strip to second count 2.667 = Half-life of Y-90, days lU =D + E*M + F*M2 (This is' the general form of the regression equation for Y~90 eff'y/sr~90 eff 'Y ratio for one particular gas proportional counter, where D, E and F are regression
.coefficients. )
N2 =X - Y, wnere X and Y are recount gross counts and background counts, respectively Nl = X1 - Yl, wnere Xl and Yl are initial gross counts and background counts, respectively 2.22 = No. of dpm per pCi Fl= EXP ((-0.693/2.667)at2) R = Count t.ime of sample and :t:llarut Using the same variable definitions as above, the 2-sigma error for sr-90 (pCi/kg dry) = Again, keepinq the same variable definitions, the LLD for sr-90 (pCi/kg dry) = 4.66111 ~~p + (Xl+;;:~*Flj 1/2 caJ.cul.ation of sr~89 Activityg sr~89 Results (pCi/kg ctry) = N6/R (2.22)*(E)~(E(l5)/E')*(S7)~(V)*(U)~(F9) S7 =G + H~N + I*M2 (This is the general. form of the normalized sr~89 efficiency regression equation for one particular gas proportional counter where G, Hand I are regression coefficients.) i
. l
**- -----.---- ---:--- * * - - - ----.--*--- .-----..,--- *0*--..~~---* ---;- *--. -~- .,..*. -**- ----- -- --- ---- ---~-;-~----r--- ..... ,. .. -**------ - :_ --~--- -**-- -- -- ****--* ------, ....... *- ---- .. ---*-*- *c-:-.--- --*
N7 = (N2 - Fl1tNl)/Wl (This represents .counts. due to sr~9a) E(lS)/E' = Ratio of Sr-89 efficiency at thickness value of l5mg/cm2 to sr-90 counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples) F9 =EXP ((-0.693/50.S);tt) t = Elapsed time from midpoint of collection period to time of recount for milk samples only. For all other samples, this represents the elapsed time from sample stop date to time of recount. so.s = Half-life of sr-89, days All other quantities are as previously defined. The 2-sigma error for sr-89 (pCi/kg dry) = 21' (sa2+s92)l/2 *W3 (Nl - N71t(l+Rl*Il)) SS = r~~) + (X1+~~*Flj l/2 S9 =* (Xl+!l)l/2 All other varialJles are as previously defined. Keeping the same varialJle definitions,. the LLD for Sr-89 {pCi/kg dry) = 4.66*{S82 +s9 2 ) 1 / 2
... ~
)
'l
- _.,. :**i
. ' ~
*t
--.--.--~-""- --.-~-::-**-.--:- *-;---,-*-*-'--- - -- - -~ . - - .....
- SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE' RADIOSTRONTIUM ANALYSIS OF SOIL AND SEDIMENT After the soil or sediment sample has been dried and pulverized, a SOgm aliquot is added to approx:ima.tely 1/3 - liter concentrated hydrochloric acid (HCl), containinq Sml of strontium carrier (lOmq sr++/ml). A blank con-taininq only 1/3 - liter concentrated HC~ and Sml strontiwn carrier is run in parallel with the sample. The samples are stirred viqorously for at least 30 minutes and then filtered. The filtrate is then diluted to a known volume and aliquots removed for stable str:ontiwn. The remaining sample is alka.linizeci with ammonium hydroXide to precipitate all the transitional elements. After filtering out these interferences, the filtrate is heated and sodium carbonate added to precipitate strontiwn and calciwn carbonate.
These carbonates are first filtered and then di.qested with 6N HN0 3
- Two
_fwn:i.nq (90%) mro 3 recrystallizations are then performed to remove calcium. Subsequently, radi.oactive impurities are removed by two precipitation steps, using ferric hydroxide and bariwn chromate as carriers. The strontium is precipitated as strontium carbonate before beinq dried and weighed. The samples are counted for beta activity in a low background gas proportional counter (Count time will vary, depending on the desired sensitivity.). There is a second count at least 14 days later. The basis for this two-count method is that sr-90 and Sr-89 are both unknown quantities requiring two simultaneous equations to solve for them. caJ.cUlation of sr-90 Activity~ sr-90 Results (pCi/kg dey) *= N4/R (2.22)*(E)*(E(lS)/E')*(S6)*(V)*(U)
= W2 where S6 =A + B*M + c~M2 (This is the genera.I. form of the normalized sr-90 efficiency reqression equation for one particular gas proportional counter, where A, Band care reqression coefficients.)
M = Thickness density of strontium. carbonate precipitate, mq/cm2 E(l5)/E' = Ratio of Sr-90 efficiency at thickness vaiue of 15mg/cm2 to Sr=90 countinq standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontiwa samples) E = sr-90 counting standard efficiency v = Sample quantity (kq dry) u = CheliCLcal. yield N4 = (N2 - Fl*Nl)/WJ. = net counts due to Sr-90 only
- Wl. = ((l + Rl*I2) - (l + Rl~Il)~Fl)
*-.--~---~--*-:--:---*--::___,,....-.-~ -.--7*..---.-*-*--..*--*----------- - --~*~,...--..,~--~~---***--*----~---~-- --* ----- *--- *- - -*----.----- -* ----~...,..--- .. ~---~ *---*
Il = l - EXP ( (-0 .693/2 .667) *tl) . I2 =l - EXP ({-0.693/2.667)*t2) tl = Elapsed time from Y-90 strip to first count t2 = Elapsed time from Y-90 strip to second count 2.667 = Half-life Of Y-90, days Rl =D + E*M + F*M2 (This is the general form of the regression equation for Y-90 eff'y/sr-90 eff 'Y ratio for one particular gas proportional counter, where o, E and F are regression* coefficients.) N2 =X - Y, where X and Y are recount _gross counts and background counts, respe(:tively Nl = Xl - Yl, where Xl and Yl are initial gross counts and background counts, respectively 2.22 = No. of dpm per pCi Fl = EXP ((-0.693/2.667)*t2) R = Count t;Lme* of sample and blank*
.*J
- Using the same varial:lle definitions as aJ:>ove, the 2-sigma error for sr-90 (pCi/kq dry) =
2*[CX+Y) + on+n~*F11 1 12 .. (Wl*W2) [ Wl2 Wl (N2-Fl*Nl) Again, keeping the same varial:lle definitions, the LLD for sr-90 (pCi/kq dry) = 4.66* Rx+;p + cxi+n~*F1J 1 12 [wi
- Wl
- calcul.ation of sr-89 Activity:
-j sr-89 Results (pCi/kq dry) = NS/R (2.22)*(E)*(E(l5)/E')*(S7)*(V)*(U)*(F9)
= W3
. i S7 =G + H*M + I*M2 (This is the general form of the normalized sr-89 efficiency regression equation for one -particular gas.proportional
.counter where G, Hand I are regression coefficients.)
150
*:-~---:* ,,.-----:-; ~ -----.-*---.*--- .... _ -.** -..--*;
N7 = (N2 = Fl~Nl)/Wl (This represents counts due to sr~90) E(lS)/E' =.Ratio of sr-89 efficiency at thickness value of 15mg/cm2 to sr-90 counting standard.efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontiwn samples) F9 =EXP ((-0.693/50.S)*t) t = Elapsed t.ime from midpoint of collection period to time of recount for milk samples only. For all other samples, this represents the elapsed time from sample stop date to time of recount. 50.5 = Half=life of Sr=89, days All other quantities are as previously defined. Th~ 2-sigma error for Sr=89 (pCi/kg dry) = 2* (se2+sg2)l/2 *W3 (Nl - N7*(l+Rl*Il)) SB =rc.x+/-Y.l + (Xl+Yla*Fl~ 1/2 [Wi2 Wl sg = cxi~u> 1 1 2 All other varial:lles are as previously defined *
'.---*----~--.*-..,..---** *-----.**.--- --*---**** -----~-------*-* - -~* ***--* - * -,***:i..-*
SYNOPSIS OF PSE&G RESEARCH CORPORATION.PROCEDURE ANALYSIS OF ENVIRONMENTAL SAMPLES FOR STA~LE STRO~TIUM It has been the practice of the Environmental Division to perform a stable strontium determination on any samples to be analyzed for strontium 90 and 89, i f they are likely* to contain significant amounts of the stable isotopes.. In the case of mineral (soil or sediment) or biological (bone and shell) media, an ashing and/or acid leaching is performed to extract the element{s) of interest. The removal of the aliquot is done early in the course of the radiostrontium analysis and involves the withdrawl of 25 ml of diluted leachate (soil and sediment only) from the regular sample, transferring it to a flask. Bone and shell are prepared by ash~ng 2 g of sample, digesting in 6N HCl, filtering out insoluble residues and then transferring to a flask. All, the above samples are analyzed by the method of Standard Additions, whereby each sample leachate is spiked with known concentrations of stable strontium. Absorbances for sample, spiked samples and blank are determined by Atomic Absorption Spectroscopy (AAS) and are then plotted graphically and the true concentration is then extrapolated. Chemical and ionization interferences are controlled by adding 1% or more of lanthanum as chloride to all samples to be analyzed. Stable strontium is then determined by AAS in the air-acetylene flame at the 460.7 run line. For analysis of water, a 60-ml aliquot of sample is removed, acidified to pH<2 with hydrochloric acid and analyzed by AAS as follows: A group of strontium standards (of similar concentration to: the unknowns) is prepared. Then, to 9 ml of each prepared sample'* blank and standard, is added 1 ml. of lanthanum oxide solution. These are ana,lyzed at 460.1* run by air"".'acetylene AAS, following the manufacturer's recommended instrument parameters. All. results (calculated as milligrams of strontium per liter) are then used to find the true chemical recovery of strontium based on both the amount of carrier added (only in the case of soil and sediment) and the quantity of strontium intrinsic to the sample.
. Sample calculation of corrected Chemical Recovery of Strontium in Soil and ~ -c *.
Sediment: Reported concentration of stal:>le strontium (mg/L):ll9 Volume of specimen (mll:2S (removed from lOOOml of diluted leachate) Proportion of sample used for aliquot: 0.025 Milligrams strontium in 25ml flask= (119mg/L) x (.025L/25ml) x (25ml)
= 2.98mg sr i
. ~ Since 2.98mg Sr represents the quantity of stable.strontium in 2 1/2 percent of the sample, total strontium (stable + carrier) in the full sample =
2.98mq Sr = 119 mg o.02s 152
-*--*-----*-~-~- ----- ...-.---~~-:"""">"*-:------.., .. -~- ..- . --~~ . -. .-:-~--.- -~-**.** *- -- -:--:-;:
~ ..
- Net weight of srco 3 precipitate.(mg): 125 Percent of Sr in precipitate: 59.35 Quantity of strontium recovered= (l25mg) x (.5935) = 74.2.
corrected chemical recovery of strontiwn = 74.2 = 0.623 ll.9.0 The calculations f_ollow the same sequence for :bone and shell samples. Sample ca.1.culation of Corrected Chemical Recovery of Strontium in Water~ Reported concentrations of stable strontium (mq/L)~ l.65
*volume of radiochemical water sample (liters): 2.0 Stable strontium in 2 liter sample = (l.65mg/t) x (2.0L)
= 3.30mg Quantity of strontium carrier added to sample (mg)~ 20.0 Total amount of strontium in sample (mg): 20.0 + 3.30 = 23.3mg Net weight of srco 3 precipitate (mg): 28.9 Percent of Sr in precipitate: 59.35 Quantity of strontium recovered= (28.9mg) x (.5935) = l7.2mg
- corrected chem.ical. recovery of strontium~ 17.2mq 23.3mq
~ .738 I
*~
--------::----.---'<-* -:----------*-- -- - ----- -* . -:--""7---~--- ----------* - *- --~- ----.. -- ------ .. ----- - * ------ ~ ----- -;---------- .... - ----* -- - - .. - . - *-*-- --- ------ --
SYNOPSIS OF PSE&G RES~RCH CORPORATION PROCEDURE GAMMA ANALYSIS OF A.IR PARTICULATE COMPOSITES At the end of each calendar quarter, 13 weekly air filters from a giv~n location are stacked in a two inch diameter Petri dish in chronological order, with the oldest filter at the bottom, nearest the detector, and the newest one on top. The Petri dish is closed and the sample counted on a gamma detector. The following are the calculations performed for the gamma activity, 2-sigma error and LLD: Result (pCi/m 3 ) = N*D =R (2.22)*(E)*(A)*(T)*(V) N = Net counts under photopeak D = Decay correction factor
.\.tl.*EXP(:\t2) 1-EXP(-.\.tl) tl = Acquisition live time t2 = Elapsed time from sample collection to start of acquisition A. = 0.693/nuclide half life
- E = Detector efficiency A = Gamma abundance factor (no. of photons per di~integration)
T = Acquisition live time, mins.
=
V Sample volume, m3 2.22 = No. of dpm per pCi 2-sigma error (pCi/m3 ) = l.96*(GC+Bc)l/2,.a N GC = Gross- counts BC = Background counts All other variables are as defined earlier. The LLD (pCi/m3) = 4.66*(Bc)l/2,.D (2.22)*(E}*(A)*(T)*(V} 154 -*** _]
. ., ...*-~- ... . ... *. -.
SYNOPSIS OF TELEDYNE ISOTOPES PROCEDURE: *. ANALYSIS OF AIR PARTICULATE FILTERS FOR GAMMA . Ai.r particulate filters are analyzed for gamma using a lithium~drifted germanium detector interfaced with a 2048 channel pulse height analyzer calibr~ted at 1.0 Kev per channel. Teledyne Isotopes employs one of three possible data acquisition and computation systems. The first, a Data General NOVA minicomputer, in series with the pulse height anaJ.yzer, calculates the _number of counts (and a one standard deviation). in the peak region by performing a linearly-interpolated background subtraction. If no peak is observed, then only the background is used (along with sample volumep collec~ tion date and length of count) to determine the detection limit. The activity or MDL of each nuclide is computed on an IBM 360. This semi-automatic system is in contrast with the other two data acquisition and computation systems, namely, a Tracor Northern TN-ll and Nuclear Data 6620 which perform all the above computations automatically. All resultant spectra are stored on magnetic tape.
. ~ .'~
.*. *1
-*1*
i .-' ::j
-~
- j
. *:_::,.I
,'I
'1".I
-. ,1
* .. _.J
.. . -~
l
.*.,. 1 ,/ .. ' ~ *. .~
SYNOPSIS OF PSE&G .RESEARCH .COREORl\TION PROCEDURE GAMMA ANALYSIS OF.RAW.MILK A well miXed 3.5-liter sample of raw milk is poured into a cal~rated Marinelli beaker along with 20ml of 37% formaldehyde solution (used as a preservative). After stirring, the sample is allowed to reach ambient temperature and then counted on a gamma detector.* calculation Of Gamma Activity: The following are the calculations performed for the gamma activity, 2-sigma error and LLD: Result (pCi/L) = N*D = R (2.22)*(E)*(A)*(T)*(V) N = Net counts under photopeak D = Decay correcti.on factor X. tl*EX1?(X.t2) 1-EXP(-x.tl) tl = Acquisition live time t2 = Elapsed time from sample collec-tion to start of acquisition
- x. = 0.693/nuclide half- life
** E = Detector efficiency A= Gamma aJJundance factor (no. of photons per disintegration)
T = Acquisition live time, mins. V= Sample volume, liters 2.22.= No. of dpm per pCi 2-sigma error (pCi/L) = l.96*(GC+Bc)l/2*R N GC = Gross counts
.. BC = Background counts
. . .*' l
*1 All.other variaJJles are as defined earlier.
The LLD (pCi/L) = - 4~66*CBc)l/2wo (2.22)*(E)*(A)*(T)*(V) _.. *~
. T'
~*. ..~. SYNOPSIS OF PSE&G RESEARCH* CORPORATION.. PROCEDURE GAMMA ANALYSIS OF WATER After thoroughly agitating the sample container, 3.5 liters of water sample is poured into a calibrated.Marinelli beaker and then counted on a gamma detector. ca1cu1ation of Gamma Activity: The following are the calculations performed for the gamma activity, 2-sigma error and IJ:.JJg Result (pCi/L) = Nao =R (2.22)*(E)~(A)*(T)*(V) N ~ Net counts under photopeak D = Decay correction factor
.\.tl*EXP(.\.t2) 1-EXP(-.\.tl) tl = Acquisition live time t2 = Elapsed time from sample collec-tion to start of acquisition
~ = 0.693/nuclide half life E ~ Detector efficiency A = Gamma. aJJundance factor (no. of
*pnotons per disintegration)
T = Acquisition live time, mins. V = Sample volume, liters 2.22 = No. of dpm per pCi 2-sigma error (pCi/L) = l.96*(GC+BC)l/2*R N GC = Gross counts BC = Background counts
;.! All other variatiles are as defined earlier.
'.*i The LLD (pCi/L) = 4.66~{BC)l/2.o (2.22)~(E)~(A)*(T)~(V)
.* 1*
.- I
- -I j
I 157
.. \------~ .. -..,. -~~-*-* --- . ***-------** - -- . - ---~-------::---*~----,...,.-.-,.--..,.,_... --* ---~-__... ... -- ..... -----.-,-.-..-- *--* - -------- ... ~ .... :**---- -- - - *-*~ ""* -. **.. - *-~ ., _,.
SYNOPSIS.OF PSE&G RESEARCH CORPORATION *PROCEDURE. GAMMA ANALYSIS OF SOLIDS several methods are employed in preparing solids for gamma anal.ysis, depending on the type of sample or sensitivity required. For high sensitivity anal.ysis of vegetation, meat and seafood, the sample is first weighed, then oven-dried to a constant weight. A ratio of wet-to-dry weight is computed before the sample is ground and compressed to unit density (lg/cm 3 ), whenever possible, in a tared al.uminum can. The can is weighed and then hermetical.l.y sea.l.ed and counted on a gamma detector. In most cases, a wet sample is prepared (assuming sensitivity can be met) by using a food processor to puree it. The sample is then poured into a cal.i-brated and tared clear plastic container until. a standard volume is reached. The sample is weighed and then seal.ad with a screw cap before gamma counting. Soil. and sediment samples are first oven dried until. a constant weight is achieved and then pul.verized. The sampl.e is added to a tared al.uminum can, compacted to a standard vol.lime and weighed. It is hermetical.l.y seal.ed and gamma counted. Benthic organisms are oven dried; followed by the physical. removal of any *
*obvious impurities-(such as shells or twigs). The dried organisms are weigh and then wet-ashed with.concentrated nitric acid~ After al.l solids have been digested, the sample is evaporated to near drYt1ess and the residual. sal.ts taken up with distilled water. The sample is filtered and the filtrate added to an al.uminum can. The* sample volume is brought up to the standard geometry with distilled water and the can hermetical.ly sealed before gamma counting.
calculation of Gamma Activity: The following are the calculations performed for the gamma activity, 2-siqma error and LLD: Result (pCi/kg) = N*D = R (2.22)*(E)*(A)*(T)*(V) N = Net counts under photopeak D = Decay correction factor.
>..tl.*EXP(>..t2) 1-EXP(->..tl) tl = Acquisition live time t2 = Elapsed time from sample collec-tion to start of acquisition
>.. = o.693/nuclide half life E = Detector efficiency A - Gamma abundance factor (no. of photons per disinteqration)
T = Acquisition live time, mins.
- v = Sample volume, kiloqrams 2.22 = No. of dpm per pCi
2~sigma error (pCi/kg) "" l.$l6"'(GC+Bc)l/4,.,e *. N GC = Gross counts BC = Background counts All other variables are as defined earlier. The LLD (pCi/kg) = 4.661'(Bc)l/2,.,o (2.22)*(E)"'(A)*(T)*(V)
/ *-.i
- J
---....-.** --.--,---------. -- -- -- ~-.- ---*--*- -~-;--------~--*.- ---*-*.--;**!----*--- *-""'.!**---~---- -----.-.---.---~-~-*-* -- ..... 7"'*-----.--"':,- ... --..---:-*---:--. *----. --- ' .... --- - - - .* ... *-*-- --**-**
---~ - -: SYNOPSIS OF TELEDYNE ISOTOPES PROCEDURE, ANALYSIS OF TELEDYNE ISOTOPES THERMOLUMINESCENT. DOSIMETERS These devices are rectangular Teflon wafers impregnated with 25% caso 4 :Dy phosphor. They are first annealed in a 2S0°C oven prior to exposure in the field. Following field exposure (for a 1-month or 3-month period) four separate areas of the dosimeter are read in a Teledyne Isotopes model 8300 TLD reader. The dosimeter is then re-irradiated by a standardized cs-137 source and the four areas are read again. Calculation of the environmental exposure is performed by computer, using the re-irradiation readings to determine the sensitivity of each area of the dosimeter. The readings of control dosimeters are sUbtracted to aJ.1ow for transit dose and system back-ground. The results are computed as follows: For. any given area of the dosimeter, the dose in mR is calculated by the following formula: DOSE = R * (REDOS~/RR)-AVC R = Initial reading of the area RR = Second reading of. the area (after re-irradiation) REDOSE = Re-irradiation dose, mR AVC =Average of control values, mR 4N where AVC = ~CDOSE/4H i=l H = Total number of control dosi-meters
*,*, CDOSE = CR*(CREDOSE/CRR)
CDOSE *= control area dose, mR CR = Initial reading of control area CRR = Second reading of the control area (after re-irradiation) CREDOSE = Re-irradiation dose of the control dosimeter, mR ' * . *i
**.l '
... '~
160
--~:---**----------- ....-.---~---:---~.-.-*"C'-..-.. - - ., ..-._ -7'1"----..-::-- ......
--~*------~...........,**- ---.----.--:---~-------------- .. -*~.~-----:--:-*--*-*-, *----* *-.---.-* ---.- - - .. *-:,-- .
APPENDIX E
SUMMARY
OF USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARISON STUDIES PROGRAM RESULTS
. j
. I
,: :*::j
~
~
l
)'
SUMMARY
O~ USEPA INTERCOMPARISON ~TUDIES PROGRAM_ Appendix E presents a
- summa.ry of the analytical* results for the 1986 USEPA Environraental Radioactivity Laboratory Intercomparison Studies Progr*am.
TABLE OF CONTENTS TABLE NO. TABLE DESCRIPTION E-1 Gross Alpha and Gross Beta Emitters in Water and Air Particulates ******************************* 164 E-2 Gamma Emitters in Milk, Water, Air Particulates and Food Products ***..*..**********.*******.*** 165 E-3 Tri ti um in Water ............* o ******************* 167 E-4 Iodine in Water and Milk ************************* 168 E-5 Strontium-89 and Strontium-90 in Air Particulates, Milk, Water and Food Products ****************** 169
- ~
1 i l
TABLE E-l USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM Gross Alpha and Gross .Beta Analysis of Water (pCi/L) and Air Particulate (pCi/filter) DATE ENV SAMPLE CODE PSE&:G EPA GRAND AVG MM-YY ENV ID MEDI-UM ANALYSIS Mean :!: s.d. Known Mean :!: s.d. Ol-86 EPA-WAT-ABl69 Water Alpha 3.6:1:0.3 3.0:!:8.7 3 .6:!:l.4 86-90 Beta 6.7:1:0.S 7.0:1:8.7 7 .2:1:l.8 03-86 EPA-WAT-ABl75 Water Alpha 18:1:3 15:1:8.7 13:!:3 86-374 Beta 8:1:1 8:1:8.7 10:!:3 03-86 EPA-APT-GABSl76 APT Alpha . l7:!:l 15+/-8.7 16+/-3 86-660 Beta 50+/-1 4"1+/-8. 7 51+/-6 04-86 EPA-WAT-Pl78 Water Alpha 18:!:1 17+/-8.7 15+/-4 86-512 Beta 29:il '35:!:8.7 32:!:5 05-86
.07-86 EPA-WAT-ABl80
'86-871 EPA-WAT-ABl89 86-1204 Water
*Water Alpha Beta*
Alpha Beta 8:1:1 14:1:1 6:1:1 lS:!:l 8:1:8.7 15:1:8.7 6+/-8.7 18+/-8.7 7:1:2' 15:!:3 6:1:2 18:1:3 08-86 EPA-APT-GABSl92 APT Alpha 24:1:1 22:1:8.7 22+/-4 86-1567 Beta 90:1:2 66:!:8.7 71+/-8 09-86 EPA-WAT-ABl94 Water Alpha 15:1:1 15:!:8.7 15:!:4 86-1766 Beta 8:1:2 8+/-8.7 10:!:3 10-86 EPA-WAT-Pl97 Water Alpha 44:!:1 40:!:8.7 36+/-10 '. '-i 86-2079 . Beta 19:!:1 51:1:8.7 47+/-6 ll-86 EPA-WAT-ABl99 Water Alpha 19:!:2 20:!:8.7 17+/-5 86-2666 Beta 16:!:1 20:1:8.7 21:!:3
- s.d. - one standard deviation of three individual analytical results
*** known value with control limits, indicating whether results are in agreement or disagreement
*** s.d~ - one standard deviation of acceptable results of all participating laboratories 164
.. \. .' J' TABLE E-2 USEPA ENVIRONMENTAL. RADIOACTIVITY LABORATORY INTE.RCOMPARSION STUDY PROGRAM Gamma Analysis of Milk, Water (pCi/L), Air Particulate (pCi/filte!-> and Food Product_s (pCi/kq) DATE ENV SAMPLE CODE PSE&G EPA GRAND AVG MM-YY ENV ID MEDIUM ANALYSIS Mean +/- s.d. Known Mean +/- s.d. 01~86 EPA-ORG-GS170 Food I~l:U <30 20:1:10.4 21+/-2 86~100 c:s~l37 14:1:1 15+/-8.7 17+/-2 K(l) 922:1:11 950+/-248 957+/-90 02-86 EPA~WAT-Gl71 Water cr-51 42+/-4 38+/-8.7 39+/-6 86-173 Co-60 18+/-1 18:1:8.7 18+/-3 Zn-65 41+/-2 40:1:8.7 41+/-4
.Ru-106 <ll 0 Cs-134 28:1:1 30:1:8.7 28+/-4 Cs-137 22:tl 22+/-8.7 22+/-3
- 04=86 04-86 EPA=APT=GABSl76 86-660 EPA=WAT-Pl78 86=512 APT Water cs-137 co-60 cs-134 cs-137 lOi:l
- 9:!:1 Sil 6+/-1 10:1:8.7 10:.tS.7 5:t8.7 5:!:8.7 ll:t2 10+/-2 S:U 6:U 06-86 EPA-MLK-GS184 Milk I-131 43:1:1 41:1:10 .6 44+/-4 86-1071 Cs-137 37+/-1 31+/-8.7 37+/-3 K(l) 1660:1:10 1600:1:140 1600:1:110 06-86 EPA-WAT~Gl81 water cr-51 <18 0 o 86-921 Co-60 66il 66:1:8.7 64+/-4 zn-ss 87+/-3 86:1:8.7 86+/-6
.Ru-106 43+/-5 50:1:8.7 SO:t:ll cs-134 46:1:1 49+/-8.7 46:i:4 CS-137 lOil 10+/-8.7 11+/-2 07=86 EPA~ORG-=GSl90 Food I=l3l 26:ll 30:1:10.4 28+/-3 86=1205 CS-137 2lil 20:1:s.1- 21:!:3 K(l) l.150:1:30 usoiloo llSO:l::l.04 oe-es EPA-APT=GABSl92 APT CS-137 2lil 22:1:8.7 24:M 86-1567
- 1 i
- .?
-. -~---.-..-.----- --""-~- .... ~.---------.,.-----.,.-*----*.-7 ....,---... ..
.....--.-,--..,..-.-~.--- -**--:-*--.~~i- ... *-:*~-,..~---------*~*-******-*** -- -- -* ---.---**--~~-*- .._,. ____ - - - - . -- - **--- --*-*-**-*-:- *--* ....* ,._ **-.*
TABLE E-2. (cont'd) USEl?A ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMl?ARSION STUDY PROGRAM Gamma Anal.ysis of Milk, Water (pCi/L), Air Particulate (pCi/filter) and Food Products (pCi/kg) DATE ENV SAMl?LE CODE PSE&G El?A GRAND AVG MM-YY ENV ID MEDIUM ANALYSIS Mean :!: s.ci. Known Mean :!: s .ci. 10-86 .EPA-WAT-Gl95 Water cr-51 57:!:8 57:!:8.7 56::1:17 86-1964 Co-60 28::1:2 3l::l:8a 7 31+/-3 Zn-65 79:!:6 85:!:8.7 85+/-7 RU-106 69+/-9 74+/-8.7 68:!:8 cs-134 26+/-2 28:!:8.7 26+/-3 Cs-137 "42:!:2 44:!:8.7 45:!:4 10-86 EPA-MLK-GSl98 Milk I-131 48:!:1 49:!:10.4 . 49+/-5 86-2147 cs-137 44+/-1 39+/-8.7 44+/-3 K(l) 1540:1:20 1565:1:135 1565::1:106 ll-86 El?A-WAT-.E'l97 Water co-60 23il 24:1:8.7 24::1:2 86-2079" CS-134 ll:l:l 12:1:8.7 11:1:2 CS-137 8::1:1 8::1:8.7 9:!:2
"' s.d. - one standarci deviation of three inciiviciual analytical results
"'"' known value with control limits, indicating whether results are in agreement or disagreement
"'"'"' s.ci. - one standard cieviation of acceptable results of all participating laboratories (l) Reported as mg/L of Potassium.
. *-~- 166
. -----------*---...-:-~*----.-.--.~**--------**---~.. --.- .. -.... -~.,----:--~*----:?-,----. **- -~-...----.--._-~*;"C""~ ... .
_,.-.---~-----~- ---:-*-----~--. *--* --- .,., **::-- --*-...,., *.---:-:
USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM Tritiwn Anal.ysis of Water (pCi/L) DATE ENV SAMPLE CODE PSE&G EPA GRAND AVG MM-YY ENV ID MEDIUM ANALYSIS Mean +/- Sod. Known Mean +/- s.do 02~86 EPA=WAT-Hl72 Water H=3 5170+/-70 5227:!:906 5105+/-340 86~244 06=86 EPA~WAT~Hl82 Water H-3 3000:1:80 3125+/-624 3052+/-347 86-981 10-86 EPA-WAT-H196 Water H-3 5890+/-l.OO 5973+/-1.034 5694+/-406 86-1965
,,. Sodo - one standard deviat.ion of three individual analytical results
** known value with control limits, indicating whether results are in agreement or disagreement
**a Sodo - one standard deviation of acceptable results of all participating laboratories
- 167
~~~ ---------* - ......,.._ -*- ----.,,-.-;.~----.-**--**- -..-- - - *---- .. -.-:--'?""""* .---;'",-*.*-- -~-- ---~-~---, **-- ** ~--**** ---- ----~ -~-- ,. ***--*--- -* --- - - *-*:*- *; ----~---~---*' -
,(
TABLE E-4 USEPA ENVI*RONMENTAL :RADIOACTIVITY LABORATORY IN'I'ER.:OMPARSION STUDY PROGRAM Iodine Analysis of Water and Milk (pCi/L) DATE ENV SAMPLE CODE* PSE&G EPA GRAND AVG MM-YY ENV ID MEDIUM ANALYSIS Mean +/- s.d. Known Mean +/- s.d. 03-86 EPA-MLK-Il 72 Milk(l) I-l3l 2.4+/-1 9::1:10.4 9+/-2 86-245 04-86 El?A-WA'I'-Il 77 Water I~131 8::1:l 9::1:10.4 9+/-2
*86-424
*08-86 El?A-WA'I'-Il9l Water I-131 39::1:1 45+/-10.4 42+/-6 86-1305
" s.d. -.one standarc1 deviation of three individual analytical results
"" known value with control limits, indicating whether results are in agreement or disagreement
""" s.d. - one standarc1 deviation of acceptable results of all participating laboratories (1) Special El?A/NRC low level study *
. /~ **';
*-~
.*. ~ "*" . i 168
...: _(\ TABLE E-5
- USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM*
Strontium-89 and Strontium-90 Analysis of Air Particulates (pCi/filter), Milk, Water (pCi/L) and Food Products (pCi/kq) DATE ENV SAMPLE CODE PSE&G EPA GRAND AVG MM-YY ENV ID MEDIUM ANALYSIS Mean :t: s.d. Known Mean +/- s.d. 01=86 EPA-WAT-5168 Water sr-89 24+/-2 31+/-10.4 31+/-5 86-26 Sr-90 12+/-1 15+/-2.6 14+/-2.2 01-86 EPA-ORG-GS170 Food sr-89 (l) 86-108 sr-90 (1) 03-86 EPA-APT-GABSl76 APT sr.:..90 16+/-1 18+/-2.6 17+/-2 86-660 04-86 EPA-WAT-Pl78 Water Sr-89 6:1::1 7+/-8.7 6+/-2 7+/-1 86-512 sr-90 6:t::l 7+/-2.6 05=86 EPA-WAT-SJ.79 water Sr=89 - 4:tl S:t8.7 5+/-2 86-675 Sr=90 4::1::1 5:1::2.6 5+/-1 os~ss EPA-MLK-GS184 Mi.lk. Sr=89 <4 o 0 86-1071 sr-9o l2il 16+/-2.6 15+/-3 07-86 EPA-ORG-GSl90 Food sr-89 24+/-2 30+/-8.7 25+/-3 86-1205 sr-90 16+/-2 19+/-2.6 19+/-7 08-86 EPA-WAT-GABSl92 APT sr-90 22+/-1* 22+/-2.6 22+/-3 86-1567 10-86 EPA-MLK-GSl98 Milk sr-89 8:t:l. 9+/-8.7 9+/-3 86 2147 00 sr-90 <l.6 0 1+/-0.S l.l-86 EPA-WAT-Pl97 Water sr-89 10+/-1 10+/-8.7 9+/-3
; 86-2079 sr-90 3:t:l 4+/-2.6 4:.t:l i
- s.d ... one standard deviation of three incli.vidual analytical results_
** known value with control l.i.mits, inclicat~ng whether results are in agreement or disagreement a*a s.d. - one standard deviation of acceptal::lle results of all. part~cipating laboratories (l) Not analyzed by PSE&G.
.j
*. i
*1
'-o.---~~*---***~-----~--**;--~-~---.-- ...,-.-.,.-.,-*--****-***-. -~ -*-----*~-**.---*-*****--*--*-. *-**--*-*-- -*---- *-***-- ----*----"' .. - *-,-**. c ... ,_. __ '**-* -- *.-*--* .. . .* I
APPENDIX F SYNOPSIS OF LAND USE CENSUS
- . '.j J
*i
- :_* :.1 .
. . :. ~
. *.}
'~
I 171
- APPENDIX F SYNOPSIS OF l986°LAND USE CENSUS A land use census was conducted to identify, within a distance of 8 km (5 miles), the location of the nearest milk animal, the nearest residence and the nearest garden of greater than 5om2 (500ft2) producing broad leaf vegetation in each of the 16 meteorological sectors.
- Tabulated below are the results of these surveys:
Milk Nearest Vegetable Animal Residence Garden Meteorological Aug., 1986 Aug., 1986 Aug., 198 6 Sector km (miles) km (miles) km (miles) N None None None NNE None 6.9 (4.3) None NE None 6.4 (4.0) None ENE None 6.1 (3.8) None E None 5.4 (3.4) None ESE None None None SE None None None SSE None None None s None 6.1 (4.1) None SSW None 5.5 (3.4) None SW None 6.9 (4.3) None WSW None 7.1 (4.4) None w 7.8 (4.9) 6.5 (4.0) None WNW None 5.5 (3.4) None NW None 5.9 (3.7) None NNW None 6.8 (4.2) None
*. 1
~-
.. *l
~
I
*_~-*~}}