Text

Artificial Island Radiological Environ Monitoring Program, 1981 Radiological Rept
	ML18087A584
Person / Time
Site:	Salem
Issue date:	08/31/1982
From:	; RADIATION MANAGEMENT CORP. (RMC)
To:	;
Shared Package
ML18087A583	List: ML18087A582; ML18087A584;
References
	RMC-TR-82-01, RMC-TR-82-1, NUDOCS 8211120381
	Download: ML18087A584 (142)
	v • d • e

{{#Wiki_filter:~ - -*. -~' *. ~* (. :* -. ~ ~- ' '.~ ~ t -~ * ~ ' '.'~

RMC-TR-82-01 1981 RAbIOLOGICAL REPORT ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM January 1 to December 31, 1981 Prepared for Public Service Electric and Gas Company by Radiation Management Corporation August 1982

!~

-~*1 i

-i~! '

(t~: '; ~f~.l; --::*":'.~ '; tt-0:

~~

ii~ -~~ -~~

.'.~

.:*.. **~*:..*.....,..~--.*;.. *~..,*:.~~*.-..::***..........

SUMMARY

INTRODUCTION THE PROGRAM Objectives Sample Collection Data Interpretation* Progra~ Ch~nge~* RESULTS AND DISCUSSION Airborne Precipitation Direct Water Aquatic Ingestion Fodder Crops CON CL US IONS REFERENCES APPENDIX A - PROGRAM

SUMMARY

TABLE OF CONTENTS APPENDIX B - SAMPLE DESIGNATION & LOCATIONS APPENDIX C - 1981 DATA TABLES APPENDIX D SYNOPSIS OF ANALYTICAL PROCEDURES (RMC) APPENDIX D SYNOPSIS OF ANALYTICAL PROCEDURES (PSE&G) APPENDIX E -

SUMMARY

OF INTERLABORATORY COMPARISONS APPENDIX F - SYNOPSIS OF DAIRY AND VEGETABLE GARDEN SURVEY ~. I -*****..--*-*.. ***********-..........................-- PAGE 1 2 3 3 3 5 6 7 7 10 10 11 15 16 19 20 21 23 31 39 99 119 137 145

NUMBER

1.

2.

3.

4.

5.

UST OF FIGURES PAGE Comparison of Average Concentrations of Beta Emitters in Precipitation and in Air Particulates, 1973 through 1981 8 Average Ambient Radiation Levels from Monthly TLDs in the Vicinity of Artificial.Island, 1973 through 1981 *******. 9 Average Concentrations of Tritium in the Delaware River in the Vicinity of Artificial Island, 1973 through 1981 12 _Average Concentrations of Beta Emitters and Potassium-40_ _in the De)awa*re ~iyer in the. Vicinity_ of Artificial Island,

1973 t~ rough 1981.*.*...*

--..... :............*. -~*.*.*.**. :... *_::...

13.

Average Concentrations of Iodine-131 in Milk in the Vici-nity of Artificial Island, May 1974 through December 1981 17

-~-*.. ~...... i>>.;.:* .'t,_-,.:*.:.:,.*,.*,.*--**,. ',... *. ~--- :.. * '-~-*.. :. ... *.,_-.. ~;._:.,,,.,, :...-. "\\*;

SUMMARY

During the period January 1 to December 31, 1981, Radiation Management Corporation (RMC) participated in the Operational Radiological Environmental Monitoring Program conducted by Public Service Electric and Gas Company (PSE&G) at Artificial Island, New Jersey. Salem Nuclear Generating Station (SNGS) Unit #1 becarre critical on December 11, 1976, thereby initiating the operational phase of the Radiological Environmental Monitoring Program (REMP). This program was designed to identify and quantify concentrations of radioactivity in various environrrental rredia and to quan-tify ambient radiation levels in the environs of Artificial Island. Unit #2 achieved initial criticality on August 2, 1980. During the operational phase, the program will JTX)nitor the operations of SNGS Units #1 and #2 and will fulfill the requirements of the SNGS Environrrental Technical Specifications. This report presents the results of therJTX)l uminescent dosirretry and radiochemical analyses of en vi ronrrental samples collected during:1981. ~

A totai of 2523 analyses were performed on 1534 environmental samples during the period covered by this report.

Samples of air particulates, air iodine, surface, ground ahd drinking water, benthos, sediment, milk, fish, crabs, vegetables, garre, fodder crops, and precipitation were collected. TherJTX)luminescent dosimeters were used to measure ambient radiation levels. A variety of. radionuclides, both naturally occurring and man-made, were found in the above samples. These nuclides were detected at levels simila-r to those found during the preoperational phase of this program. In general, results at indicator stations compared favorably to control stations. It is concluded that the radiological charac-teristics of the environment around Artificial Island during 1981 were not affected by the operation of SNGS Units #1 and #2. 1

// INTRODUCTION Radiation Management Corporation has participated in the Artificial Island Radio-logi ca 1 Envi ronmenta 1 Monitoring Program since January 1973. RMC has previously reported results from the preoperational phase of the REMP for 1973(1), 1974(2), 1975(3) and 1976(4). On December 11, 1976, SNGS Unit #1 first achieved criticality thereby initiating the operational phase of the REMP. RMC has also reported re-sults from the initial operating period between December 11 and December 31, 1976(5), January 1 and December 31, 1977(6), January 1 and December 31, 1978(7), January 1 and December 31, 1979(8) and January 1 and December 31, 1980(9). This report sum-marizes the operational period between January 1 and December 31, 1981. Artificial Island is the site of two nuclear power' reactors which are part of the Salem Nuclear Generating Station. Units #1 and #2 are pressurized water reactors (PWR), 1090 MWe and 1115 MWe respectively. Both are presently operational. Artificial. l.sland is actually a man;..m.ade penins~1a in the De'laware River, created by.the deposition of dredging spoils. It is located in Lower Alloways Township,' Salem County, New Jersey. The environment around Artificial Island is character-ized mainly by the Delaware River and Bay, extensive tidal marshes, and grass lands. These 1 and types make up approximately 85% of the 1 and area within five mi* l es of the site. Most of the remaining land is used for agricultural production (10). More specific information on the demography, hydrology, meteorology, and land use characteristics of the local area may be found in the Environmental Report (10), Environmental Statement (11), and the Final Safety Analyses Report (Units 1 and 2 for SHGS (12). 2

~********'* _.,.,_,,-:--
-~.-

--~*~- ,-1 *

--~

"*' ~..

.~ :._; '. *.. :..

~*-.

*; * '->'.~.... **.: ' ; *.* -

~.,.. -. ' ':..*._,_.. -~:*.. *'*... :: '" -.. THE PROGRAM In the operational phase of the REMP, the program was conducted in accordance with Section 3.2 of the SNGS Environmental Technical Specifications (ETS). Radioanalytical data were collected and compared with results from the preoperational phase. Differences between these periods were examined statistically, where applicable, to determine whether any station operational effects existed. Objectives The objectives of the* operational radiological environmental _program are: l.* To fulfill the obligations of the Radiological Surveillance-Environmental sections of the Environmental Technical Specifications for SNGS.

2.

To determine.whether.any si"gnificant increase occu*rs in.the concentratio.n .of radionu~lide.s in critical pathways.

3.

To determine if SNGS has caused an increase in the radioactive inventory of long lived radionucl ides.

4.

To detect any change in a'mbient gamma radiation levels.

5.

To verify that SNGS operations have no detrimental effects on the health and safety of the public or on the environment. \\ This report as required by Section 5.6 of the Salem ETS (13) summarizes the findings of the 1981 REMP. Results of the four year preoperational program have been summarized for purposes of comparison with subsequent operational reports. (4) Sample Collection In order to meet the stated objectives, an appropriate operational REMP was developed by RMC in cooperation.with Public Service Electric and Gas Company. Samples of various media were selected to obtain data for the evaluation of the radiation dose*to man and other organisms. The selection of sample types was based on: (1) established critical pathways for the transfer of radionuclides through the environment to man, and (2) experience gained during the preoperational phase. Sampling locations were determined from site meteorology, Delaware estuarine hydrology, local demography, and land uses. Sampling locations were divided into two classes--indicator and control. Indicator stations ate those which*are expected to manifest station effects, if any exist; con- . trol samples are.collected at locations which are believed* to be unaffected by station operations. Fluctuations in the levels of radionuclides and direct radiation at indi-ca~or stations are evaluated with respect to analogous fluctuations at control stations, which are unaffected by station operation. Indicator and control station data are also evaluated relative to preoperational data. The REMP.. for the Artificial Island Site in-cludes additional samples and analyses not specifically required by the Salem ETS. The summary tables in this report include these addition al samples and analyses. 3

- -**-*----~.:--" :.;.;'.,.:*:*.'-**---* -:.*.**-**** -.: - _, **-* *..

' '.. - *-*... :. ~....,:. - -........... ' - -~~ ' -,..*. .-...,.:,~*** -*-***~-:..,_:. 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 charcoal cartridges connected in series ~ehind the air particulate filters. Air sample volumes were measured with calibrated dry-gas meters corrected to standard temperature and pressure. Precipitation was collected on a 95-square-inch rain gauge. Samples were collected monthly and transferred to new polyethylene bottles. The rain gauge was rinsed at collection with distilled water to include residual particulates in the precipita-tion samples. Tritium results were corrected for the tritium content of the dis-tilled water. Ambient radiation levels in the environs were measured with energy-compensated Caso4 (Tm) thermoluminescent dosimeters (TLDs). Packets containing four TLDs each were placed on and around the Artificial Island Site at.various distances and were exposed on a monthly, quarterly and semi-annual basis. Mo~thly.well.and pot~bl~ water* samples were taken in new**two-gallon polyethyiene bottles. Separate raw and treated potable water samples were composited daily by personnel of the Salem Water Company. Surface water samples were collected by Icthyological Associates and shipped to ~~C for analysis in new polyethylene bottles. Sample containers were rinsed twice with the sample medium pri.or to collection. Edible fish and crabs were taken by net, sealed in a bag or jar and shipped frozen. Benthos and sediment were taken with a bottom grab sampler. Milk samples were taken in new polyethylene bottles and shipped fresh. Food products, fodder crops, game and bovine thyroid samples were taken and sealed in plastic bags or jars. Perishable samples were frozen at the time of sampling without any preservatives. Appendix A describes and summarizes, in the format of Table 5.6-1 of the Salem ETS, the entire operational program as performed in 1981. Appendix B describes the RMC coding system, which specifies sample type and relative locations at a glance. Also in Appendix B,. Table B-1 gives the pertinent information on indivi-dual sampling locations, while maps B-1 and B-2 show the sampling locations. 4

~--

..,,:~f;_~.,_,_. '*.. _:;,_... :~,.-..-.. ~-:.~-- .;. **-* -~*:.. *-*- - -.:.......,.:.;: '.:., \\.**.. *:*. .*.-........ ~-. ;.. ' .-,.._:.:... * ** *....... 1,-;c **

Data Interpretation Radiation Management Corporation has an extensive 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 con-trol, instrument quality control, inter-laboratory cross-check analyses, and compre-hensive data review. The analytical methods utilized in this program are summarized in Appendix D-1. The methods utilized by the PSE&G Research and Testing Lab are summarized in Appendix D-2. Results of the EPA inter-laboratory comparison program .appear in Appendix E. A full discussion of these re*sul ts can be found in the 11Qual-ity Control Data 1981 - Annual Report 11 ( 14). Several factors are important in the interpretation of the data. These factors are discussed here to avoid repetition . in sections th~t follow.

Grab ~ampring is* a* useful and acc~ptable_* p)'.'ocedure *for* taking environmental samples

.of a medium in.whkh the concentration* of radionucl i-des is expected to" vary slowly* with time or where intermittent sampling is deemed sufficient to establish the radiological chara_cteristics of the medium. This method, however, is only repre-sentative of the sampled medium-for that specific location and instant of time. As a result, variation in the radionuclide concentrations of the samples will

normally occur. *Since these variations will tend to counterbalance one another, the extraction of averages based upon repetitive grab samples is valid.

Within the data tables (Appendix C) an approximate 95% (+/-2 sigma) confidence inter-val is supplied for those data points.above the lower limit of detection (LLD). An exception to this is Sr-89 and -90 detection capabilities which are based on the minimum detectable limit (MDL). These intervals represent the range of values into which 95% of repeated analyses of the same sample should fall. Results for each type of sample were grouped according to the analysis performed. t~ans and standard deviations of these results were calculated when applicable. The calculated* standard de vi at ions of grouped data found in Appendix C represent sarrqJle and not analytical variability. When a group of data was composed of mainly (>50%) LLD values, averages were not calculated. It is characteristic of environmental monitoring data that many results occur at or below the lower limit of detection. For reporting and calculation of averages, any result occurring at or below the lower limit of detection is considered to be at that limit. As a result, averages obtained using this method are biased hign. 5 0\\**~.-;*:* 4"**- ~.**.**

o
0***_*

I-~-.:-,.**~***::.~.... -.*,<"';'°*:"""'*"!' ~-~~*- *:* *'*****.*~*-*- .*._,-:~ ** **

--*-*'*-~ --
~ ** ;_ *.. -..

Program Changes Beginning on October 1, 1981, modifications were made to the portion of the Radio-logical Environmental Monitoring Program for the Salem Nuclear Generating Station performed by RMC. The following is a list of analyses no longer analyzed by RMC. It should be noted that al 1 analyses not performed by RMC are being analyzed by the Research Corp., a wholly owned subsidiary of PSE&G.

1.

Air Partjculates - all analyses (gross alpha, gross beta, gamma emitters, Sr-89 and -90) h.a.ve been discontinued by RMC.

2.

Soil - analyses for Sr-90 and gamma emitters have been discontinued by RMC.

3.. \\{ell Water - tritium and Sr.-89 *and -90 analyses have :been discontinued.*...,

by RMC. *

4.

Rain l~ater - tritium analyses have been discontinued by RMC. In order to insure quality of the results obtained by their laboratory, PSE&G has in£tituted a quality assurance program in which a portion of those samples analyzed by PSE&G will also be analyzed by RMC~ This program is discussed below.

1.

2.

3.

Milk - Sta ti on MLK-3Gl will continue to be analyzed for Sr-89 and -90 on a monthly basis by RMC. Each month one additional station will be chosen by Public Service Electric & Gas Company to receive Sr-89 and -90 analyses. Surface Water - Station SWA-12Cl will continue to be analyzed for tritium on a monthly basis, and for Sr-89 and -90 on a quarterly composite basis by RMC. In addition, one other station will be chosen by PSE&G to receive monthly tritium analyses and quarterly composite Sr-89 and -90 analyses. Potable Wa_te r - Monthly tritium analyses and quarterly composite analyses for Sr-89 and -90 will be continued on station PWT-2F3 by RMC. 6

~

~ *".**_.*,

,. o ~u-.*~~J**"'-

~ *

,.:..;..~:... * '... -...' RESULTS AND DISCUSSION The analytical results of the 1981 REMP samples are divided into categories based on exposure pathways: airborne, direct, water, aquatic and ingestion. The anal-ytical results for the 1981 REMP samples are surrrnarized ir1 Appendix A. The data for individual samples are presented in Appendix C. Airborne Air Particulates (Tables C-1, C-2, C-3, *c-4) Air particulate samples were analyzed for alpha, beta, gamma emitters, and Sr-89 and -90. The weekly air particulate samples were analyzed for gross beta activity at eight s~ations and for gross alpha.activity at two stations. Quarterly composites were prepared using the weekly samples from each station and analyzed for Sr-89,.

sr..;90 *and* specific gamma. emi.tters.

Weekly gross beta analyses showed concentrations ranging from 0.01~ to 0.471 pCi/m3 with the average for the eight sampling stations being 0.112 pCi/m. Figure 1 shows the relation between gross beta activity in air and precipitation for the preopera-tional and the oper~tional periods, showing both seasonal and weapons-testing fluc-tuations. l~;:( Of the 104 weekly air particulate samples (two stations) analyzed for gross: alpha

,~~ll ef!1itters, 91 were above detectabl: c9ncentrations.

The rang7 o~ gross alpha acti-

/~t,;

v1ty was from 0.0006 to 0.0027 pC1/m and averaged 0.0014 pC1/m. {f. Results of gamma spec~rometry showed detectable levels of.several radionucl ides, both naturally occurring and man-made (Be-7, K-40, Mn-54, Nb-95, Zr-95, Ru-103,

'.~:~

Ru-106, Sb-125, Cs-137, Ce-141 and Ce-144). The level of man-made nuclides de- 0~ tected during the first and second quarters can be attributed primarily to fallout ~:j from the October 16, 1980 atmospheric nuclear weapons test. Concentrations of ?;~1 these nuclides decreased significantly during the third and fourth quarters. The ~;;i; presence of Be-7 throughout the year can be attributed to cosmic ray activity. The highest activity detected.was 0.12 pCi/m3 of Nb-95 in the second quarter composite for station APT-501. The Sr-89 analyses performed on the quarterly composites showed 23 qut 3f 32 samples with detectable activity. 3These ranged between 0.0007 and 0.0093 pCi/m with the average being 0.0054 pCi/m

The positiv~ Sr-89 results can also be attributed to the fallout from the atmospheri3 nuclear weapons test.

Sr-90 concen3rations ranged between 0.0003 and 0.0022 pCi/m with the average being 0.0009 pCi/m

Air Iodine (Table C-5)

Iodine cartridges were connected in series behind each of the air particulate filters for adsorption of air iodine. The adsorption media used in these cartridges was 11TEDA 11 impregnated cha3coal. All results for I-131 were below the LLD and ranged from <0.0054 to <0.026 pCi/m

7

10 CXl 1 PCi/l - - - - _. 10-3 pCi/m3---4 ,J,. I I{ I ~ I \\ 1' tt I \\ /I f \\ 11 ~I I \\/ I FIGURE l COMPARISON OF AVERAGE CONCrnrRATIONS OF BETA EMITHRS IN. PRECIPITATION AND IN AIR PARTICULl\\TES, 1973 THROUGH 1981 Precipitation Air Particulates I. I I I J. t I 11 '1 I ~ I

l.

'If I I It l.l I /(.I. I .ft I ~I~ I\\ I I .i: I t I\\ I I I I I I ii. I I + I + I f I II ,1 ,1 ,1 I 11 I I I I I t II I I II i I 11 I I 1 I I I ~I 1 1 /,, l I ~ \\ I r I I ~I I ~ \\ ~ I I t I I I I 11 I,, II I "ft,,, I t I.l. t II I' ,1 + 1' , 1 I ~. I I + t I 11 11, 11 t 'I '1 ~ I I 'I I I I I., I \\I I I 1'I I I 1) I I ~ 1 I '1 I 11 'I I 11 I ! 1/ 1i11 I/ I I 1 1 atmospheric weapons 11 Sept. 17, 1977 test l I ii I ~ II ~ 4 / \\1 I I \\ : j. I I I. 11 I l + 11 I

' t,

I I I I I I I ,1 I t I I 1 ' atmospheric weapons 1,' June 17, 1974 1, 192.l...... 19-22'._ I /. : I 11 1 I 1 1, r 1, test ~; 1' 1 ii II I/ J. I /\\ I I I I 1 I I 1/ l l l 19--2.£. i atmospheric weapons Sept. 26, 1976 r test atmospheric weapons test March 14, 1978 l i I/ I \\/. .l ~ I i \\ i* .I: ii 1 11 11 l II ). i atmospheric weapons test Oct. 15, 1980 SNGS Unit #1 initial criticality Dec. 11, 1976 Three Mile Island SNGS u

March 28, 1979 nit #2 initial criticality Aug. 2, 1980 19~

19.2.2_ 192.L._ 19...zL 19-~ 19_.!'L_ 19 __

l~~--~t\\\\fi:@!lll~f4~~Rf"'~~~&j~t'Tu.~lli~i;:,;1i;'Wiiiii:t\\c,t,;:i;;;t;fi!bJ1'iiH;s~fZlq;~0r22;1;.1;9g""l+/-tl,ti&:~>JA;;:,oll'blt.:;;,;,;;;::c'J\\li,\\iL ..c: +> c 0 E l.O -ci +> ID... E 10 9 **

'-~-*-E BEEE *.

c FIGURE 2 AVERAGE AMB!Etlf RADIATION LEVELS FROM MONTHLY TLDs IN THE VICINITY OF ARTIFICIAL ISLAND, 1973 THROUGH 1981 F:ffil:-: c1 ;n, -c-:~E'i i * ;= r- '-:m * *b=rc't=t= :::11 =l=~ =!~!:: -=ti:H+ =;-:~ =!~i=:J:=rn:i=r1~==~ ::tt ::!?2 =tti-Jl@' ~lffi *

=i*~f~ ~~

J:ol~::~,: :J :c;=!=f::f, =i=L-:fi :;, i- *=j"Et~ ::f=cEU i= ;=]::ill=*.!. f'i:i.t J~IJ.:::h, =l=J~J;:i=~ : j:'J:f=1'- '=ff:~

1::1:: ::1°!:: =~io:J:::::: ;:J~I~ ~=ff 3:: =l=l=f=l=:f:'.c;:.j~:ri=f:C -*~~!El'==i:.:i=t-Ei0 +ltJ.=:£ :: :: 't!=!= :H=FL='== ::!..~:=\\+1-= =.L:.:-4':!:. r + ft!-L *ym~r::1= =1=1 ;R=t =!=I _go '°§~: ~ -. . ~= =t =1.=: ~::f:\\~ =U~=J:!::: ff!~ =!'.U+'c: ~S.~I~ =:: TfI :tt=t1;::;:..,_:=r=t~i= i L i =iJ:. L1= i'=i~!: =EJ:::=i ::r=t= =J=l~'B::1# ** ~J= ::i=~ =: ~

=. ~ *= = =i::i=,EE; ::g:::::=:;= ~~ =:=f~~i~

tl3:::.g-J: -h1-l:'!=i= ~f:~f:lo:i~ ~ ~ =t::l~i= =1.::1~h:J-i.t% :: ! =i U lt=J~k= 'H::!iE- ~=J;:"8§::1~1=.§j~J".::0T:=l= ~,::::.::'=-::EI=:"' f= ~h:O!=r.= =;':i- :=1::r=

-*~~l::l=ti3:-1 * =~=f+/-t=-t ;:=f:;.pt ::=: 'a:fi -:J:.l:cj :*:.*. '!~i::f.cl::- ',i~::'=i=::f ~; !1J~:-, £,;~8k ~,+f:i::k ~j03:.J=):l =JYt=!=:E §: :J~a= =

=r::: ::::r; =!=Ei:c*'- -'-'::=tEJ~

iE§[=f :-!+~. i:=l: l=i:'c§;::.oi' : i~!=J:::j~i: -i=i-::i~J:;: = = :. i ~: *. i:i =!~::::; *. cGf=t;i=!; :::1~!~14'!': :Ff3=l~l= T+!~!~j~ :::f=i=-+/-'c§i~ =El:"!# =:!=§!=-~ B5¥.. :; :; i=ti~

=E'=§j=:- :::!=t=i~S:i~ ::l=P.::J::-i=' =i=-t:~=t :c : c:c;,::'.

i-f:i.=:~1-:*i=i*=":l =tTI i = =F:'r~+~:. i=-' }~~1:: :f::!::::::J--i=- =-i*+-i-=i=F ~;=t=J=l=F ~f:l~ ~: =:i_i=i::.::::'.:: ::.c.:r-=l=.u;

£t~.§EJ:l=i3=f!:=;:: =¥r:oi==t=+ =l~F=fr=i' i=ri']= =* JJ:l-'i= :i f~!=t;; ::!::i'lf!='=!=l~l:=.i.::'1~ -i+tfi =fi+i=-i: =~-:=:-:t=f:. 'i:=l::~§:=: ~!=a=:=-i~ E:t.:i ::: *. ;::t=1=f

~s}=-L~§ :::=:;-J.=.:f='l= =:=t~!=!~t= ~F~!::.£:- ::;=~=;,_:: :~i=J:::~: :i :.'\\"1-!' 'Yi~t=h=~ :s:,*:.; ~ * -J=:i°:;::' -:.: ::!=!: :~=-~~fsc: =-i=~l~Ei=J~kl-2::.~~ =cl':i-?.~' -=:'=ic1=t;:

~ :~l3.:f~i+/- ~V:-93~~ =E~~;~=i~ =1=f=t~h:~ -~ 1:i!~i~~~:.-~~:_1~r-_;A~ -:i *f;L-~--i -.. t~:::Li:!~ ~l~J~!~i:-~~---

~ -;.-.!~'..:i*: -:i::l -1_: _::. ~i=i~r=tJ:- :Jj1~~ ~::f~:= ~= ~7lji~l~-~; ~~=~~!~~A~ ~=i~=i= 0t~~=:t!=' ='l£f::~3~§'t:3:e.t c;:El~l~:c ~ ::=.r;:i=: ~i"! 'i-=i P.!::.[:;:: 'i =tU::'=i~ ::f::Lt'i::; 'f:j::[;i*i= ~i,:f::~ ~-::::: J~fo!::§i.= =@.t=f=i'=t :=j~si2~, __., *!~:=:'!~ =l=-=t='r@=i=::~=i't~= :::~~:~=f: 1 ~=i::f'f L::! :c . :~."lei<:;:;=;* !:}:!'i=!>:1~;=: '~L **::;,:i:Ji :J=fVF~;-: -!,:::::= :;~:=J=t!~:V:Jc: !-0[ _:,;=L:;.. :*!=: c' 1~: g:~,r ~-J:~::n-=~r~~:t~::*=;=.,=:~-; ~

, \\:U.::t ;~:-_='i:~Hf il{*=~-:i ~: :~-~;tj' ~t;ri~r ':1:::l~~~~fJ=m~=;-'. *:,h_-:~r=:xt=:

~i=,~'-==f

J=¥i=R= 5:¥.*t:..::t;:c,~ i"l::J:C:i::~:=*c.,.-:-,:_r:;*.:::;*

r-~L ::::::r:.

~r-:1-*_:*rr130:*t*~r~rl:f! Tl-i:U*f:.;-1~1~1:-:::-~-::-

1=.

§ 1::1 ~-::=-' f:L~;::i=i::! ~J=t-i=F_~, :*:::;~ *_;=;::;:S', .:.:i:'i ::= :,1-r-::.,-,:.;-., :::::-* ,~_::~: ~i* :=:::::'J~L:i_:f :I,,!=h~'JiLc:-:!.j:i**::*,: ':,U:: 6'i ~=13= ~~~. ~~f=ffi4=~:~::~~,~11:~ 1 ~:~~;~=i}=~i ~;z~~,~ :nJ;;: :'.-.>-',, ~. -'~-1-;~::.:-~Ut :_*;~, :=JD:l*I~_::~- r~,:'_:~::_ ~i~~iT ~~~=:~~-:~ _=:_:J~; i-~-, t: :.* f':g.::

.f=bl~~g..:§=:l=:.: :i~:~E~'t=:~.;:.::_;::;: :::Cc.l_1:::::'.C 33ocF'F=!..;:;;::.;,,=' =*: != *= :. ' ' '

i: ;,: ~~=

.

\\-'~ V r,; /

: -:. Ht i.

H~i=-1:.:t :[.::h'iTt= -:'.: ! ;_;*

t~E=.~ j~ ="1=!:::ili!§§:=r=1::: '2-=*~ =:;~=L;=;;:. =-tJ:J::!=~ -1=r:>~c;;,.: T=t f.f:.

'::!.=~=:*f-(\\!;-:\\J

-. i.,.~!*;:~=' _; f- ~L c1:'; : ':::1'=.;:;:~,::. J=f~tH". ;*L ;.

5 ~;~~~-=ri~~:~ :~~*~~~~~:;~~: 1

':~~: :~:_~;=;~",:: ~:;,r ~f-- \\: 2~ t~.,:~ 1'1:?~ =-: i :_= :>:::-*: ~~:~;~i~lrlf:_~;: :~~'.=:t;,:~~L~:~~:1~~:*>i=,_,, *

-1:::,:: :~ i;i:~~,.J

"f

=E\\if3 t :-;c.._:; l~*-/;\\;::;r::.: ::' i.JcE! ~ !~H: *!Li! : :. i L

0:. _j :.:'.ci'! :Ci_::*:,-!

=~:i i!:*:=. ::: ;-;:;"! :f'h:J'i !Ji "i i-i i:.!

~~ ~:

-~ t- ~d~-,:~~::~~I~(:~f:_fa~~~,~~;!:**i~f;I~ :~:}i=:.=: :.:_',:

,~: *:, :::.:i_;:; ;=,~=:, t\\.:t..~:S-;t::;*_.t:_::~:-~1~*;;

0 u:;:. :: :HJ != -t:.i=rC::*- ¥-I~~=~!=i=i5.~-~;L=~-;~i~::!=1t=i~i=i-==i~r~:~~i:~--~:~=1-<-*: _:~~ !:~1~i~_-J_l-! ~-1 ::. -~; *.; ~~~i=-!-i--i-.!-L; t~F -~-Ei.~~~~ --1=~~::k~~=-f:_ -I~-:: 1- ! = 1~r: ::f!:=fili~ +I=-i~~!: 3"f:;;~:::-= =1==~: f!t.L~'i.. :* :::ti =f-i= Y'f r: ; ! i ;,. :! : ;... -~ ;_*; H' *!*: :*t: :*,. : ! '.::). c'JJJ:ff U: *u i ! *! §= 3~fil:: ~~~l::~::i~ :i~i~; l-=f j~il !iii p_:;~: i ~:, ilLJ::i; j ! I:

f !*:

J: :X
;. i*' f: **!=°i0; iii~ : ; : i-=j '='jj:=j-f *f- '1<.j*

m~~r=m~;:;.=:f::i=i=~'=i~l~~~:=-:::l 0lli~d-U~J.c:!:i: 1 : 0!Sf:t ::Iii

i:i.-:

di.:_::

!;*iii-

n~r=.ii.!j:!:l=:U 0tl !! *i i_[

=I,:

19....2.L 1s....ll..._ 3', *,, *, "'" *,.,, 'I' *,, * -.-"'" * *.,, *1.*,, *, "'"...., 'I ' *,, *, "'" ; 1'.,, 'I;.,,, * ;, ;, *, 'I,.,,, " t "'" ; r., ;I, *,,

i ~ ;, ill'"',,. -,,.,,, *,, 'I, *,, *,., *,.,, 'I' *,, *,, " * *,,

... :11 c:.: A:_ c.,, oz: Q..:... :m c :11 : _ c.,, oz a..:.._ :11 c

11.....: <"'oz: Q

... :11 c llli :_ _-_... "'o z: ~ -.... =-: c ;,; ~~.:"'oz c..:.... a..: JF.:.; ~ c "'oz c..:... :a.,. :i; -._-. c "'OZ:\\_... :ii; c a -..: c"' oz o -.... ::c c

E -. -. ~"'oz: o -..... :1: c

ii; -. -. c "'oz: c 19-2'_,C 19_.K_

19~ 19...&_ 19-M_ 19__2'.L 19..2.2._ atmospheric weapons test June 17, 1974 11.tmo~~~~ri~s"'i~~~s test atmosphertc weapons test atmospheric weapons test Three H1le Island atsoospheric weapons test Sept. 17, 1977 !larch 14, 1978 !larch 28, 1979 Oct. 15, 1980 SNGS Unit 11 initial cr1ticaltty Dec. 11, 1976 SNGS Unit 12 1n1tio1 criticality Aug. 2, 1980 19_. __

/*.

',r **,.* ~~'.-* -*._' ~J-'. * ;_,_*_.,:.. :......... '**.:: ~..:.._: ***~.

~.. -.".*~*.:.......
:*:. c Precipitation (Tables C-7, C-8)

Although not specifically required by the Salem ETS, precipitation was sampled con-tinuously and collected rrnnthly at the Salem substation sampling location. The precipitation was analyzed for tritium, gross alpha and gross beta emitters on a rrnnthly basis. Tritium activity was detected in four samples and ranged from 86 to 140 pCi/l. The LLDs ranged from <87 to <130 pCi/l. Of the twelve monthly rain water samples analyzed for gross alpha emitters, three showed detectable concentra-tions. The range of gross alpha activity was from 1.2 to 2.3 pCi/l with the average being 1.6 pCi/l. The LLDs ranged from _<0.6 to <1.2 pCi/l. Gross beta emitter con-centrations were detected in all samples and ranged from 4. 7 to 70 pCi /1 with an average of 30 pCi/l. Quarterly composites of preci pita ti on were analyzed* fo.r radi ostronti um and gamma emitters.* Sr-89 analyses showed positive results for the first three quart~rs of 1981. The concentrations ranged from 0.6 to 7.5 pCi /1, and averaged 3.8 pCi/l ** Sr-90 concentrations ranged between 0.8 and 1.4 pCi/l wi~h th~ average being 1.1 pCi/l. Results of gamma spectrometry showed detectable levels of several radio-nucl ides. All of the detected nucl ides are man-made and can be attributed to fallout from the October 16, 1980 atmospheric nuclear weapons test. By the fourth* quarter, activities had returned to LLD levels. Direct (Tables C-9, C-10, C-11) Direct radiation measurements w~re made at 41 different locations, 24 monthly and quarterly locations and 17 semi-annual locations using CaSOll. (Tm) thermal uminescent dosimeters. During 1981, 288 monthly, 96 quarterly and 34 semi-annual TLD packets were collected. Each packet included four dosimeters for a total of 1672 analyses. These analyses resulted in an average dose rate of 5.47 mrads/standard month for monthly TLDs, 5.37 mrads/standard month for quarterly TLDs and 5.54 mrads/standard month for semi-annual TLDs. A 11 TLD results presented in this report have been normalized to a standard roonth (30.4 days) to eliminate the apparent differences. caused by variations in exposure periods. \\~hen the monthly data is plotted as in Figure 2, a slight peak is observed after June 1979. This peak is attributed to the elevated readings from two on-site TLD stations. Since the two stations, lOSl and llSl, are on-site they do not represent any environmental dose to the public. A comparison of the direct radiation data for 1981 shows a similarity between the average monthly dose for both indicator stations (5.40 mrads/std. month) and con-trol stations (5.84 mrads/std. month). 10 ~;':..

In *order to better evaluate the variation between TLD_results, a statistical model which is capable of separating a contribution by srrns from the background component has been developed.

The statistical rrethod utilized is a linear regression analysis which involves determining the functions which best describe the background component by the least squares rrethod. Six models *were originally tested and are described in a separate publication (14). The equation which describes the model selected is: where: y.. = Jml

f

= denotes a function of Y.. = predicted value for station j, month m, and year i Jml

x.

= preope*rational

rrean for station. j
J "CON..

im COT. 1 = average of the control stations.for rronth m a'nd year i' = avera~e of the control station for year i (a 11 p 11 in place of 11 i 1 represents the preoperational period) A computer program was developed for multiple regression analysis. The least squares fit (LSF) line based on all 1981 data was determined along with the statistics for this line. The data for 1981 was tes:ted against predicted values and prediction limits determined from the rrodel period line. Differences between predicted and observed values are terrred residuals. Residuals outsi.de the pre-diction limits of the predicted value are identified as outliers. For 198L 22 outliers were predicted from a possible 288. Four outliers at station lOSl and sixteen outliers at station 11Sl can be attri-, buted to the refueling of Unit #1. These stations are located in the vicinity of the Refueling Water Storage Tank. Since these locations are on-site they do not represent a dose to the public. No TLDs located beyond the plant boundary indicated any additional dose from SNGS operation. The remaining two outliers at stations 7Sl and 1401 can be attributed to statis-tical fluctuations. Water Surface Water (Tables C~12, C-13, C-14, C-15, C-16) Monthly surface water samples were taken at five locations in the Delaware estuary. One is downstream from the outfall area, one is in the outfall area, and another is directly west of the outfall area at the mouth of the Appoqui ni*mi nk River. Two* other stations are located upstream--one station is in the river and the other is in the Chesapeake and Del aware Canal. The station located at the mouth of the Appoquinimink River serves as the operational control. Surface water samples were analyzed for tritium, gross alpha emitters, gross beta emitters, strontium-89 and -90, and gamma emitters. 11

1000 N 100 19.2.L 19--2.'L

'.;.1 FIGURE 3 AVERAGE CONCENTRATIONS OF TRITIUM IN THE DELAHARE RIVER* IN THE VICINITY OF ARTIFICIAL ISLAND, 1973 THROUGH 1931..

+' ~ u '"" Q.I +> c: Vl z Vl 0 j,1 19--2..,:,": 19..2.JL._ 19-22_ 19...2.L 19...2.L c: Vl z Vl 19._.d'.L_ 19_

w FIGURE 4 AVERAfiE CONCENTRATIONS OF BETA EMITTERS AND POTASSIUM-40 IN THE DELAWARE RIVER IN THE VICINITY OF ARTIFICIAL ISLAND, 1973 THROUfiH 1981 100111-~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~-, u 0. gross beta - o Potassium-40 I I I +" u *;; U IO ~<>> .u~ c:~ ~ u ""(1J a +" <.!) z

9. '

/I I ,1~

1 l>

fl I u +" u 0 ~co

r-
~.

c:N ~~i~iiitl8~~~~~tili1l8~ ~~i~iiitlgJ~~~~~i~iil81~~~i~i~i118l~~~~ti*~~lS1~>~9~i~iil8.l <~i:i~i1lB2~~~i~i.i1l8~~-~~~i~i1l8f~ 19..2L__ 19---2.'L 19---2..I:: 19-.lk.. 19 -22... 19 2L 19 -21._ 19...!'.£. I 9----£L 19 --

'. ;..;,. ***---*.:.. :,,.... </*:~*,.*.:..*.,.~ ;.......;.-.. **., ;,.*,,.. *.. ~; :,, ~- *-' '._;.... *--~-.*. *... _ *............. :_ ~.....,w.*, JJ* ~~-. -.. **** :. *:.:..-.-*.;., ; *.. *

r*

Analysis of surface water. for tritium yielded an average concentration of 163 pCi/l and* ranged from 58 to 412 pCi/1. These levels are similar to those measured in the preoperational program as shown in Figure 3. A gradual decrease in tritium activity. from 1973 to 1981 can be attributed to general reduction in the world-wide tritium inventory with the cessation of. routine atmospheric weapons testing. Gross alpha concentrations were generally below LLD, which ranged from <0.2 to <1.3 pCi/l. Eleven of the 55 samples analyzed showed detectable gross alpha activity. The average (0.3 pCi/l) was within the same range as the LLDs for the year. Gross alpha activity may be expected in suspended solids from naturally occurring radio-nuclides especially during periods of high surface runoff. Gross beta concentrations ranged from 10 to 129 pCi /1 and averaged 51 pCi /1. Nearly all of the beta activity was contributed by K-40, a natural component of salt and brackish waters, as illustrated in Figure 4, which compares gross beta and K-40 conc;:entrations in the Delaware River. Due to the flow rate vari-ations and the tidal natl.ire of the.estuarine environ*ment,. large varjations in the gross be:ta*

concehtrations were ob~ierved* throughout the year.

Much of this variation* can be attributed to the tidal stage at the time of sampling. Levels of Sr-89 were below MDL (<0.6 to <2.3 pCi/1) *in thirteen of seventeen sam-ples. Concentrations of detected Sr-89 ranged from 0.5 to 1.5 pCi/l, and averaged 0.8 pCi/l. Levels of detectable Sr-90 ranged* from 0.4 to 1.3 pCi/l in four of the seventeen samples. The MDL values for the remaining samples ranged from <0.3 to <0.9 pCi/l. The maximum level of Sr-90 detected in the preoperational program was

1. 6 pCi /1 ( 4.)

Gamma spectrometric analysis of surface water samples showed detectable concentra-tions of K-40 in 53 of 55 samples.

The average K-40 concentration was 57 pCi /1 and ranged from 20 to 120 pCi/l. K~4o is a naturally occurring radionuclide which is expected to be fo.und in salt and brackish waters. Well Water (Tables C-27, C-18) Monthly well water samples were taken from two indicator wells and one control well. All well water samples were analyzed for tritium, gross alpha and gross beta acti-vity, and K-40 (by atomic absorption). Quarterly composites were analyzed for gamma emitters, and Sr-89 and Sr-90. Detectable concentrations of tritium were observed in two of the twenty-seven samples with levels of 106 and 268 pCi/l. The LLDs rangeq from <88 pCi/l to <174 pCi/l. Gross alpha concentrations were generally below LLD which ranged from <0.8 to <3.6 pCi/1 *. Two of the 36 samples analyzed showed detectable gross alpha activity (1.7 and 2.2 pCi /l). The concentrations of gross beta emitters averaged 11 pCi /l and ranged from 2.6 to 16 pCi/l. The potassium-40 activity as determined by atomic absorption averaged 8.5 pCi/l. This indicates that the gross beta activity observed in these samples is primarily the result of naturally occurring K-40, a beta emitter. 14

. ~-..:.' ~... :. *: ~. The only nuclide detected by garmia spectrometry was K-40 (19 to 22 pCi/T) ih three of twelve samples. All results for Sr-89 were below the MDL with a range of <0.6 to <2.2 pCi/l. Sr-90 was found in one sample with a concentra-tion of 0.4 pCi/l. The range of MDLs for Sr-90 was <0.4 to <1.1 pCi/l. Potable Water (Tables C-19, C-20) Both raw and treated water samples were taken at the Salem Water Company, the only drinking water processing plant in the vicinity of Artificial Island. The raw water source for this plant is Laurel Lake (a tributary of the Delaware River) and several adjacent wells. Potable water samples were analyzed monthly for tritium, grass alpha and gross ~eta activity, and K-40 (by atomic absorption); Sr-89 and -90, and garmia emitters.were analyzed on a quarterly basis. The concentration of tritium averaged 120 pCi/l for all analyses, with no signi-ficant differences betwe*en the raw and treated.samples. Detectable gross alpha activity was observed in 15 of 24 samples* ranging between 0.5 pCi/1-and 1.8 pCi/l

with an average. of 1.0 pCi /1. : Gross betp. and K-40 *con~eot rati ohs were 1 ower thari in the* saline surface water, as expected for fresh water, with K-40 generally contributing less than 50% of the beta activity.

The average gross beta concen-trations were 3.9 pCi/l (raw) and 2. 7 pCi/l (treated). The average K-40 results were 1.4 pCi/l (raw) and 1.5 pCi/l (treated). Quarterly composites of raw and treated samples were analyzed for gamma emitters and Sr-89 and -90. No nucl ides were detected by garTBTia spectrometry in any of the samples. Of the seven samples analyzed for Sr-89, two showed detectable concen-trations (0.5 and 0.7 pCi/l). The MDL range for Sr-89 was <0.7 to <1.2 pCi/l. Sr-90 was observed in four of the seven samples with concentrations ranging from 0.3 to 1.1 pCi/l, and the average being 0.7 pCi/l. Aquatic Benthos (Table C-21) .'*'.r..~* Benthic organisms were collected at four locations and analyzed for Sr-89 and Sr-90. Levels of Sr-89 were below MDL (<0.2 to <169 pCi/g-dry) for all eight analyses. The wide fluctuations in MDL values were due to inconsistencies in sample size (0.01 to 9 grams dry). Three of eight samples showed detectable Sr-90 concentration averaging 1.2 pCi/g-dry. The detectable activity of these samples is within the MDL range ( <0.8 to <83 pCi/g-dry) of the other analyses. The MDL for radiostron-ti um as required by the Environmental Technical Specifications for benthic organisms was not met in all of the samples due to the iflllracticality of obtaining a sufficient-ly large sample size of benthic organisms. Sediment (Table C-22) Sediment was collected semiannually at four locations and analyzed for Sr-90 and gamma emitters. Levels of Sr-90 were below MDL (<0.04 to <0.1 pCi/g-dry) in seven of the eight sam-ples analyzed. The single concentration (0.04 pCi/g-dry) was within the MDL range. 15

-*~.-.*.. *--** ~--.....-. --

~.

- ~ -.... :.. _,. *. ~....

... ~ ~". Results of gamma spectrometry showed detectable levels of a variety of naturally occurring radionuclides as well as man-made radionuclides. Various fa1lout nu-clides were observed intermittently in the sediment samples. Ingestion Milk (Tables C-23, C-24) Milk samples were taken twice a month from six local farms during 1981 and analyzed for I-131; gamma emitters, Sr-89 and Sr-90 were analyzed monthly. I-131 was not observed in any milk samples during 1931. Figure 5 shows the average -I-131 concen-trations in milk samples resulting from atmospheric nuclear weapons tests by the Peoples Republic of China (June 1974, March 1978, and October 1980) and the Three* Mile Island incident in 1979.

GC111ma-spectrometry showed detectab*le c::oncentrations of K-40 in all samples and.Cs-137.

in 36 *of the 72. s*amples analyzed. The annual ave.rage concentrations *were 1500 pCi/l. for K-40 and 2.9 pCi/l for -Cs-137. These levels *were not si§nificantly different between control and indicator stations. Strontium-89 was:detected in twelve of the seventy-eight sar.iples analyzed with re-sults ranging between 1.8 pCi/l and 8.5 pCi/l. The range of r.mL values for Sr-89 . was <1.7 pCi/l to <37 pCi/l. The wide range of values for.the MDL was due to low chemical yields and long decay periods in some of the analyses. All of the posi-tive results detected were within the MDL range. The concentration of Sr-90 was positive in 71 of the 78 samples analyzed and averaged 3.4 pCi/l. The MDL range was <0.7 pCi/l to <8.9 pCi/l.. Sr-90 concentrations were similar at indicator* and control stations, indicating no contribution from SNGS. D~e to the 28 year half-life and biological assimilation, Sr-90 can be expected to remain long after routine atmospheric testing has ceased. All Sr-89 and -90 analyses have been chemical yield verified by atomic absorption spectroscopy. Fish (Tables C-26, C-27) Edible fish samples (American Eel, White Perch, Channel Catfish, Spot, etc.) were collected at three locations and analyzed for tritium and gamma emitters. Fish bones were analyzed for Sr-89 and Sr-90. Gamma spectrometry of these samples showed K-40 in all six samples analyzed at an average concentratiorr of 3.6 pCi/g-wet with a range of 2.9-4.6 pCi/g-wet. All six bone samples analyzed for Sr-89 (°.Jere below the MDL (<0.06 to <0.2 pCi/g-dry). Two of the six samples analyzed for Sr-90. had detectable concentrations of 0.04-0.05 pCi/g-dry. The maximum level detected during the preoperational period was 0.94 pCi/g-dry. Tritium analyses were performed on both aqueous and organic fractions of the flesh portions of these samples. The average concentration of tritium was 82.5 pCi/l for the aqueous fraction and 200 pCi/l for the organic fraction. Of the six sam-ples analyzed, all results are essentially the same as those found in surface water for the same period. 16

Jan. Apr. ~ ti) ~~e Ck!. NOv. ~~. Feb. 4 Mir. <lfl pCi/1 atmospheric weapons test ~~ ~~[~~~~~~~==~J=u=n=e=l=7~,=1=9~7~4=::=:=::====-e ""~ Now. '4 --ll1!-~ Fd>. <C Apr,..

D Maly..

~ ~Jul~ 4 Aus. 4 I" 4 Oet... ~~: feb... Mar. i4 ~ ~~*: ~....... Ck\\. Nov. -.2!>.. J*" :, : Apr. <C

0 May..

atmospheric weapons test Sept. 26, 1976 LL atmospheric weapons test ~ ~:[ .. ~~~~::~~~Se~p=t=*=l=7=*==19=7=7==========================~-e Sep!

+

~ ~ ~ atmospheric weapons test Feb. 4 ~~;r========:'.'.~=*==r:*la~r~c~h~l~4~, =1~9~7~8~* _ ~ ~ ~!e4 .'uly 4 Aug.f4 Sep!f<lll Oct... .... 14 -~~ Three Mile Island March 28, 1979

>---+

~ ::.. N '"".. ~Aug.. Sept.. ""* ~ "'"'~14 '"' 14 .,,, i.* Apr t41

D May 14 k..i ~:::

ll:i....... atmospheric weapons test .Oct. 15, 1930 ~~..-~~~~-====~~~~~ Sepif.c -~ Jan~ '"'IC ::: ~ r~; "" ~ Ciel. t4 Nov.J4 --~k I J""

. *...,..,. ~ -

.~ *.. ~.,.,,."~'" *****. **********""'~~ i - 0 0 - -;* "~* r; ~ ~. c:

0

.;~_:'~ I fi Ef~~

'.:°'.;;.,:

~:;\\:{ G:-:-i .ftt I I

~

: ::

.,.~~~::' . : *.*,~-,..._: ";.'" :.:-~:.:*-*, ~- i". ":

/:~

-.:-:1 -~1:'~ ~M *t.*;: -~*~:~3 \\1 .-,*.t.3 ?;~ }!~

~~~1

/~~ ii /<.":;~

~;,~ I

.~.......

Blue Crab (Tables C-28, C-29) Blue crab samples were collected at two locations and the flesh was analyzed for tritium in the aqueous fraction, gamma emitters and Sr-89 and -90. The shells were analyzed for Sr-89 and Sr-90. K-40 was the only garrma emitter detected with an average of 2.1 pCi/g-wet. All results for Sr-89 in flesh were below MDL with a range of 0.01 to 0.08 pCi/g-dry. Detectable concentrations of Sr-89 were found in two of the four shell samples, and averaged 1.3 pCi/g-dry. The MDL range for Sr-89 in shells was <0.08 to <0.1 pCi/g-dry. Three of four flesh samples showed detectable activity with concentrations of 0.007 to 0.07 pCi/g-wet of Sr-90. The MDL value was <0.007 pCi/g-wet. All of the shells had detectable activity of Sr-90. The range of activiti~s was 0.24 to 1.0 pCi/g-¢ry with no differen.ce observed between indicator a.nd control sta"tions ** One.sample. from statinn. llAl showed d.etectable -~oncentrations.of tritium~ The result (123+/-68 pCi/l) was comparable to tritium values found in surface water for this same period. Food Products (Table C-30) A wide variety of other human food products was sampled and analyzed for gamma emitters and Sr-89 and -90. These included cucumbers, asparagus, peppers, cabbage, corn, squash and tomatoes. All samples contained K-40 at concentrations from 1.5 to 5.9 pCi/g-wet. No other garrma emitters were detected in these food products. Sr-89 concentrations were all below MDL, which ranged from <0.006 to <0.2 pCi/g-wet. Eight of the fourteen samples analyzed showed detectable Sr-90 activity ranging from 0.003 to 0.015 pCi/g-wet. The MDLs ranged from <0.003 to <0.007 pCi/g-wet. Game (Table C-31) Two samples of muskrat were taken during this period. Flesh from both samples was analyzed for gamma emitters while muskrat bones were analyzed for.Sr-89 and Sr-90. Only naturally occurring K-40 was detected in the flesh samples ranging from 2.4 to 3.1 pCi/g. Both results for Sr-89 in muskrat bones were below MDL (<0.2 and <0.9 pCi/g-dry). *Detectable Sr-90 concentrations averaging 0.5 pCi/g-dry were observed in both samples. Beef (Table C-31) Three beef samples were collected during this reporting period. Only naturally occurring K-40 was detected in these samples at concentrations ranging between 1.7 and 2.7 pCi/g-wet. Beef Thyroid (Table C-31) Three beef thyroids were taken during this p~riod and analyzed for garrma emitters. One samp*le showed a detectable concentration of naturally occurring K-40 at a con-I I IB

-~ -:- .... ~..

_..... *. '**....: .~.:..

tl

~

I I

-~!~

)<1

~:~~--.J centration of 1.3 pCi/g-wet. The other samples had LLDs for K-40 of <0.6 and <1.1 pCi/g-wet. Mo I-131 was detected in the samples with LLDs between <0.076 and <0.095 pCi/g-wet. Fodder Crop~ (Table C-32) Nine fodder crop samples were taken at six local farms and analyzed for garrrna emit-ters. Gamma spectrometry of these samples showed several radionuclides, both man-made and naturally occurring. Of the naturally occurring gamma emitters present, only K-40 was observed in all samples with an average. of 11 pCi/g-dry. The other naturally occurring nuclide detected was Be-7 which occurred in one weed chop sample. The man-made nuclide Cs-137 was observed in one soybean sample. The pre-sence of Cs-137 can be attributed to fallout from atmospheric n~clear weapons tests * . *~. 19

-.,; *. -******- *--*>*.. :. "~* ::*. *.*. :.

CONCLUSIONS The Radiological Environmental Monitoring Program for Salem Nuclear Generating Station at Artificial Island was conducted during 1981 in accordance with the SNGS Environmental Technical Specifications. The objectives of the program were met during this period. The data collected assists in demonstrating that SNGS Units #1 and #2 were operated in compliance with Environmental Technical Speci fi cati ans. From the results obtained, it can be concluded that the levels and fluctuations of radioactivity in environmental samples were as expected for an estuarine en-vironment. In addition no increases were observed in either radionuclide con-centrations in critical pathways or wi"th respect to radionucl.ide build up.

Ambient radiation levels were relatively low, averaging* about 5.84 mrad/st.d *

. month.

No. other unusual radi ol ogi cal* characteristics Y'ere observed j n_ the environs*of Artiftctal Island.

The operation of SNGS Unit~ #1 and #2 had* no* discernable effect on the radiological characteristics of the environs of Artificial Island. 20

( 1) {2) ( 3) ( 4). (5) (6) (7) ( 8). (9) ( 10) ( 11) (12) -~-*** *- *.. *...: *'**. *.:; '...... *~ *..."'"-,****;...:... :. .... ~-::.. :. .:.~. .-... :*.-:... :.. - ~ ;..,. REFERENCES Radiation Management Corporation. "Salem Nuclear Generating Station RadiiJlogical Environmental Monitoring Program - 1973 11

RMC-TR-74-09, 1974..

Radiation Management Corporation. "Artificial Island Radiological Environmental Monitoring Program - 1974 Annual Report 11 RMC-TR-75-04, 1975. Radiation Management Corporation. "Artificial Island Radiological Environmental Monitoring Program - 1975 Annual Report". RMC-TR-76-04, 1976. ..... -*......_** ~~- *-. _;,.:;::-~ *;...,:.. - Radiation Management Corporation. 11Artifi.cial Island Radiological Environmental Monitoring Program-.Preoperation_al S_ummary - 1973 through 1976 11

Rf4C-TR-77...;03, 1978'. * '.

Radiation Management Corporation. 11Artificial Island Radiological Environmental Monitoring Program - December 11 to December 31, 1976 11 RMC-TR-77-02, 19 77. Radiation Management Corporation. "Artificial Island Radiological Environmental Monitoring Program - 1977 Annual Report". RMC*TR-78-04A, 1978. Radiation Management Corporation. 11Artificial Island Radiological Environmental Monitoring Program - 1978 Annual Report". RMC-TR-79-03, 1979. Radiation Management Corporation. "Artificial Island Radiological Environmental Monitoring Program - 1979 Annual Report". RMC-TR-80-03, 1980. Radiation Management Corporation. "Artificial Island Radiological Environmental Monitoring Program - 1980 Annual Report"~ RMC-TR-81-03, 1981. Public Service Electric and Gas Company. "Environmental Report, Operating License Stage - Salem Nuclear Generating Station Units 1 and 2 11 1971. United States Atomic Energy Commission. 11 Final Environmental* Statement - Salem Nuclear Generating Station, Units 1 and 2 11 Docket No. 50-272 and 50-311, 1973. Public Service Electric and Gas Company. 11Final Safety Analysis Report - Salem Nuclear Generating Station, Units 1 and 2 11 1972. (13) Public Service Electric and Gas Company. "Environmental Technical Specifications - Salem Nuclear Generating Station Units 1 and 2 11 1976. (14) Radiation Management Corporation. 11Quality Control Data 1981 - Annual Report 11 , 1982. 21

( 15) "--.-~. :c.:,,:-_. __ ~~-~~----:--__ -__ ~_--,-,-_ -~----:c----:-------:-. __ _.:-----__ -__ -__ -___ --:-o:_,_,._-;:--. -~i-i'_---*"-'**--'----cc--:" - REFERENCES (cont.) Radiation Management Corporation. 11Artificial Island Radiological Environmental Monitoring Program - Sta ti sti cal Interpretation of Results of the Thermoluminescent Dosimetry Program 11 RMC-TR-78-11, 1978.

-0

a 0

)::> G) -0

a

-0 )::> rr1 N 3: 0 w Ul 1-i c: 3: 3: )::> )::>

a

.. ~"""::>i.'ror~.:f~;;.<:..01::;;:.::0;.<,,,si[;;.;;8',,,.;;;;;.,;;r;;.;;, k:~;s:1:J~;!iii~b'i."tfi;i.;;<c"1:;;Jii~;,a,;;d:i&'::li,ti1.if:ii:i.;;1.l<.~~i'; ;*;i:.c'..:i;£:;;;.:11Jii:dh:*.:';:.~*:.;,,,,;~;,;M;;1.:~*il;':d::.'i*;;~,~; ';'t1*o;i:'c;i°':'\\*;;,,j1;:"!.'::~;:*~,:<<<<: ;*,**:.. **,,,.:.o*:*;.L,:,, *:1;,:;_:t'rib.'1:::*,~*;,::.;;.;: ;,:.~).**;;;..;:.:.. '.; L,.;,;';;,:.5'ii,::::;.::; 2:.i., "'" ::*.. :.:*.*:... '. ::-./;:_.,;;,;.. :*.,,. *... :~;;;,;;:*:::::;. I': 1::

~

I* I. N <.n MEDIUM OR PATHWAY SAMPLED (UNIT OF MEASUREMENT) Air Particulates (lo-3 pCi/m3) Air Iodine ( 10-3 pCi /m3) ANALYSIS AND TOTAL NUMBER OF ANALYSES PERFORMED Alpha 104 Beta 424 Sr-89 32 Sr-90 32 Gamma 32 Be-7 K-40 Mn-54 Nb-95 Zr-95 Ru-103 Ru-106 Sb-125 Cs-137 Ce-141 Ce-144 I-131 364 ARTIFICIAL ISLAND RADIOLOGICAL EtNIRONMEllTAL MOlfffORillG PROGRAM'

SUMMARY

SALEM tWCLEAR GENERATING STATION DOCKET rm. 50-272 SALEM cournY. NEW JERSEY JANUARY 1, 1981 TO DECEMBER Jl, 1981 LOWER NUMBER OF LIMIT OF ALL IllDI GATOR LOCATIOIJS LOCATIOll WITH HIGHEST l4EAll CONTROL LOCATION NONROUTINE DETECTION MEA!l** NAME ME All MEAll REPORTED (LLD)* (RAllGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREl4ENTS 0.6 1°.4 ( 44/52) 16El 4.1 mi rrnw 1.4 (44/52) l.Z (47/52) 0 (0.6-2. 7) (0.6-2.7) (0.6-2. 7) 112 ( 369/371) 2F2 8. 7 mi IHlE 117 (52/53) 113 (53/53) Q ( 15-471) . (22-471) .. (16-386) 0.5 5.4 (20/28) 16El4.lmi rmw 6.95 (2/4) 5.8 (3/4) 0 (0.7-9.3) (6.9-7.0) ( 1. 3-8. 7) 0.3 0.9 (20/28) 3H3 110 mi NE 1.3 ( 3/4) 1.3 (3/11) 0 (0. 3-2. 2) (0.8-2.2) (0.8-2.2) 70 (28/28) 2S2 0.4 mi rmE . 80 (4/4) 66 (4/4) 0 (33-110) ( 39-110) ( 39-92) 6.1 6.4 (6/28). 2F2 8.7 mi IHJE 7.9 (1/4) 6.1 (1/4) 0 (4.9-7.9) 5Sl i.o mi E (7.9) (6.1) 0.3

1. 8 ( 10/28) 2.2 ( 1/11) 2.1 ( 1/4) 0 (0.6-2.8)

(2.2) (2.1) 1001 3. 9 mi SSW 2.2 (1/4) 56 (23/28) (2.2) 0.3 2S2 0.11 mi NNE 67 (3/4) 62 (4/4) 0 (0.5-120) (17-100) (0.6-110) 0.4 24 ( 21/28) 2S2 0.4 mi NNE 29 (3/4) 25 ( 3/4) 0 (5.1-46) . (6.6-40) (6.4-42) 0.3 11 ( 15/28) 2F2 8 *.7 mi rmE 14 (2/4) 9.5 ( 3/4) 0 ( 1.1-15) ( 13-15) (1.4-14) 0.6 16 ( 13-28) 2F2 8.7 mi NllE 24 ( 1/4) 15 ( 3/4) 0 (7.4-26) (24) (6.6-27) 0.7 - (0/28) 3H3 110 mi NE 3.2 (2/4)

3. 2 ( 2/4) 0 (3.0-3.4)

( 3.0-3.4) 0.4

2. 7 (22/28) 2F2 8.7 mi rmE 3;1* (3/4) 2.5 ( 3/4) 0 (0;3-5.5)

(L4-5.l) (0.9-11.6) 0.2 9.3 (14/2B) 5Sl 1.0 mi E 10 (2/4) 9.9 ( 2/4) 0 (6.4-12) (8.1-12) (8.7-11) 1.9 44 (24/28) 5Dl 3.5 mi E 43 (4/4) 52 (3/4) 0 ( 1.5-110) ( 1.9-110) (25-100) 5.4 - (0/312) None Detected (0/52) 0

ARTIFICIAL ISLAND RADIOLOGICAL EllVIROIJMElffAL MONITORING PROGRAM

SUMMARY

SALEM IWCLEAR GENERATillG STATION DOCKET NO. 50-272 SALEM COUllTY, NEW JERSEY JAllUARY 1, 1981 TO DECEl11JER 31, _1981 ANALYSIS AND LmJER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL IND! CATOR LOCATIONS LOCATION WITH HIGHEST* MEAll CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES DETECTIOH J4EAll** llAME MEAIJ f*1EA1l REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RAllGE) DISTANCE Arm DIRECTIOll (~AllGE) (RAllGE) MEASUREMENTS Precipitation Alpha 12 0.6 1.6 ( 3/12) 2F2 8.7 mi IHlE 1.6 (3/12) llo Control 0 (pCi /1) ( 1.2-2. 3) (1,2-2'.3) Location Beta 12 2.3 30 ( 12/12) 2F2 8.7 mi llNE 30 ( 12/12) llo Control 0 (4. 7-70) (4.7-70) Location H-3 12 87 115 ( 4/12) 2F2 8. 7 mi llllE 115 ( 4/12) No Control 0 (86-140) (86-140) Location Sr-89 4 0.8 3.8 (3/4) 2F2 8.7 mi llllE 3.8 ( 3/4) No Control 0 (0.6-7.5) (0.6-7.5.) Locatfon Sr-90 4 0.4 1.1 ( 2/4) 2F2 8. 7 mi NllE 1.1 (2/4) No Control 0 (0. 8-1.4) (0.!3-1.4) Location Gamma 4 Be-7 7.6. 34 (3/4) 2F2 8.7 mi llllE 34 (3/4) llo Control 0 (24-44) (24'-44) Location Zr-95 0.6

4. 3 (1/4) 2F2 8. 7 mi NllE 4.3 ( 1/4) llo Control 0

f'.) (4.3) (4.-3) Location m Nb-95 0.6 11 (1/4) 2F2 8. 7 mi IHlE 11 (1/4) No Control 0 ( 11) '*(1'1) Location Ru-103 ( 1) 4.7 (1/4) 2F2 8. 7 mi llfjE 4.* 7 (1/4). llo Control 0 (4. 7)

(4. 7)

Location Ce-141 ( 1) 3.4 ( 1/4) 2F2 8.7 mi WlE ~.4 ( 1/4) llo Control 0 (3.4) (3.4) Location Di re ct Ra di ati on Gamma 288 5.40 (240/240) llS 1 O.09 mi SW 7.84 (12/12) 5.84 (48/48) 0 (mrad/std. month) Dose (monthly) ( 3.28-16.51) (4.64-16.51) (4.97-7.14) Gamma 96 5.31 (80/80) llSl 0.09 mi SW 8.18 (4/4) 5.64 (16/16) 0 Dose (quarterly) (3.31-14.45) (4.94-14.45) (4.90-6.58) Gamma 34 5.46 (28/28) 11E2 5.O.mi SW 6.12 ( 2/2) 5.92 (6/6) 0 Dose (semi-annual) (4.40-6.43) (5~81-6.43) (5.55-6.30) Surface Water H-3 55 87 178 (21/44) llAl 0.2 mi SW 245 (4/11) 148 (7/11) 0 (pCi/l) ( 77-412) (97-412) (58-246) Alpha 55 0.2 0.4 (8/44) llAl 0.2 mi SI~ 0.,5 (3/11) 0.3 (3/11) 0 (0.2-0.8) (0.3-0.8) (0.2-0.4) Beta 55 50 (44/44) 7E 1 4.5 mi SE 66 ( 11/ 11) 54 (11/11) 0 ( 10-129) ( 33-122) (18-129) Sr-89 20 0.6 0.9 (3/16) 1F2 7.1 mi ll 1.1 (2/4) 0.6 (1/4) 0 (0.5-1.5) (0. 7-1.5) (0.6) Sr-90 20 0.3 0.8 (4/16) llAl 0.2 mi SW

1. 3 ( 1/4)

- (0/4) 0 (0.4-1. 3) ( 1. 3) I Gamma 55 K-40 11 60 (42/44) 7El 4.5 mi SE 88 ( 11/11) 54 ( 11/11) 0 ( 20-120) ( 49-120) (22-85) ~*..

MEDIUM OR PATHWAY SAMPLED (UNIT OF MEASUREMENT) We 11 Water (pCi /1) Potable Water Raw-Treated Benthos (pCi /g-dry) ANALYSIS AND TOTAL NUMBER OF ANALYSES PERFORMED H-3 36 Alpha 36 Beta 36 K-40 36 Sr-89 12 Sr-90 12 Gamma 12 K-40 H-3 24 Alpha 24 Beta 24 Sr-89 8 Sr-90 8 K-40 24 GalliTla 8 Sr-89 B Sr-90 8 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMEflTAL MONITORING PROGRAM

SUMMARY

SALEM flUCLEAR GENERATHlG STATIOfl DOCKET NO. 50-272 SALEM courm. NEW JERSEY JAfWARY 1, 1981 TO DECEMBER 31, 1981 LOWER LIMIT OF DETECTION - (LLD)* 88 0.8 0.6 0.4 9.3 ALL IllDICATOR LOCATIONS MEAN** (RANGE) 106 ( 1/24) ( 106) 2.2 (1/24) (2.2) 12 ( 24/24) (2.6-16) 9.1 (24/24) (2.2-14) - (0/8) 0.4 ( 1/8) (0.4) 20 ( 3/8) (19-22) LOCATION WITH HIGHEST: MEAN NAME MEAN DISTAHCE AllD DIRE CTI OH ( RAflGE) 3E 1 4. 1 mi flE 106 ( 1/24) 4S 1 Site We 11 #5 ENE ( 106)

2. 2 ( 1/24)

- ('2.2) 4S 1 Site We 11 #5 ENE 13 ( 12/12) (2.6-14) 4S 1 Site We 11 #5 ENE 10 -( 12/12) (2.6-14) None Detected 451 Site Well #5 ENE 0.4 (.1/4) (0.4) 451 Site_ lfe 11 #5 ENE 22 (1/4) (22) 2F3 8.0 mi NflE 115 (6/24) (74-180) CONTROL LOCATION MEAN (RAflGE) 268 ( 1/12) (268) 1.7 (1/12) ( 1. 7) 9.2 (12/12) (7.6-12) 7.3 ( 12/12) (1.7-9.6) (0/4) (0/4) - (0/4) flo Control Location 82 0.4 115 (6/24) (74-180) 0.99 (15/24) (0.5-1.8) 3.3 (24/24) 2F3 8.0 mi NNE 0.99 (15/24) flo Control 0.7 0.5 0.2 0.8 ( 1.4-6.2) 0.6 (2/8) (0.5-0. 7) 0.7 (4/8) (0. 3-1.1) 1.4 (24/24) (0.9-3.0) - (0/8) - (0/6) 1.2 (3/6) (0.2-3.0) 2F3 8.0 mi NNE 2F3 8.0 mi rHIE 2F3 8.0 mi rmE 2F3 8.0 mi fHIE None Detected flone Detected 16Fl 6.9 mi rmw (0.5-1.8) Location 3.3 (24/24) No Control ( 1.4-6. 2) Location 0.6 (2/8) No Control (0.5-0.7) Location 0.7 (4/8) flo Control (0.3-'l.1) Location 1.'4 ( 24/24) No Control (0. 9-3.0) Location - (0/8) flo Contra l Location - (0/2) 3:0 ( 1/2) - (0/2) (3,.o) NUMBER OF /; NON ROUTINE REPORTED MEASUREMENTS 0 0 0 0 0 0 0 II 0 0 0 0 0 0 0 0 0

ARTIFICIAL ISLAND RADIOLOGICAL EllVIROllMEllTAL MONITORING PROGRAM

SUMMARY

L SALEM llUCLEAR GEllERATING STATIOll DOCKET llO. 50-272 SALEM COUNTY, NEW JERSEY JANUARY 1, 1981 TO DECEMBER 31, 1981 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL INDICATOR LOCATIONS LOCATION WITH HIGHEST MEAll CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAU MEAN REPORTED {UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION ( RAllGE) (RAllGE) MEASUREMEIHS Sediment Sr-90 8 0.04 0.04 (1/6) 12Cl 2.5 mi WSW 0.04. ( 1/2) - (0/2) 0 (pCi/g-dry) (0.04) (0.04). Ganrna 8 K-40 14 (6/6) 12Cl 2.5 mi HSW 16 (2/2) 16 (2/2) 0 ( 13-18) (16) (16) Co-60 0.03 0.19 ( 1/6) 11Al 0.2 mi SW 0.19 ( 1/2) - (0/2) 0 (0.19) (0.19) Zr-95 0.06 0.17 (1/6) 16Fl 6.9 mi rmw 0.17 {1/2) - ( 0/2) 0 (0.17) (0.17) Nb-95 0.06 0.2 (3/6) 16Fl 6.9 mi llNH

0. 44 ( 1/2)

- (0/2) 0 (0.08-0.44) (0.44) N Cs-137 0.04 0.1 (4/6) 11Al 0.2 mi SW 0.15.(2/2) - (0/2) 0 00 (0.04-0.17) (0.13-0.17) Ra-226 0.54 (6/6) llAl 0.2 mi SW 0~6i' (2/2) 0.54 (2/2) 0 (0.46-0.65) (0.57-0.65) (0.48-0.60) Th-232 0.78 (6/6) 16Fl 6.9 mi rrnw 1.0 (2/2)

0. 88 ( 2/2) 0 (0.47-1.0)

( 1.0) (0.86-0.9) Fruits & Vegetables Sr-89 14 0.006 - (0/7) None Detected - (0/7) 0 (pCi I g-wet) 0.003 0.009 (3/7) 0.015 ( l/i) 0.005 (5/7) Sr-90 14 1F3 5.9 mi ll 0 (0.004-0.015) (0,015) (0.003~0.013) Gamma 14 2.8 (7/7) K-40 2.2 (7/7) 3H4 88 mi NE 3 *. 1 (4/4) 0 ( 1.5-2.8) (1.5-5.9) ( 1.5-5.9) Game Sr-89 2 0.2 - (0/1) None Detected - (0/1) 0 (pCi/g-dry) (bones) Sr-90 2 a.so (1/1) 3E 1 4. 1 mi NE 0.05 (1/1) 0.5 {1/1) 0 (bones) (0.50) (0.05) (0.5) 11El 4-5 mi SW 0.5 {.1/1) .'(0.5) (pCi/g-wet) Ga nm a 2 (flesh) 3.1 {1/1) K-40 2.4 (1/1) 11El 4-5 rni SW 3.1 (1/1) 0 (2.4) . (3.1). ( 3.1)

ARTIFICIAL ISLAIJD RADIOLOGICAL EtlVIRONMEIHAL MONITORmG PROGRAM

SUMMARY

SALEM llUCLEAR GENERATHIG STATIO!l DOCKET NO. 50-,272 SALEM COUlffY, NEW JERSEY .JANUARY 1, 1981.TO DECEMBER 31, 1981 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL IllDICATOR LOCATIONS LOCATIOll WITH HIGHEST MEA!l CONTROL LOCATION NON ROUTINE SAMPLED OF ANALYSES DETECTION MEAtl** llAME MEA!l MEAll REPORTED . :~ (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RAllGE) DISTANCE AND DIRECTION (RAllGE) (RANGE) MEASUREMENTS 1*~ ':.) ~*~:.: Milk 1-131 144 0.04 - (0/120) None Detected - (0/24) 0

'f; (pCi/l)

Sr-89 72 1.7 4.1 (7/60) 15Fl 5.2 mi Nl1 6.6 (2/12) 3.9 (4/12) 0

~*-:

.:.* 1 (2.0-8.5) (4.7-8.5) (3.0-4.9) Sr-90 72 0.7 3.3 (54/60)

5F2 7.0 mi E 4.7 (11/12) 4.2 (11/12) 0

i:~

(0.6-6.8) (0.6-6.0) (2.9-5.3) .:~~~ Ganma 72 K-40 1472 (60/60) 2F4 6.3 mi NNE 1533 (12/12) 1375 ( 12/12) 0

~

(1200-2000) ( 1300-1900) ( 1100-1700) Cs-137 1.2 2.8 (31/60) 5F2 7.0 mi E 3.5 (8/12) 3.2 (5/12) 0 ( 1.4-6.4) (1.4-6.4) (1.5-4.4) .82.5 (2/4) 83 (1/2) (0/2) N Edible Fish H-3 6 86 7p 4.5 mi SE 0 l.O (pCi/l) (aqueous) (82-83) (83) H-3 6 112 200 (3/4) llAl 0.2 mi SW 31'7 ( 1/2) (0/2) 0 (organic) (126-317) (317) (pCi /g-dry) Sr-89 6 0.06 - (0/4) !lone Detected (0/2) 0 (bones)

.i Sr-90 6

0.04 0.05 (1/4) 7El 4.5 mi SE 0.05 (1/2) 0.04 (1/2) 0 (bones) (0.05) (0.05) (0.04)

~

~

(pCi/g-wet) Gamma 6 i* ') K-40 3.6 (4/4) 7El 4.5 mi SE 4.0 (2/2) 3.5 (2/2) 0 (2.9-4.6) (3. 3.:4, 6) (3.2-3.8) Cs-137 0.008 0.016 (1/4) 7El 4.5 mi SE 0.016 (1/2) - (0/2) 0 (0.016) (0.016) Blue Crab Sr-89 4 0.08 0.8 (1/2) 12Cl 2.5 mi WSW 1.7 (1/2)

1. 7 ( 1/2) 0 (pCi/g-dry)

(shells) (0.8) ( 1. 7). ( 1. 7) Sr-90 4 0.59 (2/2) 12Cl 2.5 mi WSW 0.64 (2/2) 0.64 (2/2) 0 (shells) (0.24-0.94) (0. 28-1.0) (0.28-1.0) (pCi/l) H-3 4 86 123 ( 1/2) llAl 0.2 mi SW 123 ( 1/2) - (0/2) 0 /. (flesh) ( 123) .( 123) (pCi/g-wet) Sr-89 4 0.01 - (0/2) None Detected - (0/2) 0 .::i (flesh) Sr-90 4 0.007 0.07 (1/2) llAl 0.2 mi SW 0.07 (1/2) 0.02 (2/2) 0 (flesh) (0.07) (0.07) (0.02) Gamma 4 K-40 1.9 (2/2) 12Cl 2.5 mi l1SW 2:3 (2/2) 2.3 (2/2) 0 (1.7-2.1) (2.3) (2.3) ':i

~,r~~~L~~~d,\\tkl'{*lillllll'"w.'"';"'*"ii'li"'t""'11'c:":a,,";;,;""*"ili',!ii.,s;;:£:J~i:;,;"'3k'lH$;;~~i:;10ili%1,z~~,"'t!11~1.~;.<£t*rJ,ll[i;!l~Ji~;;;._ ~~1 I i~~2j '.~i~~ w 0 MEDIUM OR PATHHAY SA."1PLED (UNIT OF MEASUREMENT) Beef (pCi/g-wet) Beef Thyroid (pCi/g-wet) Fodder Crops (pCi/g-dry) ANALYSIS AND TOTAL NUMBER OF ANALYSES PERFORMED Gamma 3 K-40 Gamma 3 K-40 Gamma 9 Be-7 K-40 Cs-137 ARTIFICIAL ISLAND RADIOLOGICAL ENVIROIJ:-1ElffAL MOIHTORHlG PROGIW1 surn1ARY SALEf.1 IWCLEAR GENERATING STATIOI~ OOCKET NO. 50-2.72 SALEM COUNTY, NEii JERSEY ,JAlllJARY 1, 1981 TO DECEllfiER 31, 1931 LOUER NUMBER OF LIMIT OF ALL INDICATOR LOCATIONS LOCATION IHTH HIGHEST llEAIJ - CONTROL LOCATION NONROUTINE DETECT IO II MEAN** -!JAME MEAN MEAN REPORTED (LLD)* (RANGE) OISTAIKE Arm DIRECTION (RANGE) ( RAIJGE) MEASUREMENTS 2.2 (2/2) 3El 4.1 mi. IJE 2.2 (2/2)

1. 7 (1/1) 0 (1.7-?..7)

(1.7-2.7) ( 1.7) 0.6 1.3 (1/2) 3El 4.1 1~i. NE L3 (1/2) (0/1) 0 ( 1.3) ( 1.3) 0.1 2.3 (1/7) 15Fl 5.2 mi. IJIJ

2. 3 ( 1/3)

(0/2) 0 (2.3) (2.3) 9.9 (7/7) 3El4.lmi. NE 16 (1/1) 15 ( 2/2) 0 (5.2-16) - ( 16) (3.7-21) 0.2 0.04 (117) 3El 4.1 r:ii. IJE 0.04 (111) (0/2) 0 (0.04) (0,04) LLD listed is the lowest calculated LLD during reporting period. Strontium-39 and -90 detection levels are tlinimum Detectable Levels (MDLs). ( 1) Mean calculated using values above LLD or MDL only. Fraction of measurements above LLD or MDL are in parentheses. Indicates that no LLD was calculated for that nuclide in that media. ~.

APPENDIX B SAMPLE DESIGNATION AND LOCATIONS 31

./

-:~::~ ' ':\\') /:~} .j

~.. ~

,l
/,l

. ~ APPENDIX B Sample Designation RMC identifies samples by a three part code. The first two letters are the power station identification code, in this case 11sA11. The next three letters are for the media sampled. AIO = Air Iodine GAM = Game APT = Air Particulates GAD = Deer ECH = Hard Shell Blue Crab IDM = Immersion Dose (TLD) ESB = Benthos MLK = Milk ESF = Edible Fish PWA

Potable Water; (PWR = raw, PWT

ESS = Sediment RWA = Ra_i.n Water FPS Beef SWA. = Surface Water FPV = Food Products, Various iHB. = Bov*i ne Thyroid FPG = Corn VGT = Fodder Crops FPL = Green Leafy Vegetables WWA = Well Water The last four symbols are a location code based on direction and distance from the site. Of these, the first two represent each of the sixteen angular sectors of 22.5 degrees centered about the reactor site. Sector one is divided evenly by the north axis and other sectors are num-bered in a clockwise direction; i.e., 2=NNE, 3=NE, 4=ENE, etc. The next digit is a letter which represents the radial distance from the plant: s = On-site location E = 4-5 miles off-site A = 0-1 miles off-site F = 5-10 miles off-site B = 1-2 miles off-site G = 10-20 miles off-site c = 2-3 miles off-site H = >20 miles off-site D = 3-4 miles off-site The last number is the station numerical designation within each treated) sector and zone; e.g., 1,2,3,.... For example, the designation SA-WWA-5Dl would indicate a sample in the SNGS program SA, consisting of well water (WWA), which had been collected in the 22.5 degree sector centered on each axis (5), at a distance of 3 to 4 miles off-site (D). The number 1 indicates that this is sampling station #1 in the designated area. 33

.:_,...
0

'A."-~.*., : o ';'~.-

Sampling Locations All sampling locations and specific information about the individual locations are given in Table B-1. Maps B-1 and B-2 show the locations of sampling stations with respect to the site. TABLE B-1 STATION STATION CODE LOCATION lFl 5.8 mi. N of vent; Fort Elfsborg 1F2 7.1 mi. N of vent; midpoint of Delaware River 1F3 5.9 mi.. N rif vent; local farm

. 'lGl 1G3 2S2 2El 2F2 2F3 2F4 2F5 2Hl 3El 3F2 3F3 3Gl 3Hl 3H3 3H4 4Sl 4D2

. 13. mi. N of yent; local farm 19 mi. N of vent; Wilmington, Delaware 0.4 mi. NNE of vent

4.4 mi. NNE of vent; local farm 8.7 mi. NNE of vent; Salem Substation 8.0 mi. NNE of vent; Salem Water Company 6.3 mi. NNE of vent; local farm 7.4 mi. NNE of vent; Salem High School 34 mi. NNE of vent; RMC, Phila.

4.1 mi. NE of vent; local farm 5.1 mi. NE of vent; Hancocks Bridge Municipal Bldg. 8.6 mi. NE of vent; Quinton Township School 17 mi. NE of vent; local farm 32 mi. NE of vent; National Park, N.J. 110 mi. NE of vent; Maplewood Laboratories 88 mi. NE of vent; local farm 1400 ft. ENE of vent; site well #5 3.7 mi. ENE of vent; Alloway Creek Neck Road 34 SAMPLE TYPES APT, IDM SWA FPL FPG IDM APT,AIO, IDM IDM,FPV APT,AIQ:,RWA, IDM PWR,PWT MLK, VGT IDM IDM IDM,WWA,THB,FPV, FPG,GAM,FPB IDM IDM IDM,MLK,FPG,VGT IDM APT,AIO, IDM FPV,FPG WWA IDM ~*,. *. :~ *:. __ : *- ; *.. ~. *.

I

~*-'.. \\. j...

~ ~*. TABLE B-1 (CONT.) STATION STATION CODE LOCATION 5Sl 1.0 mi. E of vent; site access road 5Dl 3.5 mi. E of vent; local farm 5Fl 8.0 mi. E of vent 5F2 7.0 mi. E of vent; local farm 6S2 0.2 mi. *ESE of ~ent; ~bservation bldg. 6Fl 7Sl 7El 7F2 9El lOSl lODl 10F2 lOGl llSl llAl 1101 llEl 11E2 llFl 12Cl 6~4 mi. ESE of vent; Stow Neck Road 0.12 mi. SE of vent; station personnel gate 4.5 mi. SE of vent; 1 mi. W of Mad Horse Creek 9.1 mi. SE of vent; Bayside, New Jersey 4.2 mi. S of vent 0.14 mi. SSW of vent; site shoreline 3.9 mi. SSW of vent; Taylor's Bridge Spur 5.8 mi. SSW of vent 12 mi. SSW of vent; Smyrna, Delaware 0.09 mi. SW of vent; site shoreline 0.2 mi. SW of vent; outfall area 3.5 mi. SW of vent 4-5 mi. SW of vent 5.0 mi. SW of vent 5.2 mi. SW of vent; Taylor's Bridge, Delaware 2.5 mi. WSW of Vent; west bank of Delaware River 35 ~ _:: t:*'.. *;:- SAMPLE TYPES APT,AIO, IDM APT,AIO, IDM, WWA,FPV IDM, FPV MLK lDM IDM IDM SWA,ESB,ESS,ESF IDM IDM IDM APT,AIO, I DM IDM IDM IDM SWA,ESB,ESS, ESF,ECH GAM GAM IDM IDM SWA,ESF,ECH, ESB,ESS

/*-***.

TABLE B-1 (CONT.) STATION STATION SAMPLE CODE LOCATION . TYPES 12El 4.4 mi. WSW of vent; Thomas Landing IDM 12Fl 9.4 mi. WSW of vent; Townsend Elementary School IDM

13El 4.2 mi. W of vent; Diehl House Lab IDM 13E3 4.9 mi. W of vent; 1 ocal farm MLK,VGT
13Fl 9.8 mi. W of vent; Middletown, Delaware IDM 13F2
6.5 mi. W of vent; Odessa, Delaware IDM 13F3 9.3 mi. W of vent; Redding Middle School, Middletown, DE IDM 14Dl 3.4 mi. WNW of vent; Bay View, Delaware IDM 14Fl 5.5 mi. WNW of vent; 1 ocal farm MLK,FPB,THB,VGT 14F2 6.6 mi. WNW of vent; Boyds Corner IDM 14F3 5.0 mi. WNW of vent; 1 ocal farm FPV,FPG
15Fl 5.2 mi. NW*of vent; 1 ocal farm MLK,FPG,VGT 15F3 5.4 mi. NW of vent IDM 16El 4.1 mi. NNW of vent; Port Penn APT,AIO, IDM 16Fl 6.9 mi. NNW of vent; C & D Canal SWA,ESB,ESS 16F2 8.1 mi. NNW of vent; Delaware City Public School IDM 16Gl 15 mi. NNW of vent; Greater Wilmington Airport IDM 36

~-,:**.*. :*

-. *'*- :._ **"' ~--. : ____. -. -~... *..... :* *.. -.. -... ).-. --~- --- 0 SCALE OF MILIS MAP B*l ON SITE SAMPLING LOCATIONS ART IF IC IAL ISLAND 37 '~ *2~.:*.-:,.,;:* :**,...- ::"'.-*-:,:.: *-'--

- --*.... _._ *. *.;*.:. ~.. -...

":'". :'"'i

MAP B-2 OFF SITE SAMPLING LOCATIONS ARTIFICIAL ISLAND 9 O* 1 H-H I SCALI Of MILIS 38

~~~~'.!

.-... ~:-::
- (,';
  
  -~

I j;~)

~s.~

t APPENDIX C 1981 DATA TABLES 39 .*~ - ;:.* _ __,_.' -~-~*,._* -- ., !~.-

~~~~:.I~

x~~ ,,,,,J f~~~ ..;.~1.-;i I DATA TABLES Appendix C presents the analytical results of the 1981 Artificial Island Radiological Environmental Monitoring Program for the period of January 1 to December 31. TABLE TABLE TITLE PAGE NUMBER C-1 Concentrations of Gross Alpha Emitters in Air Particulates..... 43 C-2 Concentrations of Gross Beta Emitters in Air Particulates...... 45 C-3 Concentrations of Gamma Emitters in Quarterly Composites of Air Particulates................................. *............. 47 C-4 Concentrations of Strontium-89 and -90 in Quarterly Composites of Air Particulate *samples..... ;,........... ;........ *....... :... ~ 51 C-5 Concentrations of Iodine-131 in Filtered Air................... 53 C-6 Sampling Dates for Air Samples................................. 55 C-7 C-8 C-9 C-10 C-11 C-12 C-13 C-14 C-15 C-16 C-17 C-18 C-19 Concentrations of Tritium, Gross Alpha and Gross Beta Emitters in Precip*itation............................................... Concentrations of Strontium-89 and -90 and Gamma Emitters in Quarterly Composites of Precipitation.......................... Direct Radiation Measurements - Monthly TLD Results............ Direct Radiation Measurements - Q~arterly TLD Results.......... Direct Radiation Measurements Semi-Annual TLD Results........ Concentrations of Tritium in Surface Water..................... Concentrations of Gross Alpha Emitters in Surface Water........ Concentrations of Gross Beta Emitters in Surface Water......... Concentrations of Gamma Emitters in Surface Water.............. Concentrations of Strontium-89 and -90 in Surface Water........ Concentrations of T~itium, Gross Alpha and Gr~ss Beta Emitters, and Potassium-40 in Well Water........... :....*................ Concentrations of Strontium-89 and -90, and Gamma Emitters in Quarterly Composites of Well Water............................. Concentrations of Tritium, Gross Alpha and Gross Beta Emitters, and Potassium-40 in Raw and Treated Potable Water.............. 41 60 62 63 64 65 66 68 69 70 71 73 75 77

f~

( *.. ~-;' *:c* *,. ~""':"*:=~~-":.":':.;***:.-~~*-*:-~,:...::,:~*~,'~**

~*-.: ::;;. ~ * ' ".::-. ':**:: ::* *-: (~~.:.-... **, * *:*:~ 1,

'* *
- - - ~:.:: ~'.: *. ".~{\\* \\~~".;\\,;'*;* :';l *! *_.;::-';:','.* '. "'<~ -~ 1~.' :*:*'., ~*.'..'7 *". ~;~**.* "<*~ti;-,_'.~;':*:;;<-.};;';-':: '..':*: ~<::**.: *

.... ~..

DATA TABLES (cont.) . NUMBER TABLE TABLE TITLE PAGE

c-*20 Concentrations of Strontium-89 and -90, and Gamma Emitters in Quarterly Composites of Potable Water...........................

79 C-21 C-22 C-23 Concentrations of Strontium-89 and -90 in Benthos Concentrations of Strontium-90 and Gamma Emitters in Sediment... Concentrations of Iodine-131 in Milk............................ C-24 Concentrations of Gamma Emitters and Strontium-89 and -90 in 81 82 83 Mi 1 k.......... *........... ;. ~.................... ;................

84 c-25*
s~mpling Dates *for Milk -Samples.... -.::........ **... ~......... ;*....

87 C-26 Concentrations of Garrrrna Emitters in Edible Fish................. 89 C-27 Concentrations of Strontium-89 and -90, and Tritium in Edible Fish Samoles.............................................. *...... 90 C-28 Concentrations of Garrrrna Emitters in Blue Crab Samples........... 91 C-29 Concentrations of Strontium-89 and -90~ and Tritium in Blue Crab Samp 1 es.................................................... 92 C-30 Concentrations of Gamma Emitters and Strontium-89 and -90 in Food Products................................... :............ 93 C-31 Concentrations of Gamma Emitters and Strontium-89 and -90 in Meat, Game and Bovine Thyroid................................ 94 C-32 Concentrations of Gamma Emitters in Fodder Crop Samples......... 95 C-33. LLDs for Gamma Spectrometry..................................... 96 42

~

TABLE C-1 CONCENTRATIONS OF GROSS ALPHA EMITTERS IN AIR PARTICULATES STATION NUMBER SA-APT-16El SA-APT-3H3 (Control) STATION NUMBER SA-APT-16El SA-APT-3H3 (Control) Results JANUARY* 1.5+/-0.B 1.7+/-0.7 1.6+/-0.9 1.1+/-0.6 0.6+/-0.6 1.4+/-0.8 1.2+/-0.7 1.5+/-0.9 1.2+/-0.7 1.6+/-0.7 JUNE 0.9+/-0.6 <0:9 1.5+/-0.6 1.7+/-0.13 1.4+/-0. 7 1.0+/-0.6 1.1+/-0.6 0.7+/-0.6 Sampling dates can be found on Table C-6. in Units of 10-3 pCi/m3 +/- 2 sigma FEBRUARY MARCH . 1.9+/-0. 7 <0.7 1.3+/-0.5 2.0+/-0.9 1.1+/-0.6 1.4+/-0.6 1.1+/-0.8 2.7+/-0.8 1.3+/-0. 7 .0.6+/-0.6 1.2+/-0.4 1.2+/-0.6

1. 3+/-0~7 1.1+/-0.6 1.0+/-0. 7 2,1+/-0. 7 JULY AUGUST

<0.B 1.2:t0.6 1.5+/-0.6 1.6+/-0. 7 1.4+/-0. 7 <0.7 <0.7 0..9+/-0.7* <1.2 0.7+/-0.6 1.2+/-0.7 1.2+/-0.6 1.4+/-0.6 1.1+/-0.6 1.1+/-0.6 0.13+/-0. 5 1.5+/-0.7 <1.1 Program discontinued by ru~c after the third quarter. APRIL 1.2+/-0. 7 1.1+/-0.6 1.0+/-0.6 . 0.9+/-0.6 0.9+/-0.6 1.13+/-0. 7 1.3+/-0.6 . 0.9+/-0.6

SEPTEMBER**

1.3+/-0. 7 1.9+/-0.13

1. 3+/-0.13 1.2+/-0.4 1.5+/-0.7 1.4+/-0.8 1.2+/-0.1 1.0+/-0.4 MAY

<1.1 0.9+/-0.6 0.9+/-0.13 1.4+/-0.6 (.. <1.2 <1.1 <0.6 0.9+/-0.7 1.2+/-0.6 <1.0 AVERAGE 1.3+/-0.9 1.2+/-0.6

.f::> STATION NUMBER SA-APT-16El SA-APT-3H3 (Control) TABLE C-1 (cont.) COHCENTRATIO!~S OF GROSS ALPHA EMITTERS rn AIR PARTICULATES Results in Units of 10-3 pCi/m3 +/- 2 sigma (All Results Supplied By PSE&G Research Corporation) OCTOBER* HOV EMBER DECEMBER 1.8+/-0. 6 1.2+/-0.6 2.5+/-1.0 1.4+/-0.8 2.0+/-0.8 1.1+/-0.5 1.0+/-0.5 0.9+/-0.5 1.4+/-0. 7 1.0+/-0. 7 0.7+/-0.6 0.9+/-0.6 0.9+/-0.5 0.8+/-0.4 0.8+/-0.5 2.0+/-0.7 2.7+/-1.0 1.3+/-0.6 0.9+/-0.5 0.8+/-0.5 0.6+/-0.4 0.8+/-0.5 <0.6 0.8+/-0.6 1.1+/-0. 7

1. 6+/-0. 6 Program initiated by PSE&G after the third quarter

AVERAGE 1.3+/-1.0 1.1+/-1. 2

//~B!f~i0~S *. ~~:~(~~~~1i~~~~2~E;d.G~;~JJ&~~~*~~~~~~~~~~~~~~~M~t~!~i~r;:_~;~~t)!f' ~~~~;;i.d~~~... :~l ~:~.l('*.{) ~. *~~*:< >.-:*~*::~{. 1

... F~~;i: ;~,:,. -~:.~*!~:::~* /,:~:~_~;

1

~-~.x~:;~~1iJ::i;:,;,j~~ :

~;., ~~-::~~1i~:~:~:t:~jJi~hi::;~~.'~;~:;/:~~:~~;*:~[g~~~~~*i\\~j:~~;'.~f.. ~*~~~I~:'.:.\\.~ ~ * *,, ". _',;.,

,~: ; *; .*.~:~ ~:~'::.;; 1.~~

1 .'.~~~~L.

TABLE

~

i CONCENTRATIONS OF BETA EMITTERS Itl AIR PARTICULATES Results in Units of lo-3 pCi/m3 +/- 2 si!)llla STATION NO.

MONTH SA-APT-2S2 SA-APT-5Sl SA-APT-501 SA-APT-1001 SA-APT-16El SA-APT-lFl SA-APT~2F2 SA-APT-3H3 AVERAGE (Control) JANUARY* FEBRUARY MARCH APRIL MAY JUNE JULY AUGUST SEPTEMBER** AVERAGE 76+/-8 51+/-6 91+/-9 138+/-14 210+/-21 219+/-22 109+/-11 145+/-14 122+/-12 113+/-11 201+/-20 196+/-20 238+/-24 383+/-38 239+/-24 233+/-23 224+/-22 221+/-22 172+/-17 285+/-28 345+/-35 200+/-20 158+/-16 144+/-14 113+/-11 138+/-14 94+/-9 190+/-19 109+/-11 91+/-9 69+/-7 40+/-5 51+/-6 61+/-6 37+/-5 40+/-5 47+/-6 35+/-5 34+/-5 145+/-175 62+/-6 52+/-6 99+/-10 128+/-13 134+/-13 97+/-10 88+/-9 110+/-11 152+/-15 78+/-3 201+/-20 136+/-14 237+/-24 331+/-33 237+/-24 268+/-27 232+/-23 219+/-22 184+/-18 282+/-28 360+/-36 190+/-19 156+/-16 124+/-12 99+/-10 146+/-15 95+/-10 194+/-19 112+/-11 95+/-10 67+/-7 46+/-6 61+/-7 67+/-7 52+/-7 36+/-6 52+/-8 37+/-7 33+/-6 137+/-169 84+/-8 59+/-7 102+/-10 157+/-16 142+/-14 103+/-10 106+/-11 135+/-13 102+/-10 79+/-8 204+/-20 140+/-14 234+/-23 376+/-38 229+/-23 250+/-25 252+/-25 229+/-23 183+/-18 287+/-29 394+/-39 198+/-20 157+/-16 138+/-14 98+/-10 164+/-16 96+/-10 192+/-19 123+/-12 101+/-10 75+/-8 42+/-6 59+/-7 70+/-7 43+/-7 46+/-6 42+/-8 33+/-6 35+/-7 143+/-179 79+/-8 53+/-6 113+/-11 157+/-16 100+/-10. 89+/-9 101+/-10 132+/-13 92+/-9 90+/-9 208+/-21 154+/-15 234+/-23 427+/-43 249+/-25 267+/-27 209+/-21 219+/-22 201+/-20 294+/-29 359+/-36 184+/-18 149+/-15 134+/-13 124+/-12 142+/-14 84+/-9 179+/-18 95+/-10 96+/-10 67+/-8 42+/-6 58+/-7 70+/-7 40+/-6 42+/-6 57+/-7 29+/-6 40+/-6 140+/-183 Sal!1llfng d11tes can be found on Table c~6. Program discontinued by ~~C after the third quarter. 72+/-7 52+/-6 107+/-11 132+/-13 93+/-9 37+/-9 85+/-9 128+/-13 101+/-10 86+/-9 253+/-25 136+/-14 205+/-20 381+/-38 243+/-24 283+/-28 211+/-21 244+/-24 163+/-16 285+/-29 352+/-35 185+/-19 162+/-16 135+/-13 116+/-12, 131+/-13 87+/-9 175+/-17 94+/-9 100+/-10 69+/-8 39+/-5 58+/-7 69+/-7 42+/-6 41+/-5 44+/-6 34+/-6 37+/-6 136+/-178 82+/-3 74+/-7 94+/-9 142+/-14 115+/-12 101+/-10 123+/-12 117+/-12 109+/-11 109+/-11 231+/-23 162+/-16 218+/-22 363+/-46 233+/-23 283+/-28 229+/-23 237+/-24 199+/-20 287+/-29 4000+/-2300( l) 183+/-18 159+/-16 129+/-13 112+/-11 134+/-13 36+/-9 203+/-20 115+/-11 '113+/-11 67+/-3 50+/-7 63+/-8 00+/-8 46+/-6 41+/-6 46+/-7 37+/-6 29+/-6 137+/-159 ( 1) High result due to low sample volu~. This result was not 1neluded in the averages. 33+/-8 62+/-7 97+/-10 146+/-15 116+/-12 101+/-10 117+/-12 130+/-13 123+/-12 83+/-8 202+/-20 128+/-13 243+/-24 471+/-47 260+/-26 249+/-25. 224+/-22 251+/-25 184+/-18 321+/-32 333+/-34 210+/-21 165+/-16 ' 143+/-1S 109+/-11 150+/-15 95-+/-10 203+/-21 108+/-11 101+/-10 78+/-3 51+/-7 66+/-8 68+/-7 48+/-6 -31+/-5 57+/-8. 33+/-6

35+/-6 146+/-191 103+/-10 62+/-7 95+/-10 129+/-13 114+/-11 106+/-11 117+/-12 136+/-14 114+/-11 84+/-3 154+/-15 159+/-16 254+/-25 373+/-37 263+/-26

.269+/-27 179+/-18 266+/-27 196+/-20 271+/-27 336+/-39 200+/-20 180+/-18 173+/-17 106+/-11 119+/-12 100+/-10 204+/-20 127+/-13 94+/-9 86+/-9 65+/-7 63+/-7 69+/-7 46+/-6 49+/-6 42+/-6 313+/-6 32+/-5 144+/-177 80+/-23 58+/-16 100+/-15 141+/-23 128+/-74 113+/-87 106+/-28 129+/-22 114+/-37 90+/-27 207+/-57 151+/-44 233+/-30 388+/-85 244+/-25 263+/-35 220+/-43 236+/-34 185+/-27 289+/-29 362+/-41 194+/-19 161+/-18 141+/-30 110+/-17 141+/-27 92+/-11 193+/-24 110+/-24 99+/-14 72+/-14 47+/-17 60+/-9 69+/-10 44+/-9 42+/-9 48+/-12 35+/-6 34+/-7 141+/-175 t'* (

TABLE. C-2 (cont.) COllCElffRATIOllS OF BETA EMITTERS Ill AIR PARTICULATES Results in Units of 10-3 pCi/m3 +/- 2 sigma (All Results by PSE&G Research Corporation) STATION rm. MONTH SA-APT-2S2 SA-APT-5Sl SA-APT-501 SA-APT-1001 SA-APT-16El SA-APT-lFl SA-'APT-2F2 SA-APT-3H3 AVERAGE OCTOBER* 24+/-5 <41 27+/-6 21+/-6 30+/-6 36+/-7 '26+/-6 23+/-6 29+/-14 24+/-5 30+/-6 32+/-6 30+/-6 27+/-5 27+/-6 32+/-6 26+/-5 29+/-6 32+/-8 29+/-8 24+/-6 31+/-7 32+/-7 36+/-7 26+/-6 26+/-6 30+/-8 31+/-5 30+/-6 31+/-7 25+/-5 24+/-5 15+/-5 22+/-5 31+/-6 26+/-12 22+/-5 28+/-7 25+/-6 24+/-6 41+/-8 29i6 . 28+/-6 35+/-6 29+/-12 NOVEMBER 37+/-6 41+/-7 42+/-7 38+/-6 34+/-6 42+/-7 3'8+/-6 34+/-6 38+/-6 O'I 29+/-5 36+/-7 36+/-7 38+/-7 39+/-7 34+/-7 40+/-7 34+/-6 36+/-7 19+/-5 27+/-6 22+/-6 30+/-6 38+/-7 21+/-6 25+/-6 21+/-5 25+/-13 24+/-5 22+/-6 24+/-6 30+/-6 33+/-7 17+/-5 29+/-6 17+/-6 25+/-12 DECEMBER 30+/-6 28+/-6 24+/-6 27+/-6 30+/-7 26+/-6 40+6 25+/-6 29+/-10 19+/-5 18+/-6 21+/-5 19+/-5 19+/-5 19+/-6 <:551(1l 16+/-5 19+/-3 28+/-5 29+/-6 29+/-6 32+/-7 29+/-6 33+/-6 30+/-6 26+/-5 30+/-5 27+/-5 29+/-7 32+/-6 23+/-5 28+/-6 28+/-6 24+/-5 37+/-7 29+/-9 20+/-5 27+/-7 27+/-7 20+/-6 20+/-6 25+/-6 23+/-6 23+/-6 23+/-6 AVERAGE 26+/-11 30+/-13 28+/-12 28+/-12 30+/-13 2!3+/-16 29+/-13 27+/-13 28+/-19 Program initiated by PSE&G after the third quarter. This result was high due to low sample volume; therefore it was not included in the averaQe.

STATION NUMBER AND DATE Be-7 K-40 SA-APT-2S2 12-29-80 to 69+/-7 6.6+/-5.2 3-:rl-81 3-:rl-81 to 99+/-10 <7.2 6-29-81 6-29-81** to 110+/-11 <11 9-28-81 _pa -..J SA-APT-5Sl 12-29-80 to 67+/-7 4.9+/-4.3 3-:rl-81 3-30-81 to 83+/-9 <13 6-29-81 6-29-81** to 92+/-9 <15 9-28-81 SA-APT-501 12-29-80 to 65+/-7 5.0+/-4.7 3-30-81 3-:rl-81 to 91+/-10 <9.1 6-29-81 6-29-81** to 87+/-9 <15 9-28-81 TABLE C-3 CONCENTRATIOflS OF GIU*lMA EMITTERS* IN QUARTERLY COMPOSITES OF AIR PARTICULATES Results in Units of 10-3 pCi/m3 +/- 2 sigma Mn-54 Nb-95 Zr-95 Ru-103 Ru-lOfi Sb-125 0.6+/-0.3 85+/-9 40+/-4 15+/-2 8.1+/-4.0 <2.3 2.3+/-0.5 100+/-10 39+/-4 13+/-1 26+/-5 <2.3 <0.9 17+/-2 6.6+/-0.9 1.1+/-0. 7 9.7+/-4.4 <2.0 <O. 7 63+/-6 29+/-3 13+/-1 <6.1 <2.1 2.2+/-0.6 110+/-11 39+/-4 11+/-1 23+/-6 <2.,9 <0.9 17+/-2 6.0+/-1.1 <1.4 <11 <2.5 <0.6 61+/-6 27+/-3 12+/-1 <8.3 <2.2 . 2.1+/-0.5 120+/-12 46+/-5 13+/-2 24+/-7 <3.2 \\ <1.0 14+/-1 7.2+/-1.2 <1.4 7.4+/-4.8 "<_2.8 Cs-137 Ce-141 Ce-144 1.2+/-0.4 11+/-1 31+/-3 4.6+/-0.5 7.9+/-1.2 89+/-9 1.9+/-0.5 <1. 7 30+/-3 1.1+/-0.4 12+/-1 28+/-3 4.7+/-0.6 8.1+/-1.4 95+/-10 2.0+/-0.6 <1.9 29+/-4 0.9+/-0.5 11+/-1 30+/-3 5.1+/-0.7 8.3+/-1.4 110+/-11 2.5+/-0.6 <1.9 29+/-4

STATION NUMBER AND DATE SA-APT-lODl 12-29-80 to . 3-31-81 3-31-81 to 6-30-81 6-30-81** to 9-28-81 SA-APT-16El 12-29-80 to 3-31-81 3N31-81 to 6-30-81 6-30-81** . to 9-28-81 SA-APT-lfl 12-29-80 to 3-30-81 3-30-81 to 6-29-81 6-29-81** to 9-28-81 Be-7 K-40 48+/-6 <8.8 84+/-9 <13 88+/-9 <13 65+/-7 6.9+/-5.2 78+/-10 <15. 88+/-9 <8.2 49+/-8 <9.7 74+/-9 <9.8 95+/-10 6.9+/-5.5 TABLE C-3 (cont.) CQljCENTRATIONS OF GAMI*1A EMITTERS* IN QUARTERLY COMPOSITES OF AIR PARTICULATES Results in Units of 10-3 pCi/m3 +/- 2 sigma Mn-54 tlb-95 Zr-95 Ru-103 Ru-106 Sb-125 Cs-137 <0.6 52+/-5 21+/-2 10+/-1 8.4+/-4.1 <1.9 . 1.1+/-0.4 2.2+/-0.6 100+/-10 40+/-4 11+/-1 20+/-6 4.9+/-0.6 <0.9 15+/-2 5.1+/-1.0 <1.3 <8.4. <2.4 2.4+/-0.6 <0.6 60+/-6 26+/-3 12+/-1 7.6+/-4.1 <2.2 1.4+/-0.5 2,0+/-0.6 100+/-10 38+/-4

9. 8+/-1. 3 17+/-6

<3.3 5.5+/-0.8 <0.6 16+/-2 5.9+/-0.8 <0.9 13+/-5 <l. 7 2.1+/-0.5 <0.9 60+/-6 25+/-3 11+/-1 <8.4 <2.2 1.2+/-0.5 2.8+/-0.6 89+/-9 33+/-3 8.8+/-1.3 19+/-5 .. <2.8 4.2+/-0.7 0.9+/-0.5 16+/-2 6.5+/-0.9 <0.9 <9.2 -<2.0 2.2+/-0.5 Ce-141 Ce-144 10+/-1 24+/-2 6.4+/-1.4 95+/-10 <2.1 30+/-4 11+/-1 29+/-3

6. 7+/-1.5 83+/-8

<1.8 34+/-4 12+/-1 29+/-3 6.8+/-1.6 86+/-9 <1.9 34+/-4

TABLE C-3 (cont.) COfJCEtlTRATIOfJS OF GAMMA EMITTERS m QUARTERLY COMPOSITES OF AIR PARTICULATES ~ I

Results in Units of 10-3 pCi/m3 +/- 2 si~ma (All Results by PSE&G Research Corp.

STATION SAMPLED 9-28-81 to 12-28-81~ Be-7 K-40 Mn-54 fjb-95 Zr-95 Ru-103 Ru-106 Sb-i25 Cs-137 Ce-141' Ce-144 SA-APT-2S2 39+/-2 <30 <0.3 <0.3 <0.4 <0.3 <2.1 <0.7 0.3+/-0.1 <0.2 <1.9 SA-APT-5Sl 36+/-3 <42 <0.6 <0.6 <1.1 <0.5 <4.3 <1.4' <0.5 <0.7

1. 5+/-0.8 U1 C>

SA-APT-501 37+/-4 <38 <0.4 0.5+/-0.3 <0.8 <0.5 <4.0 <1.3 <0;6 <0.7 1.9+/-0.9 SA-APT-1001 35+/-5 <37 <0.G 0.7+/-0.4 <1. 3 <0.7 <0.6 <1.6 <O.7 <1.0 <3.5 SA-APT-16El 33+/-4 <37 <0.5 <0.6 <0.7 <0.5 <3.8 . <1.J <0.4 <0.7 <2.4 SA-APT-lFl 37+/-4 <38 <0.4 <O.6 <0.8 <0.5 <3.9 . <1.3 <0.4 <0.6 1.7+/-0.8 SA-APT-2F2 40+/-5 <37 <0.6 <O. 7 <1.2 <0.6 <6.2 <l.fr <0.5 <0.9 <3.5 SA-APT-3H3 39+/-4 <35 <0.6 0.6+/-0.3 <1.3 <0.6 <4.7 <1.5 <0.7 <0.9 <3.3. (Contra l) Program initiated by PSE&G after the third quarter.

i:: U1 TABLE C-4 CONCENTRATIONS OF STROlff IUM-39* AND -90 IN QUARTERLY COMPOSITES OF AIR *PARTICULATE SAMPLES Results in Units of 10-3 pCi/m3 +/- 2 sigma ,January to March April to STATION NUMBER Sr-89 Sr-90 Sr-39 SA-APT-252 7.5+/-0.3 0.4+/-0.3 6.5+/-0.8 SA-APT-5Sl 7.0+/-0.8 0.4+/-0.3 7.6+/-0.9 SA-APT-501 9.3+/-1.3 <0.8 5.9+/-1.8 SA-APT-lODl 7.3+/-0.8 0.5+/-0.3 7.8+/-1.0 SA-APT-16El 6.9+/-0.8 0.4+/-0.4 7.0+/-1.0 SA-APT-lfl 6.9+/-0.9 0.6+/-0.4 8.3+/-1.0 SA-APT-2F2 6.6+/-1.0 0.7+/-0.4 7.2+/-0.9 SA-APT-3H3 (Control)

7. 3+/-1.0 0.3+/-0.4 8.7+/-0.9 Average 7.4+/-1.7 0.6+/-0.4 7.4+/-1.8 Strontium-89 results are corrected for decay to sample stop date.

Program discontinued by RMC after the third quarter *. .lune Sr-90 2.2+/-0.3 1.7+/-0.4 1.2+/-0.7 1.4+/-0.4 1.7+/-0.4 0.3+/-0.4 1.6+/-0.4 2.2+/-0.4 1.6+/-1.0 July to September** Sr-89 Sr-90 0.3+/-0.5 0.5+/-0.,2 1.0+/-0. 5 0.5+/-0.2 0.7+/-0.6 0.6+/-0.2 0.7+/-0.5 0.4+/-0.2 <0.3 0.6+/-0.2 1.3+/-0.6 0.3+/-0.2 0.3+/-0.6 0.7+/-0.3

1. 3+/-0.5 0.8+/-0.2 0.9+/-0.5 0.6+/-0.3

~'.

Ul N STATION NUMBER SA-APT-252 SA-APT-551 SA-APT-501 SA-APT-1001 SA-APT-16El SA-APT-lFl SA-APT-2F2 SA-APT-3H3 {Control) TABLE C-4 (cont.) CONCENTRATIONS OF STRONTIUM-89

AND -90 IN QUARTERLY COMPOSITES OF AIR PARTICULATE SAMPLES.

Results in Units of 10-3 pCi/m3 +/- 2 sigma (All Results by PSE&G Research Corp.) October to December** Sr-89 Sr-90 <0.5 <0.3 <0.6 <0.4 <0.8 <0.6 <0.8 <0.5 <1.6 <0.8 <0.5 <0.4 <0.6 <0.4 <0.8 <0.6 Strontium-89 results are corrected for decay to sample stop da.te. Program initiated by PSE&G after the third quarter.

~..!'JJ\\i'-"'l~J.\\ill&i>ie'!.l'.~iii.~~~;;k\\:i<i':i;iJ~),,~,c;';i~<;'Q;:l,;\\;\\i::,t\\: :£1:'. 0;;-;;?i'i;Ji'J~i:\\::;;: ;;::!~'2k~<~!i'+/-1i:';;'k!:i :u,i~1Hol\\C'f~,£4f1!2.'J.i8.i'T!~-fils;:;;Hti~~d1itj;, i: ~... .".l TABLE C-5 CONCENTRATIONS OF IODINE-131

IN FILTERED /\\IR Results in Units of 10-3 pCi/m3 STATION NO.

SA-AI0-252 SA-AI0-5Sl SA-AI0-5Dl SA-AI0-1001 SA-AI0-16El . SA-AI0-2F2 S~-AI0-3Hi Control MONTH JANUARY** <12 <9.1 <12 <9.9 <11

<11

<12 <11 <9.0 <11 <8.1 <9.1 <11 <11 <12 <9.2 <12 <12 <14 .<11 <13 <12 <9.6 <12 <8.3 <9.7 <11 <11 <12 <8.6 <11 <11 <13 <10 <11 FEBRUARY <11 <9.3 <11 <8.2 <9.4 <11 <11 <9.9 <8.0 <9.6 <9.5 <12 <9.4 <9.9 <13 <13 <13 <10 <10 <12 <14 <12 <8.9 <12 <12 <14 <10 <11 01 w MARCH <11 <11 <11 <8.8 <8.7 <10 <12 <12 <9.5 <12 <12 <13 <9.8 <10 <11 <9.8 <11 <8.5 <9.0 <9.6 <10 <11 <11 <11 <11 <10 <10 <11 1**. I APRIL <12 <12 <13 <13 <12 <13 <12 <16 <15 <20 <14 <16 <17 <17 <10 <12 <12 <14 <13 <10 <12 <13 <13 <15 <15 <14 <12 <14 MAY <9.1 <10 <11 <11 <9.7 <9.9 <11 <6.2 <6.5 <7.0 <5.6 <5.4 <6.2 <6.4 <10 <11 <11 <13 <12 <11 <12 <8.8 <10 <11 <8.6 <7.9 <8.8 <9.8 <11 <14 <t4 <15 <15 <11 <33 JUNE <15 <15 <21 <14 <15 <17 <17 <11 <11 <14 <13 <14 <12 <12 <9.1 <11 <12 <9.3 <8.8 <9.7 <11 <11 <14 <12 <11 <9.7 <12 <11

U1 +::> TABLE C-5 (cont.) CONCENTRATIONS OF IODINE-Bl* lH FILTERED AIR Results in Units of 10-3 pCi/m3 MONTH SA-AI0-2S2 SA-AI0-5Sl SA-AI0-5Dl JULY <12 <15 <14 <12 <16 <14 <11 <14 <13 <12 <16 <13 <11 <13 <13 AUGUST <11 <15 <13 <11 <14 <13 <11 <15 <12 <11 <16 <14 SEPTEMBER <9.2 <14 <11 <19 <26 <25 <11 <16 <14 <11 <15 <16 OCTOBER <10 <36( l) <12 <9.1 <14 <12 <18 <23 <16 <8.3 <13 <12 <9.7 <17 <14 NOVEMBER <11 <14 <13 <9.3 <14 <12 <9.1 <13 <13 <16 <22 <18 DECEMBER <14 <15 <13 <26 <16 <12 <9.9 <12 <12 <9.0 <14 <10 1-131 results are corrected for dee~ to sample stop date. Actual sampling dates can be found on Table C~fi. STATION NO. SA-AIO-lODl <15 <10 <11 <12 <14 <10 <11 <11 <13 <10 <17 <15 <13 <14 <11 <15 <3.5 <15 <9.9 <12 <8.9 <18 <13 <12 <9. 7 <9.6 (1) (2) High LLD due to low sample volume resulting from a power outage. High LLD due to low sarrple volume caused by an obstruction in the air filter line. SA-AI0-16El** <13 <9.3 <9.8 <11 <12 <9.4 <10 <11 <13 <9.3 <16 <14 <12 <12 <9.5 <15 <3.8 <16 <10 <13 <11 <19 <18 <12 <12 <11 SA-AI0-2F2 SA-AI0-3H3 Control <11 <12 <14 <12 <12 <11 .<12 <13 <13 <12 <12 <13 <13 <12 <12 <12 <12 <11 <10 <11 <20 <19 <13 <12 <11 <12 <11 <12 <10 <9.8 <14 <16 I <9.1 <9.9 <8.8 <13 <11 <12 <11 <11 <11 <10 <17 <21 <9.7 <14 <1210 (2) <13 <11 <11 <9.6 <13

l-* [. I. (jJ (jJ MONTH JANUARY FEBRUARY MARCH 252 12-29-80 to 1-05-81 1-05-81 to 1-12-81 1-12-81 to 1-19-81 1-19-81 to 1-26-81 1-26-81 to 2-02-81 2-02-81 to 2-09-.81 2-09-81 to 2-17-81 2-17-81 to 2-23-81 2-23-81 to 3-02-81 3-02-81 to 3-09-81 3-09-81 to 3-16-'81 551 12-29-80 to 1-05-81 1-05-81 to 1-12-81 1-12-81 to 1-19-81 1-19-81 to 1-26-81 1-26-81 to 2-02-81 2-02-81 to 2-09-81 2-09-81 to 2-17-81 2-17-81 to 2-23-81 2-23-81 to 3-02-81 3-02-81 to 3-09-81 3-09-81 to 3-16-81 TABLE C-6 SAMPLING DATES FOR AIR SAMPLES STATION NO. 5Dl ' lODl 16El 12-29-80 12-29-80 12-29-80 to to to 1-05-81 1-05-81 1-05-81 1-05-81 1-05-81 1-05-81 to to to 1-12-81 1-13-131 1-13-81 1-12-81 1-13-81 1-13-81 to to to 1-19-81 1-19-131 1-19-81 1-19-81 1-19-81 1-19-81 to to to 1-26-81 1-27-81 1-27-81 1-26-81 1-27-131 1-27-81 to to to 2-02-81 2-02-81 2-02-81 2-02-81 2-02-81 2-02-81 to to to 2-09-81 2-10-81 2-10-81 2-09-81 2-10-81 2-10-81 to to to 2-17-.81 2-17-81 2-17-81. 2-17-81 2-17-81 2-17-131 to to to 2-23-81 2-24-81 2-24-81 2-23-81 2-24-81 2-24-81 to to to 3-02-81 3-02.:01 3-02-81 3-02-81 3-02-81 3-02-81 to to to 3-09-81 3-10-81 3-10-81 3-09-81 3-10-81 3-10-81 to to to 3-16-81 3-16-81 3-16-81 lFl 2F2 3H3 1-29-80 12-29-80 12-29-80 to to to 1-05-131. 1-05-81 1-05-81 1-05-81 1-05-81 1-05-81 to to to 1-12-81 1-12-81 1-12-81 1-12-81 1-12-81 ' 1-12-81 to to to 1-19-81. 1-19-81 1-19-81 1-19-81 1-19-81 1-19-81 to to to 1-26-81 1-26-131 1-26-81 1-26-~l 1-26-81 1-26-81 to to to 2-02-8i 2-02-81 2-02-81 2-02-61 2-02-81 2-02-81 to to to 2-09-81 2-09-81 2-09-81 2-09-81 2-09-81 2-09-81 to to to 2-17-81. 2-17-131 2-17-81 2-17~8r

2-17-81 2-17-81 to to to 2-23-81 2-23-81 2-23-81 2-23-81 2-23-81 2-23-131 to to to 3-02-81 3-02-8i 3-02-81 3-02-81 3-02-81 3-02-81 to to to 3-09-131 3-09-131 3-09-81 3-09-131 3-09-81 3-09-131 IJ to to to 3-16-81 3-16-81 3-16-81

TABLE C-6 (cont.) SAMPLING DATES FOR AIR SAMPLES STATION liO. 2S2 5Sl 501 1001 16El lfl. 2F2 3H3 3-16-81 3-16-81 3-16-81 3-16-81 3-16-81 3-16-81 3-16-81 3-16-81 to to to to to to to to 3-23-81 3-23-81 3-23-81 3-24-81 3-24-81 3-23-81 3-23-81 3-23-81 3-23-81 3-23-81 '3-23-81 3-24-81 3-24-81 3-23-81 3-23-81 3-23-81 to to to to to to to to 3-30-81 3-30-81 3-30-81 3-31-81 3-31-81 3-30-Bl 3-30-81 3-30-81 3-30-81 3-30-81 3-30-81 3-31-81 3-31-81 3-30-81 3-30~81 3-30-81 to to to to to ta to* to 4-06-81 4-06-81 4-06-81 4-06-81 4-06-81 4-06-=81 4-06-81 4-06-81 4-06-81 4-06-81 4-06-81 4-06-81 4-06-81 4-06-81 4-06-81 4.:06-81 to to to to to to to to 4-13-81 4-13-81 4-13-81 4-14-81 4-14-81 4-13-81 4-13-81 4-13-81 4-13-81 4-13-81 4-13-81 4-14-81 4-.14-81 4-13-ill 4-13-81 4-13-81 to to to to to to to to 4-20-81 4-20-131 4-20-81 4-20-131 4-20-131 4-20-131 4-20-81 4-20-81 4-20-81 4-20-81 4-20-81 4-20-81 4-20-81 4-20-8i. 4-20-81 4-20-81 to to to to to to to to 4-27-81 4-27-81 4-27-131 4-27-81 4-27-81 4-27-81 4-27-81 4-27-81 MAY 4-27-81 4-27-81 4-27-81 4-27-81 4-27-81 4-27-81 4-27-81 4-27-81 to to to to to to to to 5-04-81 5-04-81 5-04-131 5-04-131 5-.04-131 5-0~-81 5-04-81 5-04-81 5-04-81 5-04-131 5-04-81 5-04-81 5-04-81 5-04-81 5-04-81 5-04-131 to to to to to to to to 5-11-81 5-11-131 5-11-81 5-12-81 5-12-81 5-11-81 5-11-81 5-11-131 5-11-81 5-11-81 5-11-81 5-12-81 5-12-81 5-lHll 5-lHJl 5-11-81 to to to to to to : to to 5-18-81 5-18-81 5-18-131 5-18-81 5-18-81 5-18-81 ' 5-18-81 5-18-81 5-18-81 5-18-81 5-18-131 5-18-81 5-18-81 5-rn:.131 5-18-81 5-18-81 to to to to to to to to 5-26-81 5-26-81 5-26-81 5-27-81 5-27-81 5-25.:.31 5-26-81 5-26-81 5-26-81 5-26-81 5-26-81 5-27-81 5-27-81 5-26-fll 5-26-81 5-26-81 to to to to to to to to -.~ **. 6-01-81 6-01-131 6-01-81 6-01-81 6-01-81 6-01-81 6-01-81 6-01-81 {-* ,'1

TABLE C-6 (cont.) SAMPLING DATES FOR AIR SAMPLES STATION NO. MONTH 2S2 551 501 1001 16El lFl 2F2 3H3 JUNE 6-01-81 6-01-81 6-01-81 6-01-31 6-01-31 6-01-31 6-01-31 6-01-31 to to to to to to to to 6-08-81 6-08-31 6-08-81 6-09-31 6-09-81 6-03-81 6-03-31 6-03-31 6-08-81 6-08-81 6-08-81 6-09-81 6-09-81 6-08-81 6-08-81 6-08-31 to to to to to to to to 6-15-81 6-15-81 6-15-31 6-15-81 6-15-81 6-15-81 6-15-81 6-15-81 6-15-81 6-15-81 6-15-81 6-15-81 6-15-81 6-15-81 6-15-81 6-15-81 to to to to to to to to 6-22-81 6-22-81 6-22-31 6-23-81 6-23-31 6-22-81 6-22-81 6-22-31 6-22-81 6-22-81 6-22-81 6-23-31 6-23-31 6-22-81 6-22-31 6-22-81 to to to to to* to to to 6-29-81 6-29-81 6-29-81 6-30-81 6-30-81 6-29-81 6-29-81 6-29-81 (jl JULY 6-29-81 6-29-81 6-29-81 6-30-81 6-30-81 6-29-.31 6-29-31 6-29-81 -....J to to to to to to to to 7-06-81 7-06-81 7-06-31 7-06-81 7-06-31 7-06-31 7-07-31 7-06-81 7-06-81 7-06-81 7-06-81 7-06-81 7-06-81 7-06-8~ 7-07-81 7-06-81 to to to to to to to to 7-13-81 7-13-81 7-13-81 7-14-81 7-14-31 7-13-81 7-13-31 7-13-81 7-13-81 7-13-81 7-13-81 7-14-81 7-14-81 7-13-31 7-13-31 7-13-81 to to to to to to to to 7-20-81 7-20-81 7-20-31 7-21-81 7-21-81 7-20-31 7-20-31 7-20-31 7-20-81 7-20-81 7-20-81 7-21-81 7-21-31 7-20-fll 7-20-31 7-20-81 to to to to to to to to 7-27-81 7-27-81 7-27-81 7-23-31 7-28-81 7-27-81 7-27-81 7-27-81 7-27-81 7-27-81 7-27-81 7-28-81 7-2fl-81 7-27-81 7-27-81 7-27-81 to to to to to to to to 8-03-81 !l-03-81 8-03-!ll 8-03-81 8-03-!ll 8-03-81 8-03-81 8-03-31 AUGUST 8-03-81 8-03-81 8-03-81 8-03-81 8-03-81 8-03-81 8-03-81 8-03-81 to to to to to

to to to 8-10-81 8-10-81 8-10-81 8-11-81 3-lHll 8-10-81 8-10-81 3-10-81 8-10-31 8-10-81 8-10-81 8-11-31 8-11-131 3-10-31 8-10-81 8-10-31 to to to to to to to to 8-17-31 3-17-81 8-17-31 8-18-31 8-18-31 3-17"'-81 3-17-81 3-17-31

~ \\: '*

1*~~~8iiill'll'.1~1&~\\lll~~~i!'fil"'i:t~fiii1"<30\\\\ii:i<~!£0:E:hlf:d+/-"0:f!~,;iz!L\\;.~'Llc:'.7&:ii!i'tir~fr~i~~ili'iiE~~~i'.~PJir;~tl'i\\~fihlbf)j[{ef&ii'ii!l'l'.'L tt~ TABLE C-6 (cont.). I MONTH 551 s01 smPLING ~:;~A:::,:::."'~~:: 0~ AUGUST 8-~~-81 8-i~-81 8-i~-81 8-~~-81 8-~~-81. '*.'j 8-24-81 3-24-81 8-24-81 3-25-81 3-25-81 Ul CD SEPTEMBER OCTOBER* 3-24-81 to 8-31-31 8-31-31 to 9-08-81 9-08-81 to 9-14-31 9-14-81 to 9-21-81 9-21-81 to 9-28-81 9-28-81 to 10-05-81 10-05-81 to 10-13-81 10-13-81 to 10-19-81 10-19-.81 to 10-26-81 10-26-81 to 11-02-31 3-24-81 to 8-31-81 8-31-81 to 9-03-81 9-08-81 to 9-14-31 9-14-81 to 9-2H31 9-21-81 to 9-28-81 9-28-81 to 10-05-81 10-05-81 to 10-13-31 10-13-81 to 10-19-81 10-19-81 to 10-26-81 10-26-81 to 11-02-81 8-24-81 3-25-81 3-25-31 to to to 8-31-81 8-3Hll 8-31-fll 8-31-81 3-31-81 8-31-81 to to to 9-03-31 9-08-81 9-08-81 9-08-81 9-08-81 9-08-81 to to to 9-14-81 9-15-81 9-15-81 9-14-81 9-15-81 9-15-81 to to to 9-21-81 9-21-81 9-21-81 9-21-81 . 9-21-31 9-21-81 to to to 9-28-81 9-28-81 9-28-81 9-23-81 9-28-81 9-28-81 to to to 10-05-81 10-05-81 10-05-81 10-05-31 10-05-81 10-05-81 to to to 10-13-31 10-13-81 10-13-81 10-13-81 10-13-81 10-13-81 to to to 10-19-81 10-19-81 10-19-81 10-19-81 10-19-31 10-19-81 to to to 10-2'6-81 10-27-81 10-27-81 10-26-31 10-27-81 10-27-81 to to to 11-02-31 11-02-31 11-02-81 !Fl !i-17-81 to 8-?4-31 8-24-81 to 8-:n-81 8-31-!il to* 9-08-81* 9-0H-81 to. 9-14-81 9-14~81 to. 9-21-81 9-21-81 to 9-23-81 2F2 8-17-81 to 3-24-81 8-24-81 to S-31-81 3-31-81 to 9-08-81 9-08-81 to 9-14-81 9-14-81 to 9-21-81 9-21-31 to 9-28-81 9-28-81 to 10-05-81 10-05-81 to 10-13-81 10-13-31 to 10-19-81 10-19-81 to 10-26-81 10-26-81 to 11-02-81 3H3 3-17-81 to 8-24-81 8-24-81 to 8-31-81 8-31-81 to 9-08-81 9-08-81 to 9-14-81 9-14-81 to 9-21-81 9-21-81 to 9-28-81 9-23-81 to 10-05-81 10-05-31 to 10-13-81 10-13-81 to 10-19-81 10-19-81 to 10-26-81 10-26-81 to 11-02-81

.:~.

TABLE C-6 (cont.) SAMP.LING DATES FOR AIR SAMPLES STATION NO. MONTH 2S2 5Sl 5Dl lODl 16El lfl. 2F2 3H3 NOVEMBER 11-02-81 11-02-81 11-02-81 11-02-81 11-02-81 11-02-81 11-02-81 to to to to to to to 11-09-81 11-09-81 11-09-81 11-10-81 11-10-81 11-09-81 11-09-81 11-09-81 11-09-81 11-09-81 11-10-81 11-10-81 11-09-81 11-09-81 to to to to to to to 11-16-81 11-16-81 11-16-81 11-16-81 11-16-81 11-16-81 11-16-81 11-16-81 11-16-81 11-16-81. 11-16-81 11-16-81 11-16-81 11-16-81 to to to to to to to 11-23-81 11-23-81 11-23-81 11-24-81 11-24-81 11-23-81 11-23-81 11-23-81 11-23-81 11-23-81 11-24-81 11-24-81 11-23-81 11-23-81 to to to to to to to 11-30-81 11-30-81 11-30-8i 12-01-81 12-01-81 11-30-81 11-30-81 DECEMBER 11-30-81 11-30-81 11-30-81 12-01-81 12-01-81 11-30-81 11-30-81 to to to to to to to 12-07-81 12-07-81 12-07-81 12-07-31 12-07-81 12-08-31 12-07-81 12-07-81 12-07-81 12-07-81 12-07-81 12-07-81 12-08-81 12-07-81 to to to 'to to to to 12-14-81 12-14-81 12-14-81 12-14-81 12-15-81 12-14-81 12-14-81 12-14-81 12-14-81 12-14-81 12-14-81 12-15-81 12-14-81 12-14-81 to to to to to to to 12-21-81 12-21-81 12-21-81 12-22-81 12-22-81 12-21-81 12-21-81 12-21-81 12-21-81 12-21-81 12-22-81 12-22-81 12-21-81 12-21-81 to to to to to to to 12-28-81 12-28-81 12-28-81 12-29-81 12-29-81 12-28-81 12-28-81 Air Particulate program discontinued by RIK after the third quarter. I~

0\\ 0 . ~ TABLE C-7 CONCENTRATIONS OF TRITIUM, GROSS ALPHA AND GROSS BETA EMITTERS. IN PRECIPITATION STATION SA-RWA-2F2 Results in Units of pCi/1 +/- 2 sigma COLLECTION PERIOD H-3* ALPHA BETA 12-29-80 to 2-02-81 <123 <1.1 46+/-5 2-02-81 to 3-03-81 <113 <0.7 35+/-4 3-03-81 to 3-30-81 94+/-59 2.3+/-1.2 67+/-7 3-30-81 to 4-28-81 <100 <0.6 70+/-7 4-28-81 to 6-01-81 <87 <0.9 51+/-5 6-01-81 to 6-29-81 86+/-68 <0.8 19+/-2 6-29-81 to 8-03-81 <109 1.2+/-0.8 30+/-4 8-03-81 to 9-01-81 111+/-74 <0.9 9.1+/-1.6 9-01-81 to 9-28-81 <124 . <1.2 8.1+/-1.6 9-28-81 to 11-02-81 <O. 7 5.9+/-1.9 11-02-81 to 11-30-81 1.2+/-0.8 14+/-3 11-30-81 to 12-29-81 .<0,.6

4. 7+/-1.8 Average 30+/-48 Program dis continued by RMC after.hi rd quarter.

~...

f ~~,\\i!-'iJl'li""~~i;;;;;iii*f"liiii>~~W~-"l,\\lli&""~J><<ili&"'""'""'":'J"'~~"'"'"""'-'""~li'~ii&lBt{i1Kiil1'~ii>lli'18'\\->if;tt~W!illii.i.i'~~,,[ COLLECTION PERIOD TABLE C-7 (cont.) CONCENTRATIONS OF TRITIUM, GROSS ALPHA AND GROSS BETA EMITTERS IN PRECIPITATION STATION SA-RWA-2F2 Results in Uni.ts of pCi/l +/- 2 sigma (All Results by PSE&G Research Corp.) H-3* 9-28-81 to 11-02-81 11-02-81 to 11-30-81 11-30-81 to 12-29-81 <130 140+/-70 <130 Program initiated by PSE&G after the third quarter. i ~* . 0

1*:., O'I i'.. ) TABLE C-8 CONCENTRATIONS OF STRONTIUM-89* AND -90 AND GAMMA EMIITERS** IN QUARTERLY COMPOSITES OF PRECIPITATION STATION: SA-RWA-2F2 Results in Units of pCi/l +/- 2 sigma 12.. 29-80 3-30-80 6-29*81 9-28-81 to to

to.

to .NUCLIDE 3-30-81 6-29-81 9-28-81 12-29-81 Sr-89 Sr-90 Be-7 Zr-95 Nb-95 Ru-103 Ce-141 ( 1) 7.5+/-0.9 3.4+/-0.7 0.6+/-0.4 <0.8 <0.9 0.8+/-0.4 <0.4 1.4+/-0.3 35+/-10 44+/-8 24+/-8 <7.6

4.3+/-1. 3

<O.s0} <O. ff-1) <0.~1) I*' 11+/-1 <o.aOJ' <O.tf-1) <O.6( l) 4.7+/-1.2 3.4+/-1. 7 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. Nuclides not routinely sea.rched for are indicated by a dash (-). LLD for Zr-95 and Nb-95 is that of ZrNb-95.

TABLE C-9 DIRECT RADIATION MEASUREMENTS - MONTHLY TLD RESULTS STATION NUMBER SA-IDM-2S2 SA-IDM-5Sl SA-IDM-6S2 SA-IDM-751 SA-IDM-lOSl 5A-IDM-1151 SA-IDM-5Dl SA-IDM-1001 SA-IDM-14Dl SA-IDM-2El SA-IDM-~El SA-IDM-13E 1 SA-IDM* 16El SA-IDM-lFl SA-IDM-2F2 SA-IDM-SFl SA-IDM-6Fl SA-IDM-7F2 SA-IDM-11 Fl SA-IDM-13Fl SA-IDM-3Gl SA-IDM-2Hl SA-IDM-3Hl SA-IDM-3H3 AVERAGE STATION NUMBER SA-IDM-2S2 SA-IDM-SSl SA-IDM-6S2 SA-IDM-7Sl SA-IDM-lOS 1 SA-IDM-llS 1 SA-IDM-501 SA-IDM-lODl SA-IDM-1401 SA-IDM-2El SA-IDM-3El SA-IDM-13El SA-IDM-16E1 SA-IDM-lFl 5A-IDM-2F2 SA-IDM-5Fl SA-IDM-6Fl SA-IDM-7F2 SA-IDM-llFl SA-IDM-13Fl SA-IDM-3Gl SA-IDM-2Hl SA-IDM-3Hl SA-~DM-3H3 AVERAGE JANUARY FEBRUARY 5.00+/-0.43

6. 38+/-0.52 4.53+/-0.24 5.33+/-0.94 5.11+/-0.34 6.02+/-0.36 6.18+/-0.67 7.43+/-0.41 8.25+/-0.48 fl.31+/-0.69 16.51+/-0.93 12.02+/-0.59 4.77+/-0.50 5.131+/-0.33 5.69+/-0.42 6.42+/-0.56 5.64+/-0.24 6.64+/-0.33 5.13+/-0.10 6.25+/-0 *. 63 4.75+/-0.17*

6.09+/-0.84 4.93+/-0.37 6.16+/-0.92 5.39+/-0.26 6.36+/-0.52

5. 30+/-0. 35 6.55+/-0.59 4.40+/-0.21 5.10+/-0.32 4.80+/-0.14 6.17+/-1.02

4. 22+/-0.16 5.24+/-0.41 3.61+/-0. 22 4.49+/-0.41 5.62+/-0.31 6.99+/-0.138 5.01+/-0.53 6.02+/-0.18 5.69+/-0.43 6.87+/-0.53 5.61+/-0. 23 6.92+/-0.77 5.58+/-0.84 6.87+/-0.22 5.23+/-0.38 6.50+/-0.513

5. 71+/-4.91 6.56+/-2.82 JULY AUGUST

4. 71+/-0.57 4.75+/-0.17 4.61+/-0. 30 4.05+/-0.25 5.62+/-0.42 4.60+/-0.27 5.42+/-0.64 5.28+/-0.45 6.35+/-1.13 5.34+/-0.49 5.53+/-1.07 4.64+/-0.27 4.64+/-0. 39 4.66+/-0.18 6.13+/-1.03 5.43+/-0.41 7.27+/-3.21 5.54+/-0.60 5.29+/-0.22 4.88+/-0.32 5.65+/-0.61 4.87+/-0.81 5.02+/-0.54 4.130+/-0.89 5.85+/-0.71 4.83+/-0.413 5.20+/-0.38 5.00+/-0.47 4.02+/-0.23 3.95+/-0.51 4.85+/-0.47 4.84+/-0.64 4.10+/-0.20 3.96+/-0. 76 3.59+/-0.43 3.77+/-0.23 5.74+/-0.44 5.24+/-0.83 4.91+/-0.28 4.86+/-0.83 6.04+/-1.05 5.31+/-0.41 5.90+/-0.91 5.27+/-0.86 5.21+/-0.63 5.19+/-0.40 5.15+/-0.61 5.29+/-0.58 5.28+/-1.62 4.85+/-0.99 The standard month = 30.4 days.

mrad/standard month* MARCH APRIL MAY 5.83+/-0.14 5.08+/-0.68 4.82+/-0.13 5.15+/-0.34 4.58+/-0. 77 3.65+/-0.34 5.65+/-0.37 4.77+/-0.75 4.16+/-0.14 7.35+/-0.96 5.63+/-1.31

5. 34+/-0.13 7.92+/-1.~8 5.97+/-0.89 5.78+/-0.46 9.00+/-0.52 7.80+/-0.82 6.98+/-1.19 5.45+/-1.10 4.61+/-0.74 4.31+/-0.16 6.26+/-0.66 6.10+/-0. 36

4. 73.+/-0.69.

()._42+/-0.70

5.56+/-0.31 4.87+/-0.29 6.43:!;1.2[!

5.48+/-0.62 4.39+/-0.65 5.89+/-0;39 5.04+/-0.14 4.28+/-0.23 6.13+/-0.54 .5.26+/-0.54

4. 35+/-0.16

6. 75+/-0. 75 5.46+/-0. 33 4.95+/-0.58 6.29+/-0.06 5.31+/-0.66 4.94+/-0.59 5.07+/-0.65 4.39+/-0.16 3.63+/-0.69 6.45+/-0.30 4.65+/-0.13 4.55+/-0.87 5.26+/-0.73 4.36+/-0.33 3.60+/-0. :JO 4.77+/-0.51 3.87+/-0.20 3.28+/-0.61 6.64+/-0.25 5.77+/-0.79 4.87+/-0.36 5.93+/-0.26 5.15+/-0.41 4.73+/-0.31 6.63+/-0.80 5.71+/-0.22 4.97+/-0.67 7.14+/-0.92 5.46+/-0.64 5.91+/-0.93 6.65+/-0.138 5.73+/-0.85 5.03+/-0.81 6.52+/-0.70 5.84+/-0.13 5.01+/-0.58 6.32+/-1.88 5.32+/-1.56

4. 72+/-1.62 SEPTEMBER OCTOBER NOVEMBER 5.54+/-0.31 4.119+/-0.33 4.138+/-0.57 4.56+/-0.28 4.65+/-0.71l 4.25+/-0.23 4.96+/-0.20 5.60+/-0.47 5.16+/-0. 39.

6.10+/-0.91 6.29+/-0. 70 5.61+/-0.31l 6.29+/-0.38 6.06+/-0.21 6.lll+/-0.64 5.07+/-0.56 5.78+/-0.54 9.24+/-0.90 4.99+/-0.26 5.31+/-1.29 4.83+/-0.63 5.91+/-0.51 5.94+/-0.29 5.37+/-0.61 5.74+/-0.90 5.68+/-0.30 5.26+/-0. 77 5.74+/-0.25 5.39+/-0.80 5.013+/-0.79 5.43+/-0.48

5. 26+/-0.31

4. 71+/-0.19 4.91+/-0.56 5.49+/-0.15 4.81+/-0.56 5.84+/-0. 79 5.14+/-1.25 5.09+/-0.40 5.35+/-0.91 5.63+/-0.25 5.68+/-0.64 4.35+/-0.38 4.37+/-0.55 4.22+/-0.25 5.10+/-0.25 5.73+/-0.46 5.26+/-0.43 4.52+/-0.64 4.68+/-0.91 4.15+/-0.34 3.99+/-0.40 4.26+/-0.46 3.93+/-0.37 6.29+/-0.73 6.32+/-0.36 5.66+/-0.81 5.65+/-0.21 5.37+/-0.64 5.22+/-0.65 5.84+/-0.61 5.95+/-0.92 5.56+/-0.45 5.78+/-0.42 5.94+/-0.96 5.63+/-0.32 5.92+/-0.51 5.97+/-0.28 5.10+/-0.54 5.97+/-0.76 5.86+/-0.71 5.81l+/-0.73 5.41+/-1.26 5.48+/-1.15 5.31+/-2.10 63 JUtlE 5.18+/-0.30 4.44+/-0.39 4.33+/-0.58 5.28+/-0.73 6.00+/-0.87 5.74+/-0.31 4.67+/-0.53 5.58+/-0.54 4.96+/-0.43.

5.17+/-0.19 4.87.+/-0.59 4.61+/-0.57 4.93+/-0.32 5.39+/-0.44 4.24+/-0.57 4.99+/-0.48 4.13+/-0.56 4.21+/-0.28 5.66+/-1.10 4.38+/-0.36 5.96+/-0.51 5.23+/-0.72 5.36+/-0.25 5.55+/-0.49 5.08+/-1.14 DEW1£lER AVERAGE

5. 72+/-1.06 5.23+/-1.05 4.97+/-0. 313 4.56+/-0.92 5.73+/-0.39 5.14+/-1.19 6.13+/-0.41 6.00+/-1.49 6.48+/-0.49 6.63+/-1.99 5.73+/-0.46 7.84+/-6.96 5.51+/-0.19 4.96+/-0.91 5.66+/-0.30 5.77+/-0.93 5.98+/-0.80 5.80+/-1.39 5.71+/-0.24 5.41+/-1.13 5.50+/-0.45 5.20+/-1.07 5.25+/-0.43 5.15+/-1.13 5.47+/-0.23 5.55+/-1.35 5.ll0+/-0.20 5.54+/-0.98 4.56+/-0.77 4.36+/-0.34 5.26+/-0.88 5.22+/-1.20 5.14+/-0. 75 4.45+/-1.07 4.37+/-0.30 4.05+/-0.97 6.04+/-0.51l 5.90+/-1.13 5.78+/-0.47 5.30+/-0.91 5.130+/-0.36 5.86+/-1.03 6.29+/-0.56 5.92+/-1.20 6.51+/-0.56 5.81+/-1.24 6.20+/-0.46

5. 75+/-1.02 5.67+/-0.99 5.47+/-2.32

","

;7*,-,.,:!* '**;*," ;, ' ~ '.

"*' '**"*<.'" -*.*; '<*.,. *** * * *::-* *,. '":"' ;. "~" ~*: *.*.~.' 'T '* ~." *" ', ' "*<" -: *. " * '**~ *', ',*,' *' *

~
f.*.~ *

' * '*'" 1

*: *.* '* _ *" * *'** ** *" *~ *' * ****

m .p, TArlLE C-10 DIRECT RADIATIOll t1EASUl!Et1ENTS - QUARTrnL Y TLO RESULTS mrad/standard month* .JANUARY APRIL JULY to to to STATION NUMBER MARCH .JUNE SEPTEMBER SA-IOM-2S2 5.67+/-0.18 4.70+/-0.40 4.09+/-0.63 SA-IDM-5Sl 5.06+/-0.23 3.93+/-0.43 4.32+/-0.19 SA-IDM-6S2 6.00+/-0.82 4.73+/-0.39 4.74+/-0.11 SA-IDM-7Sl

6. 77+/-1.01 5.53+/-0.29 5.32+/-0.41 SA-I OM-lOS 1 8.93+/-0.44 6.26+/-0.49 5.32+/-0.46 SA-IDM-llS 1 14.45+/-1.57

6. 29+/-{). 80 4.94+/-0.78 SA-IDM-501 5.31+/-0.43 4.59+/-0.64 4.63+/-0.31 SA-IDM-1001 6.29+/-0.41 5.25+/-0.37 5.36+/-0.5G SA-IDM-1401 6.14+/-0.58 4.92+/-0.52 5.13+/-0.31 SA-I DM-2El 6.41+/-0.29 4.37+/-0.30 4.97+/-0.41 SA-IDM-3El

5. 95+/-0. lff 4.6.0+/-0.43 4.33+/-0.34 SA-IDM-13E 1 5.62+/-0.26 4.43+/-0.J.5 4.fll+/-0.40 SA-IDM-16El 6.18+/-0.52 4.97+/-0.37

5. l6iD.20 SA-I OM-lFl 6.41+/-0.46 4.fl9+/-0.17 5.02+/-0.33 SA-IDM-2F2 5.15+/-0.115 3.92+/-0. 22 3.87+/-0.32 SA-IDM-5Fl 5.76+/-0.[ll 4.69+/-0.25 4.67:t0.90 SA-IDM-6Fl 4.fl2+/-0.30 3.94+/-0.03 4.11+/-0.12 SA-IDM-7F2 4.39+/-0.30

3. 31+/-0. 79 3.51+/-0.32 SA-IDM-llFl 6.35+/-0.99

5. 71+/-0.53 5.81+/-0.16 SA-IDM-13Fl 6.26+/-0.54 4.95+/-0. 18 5.11+/-0.43 SA-IDM-3Gl 6.45+/-0.[l4 5.12+/-0.24 5.33+/-0.09 SA-W.J-2Hl 6.53+/-0.49 4.90+/-0.15 5.29+/-0.52 SA-IDM-3Hl 6.57+/-0.58 5.46+/-0.97 5.67+/-0.4li SA-IDM-3H3 5.97+/-0.82 5.03+/-0.30 5.14+/-0.43 AVERAGE 6.40+/-3.84 4.87+/-1.40

4. 90+/-1. rn The standard month = 30.4 days.

OCTOOE!l to

oi:rnmrn 4.931:0 ~ 73 4.* 23+/-0.61 5.02+/-0.62 5.99+/-0.14 5.35J:0.60 7.03+/-0.93

5. ll:t0.51 5.49+/-0. 36

5. 71+/-0.22

5. 30+/-0.45 5.10+/-0.22

5. lQ+/-O. 36 5~65J.0.26 5.46:tO. rn

.4.0U-0.4*1

4. 72:tl.15

4. 75:c0.39 4.03J.0.23 5.li5t0.37 4.97+/-0. 36 5.42:t0.30 5.33+/-0.33

~i. 75.':0.67 5

73 J.0*. 1)3

5. 2CJ+/-l. 34 AVERAGE 4.35+/-1. 31 4.40+/-0.95 5.12+/-1. 20 6.03+/-1.06 6.59+/-3.21 3.18+/-8.54 4.92+/-0.69 5.60+/-0.94 5.43+/-1.11

5. 39+/-1. 41 5.12+/-1.13 4.99+/-1.00 5.49+/-1.08 5.45+/-1. 38 4.24+/-1.22 4.96+/-1.07 4.41+/-0.89 3.31+/-0.93 5.88+/-0.64 5.32+/-1.26 5.58+/-1.19 5.65+/-1.46

5. 36+/-0. 97 5.47+/-0.91 5.37+/-2.52

m U"1 STATION NO. SA-IDM-4D2 SA-IDM-9El SA-IDM-11E2 SA-IDM-12El SA-IDM-2F5 SA-IDM-3F2 SA-IDM-3F3 SA-IDM-10F2 SA-IDM-12Fl SA-I DM-13 F2 SA-IDM-13F3 SA-I DM-14F2 SA-IDM-15F3 SA-I DM-16 F2 SA-IDM-1G3 SA-IDM-lOGl SA-I DM-16Gl AVERAGE TABLE C-11 DIRECT RADIATION MEASUREMENTS - SEtH-A!mUAL TLD RES.UL TS mrad/standard month* SEPTEMBER APRIL TO TO MARCH SEPTEMBER 5.91+/-0.45 4.97+/-0. 46 6.13+/-0.90 5.52+/-0.74 6.43+/-0.57 5.81+/-0.68 6.12+/-0. 33

5. 77+/-0.27 5.28+/-0.19 4.98+/-0.32 5.27+/-0.24 4.61+/-0.32 4.92+/-0.31 4.40+/-0.26 5.83+/-0.70 5.50+/-0.13 5.118+/-0.90 5.34+/-0.33

5. 76+/-0.87 5.12+/-0.21 5.80+/-0.93 5.11+/-0.33 5.58+/-1.06 5.02+/-0.33 6.11+/-0.59 5.84+/-0.39 4.88+/-0.33 4.95*+/-0. 74 5.91+/-0.09 6.30+/-0.74 5.55+/-0.18

5. 71+/-0. 51 5.84+/-0.22 6.23+/-0.81 5.72+/-0.85 5.36+/-1.07 The standard month = 30.4 days.

AVERAGE 5.44+/-1.33 5.83+/-0.86 6.12+/-0.88 5.95+/-0.49 5.13+/-0.42 4.94+/-0.93 4.66+/-0. 74 5.67+/-0.47 5.61+/-0. 76 5.44+/-0.91 5.46+/-0.98

5. 30+/-0. 79 5.98+/-0.38 4.92+/-0.10 6.11+/-0.55 5.63+/-0.23 6.04+/-0.55 5.54+/-1.02

TABLE C-12 CONCENTRATIONS OF TRITIUM IN SURFACE ~*JATER Results in Units of pCi/l +/- 2 sigma STATION NO. 2-17-81* 3-04-81 4-10-81 5-06-81 6-0.1-81 7-08-81 SA-SWA-1 lAl 412+/-79 <102 <103 <89 97+/-62 <115 SA-SWA-12Cl 99+/-76 75+/-65 206+/-63 58+/-54 <100 <115 SA-SWA-7El 102+/-76 <102 <103 <94 <100 <115 SA-SWA-1F2 123+/-76 <102 <103 77+/-58 <87 <115 SA-SWA-16Fl <123 77+/-65 238+/-63 <89 <100 128+/-64 Average 172+/-270 92+/-?9 151+/-132 81+/-29 97+/-11 118+/-12

l.

{J) CJ) STATION NO. 8-05-81 9-08-81 10-07-81 ** 11-03-81

12-14-81 AVERAGE

~*.** : SA-SWA-llAl <130 322+/-70 171+/-248 SA-SWA-12Cl <131 246+/-69 113+/-73

113+/-64

. 93+/-71 123+/-111 SA-SWA-7El 133+/-80 279+/-69 129+/-124 SA-SWA-1F2 <130 301+/-69 130+/-143 SA-SWA-16 Fl <131 82+/-65 195+/-74 <102 104+/-71 124+/-100 Average 131+/-2 246+/-192 154+/-116 108+/-16 99+/-16 134+/-146 No surface water samples were collected in January. Program was reduced after the third quarter. For quality assurance purposes, station SWA-12Cl continues to be analyzed for tritium on a monthly basis by RMC; in addition, one station a quarter is selected by PSE&G to receive a monthly tritium analysis **

CTI TABLE C-12 (cont.) CONCENTRATIONS OF TRITIUM IN SURFACE WATER Results in Units of pCi/l +/- 2 sigma (All Results by PSE&G Research Corporation) STATION NO. 10-05-81* 11-03-81 12-14-81 SA-SWA-llA 1 <120 150+/-80 <130 SA-SWA-12C 1 170+/-80 180+/-70 <130 SA-SWA-7El 180+/-70 180+/-70 <130 SA~SWA-1F2 <120 210+/-80 160+/-80 SA-SWA-16Fl 160+/-70 130+/-70 190+/-80 Average 150+/-50 '170+/-56 Program initiated by PSE&G after the third quarter. .. 1*:* AVERAGE 160+/-44 163+/-48 Hi3+/-'74 160+/-48

TABLE C-13 CONCENTRATIONS OF GROSS ALPHA EMITTERS IN SURFACE ~~ATER Results in Units of pCi/l +/- 2 sigma STATION NO. 2-17-81* 3-04-81 4-10-81 5-06-81 6-01-81 7-08-81 i* SA-SWA-llAl <0.3 <0.4 <0.3 <0.6 <0.5 <0.5 SA-SWA-12Cl <0.3 <0.4 0.2+/-0.2 <0.6 <0.3 <0.5 SA-SWA-7El <0.3 <0.4 <0.3 <0.5 <0.5 <0.5 SA-SWA-1F2 <0.3 <0.4 <0.3 <0.6 <0.5 <0.5 Cf) SA-SWA-16Fl <0.4 <0.4 <0.3 <0.6 <0.8 <0.5 co STATION NO. 8-05-81 9-08-81 10-05-rn 11-03-81 "12-14-31 SA-SWA-llAl <0.4 <0.4 0.8+/-0.4 0.3+/-0.2

o. 3+/-0.2.

SA-SWA-12Cl <0.4 <0.4 0.4+/-0.3 0.2+/-0.2 <0.2 SA-SWA-7El <0.4 <0.4 <0.5 0.3+/-0.3 <0.2 SA-SWA-1F2 <0.4 <0.4 <0.4 0.2+/-0.2 0.2+/-0.1 SA-SWA-16Fl <0.4 0.3+/-0.3 0.4+/-0.3 <0.5 <1.3 No surface water samples were collected in tlanuary.

,ifil.~Jiiii,-~~~;,i~'.~K~c;:J;,;~:;,~,6"~C;<;;;,;,; :Ci;;;;;;;;;.* :,,~,;J;.,>:;i:~A'.~.C;:i~*~, i... ~,.;,Q(:;.: :~.:L.,,;:.::~<.:~; ~1Lt::.* :.;;').;}~~;~:;'.\\l£i.'.:*.

f TABLE C-14 COl~CEIHRATIONS OF GROSS OETA EIUTTERS m SURFACE ~~ATER Results in Units of pCi/l +/-.2 sigma STATION NO. 2-17-81* 3-04.:..81 4-10-81 5-06-81 6-01-81 7-08-81 SA-SWA-llAl 76+/-8 78+/-8 49+/-6 76+/-8 26+/-4 37+/-5 SA-SWA-12Cl 39+/-4 42+/-4 39+/-5 54+/-6 25+/-4 40+/-4 SA-SHA-7El 37+/-4 38+/-4 60+/-7 85+/-9 41+/-5 33+/-3 SA-SWA-1F2 34+/-3 20+/-2 23+/-4 32+/-4 16+/-3 22+/-2 SA-SWA-16Fl 32+/-3 43+/-4 27+/-4 42+/-5 24+/-3 33+/-3 O'I Average 44+/-37 44+/-42 40+/-31 58+/-45 26+/-18 33+/-14 w STATION NO. B-05-81 9-08-81 10-05-81 11-03-81 12-14-81 AVERAGE SA-SWA-llAl 59+/-6 13+/-3 96+/-10 83+/-8 55+/-6 59+/-52 SA-SHA-12Cl 66+/-7 18+/-4 129+/-13 76+/-8 69+/-7 54+/-61 SA-SWA-7El 122+/-12 114+/-11 82+/-8 68+/-7 50+/-6 66:!:62 SA-SWA-1F2 20+/-3 10+/-3 97+/-10 46+/-5 46+/-5 33+/-43 SA-SWA-16Fl 68+/-7 16+/-4 72+/-7 48+/-5 57+/-6 42+/-36 Average 67+/-73 34+/-8g 95+/-43 64+/-33 55+/-17 51+/-56 No surface water samples were collected in,January.

(1) By ganma spectrometry, all other gamma emitters searched for were <LLD; typical LLDs are*given in Table C-33. No surface water samples were collected in,January. ZrNb-95 was also observed in this sample with a concentration of 1.8+/-0.8 pCi/l

TABLE C-16 CONCENTRATIONS OF STRONTIUM-89* AND -90 IN SURFACE WATER STATION NUMBER SA-SWA-llAl SA-SWA-12Cl SA-SWA-7El SA-SWA-1F2 SA-SWA-16Fl 2-17-81**

to 3-04-81 Sr-89 Sr-90 <0.6 <0.8 <0.3 <0.4 0.5+/-0.5 <0.4 <0.7 0.4+/-0.2 <0.8 0.5+/-0.3 Results in Units of pCi/1 1 +/- 2 sigma 4-10-81 to 6-01-81 Sr-89 Sr-90 <0.9 1.3+/-0.4 0.6+/-0.6 <0.5 <0.8 <0.5 0.7+/-0.5 <0.5 <1.0 <0.6 Sr-89 results are corrected for decay to sample stop date. No surface water samples were collected in January. 7-03-81 to 9-08-81. Sr-89 Sr-90 <1.6 <:0.9 <1.1 <0.6 <1.4 <O. 7 1.5+/-1.2 <0~4 <2.3

l'.1+/-0.8 10-05-81***

to 12-14-81 Sr-89 Sr-90 <0.8 <0.5 <0.8 <0.5 Strontium program was reduced after the third quarter. For quality assurance purposes, s*tation 12Cl continues to be analyzed for Sr-89 and -90 on a quarterly basis by RMC; in addition, one station a quarter is selected by PSE&G to receive a quarterly composite Sr-89 and -90 analysis.

TABLE C-16 (cont.) CONCENTRATIOllS OF STRONTIUM-89* AND -90 IN SURFACE WATER STATION NUMBER SA-SWA-llAl SA-SWA-12C 1 SA-SWA-7El SA-SWA-1F2 SA-SWA-16Fl Results in Units of pCi/l +/- 2 sigma (All Results by PSE&G Resear.ch Corp.) 10-05-81** to 12-14-81 Sr-89 Sr-90 <0.94 <0.68 <1.24 <O. 79 <0.95 <0.68 <0.95 <0.60 <1.22 <0.87 Strontium-89 results are corrected for decay to sample stop date.

- Program initiated by PSE&G after the third quarter.

I' l

TABLE C-17 ~*--.. CONCENTRATIONS OF TRITIUM, GROSS ALPHA AND GROSS BETA EMITTERS, AND POTASSIUM-40 IN. l~ELL WATER 1\\esults in Uni ts of pCi /1 +/- 2 sigma STATION NO. RAD IOACTI V ITV 1-12-81 2-09-31 3-09-31 4-13-31 5-11-81 6-03-31 SA-WWA-4Sl H-3 <105 <122 <102 <103 <94 <158 Alpha <2.5 2.2+/-1.6 <2.4 <2.8 <2.2 <3.6 Beta 11+/-3 15+/-2 11+/-2 12+/-3 13+/-3 13+/-2 K-40 12+/-1

9. 7+/-1.0 9.5+/-1.0 9.5+/-1.0 9.2+/-0,"9 13+/-1 SA-WWA-5Dl H-3

<88 <122 <102 <103 <94 <174 Alpha <1.8 <1.1 <1.8 <2.2 <1.8 <2.9 Beta 3.8+/-2.3 3.9+/-1.3 2.6+/-1.2 14+/-3 14+/-3 15+/-2 K-40 2.9+/-0.3 2.4+/-0.2 2.2+/-0.2 10+/-1 10+/-1 14+/-1 SA-WWA-3El H-3 <88 <122 <102 <103 <94 <174 Alpha <2.1

1. 7+/-1.4

<2.2 <2.4 <1.9 <2.9 Beta 9.2+/-2.6 3.4+/-2.3 7.6+/-1.5' 8.6+/-2.2 3.3+/-2.ll 9.3+/-1.6 K-40 3.2+/-0.8 3.2+/-0.8 9.2+/-0.9 7.2+/-0.7 6.8+/-0. 7 9.6+/-1.0 -i w STATION NO. RADIOACTIVITY 7-13-81 8-10-31 9-14-31 10-13-81* 11-09-31 12-14-31 SA-WWA-4Sl H-3 <91 <130 106+/-74 (1) Alpha <1.9 <3.1 <1.6 <1.1 <2.1 . <2.3 Beta 15+/-3 16+/-3 13+/-2 12+/-2 13+/-3 14+/-3 K-40 14+/-1 2.6+/-0.3 11+/-1 11+/-1 9.6+/-1.0 8.5+/-0.9 SA-WWA-5Dl H-3 <91 <l:iO <120 Alpha <1.6 <2.4 <1.2 <0.3 <1.7 <2.0 Beta 12+/-2 15+/-3 12+/-2 15+/-3 16+/-3 16+/-3 K-40 13+/-1 2.6+/-0.3 11+/-1 12+/-1 11+/-1 8.5+/-0.9 SA-WWA-3El H-3 <91 268+/-82 <120 Alpha <l.O <2.5 <1.3 <0.9 <1.6 <2.0 Beta 9.8+/-1.5 12+/-2 9.0+/-1. 7 10+/-2 !l.f!+/-2.4. *. 8.3+/-2.5 K-40 9.5+/-1.0 1.7+/-0.2 7.8+/-0.ll 7.3+/-0.8 5.f!+/-0.6 5.4+/-0.5 Tritium program was discontinued by Rl*1C after the third quarter. ( 1) Station WWA-4Sl was collected on 9-24-81.

~*.". STATION HO. RADIOACTIVITY Tritium Only* SA-WWA-4Sl SA-WWA-5Dl SA-WWA-3El TABLE C-17 (cont.) CONCENTRATIOflS OF TRITIUM, GROSS ALPHA AND GROSS BETA EMITIERS AND POTASSIUM-40 IN ~/ELL WATER Results in Units of pCi/l +/- 2 sigma (All Results by PSE&G Research Corp.) 10-13-81 <120 <120 <120 11-09-81 <120 <120 <120 Tritium program was initiated by PSE&G after the third quarter. I 12.:.14-81 <120 <120 <120 ~.

TABLE C-18 CONCENTRATIONS OF STRONTIUM-89* AND -90 AND GAMMA EMITTERS** IN QUARTERLY" COMPOSITES OF WELL ~*JATER Results in Units of pCi/l +/- 2 sigma 1-12-81 4-13-81 7-13-81 10-13-81*** STATION NUMBER to to to to RADIOACTIVITY 3-09-81 6-08-81* 9-14-81 12-14-81 SA-WWA-4Sl <O. 7( l) Sr-89 <0.6 <2.2 Sr-90 <0.4 < 1.1 0.4+/-0.3 K-40 <9.3 <9.3 22+/-8 <9.3 CJ'1 SA-W~~A-501 Sr-89 <0.6 <0.8 <0.8 Sr-90 <0.4 <0.4 <0.4 K-40 <9.3 19+/-7 20+/-10 <9.3 SA-W~~A-3E 1 Sr-89 <0.8 <1.2 <0.7 Sr-90 <0.6 <0.6 <0.4 K-40 <9.3 <9.. 3 <9.3 <9.3 Sr-89 results are corrected for decay to sample stop date. All other garrrna emitters searched for were <LLD; typical LLDs are 'given in Table C-33. Sr-89 and -90 program was discontinued by RMC after the third quarter. (1) Stop date for station WWA-4Sl was 9-24-81.

TABLE C-18 (cont.} CONCENTRATIO!JS OF STROiffIW*1-89* /\\rm -90 AND GA!*1i*1A E!'HTTERS IN ~JARTERLY COMPOSITES'OF WELL WATFR Results in Units of pCi/l +/- 2 sigma (All Results by PSE&G Research Corp.) 10-13-81** STATION tWMBER to RADIOACTIVITY 12-14-81 SA-WWA-451 Sr-89 <O. 79 Sr-90 <0.51 O'l SA-WWA-501 Sr-89 <0.56 Sr-90 <0.42 SA-WWA-3El Sr-89 <0.86 Sr-90 <0.53 Sr-89 results are corrected for decay to sample stop date.

- Sr-89 and Sr-90 program was initiated by PSE&G after the third quarter.

-....J -....J TABLE C-19 CONCENTRATIONS OF rnnrur.1, GROSS ALPHA AND GROSS BETA EMITTERS, AND POTASSIUl~-40 Ill RAI~ AND TREATED POTABLE WATER STATION SA-PWA-2F3 Results in Units of. pCi/l +/- 2 sigma RADIOACTIVITY JANUARY FEBRUARY MARCH APRIL MAY H-3 (Raw) <123 <82 <95 <100 <87 (Treated) <123 <113 <95 <100 <87 Alpha (Raw) 0.8+/-0.4 1.2+/-0.5 0.6+/-0.6 l.!l+/-O. 7 1.3+/-0. 7 (Treated) 0.9+/-0.6 0.6+/-0.4 <1.0 0.9+/-0.7 0.6+/-0.6 Beta f Raw) 2.4+/-0.4 4.3+/-0.5 3.!l+/-O.5 3.6+/-0.-4 6.2+/-0.6 Treated) 2.6+/-0.4 2.9+/-0.4 2.9+/-0.4 3.1+/-0.4 3.7+/-0.5 K-40 (Raw) 1.0+/-0.1 0.90+/-0.09 1.1+/-0.1 1.0+/-0.l 1.1+/-0.1 (Treated) 1.1+/-0.l 1.0+/-0.1 1.1+/-0.1 1.0+/-0.l 1.2+/-0.1 RADIOACTIVITY JULY AUGUST SEPTEMBER OCTOBER* NOVEMBER H-3 (Raw) 85+/-67 <120 74+/-73 (Treated) 74+/-67 <120 <119 151+/-77 <116 Alpha (Raw) <0.8 <0.6 1.0+/-0.5 <0.4 0.5+/-0.4 (Treated) <1.1 O.B+/-0.7 <0.5 <0.4 <0.6 Beta (Raw) 5.2+/-0.5 3.4+/-0.5 3.1+/-0.5 2.9+/-0.4 2.6+/-0.5.. (Treated) 3.4+/-0.5 2.7+/-0.4 2.3+/-0.4 1.4+/-0.4 1.9+/-0.5

K-40 f Raw) 1.7+/-0.2 2.2+/-0.2 1.1+/-0.1 1.1+/-0.1 1.4+/-0.1' Treated) 2.1+/-0.2 3.0+/-0.3 1.2+/-0.1 1.2+/-0.1 1.4+/-0.1 Tritium program for raw potable water samples 1~as discontinued hy R11C after the third quarter.

I' ' I JUNE <110 134+/-69 1.2+/-0.7 <0.8 5.2+/-0.5 3.1+/-0.4 1.7+/-0.2 1.7+/-0.2 DECEMBER AVERAGE <122

1. 5+/-0. 6 1.0+/-0.9 1.1+/-0.6 0.8+/-0.5 4.0+/-0.5 3.9+/-2.3 2.6+/-0.5 2.7+/-1.3 2.0+/-0.2 1.4+/-0.9 1.7+/-0.2 1.5+/-1. 2

co STATION RAD IOACTIV ITV SA-PWR-2F3 H-3 SA-PWR-2F3 H-3 ' I TABLE C-19 (cont.) COllCENTRATIOflS OF TRITIUM, GROSS ALPHA Arm GROSS BETA EMITTERS Arm POTASSIUM-40 m RAW AND TREATED POTABLE WATER Results in Units of pCi/l +/- 2 sigma (All Results by PSE&G Research Corporation) OCTOBER* NOVEMBER DECEMBER 180+/-80 <130 <140 140+/-70 <120 <130 ,I AVERAGE Tritium program for raw and treated water samples was initiated by PSE&G after the third quarter.

1

I ~ \\.0 TABLE C-20 CONCENTRATIONS OF STRONTIUM-89* AND _-90, AND GAMMA EMITTERS** IN QUARTER~ Y COMPOSITES OF POTABLE WATER STATION SA-PWA-2F3 Results in Units of pCi/l +/- 2 sigma 1-01-81 4-01-81 7-01 10-01-81 *** to to to to SAMPLE 3-31-81 6-30-81 9-30-81 12-31-81 Raw Sr-89 0.7+/-0.5 <0.3 <O.8 Sr-90 <0.5 0.6+/-0.3 . 0. 7+/-0. 3 *. Garrana Emitters <LLD <LLD <LLD <LLD Treated Sr-89 0.5+/-0.5 <0.9 <0.7 <0.7 Sr-90 <0.5 1.1+/-0.3

o. 3+/-0.'3

<0.5 Gamma Emitters <LLD <LLD <LLD <LLD 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. Strontium program for raw potable water samples was di sconti nueci by RMC after the third quarter. For quality assurance purposes, treated potable water samples continue to be analyzed for Sr-89 and Sr-90 on a quarterly basis.

00 0 TABLE C-20 (cont.) CONCENTRATIONS OF STRONTIUM-89* AND -90 AND GAMMA EMITTERS IN QUARTERLY COMPOSITES OF POTABLE WATER STATION RADIOACTIVITY SA-PWR-2F3 Sr-89 Sr-90 SA-PWT-2F3 Sr-89 Sr-90 Results in Units of pCi/1 +/- 2 sigma (All Results by PSE&G Research Corporation} 10-01-81* to 12-31-81 <0.94 <0.74 <1.19 <0.91 Sr-89 results are corrected for decay to sample stop date. Strontium program for all potable water samples was initiated by PSE&G after the third quarter.

co TABLE C-21 CONCENTRATIONS OF Sr-39* AND -90 IN BENTHOS Results in Units of pCi/g(dry) +/- 2 sigma STATION NUMBER DATE Sr-89 SA-ESB-11Al 6-02-81 <0.5 9-09-81 <0.2 SA-ESB-12Cl 6-02-81 <23 9.. 09-81 <1.6 SA-ESB-7El 6-02-81 <2.7 9-09-81 <2.1 SA-ESB-16Fl 6-02-81 <14 9-09-81 <169** Sr-89 results are decay corrected to sample stop date. High MDL due to small sample size. Sr-90

0. 2+/-0.1 0.36+/-0.09

<6.9 <0.8 <0.8 <1.1 3.0+/-2.8 <86** \\

co N TABLE C-22 CONCENTRATIONS OF STROlffIUJl-90 AND GAHMA* EMITTERS IN SEDIMENT** Results in Units of pCi/g(dry) +/- 2 sigma STATION NO. SA-ESS-llAl SA-ESS-12Cl SA-ESS-7El DATE 6-01-81 9-09-81 6-01-81 9-09-81 Sr-90 0.04+/-0.04 <O.fl5 <0.1 <0.04 K-40 13+/-1 15+/-2 16+/-2 16+/-2 Co-60 <0.06 0.19+/-0.05 <0.04 <0.04 Zr-95 <0.08 <0.1 <0.09 <0.09 Nb-95 <0.06 <0.09 <0.07 <0.07 Cs-137 0.13+/-0.03 0.17+/-0.03 <0.04 <0.04 Ra-226 0.57+/-0.06 0.65+/-0.08 0.60+/-0.06 0.48+/-0.06 Th-232 0.7+/-0.1 0.9+/-0.1 0.86+/-0.09 0.9+/-0.l All other ganuna emitters <LLD; typical LLDs are given in Table C-33. Sediment samples included associated benthic organisms. 6-01-131 9-09-m * <0.05 <0.04 13+/-1 13+/-1 <0.03 <0.05 <0.06 <0.07 0.09+/-0.03 0.08+/-0.04 0.07+/-0.02 0.04+/-0.02 0.49+/-0.05 0.46+/-0.05 0.58+/-0.07 0.47+/-0.08 SA-ESS-16Fl 6-01-fll 9-09-81 <0.06 <0.05 13+/-1 18+/-2 <0.06. <0.05 0.17+/-0.05 <0.08 0.44+/-0.05 <0.07 <0.04 <0.04 0 *. 51+/-0.08 0.57+/-0.07 1.0+/-0.1 1.0+/-0.1

TABLE C-23 CONCENTRATIONS OF IODINE-131 1tl MILK Results* in Units of pCi/l STATION NO. JANUARY** FEBRUARY MARCH APRIL J.IAY JUNE SA-MLK-13E3 <0.1 <0.1 <0.07 <0.09 <0.07 <0.09 <0.1 <0.08 <0.07 <0.08 <0.07 <0.07 SA-MLK-2F4 <0.09 <0.09 <0.07 <O. l <o:o7 <O.OB <0.09 <0.08 <0.07 <0.08 <0.08 <0.07 SA-MLK-5F2 <0.1 <0.1 <0.08 <0.09 <0.06 <0.08 <0.1 <0.08 <0.09 <0.07 <0.09 <0.08 SA-MLK-14Fl <0.1 <0.1 <0.08 <0.09 <0.07 <0.09 <0.1 <0.07 <0.07 <0.08 <.0.08 <0.08 SA-ML K-15 Fl <0.1 <0.1 <0.08 <0.09 <0.07 <0.09 <0.1 <0.07 <0.07 <0.09 <0.09 <0.08 SA-MLK-3Gl <0.2 <0.1 <0.09 <0.1

<0.06

<0.07 OJ <0.09 <0.07 <0.08 <O.07 <0.08 <0.07 w STATION NO. JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER SA-ML K-13E3 <0.1 <0.07 <0.09 <O.1 <0.07 <0.08 <0.08 <0.05 <0.07 <0.09 <0.07 <0.06 SA-MLK-2F4 <0.09 <0.07 <0.08 <0.07 <0.08 <0.1 <0.07 <0.04 <0.07 <O.O!l <0.09 <0.07 SA-MLK-5F2 <0.09 <0.07 <0.09 <0.09 '<0.08 <0.08 <O. l <0.05 <0.09 <0.1 <0.08 <0.07 SA-MLK-14Fl <0.1 <0.08 <0.09 <0.1 (0',09 <0.09 <0.1 <0.04 <0.08 <0.1 <D.1 <0.08 SA-MLK-15Fl <0.1 <0.08 <0.09 <0.2 . <0.1 <0.09 <O.O!l <0.05 <0.09 <0.1 '.<0.1 <0.08 SA-MLK-3Gl <0.09 <0.08 <0.09 <0.07 <0.09 <O. l <0.09 <0.04 <0.07 <0.08 <0.09 <0.07 I-131 results decay corrected to sample stop date. Sampling dates can be found on Table C-?.5.

-~-*~.- ':",_~. ' TABLE C-24 CONCENTRATIONS OF GAMMA EMITTERS* AND STROlffIUM-89** AND -90 IN MILK Results in Units of pCi/l +/- 2 sigma STATION NO. NUCLIDE JANUARY*** FEBRUARY MARCH APRIL MAY JUNE SA-MLK-13E3 K-40 1400+/-140 2000:t200 1500+/-150 1400+/-140 1500+/-150 1300+/-130 Cs-137 <1.2 <1.2 <1.4 1.5+/-1.2

1.8+/-1.2 1.4+/-1.0 Sr-89

<~.3 <5.2 <3.1 <37 (1) <11 (2) <9.6 (2) Sr-90 <1.0 <1. 7 4.6+/-1.4 <3.9 (1) 2'."5+/-0.8 2.8+/-0.9 SA-MLK-2F4 K-40 1600+/-160 1900+/-190 1400+/-140 1300+/-130 1500+/-150 1800+/-180 Cs-137 <1.4 1.5+/-1.2 3.3+/-1.4

1. 7+/-1.2

1. 7+/-1.2 2.3+/-1.1 Sr-89

<2.5 <I3 (2) <4.8 <6.5 <1.9 <12 (2) Sr-90 0.6+/-0.5 2.0+/-0.9 3.5+/-2.0 4.2+/-2.3 2.3+/-0.8 2.4+/-1.1 SA-MLK-5F2 K-40 1500+/-150 1500+/-150 1300+/-130 1700+/-170 1300+/-130 1400+/-140 co Cs-137 <1.2 1.5+/-1.1 1.4+/-0.9 1.5+/-1.0 3.8+/-1.1 6.4+/-1.3 -f::> Sr-89 <2.7 <9.0 4.1+/-3.1 <5.4 <14 (2) 2.7+/-2.5 Sr-90 0.6+/-0.5 3.9+/-1.8 6.3+/-2.1 6.8+/-2.0 6.6+/-1.1 <2.2 STATION NO. NUCLIDE JULY AUGUST SEPTEMBER OCTOBER"'*** l{OVEMBER DECEMBER SA-MLK-13E3 K-40 1300+/-130 1500+/-150 1400+/-140 1500+/-150 1600+/-160 1400+/-140 Cs-137 <l.6 2.6+/-1.1 5.6+/-1.3 <1.4 <1.2 2,0+/-1.1 Sr-89 <3.8 <2.9 <2.1 <4.3 Sr-90

1. 7+/-1.2 6.1+/-1.0 4.4+/-0.8 4.2+/-1.5 SA-MLK-2F4 K-40 1400+/-140 1300+/-130 1400+/-140 1500+/-150 1400+/-140 1900+/-190 Cs-137

2. 7+/-1.2

<1.4 <1.2 3.0+/-1.3 2.~+/-1.2 <1.2 Sr-89 <3.6 <2.6 <6.6

1. 8+/-1.5 Sr-90

<1.8 2.6+/-0.9 2.8+/-1.5 1.7+/-0.9 SA-MLK-5F2 K-40 1500+/-150 1400+/-140 1400+/-140 1500+/-150 i400+/-l40 1600+/-160 Cs-137 6.1+/-1.4 3.1+/-1.2 3.9+/-1.4 <1.4 <1.2" <1.2 Sr-89 <5.1 <2.8 2.0+/-1.4 Sr-90 5.4+/-1.6 5.6+/-1.0 4.1+/-0.8 I . ~. 1>

().'.) U1 TABLE C-24 (cont.) CONCENTRATIO!lS OF GAMMA EMITTERS* AND STRONTIUM-39** AND -90 IN MILK Results in Units of pCi/l +/- 2 sigma STATION NO. NUCLIDE ,JANUARY*** FEBRUARY llARCH APRIL SA-MLK-14Fl K-40 1500+/-150 1600+/-160 1400+/-140 1400+/-140 Cs-137 <1.2 <1.2 <1.2 <1.4 Sr-89 <2.7 <9.8 (2) <3.2 <4.8 Sr-90 <1.0 2.~.+/-0.8 2.9+/-1.3 2.7+/-1.7 SA-MLK-15Fl K-40 . 1600+/-160 1600+/-160 1600+/-160 1400+/-140 Cs-137 <1.4 <1.2 <1.4 2.1+/-1.3 Sr-89 <12 (2) 8.5+/-5.0 <3.4 <25 (2) Sr-90 2.3+/-1.0 4.7+/-2.4 4.0+/-1.4 3.0+/-1.2 SA-MLK-3Gl K-40 1500+/-150 1400+/-140 1400+/-140 1300+/-130 Cs'-137 <1.4

1. 5+/-1. l

<1.4 <1.2 Sr-89 <2.4 <6.9 <48 (2) 3.0+/-2.3 Sr-90 <0.7 4.4+/-1.4 3.9+/-1.4 4.1+/-1.6 STATION NO. NUCLIDE JULY AUGUST SEPTEMBER OCTO~ER**** SA-MLK-14Fl K-40 1300+/-130 1400+/-140 1300+/-130 1600+/-160 Cs-137 <1.6 <1.4 2.6+/-1.4 <1.4 Sr-89 <3.5 <2.8 <4.4 Sr-90 2.0+/-1.1 3.6+/-0.9

2. 7+/-1.5 SA-MLK-15Fl K-40 1400+/-140 1400+/-140 1300+/-130 1300+/-130 Cs-137 1.6+/-1.1

<1.2 2.6+/-1.3 2.7+/-1.4 Sr-89 <6.0 <3.0 <2.!l Sr-90 2.9+/-0.8 4.1+/-1.0 2.9+/-1.0 SA-MLK-3Gl K-40 1500+/-150 1200+/-120 1100+/-110 1300+/-130 Cs-137 2.8+/-1.5 <1.4 <1.4 3.1+/-1.2 Sr-89 <4.2 '<2.4 3.3+/-1.7 <3.4 Sr-90 3.6+/-1.4 5.2+/-0.9 2.9+/-1.0 2.9+/-1.2 All othar garrma emitters searched for were <LLD; typical LLDs are given in Table C-33. Sr-89 results are corrected for decay to sample stop date. MAY JUNE 1400+/-140 1400+/-140 2.6+/-1.1 5.0+/-1. 3 3.5+/-1.6 2.9+/-1.6 3.1+/-1.0 3.4+/-0.9 1200+/-120 1400+/-140 3.1+/-1.0

3. 5+/-1. 3 4.7+/-2.7

<2.7 3.0+/-1.5

2. 7+/-1.0 1700+/-170 1400+/-140 4.4+/-1.3 4.0+/-1.2 4.9+/-2.1 4.2+/-2.3 4.9+/-1.3 5.3+/-1.5 l~OV E~*1BER DECEMBER 1500+/-150 1600+/-160

<1.4 <1.4 <2.5 3.1+/-1.0 1600+/-160 1400+/-140 <1.4 <1.2 1300+/-130 1400+/-140 <1.4 <1.4 <5.2 <1.8 3.4+/-1.9 3.7+/-0.7 Sampling dates can be found on Table C-25. Strontium program was re4uced after ~he thi.r4 quarter.. F?r quality a~surance purposes, station MLK-3Gl continues to be* analyzed for Sr-89 and -90 on a monthly basis by RMC; in addition, one station a month is selected by PSE&G to be analyzed for Sr-!l9 and -90. (1) (2) High MDL due to low chemical yield. High MDL due to long decay period.

co O'I STATION NO. SA-MLK-13E3 SA-MLK-2F4 SA-MLK-5F2 SA-MLK-14Fl SA-MLK-15Fl SA-MLK-3Gl TABLE C-24 (cont.) CONCENTRATIONS OF GAMMA EMITTERS Arm STROlffIUM-89* Alm -90 Ill MILK Results in Units of pCi/l +/- 2 sigma (All Results by PSE&G Research Corp.) NUCLIDE OCTOBER* NOVEMBER Sr-89 <2.10 <1.95 Sr-90

2. 77+/-0. 78 3.13+/-0. 73 Sr-89

<2.19 <1.83 Sr-90 3.27+/-0.80 2.26+/-0.66 Sr-89 <2.10 <2.08 Sr'-90 3.88+/-0.80 4.06+/-0.78 Sr-89 <1.80 <1.92 Sr-90 2.72+/-0.68 3.34+/-0.67 Sr-89 <1.94 <1.94 Sr-90 2.45+/-0. 72 2.74+/-0.73 Sr-89 <2.37 <1.99 Sr-90 4.77+/-0.89 3.86+/-0.75 Sr-89 results are corrected for decay to sample stop date. Strontium program was initiated by PSE&G after the third quarter... DECEMBER <1. 73 2.74+/-0.66 <1.68 1.52+/-0.66 . I <l. 77 4.29+/-0.69 <1.66

1. 98+/-0. 63

<1.67

2. 71+/-0. 65

<1. 72 3.61+/-0.66

TABLE C-25 SAMPLING DATES FOR f.IILK SAMPLES MONTH 13E3 2F4

5F2 14Fl 15Fl 3Gl JANUARY 1-05-81 1-05-81 1-04-81 1-04-!ll 1-04-!ll 1-04-!ll to to to to to.

to 1-06-31 1-06-81 1-05-81 1-05-31 1-05-Ul 1-05-!ll 1-19-81 1-19-81 1-16-81 1-18-!ll 1-13-!ll l-l!l-31 to to to to to to 1-20-81 1-20-31 1-19-81 1-19-!ll 1-19-81. 1-19-31 FEBRUARY 2-02-81 2*02-81 1-31-31 2-01-!ll 2-01-31 2-01-31 to to to to to to 2-03-81 2-03-81 2-02-81 2-02-31 2-02-3.1 2-02-31 2-17-81 2-16-31 2-14-31 2-17-31 2-17-81 2-17-31 to to to to to to 2-18-81 2-17-81 2-17-81 2-13-!ll 2-18-3,1 2-13-131 MARCH 3-02-81 3-02-81 3-02-!ll 3-01-81 3-01-131 3-01-81 to to to to to to 00 3-03-81 3-03-81 3-03-31 3-02-81 3-02-131 3-02-[ll 3-16-81 3-16-81 3-15-81 3-15-81 3-15.-31 3-15-131 to to to to to to 3-17-81 3-17-131 3-16-3.1 3-16-3.1 3-16-31 3-16-131 APRIL 4-06-81 4-05-81 4-06-81 4-06-81 4-05-(31 4-06-31 to to to to to to 4-07-81 4-06-31 4-07-81 4-07-81 4-07~31. 4-07-81 4-20-81 4-19-81 4-20-31 4-21-31 4-19-!li 4-20-31 to to to to to to 4-21-31 4-20-81 4-21-!ll 4-21-!ll 4-20-13i 4-21-!ll MAY 5-04-81 5-03-81 5-04-81 5-05-81 5-03-!ll 5-04-31 to to to to to to 5-05-81 5-04-81 5-05-81 5-05-81 5-05-81 5-05-31 5-18-81 5-17-81 5-17-81 5-17-81 5-17-!ll 5-13-!ll to to to to to to 5-19-81 5-18-81 5-18-81 5-18-81 5-l!l-81 5-19-31 JU.NE 6-01-81 5-31-81 5-31-81 5-31-!ll 5-31-81 6-01-81 to to to to to to r 6-02-81 6-01-31 6-02-81 6-01-!ll 6-01-81 6-02-81 6-15-81 6-14-81 6-13-81 6-14-81 6-14-81 6-15-!ll to to to to to to 6-16-81 6-15-81 6-15-81 '6-15-81 6-15-8~ *. 6-16-31 .\\*.:

~*

,f.'

TABLE C-25 (cont.) SAMPLING DATES FOR MILK SAMPLES MONTH 13E3 2F4 5F2 14Fl 15Fl 3Gl JULY 7-06-!ll 7-06-81 7-05-!ll 7-06-81 7-06-!ll 7-05-81 to to to to to to 7-07-!ll 7-07-81 7-06-81 7-07-81 7-07-!ll 7-06-81 7-20-81 7-20-81 7-18-81 7-20-81 7-20-81 7-19-81 to to to to to to 7-21-81 7-21-81 7-20,-81 7-21-81 7-21-~l 7-20-81 AUGUST 8-03-81 8-03-81 8-03-81 8-03-!ll 8-03-81 !l-02-81 to to to to to to 8-04-81 !l-04-81 8-04-81 8-04-81 8-04-31 8-03-!ll 8-17-81 8-17-81 8-16-81 8-17-81 8-17-81 !l-16-81 to to to to to to 8-18-81 8-18-81 8-17-81 8-Hl-81 8-18-81 8-17-81 SEPTEMBER 9-07-81 9-08-81 9-07-81 9-08-81 9-08-81 9-07-81 to to to to to to co 9-09-81 9-09-81 9-0B-81 9-09-81 9-09-81 9-08-81 co 9-21-81 9-20.-81 9-19-81 9-?.1-81 9-20-31 9-21-81 to to to to to to 9-22-81 9-21-81 9-21-81 9-22-81 9-21-81 9-22-81 OCTOBER 10-05-81 10-04-81 10-05-31 10-04-81 10-04-8.l. 10-05-81 to to to to to to 10-06-81 10-05-81 10-06-81 10-05-81 10-05781. 10-06-81 10-19-81 10-18-81 10-17-81 10-19-81 10-13-81 10-19-81 to to to to* to to 10-20-31 10-19-81 10-19-81 10-20-31 10-19-81 10-20-81 NOVEMBER 11-01-81 11-01-81 10-31-81 11-01-81 11-01-81 . 10-31-81 to to to to to to 11-02-81 11-02-81 11-02-81 11-02-81 11-02-ili 11-02-81 11-16-81 11-15-81 11-16-81 11-15-81 11-15--31 11-16-81 to to to to to to 11-17-81 11-16-81 11-17-81 11-16-81 11-16-81 11-17-81 DECEMBER 12-06-81 12-07-81 12-07-81 12-07-81 12-07-8'1 12-06-81 to to to to to to 12-08-81 12-08-81 12-07-81 12-08-81 12-08-81 12-07-81 12-14-81 12-13-81 12-13-81 12-13-81 12-13-81 12-14-81 to to to to to to 12-15-81 12-14-81 12-14-81 12-14-81 12-14-81 12-15-81

l~~&~it.<iI~; ' '~~&i'\\'-'!iji,(,i;iji;@5:t1dit"1l;>c:~::li1<!&1riii:!l';;;er;2rc:1uL(,{t1;,;"W:,,:,c,: ?:: ::IJ:liii::&;;:1;;,;,,,~,cfatt;;,;ic'1fa:~Lidf1ibJ;Z;;z-o;L;;::,;;c2:ii!itliz, co ID TABLE C-26 CONCENTRATIONS OF GAMMA EMITTERS* IN EDIBLE FISH Results in Uni ts of pCi /~(wet) +/- 2 sigma

I STATION SAMPLING K-40
Cs-137 NUMBER DATE SA-ESF-llAl 6-01-81 to 2.9+/-0.3

<0.003 7-02-81 3-27-81 to 3.5+/-0.4

<O.009 9-18-81 SA-ESF-12Cl 6-01-81 to 3.2+/-0.3

<0.* 009 7-02-81 8-27-81 to 3.8+/-0.4 <O.01 9-18-81 SA-ESF-7El 6-01-31 to 3.3+/-0.3 0.o16+/-0.009 7-02-31 8-27-81 to 4.6+/-0.5 . : <0.009 9-18-81 All other gamma emitters searched for were <LLD;.typfoal LL Os are given in Table C-33. i - *_.

TABLE C-27 CONCENTRATIONS OF STRONTIUM-89* AND -90, AND TRITIUM IN EDIBLE FISH SAMPLES Bones Flesh Aqueous Fraction Organic Fraction (pCi/g(dry) +/- 2 sigma) (pCi/l +/- 2 sigma) (pCi/l +/- 2 sigma) STATION DATE Sr-89 Sr-90 H-3 H~3 SA-ES F-llAl 6-01-81 to <0.2 <0.08 82+/-63 317+/-72 7-02-81 8-27-81 to <0.08 <0.05 <110 <112 9-18-81 l.O 0 SA-ESF-12Cl 6-01-81 to <0.09 0.04+/-0.03 <86 <112 7-02-81 8-27-81 to <0.06 <0.04 <110 <112 9-18-81 SA-ESF-7El 6-01-81 to <0.09 0.05+/-0.03 <86 156+/-70 7-02-81 8-27-81 to <0.07 <0.04 83+/-68 126+/-69 9-18-81 Sr-89 results are corrected for decay to sample stop date.

TABLE C-28 CONCENTRATIONS OF GAMMA EMITTERS* IN BLUE CRAB SAMPLES Results in Units of pCi/g(wet) +/- 2 sigma STATION NUMBER DATE SAMPLE TYPE K-40 SA-ECH-llAl 6-01-81 to Flesh 1.7+/-0.2 7-02-81 l.D 8-27-81 to Flesh 2.1+/-0.2 9-18-81 SA-ECH-12Cl 6-01-81 to Flesh - _ 2.5+/-0.3 7-02-81 8-27-81 to Flesh 2.1+/-0.2 9-18-81 All other gamma emitters <LLD; typical LLDs are given i-n Table* C-33.

'.**I \\.:: TABLE C-29 CONCENTRATIONS OF STRONTIUM-89* AND -90 AND TRITIUM IN BLUE CRAB SAMPLES STATION NUMBER SA-ECH-llAl SA-ECH-12Cl DATE 6-01-81 to 7-02-81 8-27-81 to 9-18-81 6-01-81 to 7-02-81 8-27-81 to 9-18-81 Sr-89 SAMPLE pCi/g +/- 2 sigma Flesh <0.02 Shell 0.8+/-0.2 Flesh <0.08 Shell <0.1 Flesh <0.01 Shell

1. 7+/-0.2 Flesh

<0.06 Shell <0.08 Sr-89 results are corrected for decay to sample stop date. Indicates tritium analysis not *performed on shells. Sr-90 pCi/g +/- 2 sigma <O.007 0.94+/-0.09. 0.07+/-0.02 0.24+/-0.04 0.007+/-0.004 1.0+/-0.1 0.03+/-0.02 0.28+/-0.04 H-3 (Edible Portion) pCi/l +/- 2 sigma <86 123+/-68 <86 <110

1~~~~~~1~.E.z~.:~~:~~.~~;Sk:~.~:'1~~tk::*:rt.;:~~~2~i~i.!:.~~;~fi<~~:{~~.s~(i~;,:,-:;Zi~~:.~.. :~!}i:;.:~~~::r;~:'.1~~i~;.-;~@~*i}':isi~t~tf;~~t;i:;*:~*t~:~;_;~:!.\\f~1~~£~~*;*f::i..~*~f~;-~:~i~'~;~!.~:~L:::.{:J.;"*;.:t:~:;~~1.t~r!W~~;~~-~~-!::~~~~<5~\\:~.~~.:!S:t2i.. '.f\\!_7:,}Y~1!f::~~:1~~*';.r.;~.. ~t~~t:~~:l:~,:J[;1;:!.l~1:;.:.}.:,SjJ:;E~s~.i.:._~:.:_*~:~.~.:~~\\:.:-**

.. :i;(~~~~:;:i},(,';;:::.*/;f~'.;;~~~-h;1!;)i~8;:t-... *. ~;! ~ TABLE C-30 CONCENTRATIONS OF GAMMA EIHTTERS* AND STRONTIUM-89** AND -90 IN FOOD PRODUCTS Results in Units of pCi/g(wet) +/- 2 sigma STATION NO. DATE SAMPLE TYPE K-40 Sr-89 Sr-90 SA-FPV-2El 5-03-81 Asparagus 2.2+/-0.2 <0.01 <0.007 SA-FPV-2El 7-27-81 Peppers 2.0+/-0.2 <0.006 <0.003 SA-FPL-1F3 7-27-81 Cabbage 2.4+/-0.2 <0.02 0.o15+/-0.006 SA-FPV-5Fl 7-27-81 Tomatoes 2.8+/-0.3 . <0.008 0.004+/-0.002 SA-FPG-lGl 7-27-31 Corn

2. 8+/-0. 3

<0.008 0.003+/-0.002 ID SA-FPV-lGl 7-27-81 Tomatoes 2.5+/-0.3 <0.006 0.004+/-0.002 w SA-FPG-3H4 7-27-81 Corn 5.9+/-0.6 <0.008 <0.004 SA-FPV-3H4 7-27-31 Cucuni:Jers 1.5+/-0.2 <0.008 0.003+/-0.003 SA-FPV-3H4 7-27-81 Peppers 1.7+/-0.2 <0;*02 0.013+/-0.007 SA-FPV-3H4 7-27-81

Tomatoes 3.1+/-0.3

<0.006 <0.003 SA-FPV-501 7-28-31 Squash 1.5+/-0.2 <0.01 0.008+/-0.003 SA-FPV-lGl 7-23-81 Peppers 2.0+/-0.2 <0.009 0.004+/-0.002 SA-FPV-14F3 8-08-31 to Tomatoes 2.1+/-0.2 <0.003 <0.004 8-10-81 SA-FPG-14F3 8-11-31 Corn. 2.1+/-0.2 <0.00~ <0.0Q4 All other gamma emitters searched for were <LLD; typical LLDs are given i.n Table C-33. Sr-89 results are corrected for decay to sample stop date.

~ .+>>

~

STATION NO. SA-GAM-3El SA-GAM-llEl SA-FPB-3El SA-THB-3El SA-FPB-3El SA-THB-3El SA-FPB-14Fl SA-THB-14Fl TABLE C-31 CONCENTRATIONS OF GAMMA EMITTERS* AND STRONTIUM-89 AND -90** IN MEAT, GAME, AND BOVINE THYROID Results in Units of pCi/g(wet) +/- 2 sigma DATE SAMPLE TYPE K-40 Sr-89 Sr-90 pCi/g(dry)+/-2 sigma 1-08-81 to Muskrat 2.4+/-0.2 .<0.2 0.50+/-0.05 1-09-81 3-05-81 to Muskrat 3.1+/-0.3 <0.9 0.5+/-0.3 3-06-81 3-09-81 Beef 2.7+/-0.3 3-09-81 Bovine Thyroid 1.3+/-0. 7 11-02-81 Beef 1.7+/-0.2 11-02-81 Bovine Thyroid <0.6 12-08-81 Beef 1.7+/-0.2 12-08-81 Bovine Thyroid <1.1 All other ganrna emitters searched for were <LLD; typical LLDs are given in Table C-33. Radiostrontium performed on muskrat only. Sr-89 results are corrected for decay to sample stop date. Indicates strontium analyses not performed.

1-~liMi&~~~~IJ,ii.,;;JOJi;_t§;Jm;e1iif1l:lm.%c;Ji""~&:i*C/h,\\i:sl\\'Oit,fo1!t:-i>lll';\\GZ:dlkiillc'i'b&'!ilit~;!::ic;i\\ii:)1i'i~'.l&c;iwci;*:;!'t,'~lifciiio'ijiJc~;,' TABLE C-32 CONCENTRATIONS OF GAMMA EMITTERS* IN FODDER CROP SAMPLES Results in Units of pCi/g(dry) +/- 2 sigma STATION SAMPLE NUMBER DATE TYPE Be-7 K-40 Cs-137 SA-VGT-3Gl 8-01-31 to Sil age <1.2 . 8. 7+/-1.8 <O.1 8-31-31 SA-VGT-2F4 9-03-81 Green Chop <1.1 12+/-2 <O.1 lD (J1 SA-VGT-14Fl 9-08-81 Green Chop <0.4 5 *. 6+/-0. 6 <0.05 SA-VGT-13E3 9-21-31 Green Chop <0.5 "5.2+/-0.8 <0.06 SA-VGT-15Fl 9-21-81 ~*Jee ct Chop 2.3+/-0.7 . 10+/-1 <0.03 SA-VGT-15Fl 10-05-81 Corn Sil age <1.3 7'. 5+/-1.4 <O.l SA-FPG-3E1 10-14-81 Soybeans <O ~3 16+/-2 0.04+/-0.03 SA-FPG-3Gl 11-17-81 Soybeans <0.5 21+/-2 <0.05 SA-FPG-15Fl 11-30-81 Soybeans <0.2 13+/-1 <0.03 i All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-33.

TABLE C-33 LLDs FOR GAMMA SPECTROMETRY SURFACE AIR WELL/POTABLE WATER FISH SEDIMENT* PARTICULATES PRECIPITATION WATER NUCLIDES (pCi/l) ( pCi /g-wet) (pCi/g-dry) ( 10-3pCi/m3) (pCi/l) (pCi/l) Be-7 5.2 0.07 0.3 7.6 7.0 Na-22 0.8 0.009 0.6 0.6 K-40 11 7.2 7.8 7.8 Cr-51 5.3 0;06 0.4 7.6 5.9 5.8 Mn-54 0.6 0.008 0.03 0.3 0.6 0.6 Co-57 0.02 0.3 1.0 Co-58 0.7 0.009 0.03 0.5 0.7 0.7 Fe-59 1.5 0.02 0.09 1.1 1.6 1.4 Co-60 0.8 0.009 0.03 0.5 0.8 0.8 l.O Zn-65 1.4 0.02 0.08 0.9 1.5 1.4 CJ) Zr-95 0.06 0.4 Nb-95 0.06 0.3 ZrNb-95 0.6 0.008 0.6 0.6 Mo-99 18 1.1 39 51 40 Ru-103 0.04 0,3 Ru-106 6.3 0.08 0.02 0.6 13 6.3 .;): Ag-llOril 0.6 0.008 0.03 0.6 0.8 0.6 Sb-125 0.07 0.7 Te-129m 12 0.2 1.4 28 13 13 I-131 1.0 0.02 0.2. 3.4 1.4 1.3 .~:- Te-132 1.5 0.07 3.6 3.0 I-133 Cs-134 0.6 0.008 0.03 0.5 0.8 0.6 Cs-136 1.2 0.02 0.1 1.2 1.6 1.5 Cs-137 0.6 0.008 0.04 0.4 0.8 0.6 Ba-140 0.5 9.7 9.8 La-140 0.1 1.6 2.8 BaLa-140 1.0 0.02

1. 3 1.2 Ce-141 0.07 0.2 Ge-144 1.6 0.03 0.2 1.9 3.2 1.6 Ra-226 1.1 0.01 1.1 1.2 1.2 Th-232 3.1 0.03 1.8 3.1 3.1

TABLE C-33 (cont.) LLDs FOR GAMMA SPECTROMETRY FOOD FODDER MILK PRODUCTS CROPS GAME SHELLFISH NUCLIDES (pCi/l) (pCi/g-wet) (pCi/g-dry) ( pCi I g-wet) ( pCi I g-wet) Be-7 9.4 0.02 0.3 0.7 0.09 Na-22 1.3 0.003 0.03 0.008. 0.01 K-40 Cr-51 6.7 0.02 0.2 0.06. 0.1 Mn-54 1.0 0.003 0.03 0.008 0.01 Co-57 Co-58 1.1 0.003 0.03 0.008* 0.01 Fe-59 3.7 0.007 0.09 0.02 0.02 Co-60 1.2 0.003 0.03 0.0013 0.01 Zn-65 3.2 0.0013 0.013 0.02 0.03 Zr-95 \\0 Nb-95 ZrNb-95 1.2 0.003 0.03 0.008 0.009 Mo-99 130 0.08 0.9 0.2 1.9 Ru-103 Ru-106 8.0 0.03 0.3 0.08 0.1 Ag-llOm 1.0 0.003 0.03 0.0013 0.01 Sb-125 Te-129m 19 0.06 0.5 0.2 0.2 'j}!.. : I-131 2.3 0.004 0.06 0.01 0.03 Te-132 6.1 0.004 0.07 0.02 0.1 I-133 0.09 3.1 0.:4 Cs-134 0.9 0.003 0.03 0.008 0.01 Cs-136 2.7 0.007 0.07 0.02 0.03 Cs-137 1.2 0.003 0.05 0.009. 0.01 Ba-140 La-140 Bata-140 1.7 0.004 0.05 0.01 0.02 Ce-141 Ce-144 3.2 0.01 0.01 0.03 0.03 Ra-226 1.6 0.005 0.06 0.01 0.02 Th-232 4.7 0.01 0.1.. 0.03 .0.05 Indicates a positive concentration was measured in all samples analyzed. Indicates that no LLD was calculated for that nuclide in that media.

.. *. :*. :_,. *.. ~ - ~. - APPENDIX D-1 SY NO PS IS OF ANAL YT! CAL PROCEDURES UTILIZED BY RMC 99

., v,:.

~* -*
:: L:,.. *'*...* ::... **;.- -

GROSS ALPHA ANALYSIS OF SAMPLES Total Water (A~, Al) A 250 ml (A0) or one 1 (Al) aliquot of the sample is evaporated to dryness on a hot plate in a preweighed, 2 11 X 1/4 11 ringed planchet, allowed to cool, and re-weighed. The planchet is counted in a low-background, gas flow proportional counter. Sel.f-absorption corrections are made bas.ed on the measured sample weight and calculated thickness. The calibration standard.used is Pu-239. A 250 ml or one l sample of distilled water is evaporated in the same manner and used as a blank. Total Salt i~ater (AA)

Alpha emitte.rs are concentrated initi a fly from a 1 i.ter aliquot of wa.ter sample by coprecipitatiori with magnesium hydroxide.

The precipitate is then dissolved in hydrochloric acid and titanium trichloride is added to the solution. The alpha emitters are coprecipitated by adding barium chloride and sulfuric acid to pre-cipitate barium sulfate. The precipitate is transferred to a tared stainless steel planchet and dried. The plahchet is reweighed and counted in a low back-ground gas-fl ow proporti anal counter. Self-absorption corrections are made on the basis of the weight of the precipitate. Calculations are made utilizing the following equations: Result (pCi/l) = ({S/T) - (B/t))- I (2.22 V E TF) 2 sigma error (pCi/l) = 2 ((S/T2) + (B/t2)) 112 / (2.22 VE TF) where: S = Gross counts of sample B = Counts of blank E = Fractional Pu-239 counting efficiency T = Number of minutes sample was counted t = Number of minutes blank was counted V = Sample aliquot size (liters) TF = Transmission factor (based on net weight of sample in counting planchet) Calculation of lower limit of detection (LLD) The detection limit is assumed to be exceeded when the counting result is different from the blank reading by at least 4.66 times the standard deviation of that back-ground. LLD (pCi/l) = 4.66 (B112) I (2.22 VE TF t) 101 q L_.7!.~*~r=*-*=*** =---=***-~*** *~--~-~~~-~*

- -~---'---'-- -*

....... *****-*~-~-~~~~*

. : -~.: ~- :... _,._.

where:

B E t v TF = = = = = Counts of blank Fractional Pu-239 counting effkiency Number of minutes blank was counted Volume of aliquot (liters) Transmission factor (based on net weight of sample in counting planchet) Air Particulates (AD) After a decay period of three to seven days, to allow for the decay of short lived radium and thorium daughter products, the filters are counted in a gas-flow.proportional counter.. The alpha activity per unit volume is ca.lculated

from the volurTE of *air filtered.

An unused filter is used as a blank. Calculations are.made utilizing.the followi~g equatio~s:

Result (pCi/m3) = ((SIT) - (B/t)) I (2.22 V E) 2 sigma error (pCi/m3) = 2 ((S/T2) + (B/t2)) 112 / (2.22 V.E) where:

s = Gross counts of sample B = Counts of blank E = Fractional Pu-239 counting efficiency T = Number of minutes sample was counted t = Number of minutes blank was counted v = VolurTE of aliquot (cubic meters) Calculation of lower limit of detection (LLD) ~.. The detection limit is assumed to be exceeded when the counting result is different from the blank reading by at least 4.66 times the standard deviation of that back-ground. LLD (pCi/l) = 4.66 (8112) I (2.22 VE t) where: B = Counts of blank E = Fractional Pu-239 counting efficiency t Nuriber of minutes blank was counted V =.Volume of aliquot (cubic rJEters) 102

1f ~~ t1 I .*.. '. *=-**.*.:..

I *

,.: ;._.,,; '*;: :~

GROSS BETA ANALYSIS OF SAMPLES Total Water (B0, Bl)

A 250 ml (B~) or one l (Bl) aliquot is evaporated to dryness on a hot plate in a prewei ghed, 2 11 x 1/4 11 , ringed pl anchet and reweighed. The pl anchet is then counted in a low background gas-flow proportional counter. Self-absorption corrections are made based on the measured residue weight and calculated thickness. The calibration standard used is Sr Y-90. A 250 ml or one l sample of distilled water is evapo-rated in the. same manner and used as a blank. Calculations are made utilizing the following equations: Result (pCi/l} = ((S/T) - (.B/t)) I (2.22 V E TF) 2: siw.ia*erro~_(pCi/1) = 2 ((SiT2} +. (B/t2 ))?~~*{. (2~22 V*E TF)* where: s B E T t v TF = = = = = = = Gross counts of sample Counts of blank Fractional Sr-90-Y-90 counting efficiency Number of minutes sample was counted Number of minutes blank was counted Volume of aliquot (liters) Transmission factor (based on net weight of sample in counting planchet) Calculation of lower limit of detection (LLD) The detection limit is assumed to be exceeded when the counting result for the sample is different from the blank reading by at least 4.66 times the standard deviation of that background. LLD (pCi/l) = 4.66 (B1/ 2) I (2.22 VE TF t)

where:

B = Counts of blank E = Fractional Sr-90-Y-90 counting efficiency t = Number of minutes blank was counted V = Volume of aliquot (liters) TF = Transmission factor (based on net weight of sample in counting planchet) Air Particulates (BD) After a decay period of three to seven days, to allow for the decay of short. lived radium and thorium daughter products, the filters are counted in a gas-flow proportional counter. The beta activity is calculated from the volume of air filtered. An unused filter paper is used as a blank. Calculations are made utilizing the following equations: Result (pCi/m3) = (S/T) - (B/t)) I (2.22 V E) 103 ~ :*.*;.-,.-2,.*.-... -:.:-** -~~*.... **.~*'*"'. - **.*.,_., ~ *-*.*~.. ~*.-._.., *..**..* ~'":'~*, *. -****................ *-*.***.,..,. _..,..,, '

2 sigma error (pCi/m3) = 2 ((S/T2) + (B/t2)) 112 / (2.22 V E) where: S = Gross counts of sample B = Counts of blank E = Fractional Sr-90-Y-90 counting efficiency T = Number of minutes sample was counted t = Number of minutes blank was counted V = Volume of sample (cubic meters) Calculation of lo~er limit. of detectiorr (LLD) The detection-limit is assumed tn be exceeded. when the counting result for the. _. sample i_s different from the *blank reading by at least 4.66 times the standard deviation of that background. LLD (pCi/m3) = 4.66 (8 112) /.:(2.22 V.E t) where: B = Counts of blank E = Fractional Sr-90-Y-90 counting efficiency t = Number of minutes blank was counted V = Volume of sample (cubic meters) 104

.~. **. '.**"_.* ** :.. ;,.<.... -* -* -*.:': ~* *-** -...;. *:*, : ::: ;_*

GAMMA SPECTROMETRY OF SAMPLES Water (Nl) Four liters of sample is reduced to 100 ml and sealed in a standard container and counted with a NaI(Tl) detector coupled to a multi-channel pulse-height analyzer. The counting time is 50,000 seconds. Milk (N7) A 4 liter aliquot is dried at 175°C, ashed at 500°C until no carbon residue . is present, *compressed and sealed in a standard container,. and then counted wjth a Na I (Tl). detector, coupled to a multi-channel pulse-height analyzer.

The counting time is 50;0~0. sec*onds~

Qried Solids (NB, GB) A large quantity of the sample is dried at a low temperature, less than 100°C. A 100 gram aliquot (or the total sample if less than 100 grams) is taken, compressed to unit density, sealed *in a standard container, and counted with a NaI(Tl) or Ge(Li) detector, coupled to a multi-channel pulse-height analyzer. The counting time is 50,000 seconds. Air Dried Solids (NA) A large quantity of sample is air dried. A 100 gram aliquot (or the total sample if less than 100 grams) is taken, compressed to unit density, sealed in a standard container and counted with a NaI(Tl) detector, coupled to a multi-channel pulse-height analyzer. The counting time is 50,000 seconds.

Air Particulate (GB)

All samples received for the month are mixed, compressed, and sealed in the standard container, and counted with the high resolution Ge(Li) detector, coupled to a multi-channel pulse-height analyzer. Calculation of result and two sigma error* The spectrum obtained is sJTDothed to eliminate spurious statistical noise. Peaks are identified by changes in the slope of the gross spectrum~ The net counting rate above the baseline is calculated. This counting rate is con-verted to activity in curie units, making allowance for counting efficiency and ganma ray abundance. A PDP-11 computer program was introduced for spectrum analysis. Calculations are made utilizing the following equations: Result (pCi/l 1 g or m3) = ((S/T) {B/t)) I (2.22 V E F) 2 sigma error {pCi/1 1 g or m3) = 2 {(S/T2) + {B/t2))112 I (2.22 VE F) 105 ..,......,.,,.....,. "*""'"....................,.,,,....,....,.. -~-.--*-*"*.----.-... -............................................ -.-~---~-~--"-"-'-""---'-'-'-"'-'-""'-'--'--'-""-=*--'"""--=---=---=*= ... =... ~.-~---

.: ~* ~.* V* where: s B T E v F = = = = = = ~. ~.;... ' Sample counts in energy channels for peak being quantitated Background counts in energy channels for peak being quantitated Number of minutes sample was counted Detector efficiency for energy of interest Sample aliquot size Fractional galTJ'lla abundance Cal cul at ion of lower 1 imit of detection (LLD) for GB and GB LLD (pCi/l, g or m3) = 4.66 (6 S) 112 I (~.22 VE FT) where: S * '= Sample counts in energy channels. for peak being quantitated T = Number of minutes sample was counted E = Detector efficiency for energy of interest V = Sample aliquot size F = Fractional gal!'ITla abundance Calculation of 1 ower 1 imit of detection (LLD) for Nl, N7, NB and NA LLD (pCi/l, g or m3) = 4.66 (.63 6 S) 1/ 2 I (2.22 V E FT) where: s T E v F = Sample counts in energy channels for peak being quantitated * = Number of minutes sample was counted = Detector efficiency for energy of interest = *Sample aliquot size = Fractional gamma abundance 106

. ;.. ~ '.. . I ANALYSIS OF ~~ATER SAMPLES FOR POTASSIUM-40 BY AA (E0) Sample Preparation An aliquot sample size of 100 ml is filtered. The concentration of potassium is determined spectrophotometrically on a Perkin Elmer Model 373 atomic absorption unit. The result obtained, in micrograms per milliliter, is multiplied by the specific activity of 0.12% for natural potassium to deter-mine the amount of potassium-40 present in the sample. The error reported is 10% of KCl are determined with each sample set. Calculations are made using the following equations: . K-40. (pCi/l). = cs* D (C/S) K 103 3 LLD (pCi /1) Cs. D_ (.1/S) K 10.

where:

Cs = Concentration of Standard (µg K/ml) C = Sample reading S = Standard reading D = Dilution factor K = Specific activity of K-40 per unit \\'Jeight of potassium =.* 852 pCi/mg 107

, v* ' - l ~ r I , ** * ~ . *J' .~:..*,' ANALYSIS OF SAMPLES FOR TRITIUM Water {H2) A 15 ml aliquot of the sample is vacuum distilled to eliminate dissolved gasses and non-volatile matter. The distillate is frozen in a trap cooled with a dry ice-isopropanol mixture. Eight (8) ml of the distillate are mixed with ten (10) ml of Insta-Gel liquid scintillation solution. The sample is then counted for tritium in a liquid scintillation counter. A sample of low tritium (<50 pCi/l) water is vacuum distilled as a blank and is counted with each batch of samples. In the calculation of the result it is assumed that the condensated and original sample are of equivalent volumes. The vnlume change associated \\'lith the rerooval of dissolved gases and non-volatile matter is not significant compared to the other errors in.the analysis. Calculations are made.utilizing* the following equati-ons: Result {pCi/l) = {(S/T) (B/t)) I (2.22 VE) 2 sigma error (pCi/l) = 2 ((S/T2) + (B/t2)) 112 / (2.22 VE) where: s B E T t v = Total gross counts of sample = Counts of blank = Fractional H-3 counting efficiency = Number of minutes sample was counted = Number of minutes blank was counted = Aliquot volume (liters) -~*

r.....

Gross counts of sample may be corrected for the blank activity. If the collection container is rinsed with distilled water and the rinse is added to the sample, the rinse plus sample and a separate aliquot of the distilled water are counted. The corrected gross counts fo~ the sample only are calculated using the follm'ling equa-tions: s = {(s-b)v) I G s = (c(G+H)) I V

b. = (d(H)) I V v

= G V /(G+H) where: s G H s b v c d = Gross counts of sample = Volume of sample = Volume of rinse = Volume corrected gross counts of sample plus rinse = Volume corrected gross counts of rinse = Corrected al i quot vol ume = Uncorrected gross counts of sample plus rinse = Uncorrected gross counts* o*f rinse 108

~ :

Calculation of lower limit detection (LLD)

The detection limit is assumed to be exceeded when the counting result is different from the blank reading by at least 4.66 times the standard deviation of that background. LLD (pCi/l) = 4.66 (B112) I (2.22 y Et) where: B = Counts of blank E = Fractional H-3 counting efficiency t = Number of minutes blank was counted V = Aliquot volume (liters) ~que_o.us and Organic Fraction of Milk.*or Organic *Solids (H3, H4., ~9) A carefully measured aliquot of a food product, such as milk or fish, is dried in a rotating vacuum flash evaporator. During the evaporation pracess, the evaporated water fraction is trapped out by a dry ice isopropanol mixture for coanting as in (a) below. The dried residue is reserved for (b). The wet sample is analyzed as in (c).

a.

Aqueous H-3 in Food Products An eight (8) ml aliquot of the cold-trapped water is counted in a liquid scintillation counter in the same manner as surface water samples are counted.

b. Organic Bound H-3 in Food Products The dried residue is combusted in an RMC designed oxidizer.

The collected water - organic fraction is measured and vacuum distilled to remove any impurities. Permanganate in KOH solution is added to remove impurities which may cause quenching *. An eight (8) ml aliquot is counted in a liquid scintillation counter. If less than eight (8) ml are coll~cted, the entire portion collected is carefully measured with a 10 ml pipette and then counted. A sample of deep well water is counted as a blank.

c. Aqueous and organic Bound H-3 in Food Products

~--*.... ::*.:,._.:. A wet weight aliquot *i.s combusted in an RMC designed oxidizer. The collected water fraction is meas*ured and vacuum distilled to remove any impurities. Per:- manganate in KOH solution is added to remove i!Tl>urities which may cause quenching. An eight (8) ml aliquot is counted in a liquid scintillation counter. If less than eight (8) ml are collected, the entire portion collected is carefully measured with a 10 ml* pipette and then counted. A sample of deep well water is counted as a blank. Calculations are made utilizing the following equations: Result (pCi/1) = ((S/T) - (B/t)) I (2.22 VE) of distillate 2 sigma error (pCi/l) = 2 ((S/T2) + (B/t2)) 112 I (2.22 VE) of distil 1 ate 109

. -~* :- . : : **.... -.. :.:*>.:,:.:.:: :.. ~:.. *:.;'..... ';*:,.. ::,:. Result (pCi/g of freeze dried sample) = A (YI) 2 sigma error (pCi/g of freeze dried sample) = C (YI) Result (pCi/g or l of original sample) = A (VF) 2 sigma error (pCi/g or l of original sample) = C (VF) where: s B E T t v YI VF A c = = = = = = = = Gross counts of sa~ple Counts of blank Fractional H-3 counting. effidency Number *of minutes sampl~ was counted. Number of minutes blank wa~ co'unted. Volume of distillate counted Liters of water-organic recovered/ g of freeze dried sample .Liters of water recovered/ (1 or g) of sample aliquot taken Result in pCi/l of distillate 2 sigma er~r in pCi/l of distillate Calculation of lower limit detection (LLD) The detection limit is assumed to be exceeded when the counting result is dif-ferent from the blank reading by at least 4.66 times the standard deviation of that background. LLD (pCi/l) = 4.66 (B1/ 2) I (2.22 VE t) LLD (pCi/g of freeze dried sample) = -- F (YI) LLD (pCi/l or g) = F (VF) of original sample where: B E t v YI VF F = = = = = = = Counts of blank Fractional H-3 counting efficiency Nunt>er of minutes blank was counted Volume of distillate counted Liters of water-organic recovered/g of freeze dried sample Liters of water recovered/(l or g) 1Jf sample aliquot taken LLD in pCi/l of distillate

~;i I '......., *~'. ... *. ~. : -*. -**. *.

.... ::. ~.:... :, ~*. *. - :. ;

........ *:. *... -~'... *.. : :-..,.. :...'.,,. '*..... ANALYSIS OF SAMPLES FOR IODINE-131 Milk or Water (!0) The initial stable iodide concentration in milk is determined with an iodide ion specific electrode. Thirty milligrams of stable iodide carrier is then added to four (4) liters 6f milk. The iodide is removed from the milk by passage through ion-exchange resin. The iodide is eluted from the resin with sodium hypochlonite, and purified by a series of solvent extractions with the final extraction into a toluene phase. The toluene phase is mixed with a toluene-based liquid scintillation solution. The sample is then counted in a beta-gated ganma coincidence detector, shielded by six inches of steel. Distilled water is used as a blank. The yield is calculated from stable iodide recovery based on the recovered volume. Calculations are made utilizi.ng the follow.ing. equations:

Result * = ((SIT) -* (B/t)) / *(2.22 V E *F Y)

(pci11). 2 sigma error = 2 ((S/T2) + (B/t2)) 112 / (2.22 V E FY) (pCi/l) LLD = 4.66 (8112) I (2.22 V E F Y t) (pCi/l) where: s B T = = = Gross counts of sample in channels containing I-131 peak Background counts in channels containing I-131 peak Number of minutes sample was counted t = Number of minutes background was counted E = Iodine-131 counting efficiency v = Sampl'e aliquot size F = Fractional ganma abundance y = Chemical yield of iodine Air Cartridges (Il) An iodine absorber composed of charcoal is emptied into an aluminum can (6 ems high by 8 ems in diameter) and counted with a Na! (Tl) detector, coupled to a multi-channel pulse-height analyzer. Calculation of results and two sigma error Peaks are identified by changes in the slope of the spectrum. If peaks are iden-tified the spectrum obtained is smoothed to eliminate spurious statistical noise. The presence of iodine-131 is identified by the presence of a 364 Kev peak. The net counting rate above the baseline is calculated. This counting rate is con-verted to activity in curie units, making allowance for counting efficiency and gamma ray abundance. A PDP-11 computer program is used for spectrum analysis. Results are corrected for decay from the sampling time to the middle of the counting period, using a half-life value for I-131 of 8.06 days. Calculations are made utilizing the following.equations: Result3 = (pCi /m ) ((S/T) - (B/t)) I (2.22 V E FY) 111

-*.. :~~** ~~-***-**~"

-*--~***-**

~* ~

_:___~.'.::-'*'.... _..... _,*_'-.....'.._****-.*

2 sigm~ error = 2 ((S/T2) + (B/t2)) 112 I (2.22 V E F Y) (pCi/m ) LLD 3 = 4.66 (8112) I (2.22 V E F Y t) (pCi/m ) where: . **~**: o... s B t = = = Gross counts of sample in channels containing I-131 peak Background counts in channels containing I-131 peak Number of minutes.background was counted E = Iodine-131 counting efficiency v = Sample aliquot size F = Fractional _gamma abundance 112

"*. _._. ~ '.......

. _,... _*. - ;, ~-* :. -- *~' .:*~-* ANALYSIS OF SAMPLES FOR STRONTIUM-89 AND -90 T.Water (S0, T(.f) A two liter aliquot of sample is used. Stable strontium carrier is added to the liquid to facilitate chemical separation of Sr-89 and -90, and to determine the strontium recovery. Strontium concentration and purification is ultimately real-ized by at least two precipitations of strontium nitrate in concentrated nitric acid. Additional iron rare earth scavenging and barium chromate separations are performed to reroove suspected interfering nuclides. The purified strontium is converted to a carbonate for weighing and counting. Soon after the separation,. the sample is counted in a low-background gas-flow proportional counter. After about 14 days, the sa111>le is recounted, then Sr-89 and -90 activities are calcu-lated on the'bas is of Y-90 ingrowth. and Sr-89 decay. A sample of distilled water .is used as a b.lank. Mi.lk (54, t4). . A one and half liter aliquot of milk is ashed to destroy organic material and then dissolved in concentrated mineral acid. Stable strontium is added to the dissolved ash to facilitate chemical.. separation of Sr-89 and -90, and to determine the strontium recovery. Strontium concentrations and purification is ultimately realized by at least two.. precipitations of strontium nitrate in concentrated nitric. acid. Additional iron rare earth scavenging and barium chromate separations are performed to reroove suspected interfering nuclides. The purified strontium is converted to a* carbonate for weighing and counting. Soon after the separation, the sample is counted in a low background gas-flow proportional counter. After about 14 days, the sample is re ed, then Sr-89 and -90 activities are calculated on the basis of Y'."'90 ingrowth an 89 decay. A sample of distilled water is used as a blank. Bones and Shells (SS, TS) A large quantity of the sample is dried, ashed and a 2S g portion is then dissolved. in concentrated acid. Stable strontium carrier is added to the dissolved sample to facilitate chemical separations of Sr-89 and -90, and to determine the strontium recovery. Strontium concentration and purification is ultimately realized by at least two precipitations of strontium nitrate in concentrated nitric acid. Addi-tional iron rare earth hydroxide scavenging and barium chromate separations are per-formed to relll)ve suspected interfering nuclides. The purified strontium is converted to a carbonate for weighing and* counting. Soon after the separation, the sample is counted in a. low-background gas-flow proportional counter. After about 14 days, the sample is recounted, then Sr-89 and -90 activities are calculated on the basis Jf Y-90 ingrowth and Sr-89 decay. A sample of distilled water is used as a blank. Soil and Sediment (S6, T6) \\ large quantity of sample is dried, and a 25 g portion is then leached with concen-trated HCl before drying. Stable strontium carrier is added to the sample to facili-tate isolation of the strontium and to determine the strontium recovery. Strontium

oncentrations and purification is ultimately realized by at least two precipitations Jf strontium nitrate in concentrated.nitric acid. Additional iron rare earth scavenging ind barium chromate separations are performed to remove suspected interfering nuclides.

The rified strontium is converted to a carbonate for weighing and counting. Within 3 after the separation, the sa~le is counted in a low-background gas-flow pro-lO al counter. After about 14 days, the sample is recounted, then Sr-89 and -90 113

~-.... *.

....::*...... :, ;..,":*~*.:*:.1.* ~.:*;.~.\\;.:1*.. \\:.,*::.,... :,_~.*.:.:-.: "- *.,~:-..,:.*:.. ~*.....* - -*.... i ::.... : '.*: *.:,,;. *::*.~: * ;.,. _,_ activities are calculated on the basis of Y-90 ingrowth and Sr-89 decay. A sample of distilled water is processed with each batch of samples. Organic Solids (SB, TB) A 250 g portion of the sample is ashed and then dissolved in concentrated acid.

Stable strontium carrier is added to the dissolved sample to facilitate chemical separation of Sr-89 and -90, and to determine the strontium recovery. Strontium concentration and purification is ultimately realized by at least two precipitations of strontium nitrate in concentrated nitric acid. Additional rare earth iron hydrox-ide scavenging and.barium chromate separations are performed to renDve suspected inter-fering. nucl ides *. The purified strontium is converted to a.carbonate for weighing

.and counting. Soon -after the separation,. the sample is* counted. in a low-background gas-flow proportional counter *. After about 14 days, the sample is :recounted, then Sr~89 and -90 activities are calculated ori the basis of Y-90 ingrowth and**sr.. 89 decay. A sample of distilled water is used as a blank. Air Particulates (SA, TA) Stable strontium carrier is added to facilitate chemical isolation of Sr-89 and -90 and for determination of the strontium recovery in the.procedure. Strontium concentrations and purification is ultimately realized by at least two precipitations of strontium nitrate in concentrated nitric acid. Additional hydrox-ide precipitations and barium chromate separations are performed. The purified strontium is converted to a carbonate for weighing and counting. Gross beta counts are made soon after the strontium isolation and again after a 7-14 day interval and Sr-90 and Sr-89 activities are calculated on the basis of appropriate Sr-89 decay and Y-90 ingrowth equations. Calculations are ma9e using the following equations: Result Sr-90 =3((Z(Sl-81)) ~ (52-82)) I (2.22 KV E9 Y T) (pCi/l, g or m) 2 sigma error jr-90 = 2 (Z2{S1+81) + S2+82) 112 I (2.22 {K2)112 V E9 Y T) {pCi/l, g or m) MDL = (-9 -6(§ 82+Z(Sl-Bl))l/2 + 2.25 + z2(Sl+Bl))/(4.44 V E9 YT) (pCi/l, g or m) Result Sr-89 =3(F(Sl-Bl) + H(S2-B2)) I (2.22 V EBY T exp (-.693t4/52.7)) (pCi/l, g or m) 2 sigma error jr-89 = 2(F2(Sl+Bl) + H2(S2+B2)) 112 I (2.22 V EB Y T exp(-.693t4/52.7)) (pCi /1, g or m ) MDL = (F(X-83) + H (52-82)) I (2.22 V E8 YT exp (-.693t4/52.7)) (pCi/l, g or m ) 114

~.;,. ~ ... l ****** -* *.'..-

-..,.,. ~ ~' -

. -. *:. **..:._:.. *. *:,:-. '~ *.

~.-

~-: ~.,.... ::::*.~*.. *:.*: *-

.. :.:.:. ~ :.~ _,,**-:.~ -..... **-"

1*

~:~.~1a

'i ~~~~* I I I ~ .f;*i~ cl?.~ I where: Sr-89 ( 1) = Sr-90 = Y-90 (1) = Y-90(2) = Sl = S2 = Bl = 82 = t1 = t2 = t3 = t4 = Ei = E2 = z = R = H = K* = F = c = B = x = E9 = EV = E8 = T = y = v = Sr-89 counts on first count Counts of Sr-90 Counts of Y-90 on first count Counts of Y-90 on second (after equil.) Sr-89(1) + Sr-90 + Y-90(1) + B(l) Sr-89(2) + Sr-90 + Y-90(2) + 8(2) Blank counts in first count Blank counts in second count Time in hours from separation time to Sl Time in days from separation time to S2 Time in days from Sl to S2

Time in days from sampling date.to separation date 1 - *exp {-.693tl/64 hours) :

1 - exp (-.693t2/2.667 days) exp (-.693t3/52.7 days) E9/EY ( 1 + El/R)/K Z (El/R + 1) (E2/R) 1 - (2/K) - Z (E~/KR) (-9 F Bl) - 9 H (S2+B2}+(F 81) 2-2 F H 82 S2+2 F H Bl 82 2 + (H(S2-B2)) 2 F H ( S2-B2) - 2 F2 B 1 - 9 F2 ((B2 - 4 F2 c)l/Z - B) I (2 F2) Counting eff. of Sr-90 =.3590 -.7082 X (l~t. strontium carbonate) Counting eff. of Y-90 =.4380 -.1337 X (\\~t. strontium carbonate) Counting eff. of Sr-89 =.4568 -.2060 X (\\~t. strontium carbonate) Number of minutes sample and blank were counted Yield Sample aliquot size in g of in g of* in g of Calculation of minimum detectable levels (MDLs) Due to the method of calculating the activity of Sr-90 in the presence of Sr-89, the form used in the NBS Handbook 80 for calculating minimum detectable activities is not applicable. 115

~1~~

~~'.~;[~ I I ,,.~ 'i '~~ ....,,,.. ""** '. '. :*.,,..*.* ;: *.........., *.......**........*... _.,._,.:*....... ********* -... ~ ......,.,...*.*.. -. --.,--,-_ -. =* .... -... ~-. ~ ..*. c-c .. _,_-;-c,_.,,=*;:-""'*;.,c- ... -*. ~ ENVIRONMENTAL DOSIMETRY (D~, Dl, D2) Measurement Techniques Each dosimeter utilized is a capillary tube containing calcium sulfate. (Tm) powder as the thermoluminescent dosimeter (TLD) material. This was chosen primarily for its high light output, minimal thermally induced signal loss (fading), and lack of self-dosing. The energy response curve has been flattened by a complex multiple element energy compensation shield supplied by Panasonic Corporation, manufacturer of the TLD reader. The four dosimeters per station* are sealed in a polyethylene bag.to demonstrate integrity at time of measurement. Visible through the bag are the sample placement instru.ctions. One set of TLDs is placed in a lead shield at RMC and represents a ze.ro dose. The TLDs are then taken and placed in the field stations; one field TLD set is placed in a field le.ad sh-ield-.at station 18.and i's us.ed in calculating the _in*-transit dose. Following the pre-designated exposure period the TLD is heated with hot gas and the luminescence measured with a TLD reader. Data are normalized to standard machine conditions by correcting machine settings to zero before readout. Data are corrected for in-transit dose using a set of TLDs which is kept in a lead shield in the field and only exposed d~ring transit. Average dose per exposure period, and its *error, are calculated. The basic calibration is in mR exposure to a standard Cs-137 source. This is converted to absorbed dose in tissue by the factor : 0.955 rad/Roentgen and to dose equivalent by using a quality factor of 1. Calculation of results and two sigma error gross TLD(i) = (TLD(i) - D~(i)) (CF (ins)} (CF(i)) 0.955 mrad/mRoentgen ITO = NET(site~) - (NET(RMC~) (D(sta) I D(RMC~))) NET TLD(i) = gross TLD(i) - ITO AVG n = ((sigma i=l NET TLD)/n)(D(STD) I D(EX)) ERROR (95% CL) = t(n-1) sigma NET TLD(i) In) (D(STD)/D(EX)) 116 .. t~

~J~

l~ii'i:<!itlt~'.1"9:;.'i:~;;#,:\\l0JiiE'1~K(~f;,,1f~>\\!iffi\\i~~ii;:;o~Fiii1','l'.\\i<~;;s;;;rs;;;;;;c;;,i~'Nlii\\~~~;t,:;;;;;e;cr;:, 'i'

~ '~l }_~.~ .*i ENVIRONMENTAL DOSIMETRY (cont.) ,,*:o_;,; .\\~7~ '*\\:~(~ 'f~~ ~~~~i.j l?~

!~~~

~i where: Gross TLD(i) TLD(i) NET TLD( i) CF( ins) ELS D0 (i) CF(i) !TD NE'.T(si te )0 _._ NEl( RMC )"~ D(sta) D(RMC~) AVG n D(EX) D(STD) t(n-1) sigma NET TLD( i) ERROR

*,1 ;.:**:.::*'.*.*.-** ">_.;~*.'.~.?~:-;****.,.. *.:.*.:.... :-~ *.*

~.j,*",;.':;-~,.,.* **::*~~;.;*-**,;. *--*-."":' ~- ".:'-~*:,. *. * = Individual TLD reading corrected to standard instrument conditions = Gross reading of dosimeter i = Net dose obtained during exposure period iB ~§e = Correction factor of reader = (6.21) (ELS- * ) = External light source = Zero for dosimeter, i = Calibration factor for dosimeter i = In-Transit dose = Mean o.f n dosimeters in site le.ad shield = Mean of n *dosirne.ters in RMC lead shield Exposure perioa of station = Exposure period of RMC~ * = Mean exposure per standard exposure period at a given station = Number of readings = Days exposed = Days in standard exposure period = t-distribution (student) factor for 95% CL =':---standard deviation of n readings of !~ET TLD(i) = The 95% confidence limit error of AVG 117 field

. *.~.... *':...... -... ~-- ;;:._:. **:-. .. -. : - ~.. APPENDIX D-2 SYNOPSIS OF ANALYTICAL PROCEDURES UTILIZED BY THE RESEARCH AND TESTING.* LABORATORY \\ 119 .:. ~.> ----.

I

t.~~ I

~t~ g~

~~

'.~~ M~ _:~:l\\~ ~. :;.. *... .... ~ ' .:.' :*.* ; -i-'l..;::-,"; ~:.'. * -;**~', GROSS ALPHA 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 then counted for gross alpha activity on a low background gas proportional counter. Along with a set of air particulate samples, a clean air filter is included as a blank with an Am-241 air filter geometry alpha counting standard. The specific alpha 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 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 Alpha Activity: Air.flow is corrected first by usfog the. following equatfo.ns*: P = (B-V)/29.92 V = F*P*0.946*0.0283 E P = Pressure correction factor B = Time-averaged barometric pressure during sampling

period, 11Hg V = Time~averaged vacuum during sampling period 29.92 =Standard atmospheric pressure at 32°F, "Hg F = Uncorrected air flow, ft3 0.946 = Temperature correction factor from 60°F to 32°F 0.0283 = Cubic meters per cubic foot E = Gas meter efficiency (= %

efficiency I 100) V = Corrected air flow, m3 P = Pressure correction factor Using these corrected air flows, the gross alpha activity is computed as follows: Result (pCi/m3) = (G-8~/T (2.22)* E)*(V) 2 sigma error (pCi/m3) G = Sample gross count B = Background counts (from blank filter) T = Count time of sample and blank, mins. E = Fractional Am-241 counting efficiency V = C~rrected air flow of sample m 2.22 = No. of dpm's per pCi 121 A= Gross alpha activity, pCi/m3 G = Sample gross counts B = Background counts (from blank filter) . *. ~ *.~:*{*.'.!'~::". '.: -:.:** ~" ;;.::. ::;**; *.*:.-;:~***.,-:- * :**..,.. *"--:-:' *- ~=-~. -.,:.*

.-.~.,,--~,"".*.-., "'T* ;*.-.. -*-.: * ~.;:*.:

c*. ~ * '":* ~ *. *.~.:-* *,... .-. t.~~*:*'- *-.;.: ', 1 ** '*:*."~**-.-:*.-:-*/'.".*!';..~. ** '1'<'1',*: *'.':".. ! *.".*'.: **~ ** ;,.,, ~ !

*'. *: ;*~ *. *-* -*_-,.... ** ~~ :'"*.'...,_.. _..-.:.*, \\.' * "'~" * ;< **,.'

~ I I . **.*.~J ~}!~

.. ".::~ I I

\\1 ~-t~-~* ~' ~l . -** :.. :}._.. ~,_ *- *~.. ;,;.:~ *:.'

: * -:.,... ~ *
~ ** ** :

"l,....

' *.*:.'. ~* ::-_ ::, ::~. *.. :'.. . '.... '..~'.: .....,*.... ** :...... : *~*-*

.** *: ***,. "'. *....,., :,1
:,. ;'.:.~,~,; *:.* _::. :~* ;.~*......... :. :.* * :,

Calculation 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

fB~l/

2 B f2.22)* E *(V)*(T) = Background fi 1 ter) counts (from blank E = Fractional Am-241 counting efficiency v = C~rrected air flow of sample, m T = Count time of blank, mins. 122 )~~}~:~t}i((jf~~i;~!.(~t::;~:':.i'f:~*.:~:: *._..

- ~

..,*.\\:,.... _;.. :_; 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 then *counted for gross beta activity on a low background gas proportional counter. Along with a set of air particulate samples, a clean air filter is included as a blank with an Sr-90-Y-90 air filter geometry beta counting standard. The s peci fi.c beta activity is computed on the basis of tota 1 corrected air fl ow 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 it-self. Calculation.of Gross Beta. Activity:

Air flow is corrected first by using the* following equations:

P = (B-V)/29.92 F*P*0.946*0.0283 E P = Pressure correction factor B = Time-averaged barometric pressure during sampling peri ad, 11Hg -V = Time-averaged vacuum during sampling period 29.92 = Standard atmospheric pressure at 32°F, 11Hg F = Uncorrected air flow, ft3 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) = 2 sigma error (pCi/m3) G = Sample gross counts B = Background counts (from blank filter) T = Count time of sample and blank, mins. E = Fractional Sr-90 counting effic~ency V = Corrected air flow of salll>le, m 2.22 =No. of dpm's per pCi 123 A= Gross beta activity, pCi/m3 G = Sample gross counts B = Background counts (from blank filter)

- -""':,-:.~--*::-.~- "'.*~-, *...
*.... -*.,.:*.-,.,.., ".,.* - *,* ~,,. *". * :.. *,..*~*......, ****~** *.,--

...,..,.. ** * ****.-*..,. *, *, *.* * * ~::.-**. *. * *:...,,~ t.*.*.*! -<;.:* **..:."; **, *:* **" " '*'! ** ***~-'.*, '...., *,,.... *.-,,'* * ""'."\\.<',';' ';.'*.* *:*-~ - >." -~*. _::*_*(.*~ '* ~"-'* C:'...-. r:--* *.""* '"" *.,.

.-.1 Calculation 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) = "f2.22)* E *(V)*(T) 124 B = Background counts (from blank filter) E = Fractional Sr-90 counting efficiency V = C~rrected air fl ow of sample m T = Count time of blarik, mins *

~

-.*:l GAMMA ANALYSIS OF AIR PARTICULATE COMPOSITES At the end of each calendar qu~rter, 13 weekly air filters from a given location are stacked in a two inch diameter Petri dish in chronological order, active area facing down, 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 Ge(Li) detector for 500 minutes. Calculation of Gamma Activity A special program developed by Tracor Northern is run on a PDP-11 computer. Photo-peaks are located by passing a digital filter through the spectrum, channel-by-channel, with the effect that the background portion of the spectrum is greatly reduced, leaving the peaks intact. To compute the desired net count under any one of these photopeaks, a background baseline is established extending from 1.5 times the full-width-at-half-max above, to the same distance below the centroid. The counts under this baseline are then subtracted out from the total number _of-counts -.under the photopeak. - The following are the calculations performed for the gamma activity, 2 sigma error and LLD: Result = (pCi /m3) = --~r~~*..;;;..D-~-- t2. 22)*(E)*(A)*(T)*(V) 2 sigma error (pCi/m3} = 2* (crk 2+crs 2)1/2 crk = 1 1/2 n 1

A (y)~

l: cr 2 i=l = R N = Net counts under photopeak D = Decay correction factor Xtl*EXP Xt2 1-EXP -X ti tl =Acquisition live time t2 = Elapsed time from sample collection to start of acquisition = 0.693/nuclide half life E = Detector efficiency A = Gamma abundance factor (no. of photons per disintegration) T = Acquisition live time, mins. V = Sample volume, m3 2.22 = No. of dpm's per pCi crk = statistical error of the activity measurement. It is determined from the accuracy of the least squares evalu-ation performed on the peaks of a particul~r nuclide. n = number of peaks in the nuclide of question cri = (GC+Bc)l/2, where GC and BC are gross counts and background counts, respectively. 125

-:.~. '... *....., A (y) i = N*D (E)*(R)*(2.22)*(T)*(V) = g~wna abundance factor for the i peak under consideration, for a given nuclide as represents systematic errors (such as errors in detector efficiency) over and above the statistical error of the activity measurement. It is assigned a fixed value representing 5% of the computed activity and should be regarded as a minimum estimate of the activity error. All other variables are as defined earlier. The LLD (pCi/m3) = (2.22)*(E *(A)*(T *(V) Again, all other variables are as defined ear_lier. _ \\ 126 '.c.!__**

~_.

-- l

1~~

.. ;::_~ I I I * ~ ~...... .. ~... ANALYSIS OF AIR FILTERS FOR RADIOSTROtffIUM The air filters are placed in a small beake; and just enough concentrated nitric acid is added to cover the filters. A blank, composed of the same number of clean air filters, is prepared in the same way. Stable strontium carrier is then intro-duced into each sample and several 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, now largely devoid of any radio-logical impur.ities, is converted to a carbonate form which is 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. Calculation of Sr-90 Activity:

Sr-90 Results (pCi/m3)

N4/R = (2.22) * (E) * (0.7621) * (S6) * (V) * (U) = W2 where S6 = 1.4115 - 0.03409*M + 0.000443*M2 (This is normalized Sr-90 efficiency regression equation for one particular gas proportional counter) M = Thickness density of strontium carbonate precipitate, mg/cm2 0.7621 = Ratio of Sr-90 efficiency at thickness value of 15 mg/cm2 to Sr-90 counting standard efficiency (This standard is run with each group of environmental strontium samples) E = Sr-90 counting standard efficiency V =Sample quantity (liters, m3 or kg) U = Chemical yield N4 = (N2 - Fl*Nl)/Wl = net counts due to Sr-90 only Wl = ( ( 1 + Rl*I2) - ( 1 + Rl*Il)*Fl) Il = 1 - EXP ((-0.693/2.667)*tl) 12 = 1 - EXP ((-0.693/2.667)*t2) tl = Elapsed time from Y-90 strip to f1rst count t2 = Elap$ed time from Y-90 strip to second count 2.667 = Half-life of Y-90, days 1.....

~* ***********..........................************.........

127

Rl = 1.242 + 0.0179*M + 0.000151*M2 (This is regression equation for Y-90 eff'y/Sr-90 eff'y ratio). 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's per pCi Fl = EXP ((-0.693/2.667)*t2) R = Count time of sample and blank Using the same variable pefinitions as above, the 2 sigma error for Sr-90 (pCi/m3) = 2* l(X+Y~ :.f. (Xl+Yp *F12l 1/2* (Wl*W2)

. l-Wl Wl j *

(N2-Fl*Nl) Again, keeping t9e same variable definitions, th2]112 LLD Sr-90 (pCi/m ) = 4.66* l(X+Y~ + (Xl+Yl~*Fl [ Wl Wl Calculation of Sr-89 Activity: Sr-89 Results (pCi/m3) = N6/R N6 = Nl - N?* (1 + Rl*Il) N? = (N2 - Fl*tH) /Wl (This represents counts due to Sr-90) 1.0922 = Ratio of Sr-89 efficiency at thickness value of 15 mg/cm2 to Sr-90 counting standard efficiency (This standard is run with each group of environmental strontium samples) F9 = EXP ((-0.693/50.5)*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 variables are as originally defined. The 2 sigma error for Sr-89 (pCi/m3) = 2* (S82+s92)1/2*W3 (Nl - N7* (l+Rl*Il)) 128 '..:~;,:::

-~:;;i -~.{~

,,~{ *.
~i~

1f~~ ~ V;i~ 58 = ~~~p + (X~~pl*:1~ 1 / 2 59 = (Xl+Yl)l/2 All other variables are as originally defined. Keeping t~e s~~/~ariable definitions, the LLD 5r-89 (pCi/m3) = 4.66* (SB +59 ) 129 ,._..~--:.,. -*-~*c*:-,-:~*-,.*_.* *.. -.~.**-~,-...,.... *.-*"-'-*"~-c..:.:***c:....:.*.:_:_"-"-'"'C:C:"*""-'=-'-..:._:_"='*_::""-""*'*"-"'"'-'-' _;_..,;..:..;..;;,*...;.*;.;;,*.-.;;,;;*.-.,~* ;..;....;,.*.;.;:."~* -~***--..;..*-**..;..* ;:...;.;.._._......._....................... --... """""-=..;;.-

.. *.*--*... ~.,1*_,,,-, ___ ~'.::.::...."...~*-**-~*-'-*"-**-*,..*,~...... ~,::....,~-*-.. *: -*,_ *- '-***.....*,......*.. ' :;*.*:........ - ~-" _ ;.* -... ~c*...... _ -~-*

ANALYSIS OF RAW MILK-FOR RADIOSTRONTIUM A stable strontium carrier is first introduced into a one liter milk sample and into a distilled water sample of equal volume to be used as a blank.

The sam-ple(s) and blank are passed through cation resin columns which pick up stron-tium, calcium, magnesium and other cations. These cations are then eluted off with a TRIS-buffered 4N sodium chloride solution into a beaker and precipitated as carbonates upon heating. The carbonates are converted to nitrates with 6N nitric acid and, by acidifying further to an overall_ concentration of 70% ni-tric acid, strontium is forced out of solution somewhat ahead of calcium. Barium chromate precipitation is then performed to remove any traces of radium and radio-bari um. Strontium recrystallization is carried out to remove residual calcium which may have been coprecipitated with the initial strontium precipitation. Another recrystallization removes ingrown Y-90, marking the time of the yttrium strip. The strontium is _reconverted_ to the carbonate, filtered, dried and weighed 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 quanti-- ties requiring two simultaneous equations to solve for them. Calculation of Sr-90 Activity: Sr-90 Results (pCi/l) = . N4/R (2.22) * (E) * (0.7621) * (S6) * (V) * (U) = W2 where S6 = 1.4115 - 0.03409*M + 0.000443*M2 (This is normalized Sr-90 efficiency regression equation for one particular gas proportional counter) M = Thickness density of s_trontium carbonate precipitate, mg/cm2 0.7621 = Ratio of Sr-90 efficiency at thickness value ~f 15 mg/cm2 to Sr-90 counting standard efficiency (This standard is run with each group of environmental strontium samples) E = Sr-90 counting standard efficiency V = Sample quantity (liters, m3 or kg) U = Chemical yield N4 = (N2 - Fl*Nl)/Wl = net counts due to Sr-90 only Wl = ((1 + Rl*I2) - (1 + Rl*Il)*Fl) Il = 1 - EXP ((-0.693/2.667)*tl) 12 = 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 130 "1 11 -:?f~ II

Rl = 1.242 + 0.0179*M + 0.000151*M2 (This is regression equation f6r

Y-90 eff'y/Sr-90 eff'y ratio)

N2 Nl = X - Y, where X and Y are recount gross counts and background counts, respectively Xl - Yl, where Xl and Yl are initial gross counts and background counts, respectively 2.22 = No. of dpm's 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 e.rrqr for Sr-90 (pCi/l) = . 2* r(X+Y~ -. +- (Xl+~l)*F1 2Jl/2*:. W'l*W2 L Wl Wl N2-Fl*Nl Again, keeping the* same variable definitions, t~e 112 LLD Sr-90 (pCi/l) = 4.66*[ (X+Y~ + (Xl+YE)*Fl ] L Wl Wl Calculation of Sr-89 Activity: N6/R Sr-89 Res~lts (pCi/l) = (2.22) * (E) ~ (1.0922) * (S7) * (V) * (U) * (F9) = W3 S7 = 1.052 - 0.00272*M - 0.00005*M2 (This is normalized Sr-89 efficiency regression equation for one particular gas p*roportional counter) N6 = Nl - N1* (1 + Rl*Il) N7 = (N2 - Fl*Nl) /Wl (This represents counts due to Sr-90) 1.0922 = Ratio of Sr-89 efficiency at thickness value of 15 mg/cm2 to Sr-90 counting standard efficiency (This standard is run with each group of en*vironrrental strontium samples) F9 = EXP ((-0.693/50.5)*t) t = Elapsed time from midpoint of collection period to time of recount for mfl k 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 variables are as originally defined 131

-~---.... :.-.. -~ ~... .... : ~. :. The 2 sigma error for Sr-89 (pCi/l) = 2* (S82+s92)1/2 *W3 (Nl - N7* (l+Rl*Il)) S8 = [~ + (Xl+Y~)*F12l 112 Wl Wl j S9 = (Xl+Y1) 1/ 2 All other variables are as originally defined Keeping t~e s~mT/~ariable definitions, the LLD Sr-89 (pCi/l) = 4.66* (SS +S9. ) 132

l I ' '. *:.:-*.... :.. ~ :..-,>."* :,_-.* :.**** : ;.-.. ~.* ~:.:* _:*; ' ~* .':*~-* *.'. -~. :::: "" ::;... :..,.;,:. ~-, *-* ANAL VS IS O( WATER SAMPLES FOR TRITIUM Approximately 50 ml of raw sample is mixed with sodium hydroxide and potassium permanganate and is distille~ under vacuum. Eight ml of distilled sample is mixed with 10 ml of Instagel liquid scintillation solution, and placed in the liquid scintillation spectrometer for counting. Prepared simultaneously for counting is the internal standard. This is done by mixing eight ml of sample, 10 ml of Instagel, and 0.1 ml of a standard with known activity. The efficiency is determined from this. Also prepared is a blank consisting of eight ml of distilled low-tritiated water and 10 ml of Instagel, to be used for a background determination. This is done for each pair of samples to be counted. Activity is computed as follows: A ( pCi I 1 ) = 4-( G;;;.,.-.;;,..B }"='<-~--.-..... 2.22(E) (V) (T) Efficie~cy (E) is computed as follows: E = (N) ~D) A N is determined as follows: A B "G E v T 2.22 = Activity = Background count of sample ~ Gross. c6ijnt of sample* ,;, _Gaunting efficiency = Aliquot volume (L) = Count time (min) = dpm/pCi N = Net cpm of spiked sample D = Decay factor of spike-A 1 = dpm of spike N = C-(G/T) C = cpm of spiked sample G = Gross counts of sample T = Count time (min) The associated error is expressed at 95% confidence limit, as follows: 1.96(G/T2+B/T2)112 2.22 (V) (E) If collection container is rinsed with distilled water (e.g., rainwater), the sample is corrected for the blank as follows: A (pCi/l} =.(G) (Sl) - (R) (S2) v v 2.22(V-S2) (E) (1000) Sl = Rainwater volume V = Sample volume 52 = Rinsewater volume R = Rinse counts Note: G and R are corrected for background counts Samples are designated LLD if the activity is less than the following value: LLD = (4.66~ ~B~l/ 2 2.22 V E) (T) 133

-:;:t: -~Ji~ fi~~

=.:*.::t-"t

~~

!I

_.:..tJ I

I I

.:.*~*-**-***; __ ~_-.:.:.:.:~.:,.:?-,

~--*-*----~.. -... ~...

~ '..

. ~*.:..... -....

RADIOSTRONTIUM IN WATER Stable strontium carrier is first introduced into a two liter water sample and into a distilled water sample of the same volume which is used as a blank. The sample(s) and blank are then made alkalin_e and heated to near boiling before pre-cipitating the carbonates. The carbonates are converted over to nitrates by fuming nitric acid recrystallization which acts to purify the sample of most of the calcium. Radioactive interferences are stripped out by coprecipitation on ferric hydroxide (yttrium strip) followed by a barium chromate strip. The stron-tium, now largely devoid of any chemical or radiological impurities, is converted back to a carbonate form 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 d~inking water* sampl~s,_ have. be~n found to contain signif.icant amounts of stable strontiUm~ a separate aliquot from e*ach sample is analyzed for stable strontium via DC.Argon Plasma Emission.*. These results are used in correcting the chemical recovery of strontium to its true value. Calculation of.Sr-90 Activity: N4/R Sr-90 Results ( pCi /1) = (2.22) * (E) * (0.7621) * (S6) * (V) * (U) = W2 where S6 = 1.4115 - 0.03409*M + 0.000443*M2 (This is normalized Sr-90 efficiency regression equation for one particular gas propor-tional counter) M = Thickness density of strontium carbonate precipitate, mg/cm2 0.7621 = Ratio of Sr-90 efficiency at thickness value of 15 mg/cm2 to Sr-90 counting standard efficiency (This standard is run with each group of environmental strontium samples) E = Sr-90 counting standard efficiency V = Sample quantity (liters, m3 or kg) U = Chemical yield N4 = (N2 - Fl*Nl) /Wl = net counts due to Sr-90 only Wl = ( (1 + Rl*l2) * (1.+ Rl*H)*Fl) 11 = 1 - EXP ((-0~693/2.667)*tl) 12 = 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 134

.:.:.. ~:: ...... -.. :*..,' ':. ". :.,*~* 2.667 = Half-life of Y-90, days Rl = 1.242 + 0.0179*M + 0.000151*M2 (This Y-90 eff'y/Sr-90 eff 1y ratio) is regression equation for 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 1s per pCi Fl = EXP ((-0.693/2.667)*t2) R = Count time of s~mple. and blank Using the same variable definitions as above, the 2 sigma error for Sr-90 (pCi/l) = 2* [.w + (Xl+p)*F12] l/2* Wl*W2 Wl Wl

N2-Fl*Nl Again, keeping the same variable definitions, the LLD Sr-90 (pCi/1) =

4.66* l-(X+~f- + (Xl+Y~)*F12] 1 / 2 ~H Wl Calculation of Sr-89 Activity: Sr-89 Results (pCi /l) = N6/R (2.22) * (E) * (1.0922) * (S7) * (V)* * (U) * (F9) = W3 57 = 1.052 - 0.00272*M - 0.00005*M2 (This is nonnalized Sr-89 efficiency regressipn equation for one particular gas proportional counter) N6 = Nl - N7*(1 + Rl*Il) N7 = (N2. - Fl*Nl)/Wl (This represents counts due to Sr-90) 1.0922 = Ratio of Sr-89 efficiency at thickness value of 15 mg/cm2 to Sr-90 counting standard efficiency (This standard is run with each group of environmental strontium samples) F9 = EXP ((-0.693/50.5)*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 135

. *Y/J

.?~f I

I

,~'

~ti~ All other variables are as originally defined The 2 sigma error for Sr-89 (pCi/l) = 2* sa2+s92 112 *W3 Nl - N7* l+Rl*Il SB = l(x+*) + (Xl+Y~)~FI2] 11 2 L Wl Wl S9 = (Xl+Yl) 1/2 All other variables are as originally defined Keepin~ the same variable definitions, the LLD Sr-89 (pCi/l) = 4.66* lS82+S9L)l/2 136 ~i'i'ffi~t5;cc:w,:,'t'.!itl~,:;0f'.E'~il'f,', :?,,';i:.)f§;;i(~i';*:*s* ';S'L);,, *,., :* :;;:. '.., * *.;** c**:;: : *.. :**,::.**.. ::;, !;;,,,,,,

APPENDIX E

SUMMARY

OF INTERLABORATORY COMPARISONS 137

~!:

0 ~~ '.}~.. DATE Jan 1981 March 1981 March 1981 April 1981 May 81 ne 1981 July 1981 Sept 1981 Sept 1981 Oct 1981 Nov 1981 R.lv1C # 43613 . 53663 54441 54841 55883 56994 57789 60388 60776 62491 64277 ~ ~.. : __,, *:.. ~-- .. *... ~*- TABLE E-1 INTER-LABORATORY COMPARISONS GROSS ALPHA AND BETA IN WATER (pCi/liter) and AIR PARTICULATES (pCi/filter) SAMPLE RMC EPA TYPE ANALYSIS MEAN+/-s.d. MEAN+/-s. d. Water

a.

10+/-2 9+/-5 f3 40+/-3 ~4+/-5 APT

a.

. 33+/-1 3o+/-a f3 74+/-2 50+/-5 Water

a.

26+/-3 25+/-6 s 31+/-2 25+/-5 Water

a.

64+/-7 91+/-23 B 134+/-9 141+/-7 Water a 25+/-2 21+/-5 s 15+/-2 14+/-5 APT*

a.

30+/-2 28+/-7 f3 79+/-5 54+/-5 Water

a.

19+/-3 22+/-6 f3 16+/-1 15+/-5 Water

a.

48+/-4 33+/ s 26+/-1 28+/-5 APT a 27+/-3 25+/-6 B 63+/-7 51+/-5 Water ex 52+/-5 80+/-20 s 106+/-3 111+/-6 Water

a.

24+/-2 21+/-5 f3 21+/-1 23+/-5 139 All Participants MEAN+/-s.d. 9+/-3 44+/-6* 32+/-5 56+/-11 24+/-6 28+/-5 76+/-24 140+/-21 19+/-5 16+/-4 32+/-6 64+/-10 18+/-5 17+/-4 28+/-8 25+/-6 26+/-6 61+/-10 70+/-17 103+/-15

20+/-5 23+/-5

DATE Feb 1981 1;1_.. Apr ~';\\ .. 1981.

June 1981 Aug 1981 Oct 1981 Dec 1981 SAMPLE RMC #

TYPE 44003 Water 53660 Water 56309 Water 58155 Water 61871 Water 64936 Water TABLE E-2 INTER-LABORATORY COMPARISONS TRITIUM IN WATER pCi/liter RMC ANALYSIS MEAH+/-s.d. H-3 1680+/-137 H-3 2727+/-6 H-3 2053+/-32 H-3 2693+/-40 H-3 2467+/-106 H-3 2637+/-90 140 o<

~

' ~: ':~* ** EPA All Participants MEAN+/-s.. d. MEAN+/-s.d. 1760+/-341 1778+/-230 2.710+/-355 2717+/-373 1950+/-344 1946+/-241 2630+/-354 2616+/-361 2210+/-348 2133+/-214 2700+/-355 2676+/-244

DATE Jan 1981 Jan 1981 Ma.rch 1981

March 1981 Apr 1981 May 1981 May 81

.. ' ~* '.. :. -*. ~... -. *. --*-*. ':.. :.1.

** -~-

RMC # 43229 43514 44815 53663 54841 54879 55248 56994 57331 57812 59585 60776 62491 62547 63205 SAMPLE .TYPE Water Milk Food* APT Water Water Milk APT Food Milk Water APT Water Milk Food TABLE E-3 INTER-LABORATORY COMPARISONS* STRONTIUM-89 AND STRONTIUM-90{ 1) ANALYSIS Sr-89 Sr-90 Sr-89 Sr-90 . Sr-89 Sr-90. Sr-90 Sr-89 Sr-90 Sr-89 Sr-90 Sr-89 Sr-90 Sr-90 Sr-89 Sr-90 Sr-89 Sr-90 Sr-89 Sr-90 Sr-90 Sr-89 Sr-90 Sr-89 Sr-90 Sr-89 Sr-90 141 RMC MEAN+/-s.d. 24+/-11 27+/-7 <8 22+/-3 74+/-13 32+/-2. 16+/-2 32+/-6 29+/-5 51+/-2 26+/-10 9+/-2 9+/-1 18+/-2 36+/-14 23+/-1 20+/-7 16+/-0 21+/-5 6+/-2 16+/-1 24+/-7 9+/-6 26+/-2 17+/-2 31+/-6 21+/-2 EPA MEAN+/-s.d. 16+/-5 34+/-2 0 20+/-3 47+/-5. .29+/-2

18+/-1.5 38+/-5 28+/-1.5 36+/-5 22+/-1.5 25+/-5 11+/-1.5 19+/-2 44+/-5 31+/-2 25+/-5 17+/-2 23+/-5 11+/-2 16+/-2 21+/-5 14+/-2 23+/-5 18+/-2 38+/-5 23+/-2 All Participants MEAN+/-s *. d~

15+/-5 32+/-5 29+/-37 19+/-3 43+/-18 27+/-8 17+/-3 34+/-9 26+/-7 32+/-10 22+/-6 22+/-6 10+/-3 19+/-3 44+/-9 29+/-3 24+/-6 16+/-2 22+/-3 11+/-2 17+/-3 22+/-6 13+/-3 22+/-5 18+/-3 35+/-6 23+/-4

SAMPLE ATE RMC # TYPE pr -53750 Water 981 ug 58205 Water 981 ec 64544 Water 981 I. TABLE E-4 INTER-LABORATORY COMPARISONS IODINE-131 IN WATER pCi /1 i ter RMC ANALYSIS MEAN::ts.d. I-131 31+/-3 I-131 66+/-5 I-131 64+/-3 EPA All Participants MEAN+/-s.d. MEAN+/-s. d. 30+/-6 29+/-5 73+/-7. 72+/-}... 76+/-8 69+/-10

.~* * '""

1:'~'u*

.~....-.

._,_.,f,_-.,.,~:;~~,*;,.,,.._'

TABLE E-5 INTER-LABORATORY COMPARISONS GAMMAt 1)

DATE July 1981 Sept

1981 Oct 1981 Oct 1981 Oct 1981 Nov 1981 (1)

{a) c .~ *** *.~ - ~ *' ** * ** SAMPLE RMC # TYPE 57812 Milk 6077£ APT 62282 Water.

62491 Water*

62547 Milk 63205 Food TABLE E-5 (cont.) INTER-LABORATORY COMPARISONS GAMMAt lJ RMC ISOTOPE MEAN+/-s.d. .I-131 <8 Cs-137 31+/-1 Ba-140 <25 K 1136+/-49 Cs-137

18+/-3 Cr-51

<75 (a) Co-60 25+/-2 Zn-65 25+/-2 Ru-106 <29 Cs-134 21+/-1 Cs-137 33+/-2 Co-60 <3 Cs-134 11+/-1 Cs-137 16+/-1 I-131 53+/-1 Cs-137 26+/-2 Ba-140 <17 K 1526+/-0 Co-60 26+/-2 Cs-137 27+/-1 Ba-140 <35 K 2113+/-0 .,: -**.:.. *.*. *~..... >., -. *,.'J).:..: -~~.** : ;,....... _. EPA All Participants MEAN+/-s.d. MEAN+/-s. d. o 7+/-7 31+/-5 32+/-4 0 0 1600+/-80 1593+/-99 19+/-5 24.+/-6 34+/-5 36+/-9 22+/-5 23+/-3 24+/-5 24+/-4 .o 0 21+/-5 20+/-4 32+/-5 33+/-4 0 0 12+/-5 12+/-2 15+/-5 16+/-3 52+/-6 53+/-7 25+/-5 27+/-3 o o 1530+/-77 1532+/-108 30+/-5 30+/-4 33+/-5 34+/-4 0 6+/-6 2730+/-137 2758+/-331 Results reported in pCi/liter for milk and water, pCi/sample for air particulates, and pCi/kilograms for food products except K which is reported in mg/liter for milk and mg/kilogram for food products. Sample was not analyzed within one half-life resulting in large LLD due to a long decay period. 144

i ~

'*i

~--.-..:... **.*-: *.***.*.,...

_.~. "... "'**.., ~. ~.... ""'"'" *?. APPENDIX F SYNOPSIS OF DAIRY & VEGETABLE GARDEN SURVEY 145

- - -*-*;***.. * -~:*. *:*.... **;.**.***..... ~.*.-**..,.

.-~*.-...,****.., ~-.*

...,...., -.. ~.* ',.,. _,.... *.... *:,. *; '...

'**,*.~*:**,;*.~.... - ~

....,..,._... ~*-.,_*. *: *:. ",*. *.. _, ':. APPENDIX F SYNOPSIS OF DAIRY & VEGETAB~E GARDEN SURVEY A door-to-door survey of dairy farms within 5 miles of SNGS was performed in April and July. The results of the April survey were as follows: One dairy farm, located 4.9 miles from SNGS*in the west sector was located.* The results of the July survey were as follows: No ~hange* from A~rfl survey: Since a dairy farm was located within 5 miles of the site, the vegetable garden survey was performed to a distance of one mile. No vegetable gardens were found in this area. 147}}

ML18087A584

Contents

Text

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

Potable Water; (PWR = raw, PWT

SUMMARY

Navigation menu

ML18087A584

Text

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

Potable Water; (PWR = raw, PWT

SUMMARY

Navigation menu

Search