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=Text=
=Text=
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-! ; * ., . *-.j I RTL-ENV-"'87-01 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Fc.w Salem Generating Stat.icn.
RTL-ENV-"'87-01 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Fc.w Salem Generating Stat.icn. Unit i: Doc:l<et No. 50=272 Salem Generating Staticmo Unit 2: Docket No. 50-<:H,,1 Hope Creel< Generating Stat ion: Doc:l<et No. 50-354 I
Unit i: Doc:l<et No. 50=272 Salem Generating Staticmo Unit 2: Docket No. 50-<:H,,1 Hope Creel< Generating Stat ion: Doc:l<et No. 50-354 1986 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ..JANUARY 1 TO DECEMBER 31, 1986 PUBLIC SERVICE ELECTRIC ANO GAS COMPANY Sy RESEARCH CORPORATION ANO TESTING APRIL 1987 . . * .. ' ' ., ,, I .  
1986 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT
-----.--*  
                                                                        ..JANUARY                     1     TO DECEMBER 31, 1986 PUBLIC SERVICE ELECTRIC ANO GAS COMPANY Sy
*-:-. -.--.----** *-* .. ----. ------. --
                                                                                        ~SE&G              RESEARCH CORPORATION
...  
      ;                                                                          RESEA~CH                    ANO TESTING LABORATOR~
.. *-*--*---.--***-.-*  
. *-.j APRIL 1987 I
-*---*
    . *-*......,.---~..,.------ *--~- ----------..-~-----:*--*-****----*-- -----.--* *-:-. -.--.--- -** *-* .. ----. ------  . - - **--*---**--**------.---:-~..:~ ...~if---'*-*--*** .. *-*--*---.--***-.-* - *- - -*
*.* TABLE OF CONTENTS ' '
 
TABLE OF CONTENTS


==SUMMARY==
==SUMMARY==
o*****  
o*****           *0*111e1oocieo11e1e1c()CDeoc**g****C11E10***C1**0*0C                                                          ' 1'                                    1 INTRODUCTION.         eC1eeeC1Geeeeee*eeeeeeGeeeee                                                                                 *'. 0 ******           Cl
*0*111e1oocieo11e1e1c()CDeoc**g****C11E10***C1**0*0C1 INTRODUCTION.
* 2 THE PROGRAM **             **oc*C1*e*****oeeeec1>eo1:1t1*                                                                                                                       3 Objectives.     c o o o e o o E> o o o o o o o     Cl e o o o o *
eC1eeeC1Geeeeee*eeeeeeGeeeee  
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* THE PROGRAM ** **oc*C1*e*****oeeeec1>eo1:1t1*
Objectives.
c o o o e o o E> o o o o o o o Cl e o o o o *
* o o o *
* o o o *
* c. '' '. ' OOOCIOCCCICO sample Collection.
* c.
oeooo0ceGeoooeoe O.eOCCICI000CO Data Interpretation.
OOOCIOCCCICO                           3 sample Collection.                   oeooo0ceGeoooeoe                                                                     O.eOCCICI000CO                           4 Data Interpretation.                 e e   e e   Cl o Cl Cl* e e 0   G   e e     Cl e             D. O Cl   e   !I* O G Cl e Cl Cl Cl Cl 0 e Cl Cl           5 Quality Assurance Program.                                                                                                                                           6 Program     Changes~      ***                                                               .   '**
e e e e Cl o Cl Cl* e e 0 G e e Cl e ., D. O Cl e !I* O G Cl e Cl Cl Cl Cl 0 e Cl Cl Quality Assurance Program. Program  
                                                                                                                                            . *t ID !~  e e e                                       7 RESULTS AND DISCUSSION.                                                                                                         efloeooo1D*eoo                               7 Atmospherieo       0 0 0 0 D 0 e cc c     0 Cl) 0 0 0 0   0 0 0   0 0   c' 0   (!) 0 *11 o'   0   0 C>   ~;o    0. e Cl 0 0.0   0 0 Cl 0 0           7 Direct Radiation ***               OCODOCCIC8()0000000                                                                                                             10 Terrestrial ** " o e      OG   Cl 0 00   00   OC!IOGGOO           0   0   0   Cl                                                                               10 Aquatic *****           * * * * * *. * * *   *
*** . '** . ' ;"; *t ID e e e ;. '. RESULTS AND DISCUSSION.
* o *   * * *
efloeooo1D*eoo 1 2 3 3 4 5 6 7 7 Atmospherieo 0 0 0 0 D 0 e cc c 0 Cl) 0 0 0 0 0 0 0 0 0 c' 0 (!) 0 *11 o' 0 0 C> 0. e Cl 0 0.0 0 0 Cl 0 0 7 *. ! ' " " -. ' * .. 1 1 I I ', *1 Direct Radiation  
*** OCODOCCIC8()0000000 Terrestrial  
** "oe OG Cl 0 00 00 OC!IOGGOO 0 0 0 Cl Aquatic ***** * * * * * *. * * * *
* o * * * *
* c *
* c *
* e **
* e ~* **
* 0 PROGRAM DEVIATIONS.
* 0                                                               16 PROGRAM DEVIATIONS.               e e Cl e e e e e   G   Cl G Cl e e e e e e e e           e ,e e   e   e e   e e e e         e Cl e e   ID 8 e e e   Cl e         19 CONCLUSIONS ******           ************cioeoeeooocoe                                                                 C1eeeOGCOGeC1eee                                   19 PROGRAM OVERVIEW.             0000CICIOOCICOCICI080000DOCI
e e Cl e e e e e G Cl G Cl e e e e e e e e e ,e e e e e e e e e e Cl e e ID 8 e e e Cl e ' CONCLUSIONS  
* e*   Cl o. c     a o *
****** ************cioeoeeooocoe C1eeeOGCOGeC1eee PROGRAM OVERVIEW.
0000CICIOOCICOCICI080000DOCI
* e* Cl o. c a o *
* e
* e
* o o
* o o
* c o o c
* c o o c
* REFERENCES.
* 21 REFERENCES.         ooocaooooeeeoccooooocociao                                                    eaeooooocoeooeeoooo                                                    36 APPENDIX A             PROGRAM  
APPENDIX A APPENDIX B APPENDIX C APPENDIX D APPENDIX E APPENDIX F ooocaooooeeeoccooooocociao eaeooooocoeooeeoooo PROGRAM  


==SUMMARY==
==SUMMARY==
. () ... 'ci. 0 0 Cl c Cl 0 SAMPLE DESIGNATION AND:LOCATIONS.
.                                   () ... 'ci. 0   0 Cl c Cl 0                                                                   39 APPENDIX B            SAMPLE DESIGNATION AND:LOCATIONS.                                                                                                                   51 APPENDIX C            DATA TABLES **********                             Q   0 '*   . '* CIOOOOOOOOCCCOCIOCIOCOOO                                                       59 APPENDIX D            SYNOPSIS OF ANALYTICAL'PROCEDURESo                                                                   Cl Cl 0.0. Cl 0 0 cc 0             113
DATA TABLES **********
    "'                    APPENDIX E           
Q 0 '* . '* CIOOOOOOOOCCCOCIOCIOCOOO SYNOPSIS OF ANALYTICAL'PROCEDURESo Cl Cl 0.0. Cl 0 0 cc 0  


==SUMMARY==
==SUMMARY==
OF LABORATORY USEPA ENVIRONMENTAL RADIOACTIVITY INTERCOMPARISON STUDIES PROGRAM RESULTS 0&deg;0 Cl c Cl* 0. 0 0. c G G. 0&deg; 0 0. :0 0 0 SYNOPSIS OF LAND USE CENSUS. 0 0 0 o_o 0 0 0 0 0 0 0 0. 0 0 .-0 ... '! __ ---.. ------*---*:*-
OF USEPA ENVIRONMENTAL RADIOACTIVITY
------,------
      "                                            LABORATORY INTERCOMPARISON STUDIES PROGRAM RESULTS     0&deg;0 Cl c Cl* 0 . 0   0. c G   G. 0&deg; 0   0 . :0     0   0                                                                     161 APPENDIX F            SYNOPSIS OF LAND USE CENSUS.                                                 0 0   0   o_o     0   0   0 0 0 0 0 0. 0 0 .-0   ... 171
-* 10 10 16 19 19 21 36 39 51 59 113 161 171 *-.. --* .... **-,-. *--
    *. 1 1
. ' ''.* *.**; *.* . *' ,, *, '.*. :/ .. * .. ,.j ' *-. * .
I I
* LIST OF. FIGU.RES .. * .. FIGURE* NUMBER. . FIGURE DESCRIPTION.
  ', *1
PAGE 1. Comparison of Average Concentrations of Beta Emitters in Precipitation and in Air Particulates,.
                                                                                                                                                                                                                ~
1973 through 1986..................................
 
26 lA. Comparisbn of Average Concentrations of Beta Emitters in Precipitation and in Air Particulates, 1983 1986 *********
LIST OF. FIGU.RES .. *..
27 2. 2A. 3. 3A. 4. 4A. s. SA. Average Ambient Radiation*
FIGURE*
Levels from Quarterly TLDs in the Vicinity of Artificial Island, 1973 through  
NUMBER. .                        FIGURE DESCRIPTION.
.......* ** ............................. . Comparison of Ambient Radiation Levels of Off-Site Indicator vs.
                          ~~~~~~~~..;;..;;;..;;..~;;;...;..~.=...:;:;.;.::.=...:;~.;.;;.....;_~~~~~~~-*
Stations, 1982 through 1986 ***************************************
PAGE
Average Concentrations of Iodine-131 in Milk in the Vicinity of Artificial Island, May 1974 through December 1986 **********.**  
                                                                                                                    ~
:.-*.***************  
: 1. Comparison of Average Concentrations of Beta Emitters in Precipitation and in Air Particulates,.
* *******. Average Concentrations of Iodine-131 in Milk in the Vicinity of Artificial Island, 1983 througn 1986 ... Average Concentrations of Beta Emitters and Potassium-40 in the Delaware River in the Vicinity 6f Artificialjisland, 1973 through 1986 ****** ***** Average of Beta Emitters and Potassium-40 in the Delaware River in the Vicinity of Artificial Island, 1983 through 1986 ************
1973 through 1986..................................                                         26 lA.     Comparisbn of Average Concentrations of Beta Emitters in Precipitation and in Air Particulates, 1983 th~ough 1986 ********* ~........................                                       27
Average Concentrations of Tritium in the Delaware River in the Vicinity of Artificial Island, 1973 through 1986* ..*.....*..*.  
: 2. Average Ambient Radiation* Levels from Quarterly TLDs in the Vicinity of Artificial Island, 1973 through   1~86  .......* ** . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 28 2A.      Comparison of Ambient Radiation Levels of Off-Site Indicator Station~ vs. Cont~ol Stations, 1982 through 1986 ***************************************                                       29
* ............*.  
: 3.      Average Concentrations of Iodine-131 in Milk in the Vicinity of Artificial Island, May 1974 through December 1986 **********.** :.- *.*************** * *******.                               30  ~
* ...*... :. ..... Average Concentrations of Tritium in *the Delaware River in the Vicinity of Artificial Island, 1983 through 1986 *************************** ***********
3A.      Average Concentrations of Iodine-131 in Milk in the Vicinity of Artificial Island, 1983 througn 1986 ...                                       31
1:1. 28 29 30 31 32 33 34 
    *.**;          4.      Average Concentrations of Beta Emitters and Potassium-40 in the Delaware River in the Vicinity
* *, ;_ ' . I ,, . ' **: .. i .'-! ... -, . : -, *: '. _;. r:
*.*  . *'                6f Artificialjisland, 1973 through 1986 ****** ~ *****                                     32 4A.      Average Concen~rations of Beta Emitters and Potassium-40 in the Delaware River in the Vicinity of Artificial Island, 1983 through 1986 ************                                         33
: s. Average Concentrations of Tritium in the Delaware River in the Vicinity of Artificial Island, 1973 through 1986* ..*.....*..*. *............*. *...*... :. .....                               34
: / ..
SA.      Average Concentrations of Tritium in *the Delaware River in the Vicinity of Artificial Island, 1983
  *.. ,.j                  through 1986 *************************** ~ ***********
1:1.


==SUMMARY==
==SUMMARY==
During the per.iod from January l through December*
 
31, 1986;. the*. Research*
During the per.iod from January l through December* 31, 1986;. the*.
and Testing Laboratory (RTL), PSE&G Research ration, has been responsible for the collection and analysis of all samples and the maintenance of sampling equipment connected with the Radiolog_ical Environmental Monitoring Program (llEMP');
Research* and Testing Laboratory (RTL), PSE&G Research Cor.po-ration, has been responsible for the collection and analysis of all samples and the maintenance of sampling equipment connected with the Radiolog_ical Environmental Monitoring Program (llEMP');
at Artificial Island, Salem County, New Jersey. This program was designed to identify .and quantify tions of radioactivity in various environmental media and ta quantify ambient radiation levels in therenvirons of Artificial Island. Due to the proximity of the Hope Creek ating Stations a common REMP is beinci' co.hducted.
at Artificial Island, Salem County, New Jersey.
Salem ating Station (SGS) Unit One became* crit:ic!al on December 11., 1976, thereby initiating the operational phase of the REBPo Data collected during the operaJ:,ion,al!
This program was designed to identify .and quantify concentra~
phase served as a of preoperational data for Salem Uqit and the Hope Creek Generating Station. Salem Unit Two achieved initial criticality on August 2, 1980 and the Hope  
tions of radioactivity in various environmental media and ta quantify ambient radiation levels in therenvirons of Artificial Island. Due to the proximity of the Salem~and Hope Creek Gener-ating Stations a common REMP is beinci' co.hducted. Salem Gene.r-ating Station (SGS) Unit One became* crit:ic!al on December 11.,
:G:enerating Station achieved initial criticality on June 28, '! This report presents the results of thermoluminescent arid radiological analyses of environmental samples 1986. : :; .. A total of 4091 analyses were perf'ormed on 1615 environment.al samples during the period covered' by .this report.-Samples of air particulates, air iodine, surface, ground and drinking water, benthic organisms, sediment, milk, fish, crabs, bles, game, fodder crops, meat, soi1,:* and precipitation were collected.
1976, thereby initiating the operational phase of the REBPo Data collected during the operaJ:,ion,al! phase served as a sourc:e.-
Thermoluminescent were* used to measure radiation levels. Ambient radiation levels remained .at normal levels observed in previous years until May 9, when radioactivity from the Chernobyl-4 reactor accident detected.
of preoperational data for Salem Uqit ~wo and the Hope Creek Generating Station. Salem Unit Two achieved initial criticality on August 2, 1980 and the Hope Cre~k :G:enerating Station achieved initial criticality on June 28, 19:~6 ~ '! This report presents the results of thermoluminescent dosi~~t~i arid radiological analyses of environmental samples collected~d~iing 1986.
According to reports provided to Western scientists at:the International Atomic Energy Agency conference on Chernc;>byl held in Vienna, Austria, it is now known that the accident occurred as a result of a poorly planned reactor experiment.
A total of 4091 analyses were perf'ormed on 1615 environment.al samples during the period covered' by .this report.- Samples of air particulates, air iodine, surface, ground and drinking water, benthic organisms, sediment, milk, fish, crabs, vegeta-bles, game, fodder crops, meat, soi1,:* and precipitation were r:
Soviet plant personnel deliberately took actions which blocked the plant's safeguard systems that would have automatically prevented the accidento This action resulted in a reactivity excursion accident in which the reactor became prompt c;ri.tical  
collected. Thermoluminescent dos~meter$ were* used to measure ambien~ radiation levels.
[ 24 I. The excursion resulted in a power escalation which resulted in fuel melting and finally a steam explosion which fuel fragments, activation products and burning graphite into the environmente The intense heat of the graphite fire.provided a mechanism for the active fission products and activation products to_ become_. sufficiently buoyant to enter :the upper atmosphere  
Ambient radiation levels remained .at normal levels observed in previous years until May 9, 19~~ when radioactivity from the Chernobyl-4 reactor accident wa~ detected. According to reports provided to Western scientists at:the International Atomic Energy Agency conference on Chernc;>byl held in Vienna, Austria, it is now known that the accident occurred as a result of a
[ 25]. Actions taken to fight the fire resulted in additional tion of.the core which caused*airborne releases into the environment to fluctuated by several orders of magnitude for several days after the
      -~
.. *:*-*. ' .. ' .. *.: .. t. .. * . . . .. *: . ' Estimates*:
poorly planned reactor experiment. Soviet plant personnel I
of projected
deliberately took actions which blocked the plant's safeguard
:I-131 concentrations
      .  '        systems that would have automatically prevented the accidento
:i;n milk*. in the. town .... of Pr ipyat, . USSR. were .'reported*.
**: .. i This action resulted in a reactivity excursion accident in which the reactor became prompt c;ri.tical [ 24 I. The excursion resulted in a power escalation which resulted in fuel melting and finally
as :high as 10 3, 700 ,*ooo pCi/L [ 25 l
          -,        a steam explosion which prdp~lled fuel fragments, activation products and burning graphite into the environmente The intense heat of the graphite fire.provided a mechanism for the radio~
* The Soviets arid the Scandariavian countries.also.repcirted ing excessive concentrations of radioactivity in.soiis,, reindeer flesh, fish, wells, rainwater and goat milk.* .Since all releases from*our nuclear stations were within our technical tions, the increases in radioactivity measured in various environmental media in the vicinity of the Artificial Island were due to the accident at Chernobyl-4 and not to the operation of the Salem or Hope Creek. Generating Stations *. INTRODUCTION Artificial Island is the site of Salem and Hope Creek Generating Stations.
active fission products and activation products to_ become_.
The Salem -Generating Station (SGS) consists of two operating pressurized water nuclear power reactors.
sufficiently buoyant to enter :the upper atmosphere [ 25].
Salem Unit One has *a net rating of 1090 MWe (3338 MWt), and Salem Unit Two is rated at 1115 MWe (3411 MWt). The Hope Creek Generating Station (HCGS) is a boiling water nuclear power reactor which achieved initial criticality on June 28, 1986. The Hope Creek Unit has a* net rating of 1067 MWe (3293 MWt). Artificial .Island is a* man-made peninsula on the east bank of th Delaware River and was created by the deposition of hydraulic fill from dredging operations.
      '.*:~        Actions taken to fight the fire resulted in additional destruc~
It. is located in Lower Alloways Creek Township, Salem County, New Jersey *. The environment
tion of.the core which caused*airborne releases into the environment to fluctuated by several orders of magnitude for several days after the accident~
* surrounding Artificial Island is characterized mainly by the Delaware River and Bay, extensive tidal marshlands, and low-lying meadowlands.
 
These land types make up approximately 85% of the land area within five miles of the site. Most of the remaining land is used for agriculture  
Estimates*: of projected :I-131 concentrations :i;n milk*. in the. town ....
[7,8]. More specific informatfon .on the demography, hydrology, meteorology, and land use of the area may be found *in the Environmental Beports [7,8], mental Statements  
of Pr ipyat, . USSR. were .'reported*. as :high as 10 3, 700 ,*ooo pCi/L [ 25 l ~.
[9,10], and the Updated Final Safety Analysis Report for SGS [11] and the Final Safety Analysis .Report for HCGS [ 12]. / Since 196a an off-site Radiological Environmental M6nitoring Program (REMP) has beeri conducted at the Artificial Island Site. *Starting in December*
* The Soviets arid the Scandariavian countries.also.repcirted measur--
1972, more extensive radiological monitoring programs were. initiated.
ing excessive concentrations of radioactivity in.soiis,, reindeer flesh, fish, wells, rainwater and goat milk.* .Since all releases from*our nuclear stations were within our technical -specifica-tions, the increases in radioactivity a~ measured in various environmental media in the vicinity of the Artificial Island were due to the accident at Chernobyl-4 and not to the operation of the Salem or Hope Creek. Generating Stations *.
The operational REMP. was initiated in December 1976 when Salem Unit 1 achieved criticality.
INTRODUCTION Artificial Island is the site of Salem and Hope Creek Generating Stations. The Salem -Generating Station (SGS) consists of two operating pressurized water nuclear power reactors. Salem Unit One has *a net rating of 1090 MWe (3338 MWt), and Salem Unit Two is rated at 1115 MWe (3411 MWt). The Hope Creek Generating Station (HCGS) is a boiling water nuclear power reactor which achieved initial criticality on June 28, 1986. The Hope Creek Unit has a* net rating of 1067 MWe (3293 MWt).
The Research and Testing Laboratory (RTL), PSE&G Research ration, a wholly-owned subsidiary of Public Service Electric and Gas Company,.
Artificial .Island is a* man-made peninsula on the east bank of th Delaware River and was created by the deposition of hydraulic fill from dredging operations. It. is located in Lower Alloways Creek Township, Salem County, New Jersey *. The environment
has been involved in the REMP since its inception
* surrounding Artificial Island is characterized mainly by the Delaware River and Bay, extensive tidal marshlands, and low-lying meadowlands. These land types make up approximately 85% of the land area within five miles of the site. Most of the remaining land is used for agriculture [7,8]. More specific informatfon
* The RTL is responsible for the collection of all radiological environmental samples, and, from 1973, through June, 1983, conducted a quality assurance program in which duplicates of a portion of those samples analyzed by the primary laboratory were also analyzed by the RTL. *
                                                          .on the demography, hydrology, meteorology, and land use of the area may be found *in the Environmental Beports [7,8], Environ-mental Statements [9,10], and the Updated Final Safety Analysis Report for SGS [11] and the Final Safety Analysis .Report for HCGS
* 2  
                ..                                        [ 12].                                                                                           /
-:::--: -*. -:.:--* ...  
Since 196a an off-site Radiological Environmental M6nitoring Program (REMP) has beeri conducted at the Artificial Island Site.
.. -----. -. -. "-;-"?-..... -.*---. .-.  
                                                        *Starting in December* 1972, more extensive radiological monitoring programs were. initiated. The operational REMP. was initiated in December 1976 when Salem Unit 1 achieved criticality. The
...  
                  .. t.                                    Research and Testing Laboratory (RTL), PSE&G Research Corpo-ration, a wholly-owned subsidiary of Public Service Electric and
---------** -*--;--* *----*----*-** * .. * .. 
. ~ .. *: . ~
.. ,.. ** .. ; .. , ' . ; . i i ! . ' _, .. . ; *. *j . *,_ .. I . :. j .****** \'! ' . . . ; From January1 1973, through. June, ,.1983 1 .. Radiation Management
              .. *.                                        Gas Company,. has been involved in the REMP since its inception
* Corporation (RMC) had primary responsib-ility.
* The RTL is responsible for the collection of all radiological environmental samples, and, from 1973, through June, 1983, conducted a quality assurance program in which duplicates of a portion of those samples analyzed by the primary laboratory were also analyzed by the RTL.                                                                                                     *
for _the analysis of all samples under the Artificial.
* 2
Island REMP and the annual reporting of* results.
                    '-.~._..-...,."'."'-, ---*~-:**.---;--~ - : : : - - :-    *. - : . : - - *~
* RMC reports for the *the preopera tional phase from* 197 3 to 1976 and for *the operational phase from 1976 through 1982 are referenced in this report [l-3]. On July 1, 1983, the RTL assumed primary responsibility.for the analysis of all samples (except TLD's) arid the reporting of results. Teledyne Isotopes (TI), Westwoo9, NJ, at that time was made responsible for third-party QA analyses and TLD's *. RTL reports for the operational phase from i983 to 1985 are in this report  
                                                                                                ... _,-~-                                                                                         ...
' " t ; This report summarizes the r.esu:lts from January l through December 31, 1986, for the* A;rtffi!cial Island Radiological Environmental Monitoring  
                                                                                                                                  ..... - . * - -- .. - .~*-::~-:-'-. -:~*-7""-~~--~---~~-~~.--:-: ~:---:*--~*-*.
* . , . '1 I ** : ;, .. THE PROGRAM t; r :-; The operational phase of  
                                                                                                        .. - - - - - .- .- . "-;-"?-                                                                              ------ ---** -*--;--* *--- -*--- -*-**
:;REMP was conducted in accordance with Section Sections 6.9.1.10 of Appendix A to SGS Oper*ting Licenses DPR-7& and DPR-75 [14,15] and. Sections 3/4.12 and 6c9.l *. of Appendix A to:HCGS Operating License NPF=57 [lSlo An overview of the program is provided in Table 1 (page 21). Radioanalytical data from samples collected under this program were compared with results from the preoperational phase. Differences between these periods were examined statistically, where applicable, to the effects, if any, of station operations.  
 
* *
**                                       From January1 1973, through. June, ,.1983 1.. Radiation Management
* The REMP for the Island Site includes additional samples and analyses not specifically required by the Salem and Hope Creek Generating  
* Corporation (RMC) had primary responsib-ility. for _the analysis of all samples under the Artificial. Island REMP and the annual reporting of* results.
:Stations Technical Specifications.
* RMC reports for the *the preopera tional phase from* 197 3 to 1976 and for *the operational phase from 1976 through 1982 are referenced in this report [l-3]. On July 1, 1983, the RTL assumed primary responsibility.for the analysis of all samples (except TLD's) arid the reporting of results.
The summary tables in this include these additional samples and analyses
Teledyne Isotopes (TI), Westwoo9, NJ, at that time was made responsible for third-party QA analyses and TLD's *. RTL reports for the operational phase from i983 to 1985 are refere~ced in this report [4~6].
* Objectives  
                                                                                                          ' "         t     ;
*. '
This report summarizes the r.esu:lts from January l through December 31, 1986, for the* A;rtffi!cial Island Radiological Environmental Monitoring ~r~gram
* l The objectives bf'.: th'e Operational Radiological*
* I:  **
Environmental Monitoring Program  
                                                                                                        '1 THE PROGRAM                                                 t;   r .t~
: 1. To obligations of the Radiological surveillance sections of the Technical Specifications for the Salem Generating"Station 1SGS) and the Hope Creek Generating Station (HCGS). ' : 2. To determine whether any significant increase occurs in the concentration'of radionuclides in critical pathways * :. j '*1
                                                                                                            ~    :-;
...
The operational phase of !th~ :;REMP was conducted in accordance with Section Sections 3/4~l~~and 6.9.1.10 of Appendix A to SGS Oper*ting Licenses DPR-7& and DPR-75 [14,15] and. Sections 3/4.12 and 6c9.l *. ~. of Appendix A to:HCGS Operating License NPF=57 [lSlo An overview of the program is provided in Table 1 (page 21).
.. -.  
Radioanalytical data from samples collected under this program were compared with results from the preoperational phase.
.. ,-.... c7 ..
Differences between these periods were examined statistically, where applicable, to d~te~mine the effects, if any, of station operations.                                         * *
--**-----.. --.. -_ .... *----.----, ..... _
* The REMP for the Artii~cial Island Site includes additional samples and analyses not specifically required by the Salem and Hope Creek Generating :Stations Technical Specifications. The summary tables in this r~port include these additional samples and analyses
* ******-*r,***--i-*-* 
* Objectives
. *, .* ;! ' .* . . . -: :**. -.. ** ... ; ; * ' .1 4. 5. To determine-if SGS or HCGS
          . .,                                                                  *. '
:an increase*in . . To detect any change .in ambient gamma.radiation.levels.
* l
To verify that SGS and HCGS operations have no detrimental effects on the health and safety of the public or on. the environment.
          ' .; .~
This report, as required by Section 6.9.1.10 of the Salem Technical Specifications, and Section 6.9.l.,6 of the Hope Creek Technical Specifications summarizes the findings of the 1986 REMP. Results of the four-year preoperational program which was conducted prior to the operation of any reactors on the ficial Island have been summarized for purposes of comparison with subsequent operational reports [2]. Sample Collection In order to meet the stated objectives, an appropriate tional REMP .was developed." samples of var.ious media were selected to obtain data for the evaluation of the radiation dose to man and other organisms
i                    The objectives bf'.: th'e Operational Radiological* Environmental i                    Monitoring Program ~re:
*. The selection of sample types was on: (1) established critical pathways for the transfer of radionuclides through the environment to man, and .(2) experience gained during the preoperat.ional phase. Sampling l.ocations were determined from site meteorology,*
                  !                          1. To fulfill.~h~ obligations of the Radiological surveillance
Delaware estuarine hydrology, local demography, and land
_,'                              sections of the Technical Specifications for the Salem
* Sampling locations were divided into two classes -indicator and control. Indicator statioris are those which are expected to manifest station effects, if any exist; control samples are collected at locations which are believed to be unaffected by station operations.
                  .                                Generating"Station 1SGS) and the Hope Creek Generating
Fluctuations in the of radionuclides and direct radiation at indicator stations are evaluated with respect to analogous fluctuations at control. stations.
            *.    *j Station (HCGS).
Indicator and control station data.are also evaluated relative to ational data. Air particulates were 'collected on Schleicher-Schuell No. 25 glass fiber filters with low-volume air samplers.
: 2. To determine whether any significant increase occurs in the concentration'of radionuclides in critical pathways *
Iodine was collected from air by adsorption on TEDA-impregnated charcoal cartridges connected -in series after the air particulate filters. Air sample volumes were measured with calibrated dry-gas meters and were corrected to standard temperature and pressure.  
            .. ~ I
* .. Precipitation was collected in a. Wong Laboratory Automatic Precipitation Collector having a 95 square inch collection area. The collector is automatically covered during periods of* no precipi. ta ti on to exclude fallout resulting from dry. deposition
    . :. j
** Samples were collected monthly and transferred to new polyethyle 4 
.******. . \'!'
. .. -*-,.,-.. ' ., 1 *** ..... : ***' .. ** ; *'" .J :* .* *:Z ... -j *j . . l The distilled watet to ... include residual particulates-in the precipitation samples * . Tritium results were corrected.
:. j
f.or. the tritium. content *o*f the. distilled water. Ambient radiation levels in the environs were measured with energy-compensated CaS04 (Dy) thermoluminescent dosimeters (TLD's) supplied and riead by Teledyne Isotopes.
                    ~
Packets for monthly and were placed on and around the Artificial Island at various distances.
                '*1
Well water samples. were. collected monthly by PSE&G personnel and separate raw and potable water samples were composited daily by the City of Salem water treatment plant. *New polyethy!lene containers were used .for all water samples. ; *' I . ., All estuarine sa,mples were collected by V. J. Schuler Associates f Inc. and PSE&G personnel.
                    *~--- *---~-;""'r~- ,---------**---~
surface water samples were collected containers which were rinsed twice with the sample medium collection.
                          ...         .. - .            .. ,-.... c7 .. *--,..,..,*~~~~.;.;.,~.:- -- **-----..-- .. - _.... *----.----, ..... _ .*---.,:--*~~--- * ******-*r,***- -i-*-*
Edible fish and crabs were taken by net, f..rozen in sealed polyethylene containers.
 
Benthos and sedim*it samples were taken with a bottom grab sampler. Milk samples were taken semi-monthly when cows were on pasture and monthly when cows were not grazing on open pasture. Samples were collected in hew polyethylene containers.
4.
Food products, fodder crops, and beef were sealed in new plastic bags or jarso All perishable samples were transported in ice chests, and no preservative$
To determine-if SGS or HCGS      has*~caused :an increase*in radidactive,inventory.of;long~lived radionuclides~.
Soil  
To detect any change .in ambient gamma.radiation.levels.
*are collected once every three years were collected at several locations in New Jersey and Delaware.
                                                                                        ~he
Appendix A describes and summarizes, in accordance with Section 6. 9. l 10 of .the Salem TS and Section 6. 9 .1 *. 6
: 5. To verify that SGS and HCGS operations have no detrimental effects on the health and safety of the public or on. the environment.
* of the Hope Creek TS, the program as performed in 1986. Appendix the coding system which identifies sample type and location.
This report, as required by Section 6.9.1.10 of the Salem Technical Specifications, and Section 6.9.l.,6 of the Hope Creek Technical Specifications summarizes the findings of the 1986 REMP. Results of the four-year preoperational program which was conducted prior to the operation of any reactors on the Arti-ficial Island have been summarized for purposes of comparison with subsequent operational reports [2].
Table B-1 lists the sampling stations and the types of. samples collected at each station. These sampling stations are indicated on maps and B-2. Data . ' . Results.
Sample Collection In order to meet the stated objectives, an appropriate opera-tional REMP .was developed." samples of var.ious media were selected to obtain data for the evaluation of the radiation dose to man and other organisms *. The selection of sample types was bas~d on: (1) established critical pathways for the transfer of radionuclides through the environment to man, and .(2) experience gained during the preoperat.ional phase. Sampling l.ocations were determined from site meteorology,* Delaware estuarine hydrology, local demography, and land uses~
analyses were grouped according to the analysis.
Sampling locations were divided into two classes - indicator and control. Indicator statioris are those which are expected to manifest station effects, if any exist; control samples are collected at locations which are believed to be unaffected by station operations. Fluctuations in the le~els of radionuclides and direct radiation at indicator stations are evaluated with respect to analogous fluctuations at control. stations. Indicator and control station data.are also evaluated relative to preoper-ational data.
performed for each type of sample and are presented in the data tables : in :Appendix  
Air particulates were 'collected on Schleicher-Schuell No. 25 glass fiber filters with low-volume air samplers. Iodine was collected from air by adsorption on TEDA-impregnated charcoal cartridges connected -in series after the air particulate filters.
: c. All results above the lower limit of detection 1 (:LLD) are at a confidence level of +/- 2 sigma. This represents:  
Air sample volumes were measured with calibrated dry-gas meters and were corrected to standard temperature and pressure. *
*the range of values into which 95% of repeated analyses of the same sample should fall. As defined in tory Guide:4.8, LLD is the smallest concentration of radioactive  
. . . - : :**. ~
.. : .* . *---
                -~
.. j--*-** *-* --*--*---.*.*-*-
Precipitation was collected in a. Wong Laboratory Automatic Precipitation Collector having a 95 square inch collection area.
*--.-*-**-*---.-*,-----.**---.-
The collector is automatically covered during periods of* no precipi. ta ti on to exclude fallout resulting from dry. deposition *
----* -,....----;-***--;--*---*--
* Samples were collected monthly and transferred to new polyethyle
.. --**--****.-**-**-.--
* '              .1                                      4
--*.**** .,. .. ______ ;-*---* ----*----.... ---.-. I I I. ! *,; . *.: .. '* .. ' * . material.*
 
in *a sample that* will. yie-ld a' net count (above system*. . backgrouIJ,dJ that wil,l. be detected*
bottles~                    The collecto~~as rinsed~with distilled watet to ...
wi-.th 95% probabi*li&deg;ty with only 5% probability of falsely concluding that a *blank observation represents  
include residual particulates-in the precipitation samples *
: a. "real signal". LLD normally calculated as times one standard deviation of the background count or of the blank sample count as appropriate.
                                                . Tritium results were corrected. f.or. the tritium. content *o*f the.
The grouped data were averaged and standard deviations calculated in accordance with Appendix B of Reference  
distilled water.
: 18. Thus, the 2 sigma deviation*
Ambient radiation levels in the environs were measured with energy-compensated CaS04 (Dy) thermoluminescent dosimeters (TLD's) supplied and riead by Teledyne Isotopes. Packets for monthly and quarte~ly:exposure were placed on and around the Artificial Island Sit~ at various distances.
of the averaged data represent sample and not analytical variability.
Well water samples. were. collected monthly by PSE&G personnel and separate raw and ~~ea~ea potable water samples were composited daily by personnel.of~ the City of Salem water treatment plant.
When a group of was composed Of 50%* or more LLD values, averages were not calculated.
                                                  *New two~gallon polyethy!lene containers were used .for all water samples.                                       ;
Grab sampling is a useful and acceptable procedure for taking environmental samples of a medium in which the concentration of radionuclides expected to vary slowly with time or where intermittent sampling is deemed sufficient to establish the radiological of the medium. This method, however, is only representative of the sampled medium for that specific location and instant of time. As a result, variation in the radionuclide concentrations of the samples will normally occur. Since these variations will tend to counterbalance one another, the extraction of averages based upon repetitive grab samples is considered valid.
I All estuarine sa,mples were collected by V. J. Schuler Associates f Inc. and delive~ed ~y PSE&G personnel. surface water samples were collected ~n!n~w containers which were rinsed twice with the sample medium p~i~rj t~ collection. Edible fish and crabs were taken by net, and~ f..rozen in sealed polyethylene containers.
* Quality Assurance Program PSE&G Research Corporation, Research and Testing Laboratory (RTL), has a quality assurance program designed .to maximize confidence in the analytical procedures used. Approximately 20% of the total analytical effort is spent on quality control, including process quality control, instrument quality control, interlaboratory cross-check analyses, and data review. The analytical methods utilized in this program are summarized in Appendix*
Benthos and sedim*it samples were taken with a bottom grab sampler.
D. The quality of the results obtained by the RTL is insured by the implementation of the Quality Assurance Program as described in . the Environmental Division Quality Assurance Plan [19,20] and the Environmental Division Procedures Manual The internal
Milk samples were taken semi-monthly when cows were on pasture and monthly when cows were not grazing on open pasture. Samples were collected in hew polyethylene containers. Food products, fodder crops, game;~ and beef were sealed in new plastic bags or jarso All perishable samples were transported in ice chests, and no preservative$ wer~'added.
* quality control activity of the Laboratory includes the quality control of instrumentation, equipment and reagents; the use of reference standards in calibration, documentation of established procedures and computer programs, and analysis of duplicate and spiked samples. The external quality control activity is mented through participation in the USEPA Laboratory par ison Studies Prog*ram.
Soil samples:.wh~ch *are collected once every three years were collected at several locations in New Jersey and Delaware.
These results are listed in Tables E-1 through E-5 in Appendix E * '-.
Appendix A describes and summarizes, in accordance with Section
_.  
: 6. 9. l ~ 10 of .the Salem TS and Section 6. 9 .1 *. 6
.. -*-*----.-... * * ... 
* of the Hope Creek TS, the enti~e*operational program as performed in 1986.
* ' *.:.. .-.. *;: . *"! *-. l . 1 Program*changes*
Appendix B.des~ribes the coding system which identifies sample
Location 2F4 from which crops and soil were collected, terminated milk production in and was. replaced by location 2F7. No samples were missed due to this change. : RESULTS AND DISCUSSION The analy:ticai:
              .'                                    type and location. Table B-1 lists the sampling stations and the
results of the 1986 REMP samples are divided into categories on exposure atmospheric, direct, terrestrt;al .. aquatic. The analytical results for the 1986 REMP are *;summarized in Appendix A. The* data for individual in Appendix Co "* .. This discusses the data for REMP.
            .,                                    types of. samples collected at each station. These sampling 1                                  stations are indicated on maps B~l and B-2.
not include the data program previously.  
Data         Inter~retation
;: ! ;; . ! : J. !! . AtmosPheric samples under the from the quality assurance . Air Part!culates (Tables C-1, C-2, C-3) The.* weekl:y air particulate samples were analyzed for gross alpha and gros$ beta. Quarterly composites of the weekly samples from each* station, were analyzed for specific gamma emitters and a .single quarterly composite sample was analyzed for Sr-89 and Total data recovery for the eight sampling stations 1986 was 98.4 percent. Concentrations were detected in 359 of the 416 weekly samples for gross alpha emitters (Table C-1). Alpha tions: ranged from 0.8 x io-3 to 22 x lo-3 pCi/m3 with the average for all stations being 2.6 x lo-3 pCi/m3. i Analysis of weekly air samples for gross beta (Table ..... --C=2) , indicated concentrations were detected in 410 of the 416 .";**samples ranging from 6.7 x io-3 to 370 x pCifm3, with
  *** .....   :                                  Results. 0~*~11 analyses were grouped according to the analysis.
* grand average for a11* stations being 41 x io-3 pCi/m3. .' . f'.*'. f : *. t! ' I Figure 1 indicates the relation between gross beta activity in particulates and precipitation for the preoperational and operational periods, including the effects of atmospheric weapons testing and the accident at the Chernobyl-4 nuclear power* reactor.'  
performed for each type of sample and are presented in the data tables : in :Appendix c. All results above the lower limit of detection (:LLD) are at a confidence level of +/- 2 sigma. This 1
'
represents: *the range of values into which 95% of repeated analyses of the same sample should fall. As defined in Regula-tory Guide:4.8, LLD is the smallest concentration of radioactive
and sr-90 analyses are no longer required by the T*chnical Specifications for the Salem or Hope Creek Generating s.tat:ions.
  *'"        .J
In order to maintain documentation of the ambient i r * -* .  
:* .**:Z
.. ! _,,  
...           -j
--*--------*-----**** --.. -------.
            *j
*-* .. *-*-**-.----**, _, ______ --**-;---------**--... -. . . ---*---*---=---.* ***-----.--.*.-
                .                                                          ..:~  .* .
'*. *: *,_.,.; -" *. i . . : . .. -* ., . ;;-: ., ., -**: --. ' . .. ., -.. levels of and tha stations,:  
l
.. strontium analyses are performed on.the -.lst quarterly:
                  -,....----;-***--;--*---*-- *--- -----.-~----**.:. --.-~.*.~r,f~
from each location as a management*
                                                                        ..     ..j--*-** *-* --*- -*---.*.*-*- *--.-*-**-*---.-*,-----.**---.- -- -- * --**--****.-**-**-.-- --*.**** .,. .. ______ ;-*---* -- --*---- .... - - - .- . I
audit .. sampl:e. : Strontium::-89 and
 
* Sr-90 was not detected in any of the e:l.ghtmorithly composited samples analyzed; LLD sensitivities ranged from x io-3 to <2.0 x lo-3 pCi/m3 and from <0.2 x io-3 to <0.3 x lo-3 pCi/m3 for sr-89 and sr-90 respectively.
I.
Results of gamma spectrometry indicated detectable levels Be-7 in all of the 32 monthly composites, with a maximum of 110 x lo-3 pCi/m3. Berylium-7 is a naturally-occurring radionuclide attributed to cosmic ray activity in the atmosphere.
                                          . material.* in *a sample that* will. yie-ld a' net count (above system*.
During this reporting period detectable levels of Ru-103, Ru-106, cs-134, Cs-137, Ra-226, and Th-232 were noted in many of the locations sampled. Ruthenium-103 levels ranged from 7.5 x lo-3 to 9.2 x lo-3 pCi/m3. Ruthenium-106 levels ranged from 4.0 x lo-3 to 8.3 x lo-3 pCi/m3. Cesium-134 levels ranged from 8.4 x lo-3 to 10 x pCi/m3. Cesium-137 levels ranged from 16 x lo-3 to 18 x lo-3 pCi/m3. In reviewing the data it is noted that Ru-103, Cs-134 and cs-137 levels increased significantly during the second quarter of 1986. The Ru-103; Cs-134 and cs-137 increased levels are not able to the operation of the Salem or Hope Generating Stations.
                                        . backgrouIJ,dJ that wil,l. be detected* wi-.th 95% probabi*li&deg;ty with only 5% probability of falsely concluding that a *blank observation represents a. "real signal". LLD i~ normally calculated as 4~66
Based on their respective effluent release reports, there were no releases of Ru-103, Cs-134 or Cs-137 during the second quarter (22,23]. The increased levels are attributable to the Chernobyl-4 reactor accident.
                                                                                                                                                                                        *~
since similar concentrations existed at indicator arid control station locations  
times one standard deviation of the background count or of the blank sample count as appropriate.
* . . Radium-226 was also detected in one of the samples at a tration of 1.2 x lo-3 pCi/m3, which is within the variations  
The grouped data were averaged and standard deviations calculated in accordance with Appendix B of Reference 18. Thus, the 2 sigma deviation* of the averaged data represent sample and not analytical variability. When a group of d~ta was composed Of 50%*
*of the LLD sensitivities for the samples which.ranged from <0.3 x lo-3 to <10 x lo-3 pCi/m3. Thorium-232 was detected
or more LLD values, averages were not calculated.
* in one of the samples at a concentration of 1.7 x la-3 pCi/m3. This value* is within the variations of the LLD sensitivities for the other samples which ranged from <l.l x l0-3 to <2.7 x lo-3 pCi/m3. Air Iodin&* (Table c-4) cartridges for the adsorption of air*iodine were connected in *series after each of the air particulate filters. The adsorption media in these cartridges is triethylenediamine (TEDA) impregnated charcoal.
Grab sampling is a useful and acceptable procedure for taking environmental samples of a medium in which the concentration of radionuclides i~ expected to vary slowly with time or where intermittent sampling is deemed sufficient to establish the radiological characteristic~ of the medium. This method, however, is only representative of the sampled medium for that specific location and instant of time. As a result, variation in the radionuclide concentrations of the samples will normally occur. Since these variations will tend to counterbalance one another, the extraction of averages based upon repetitive grab samples is considered valid.
Iodine-131 was below detectable levels for the first four months of the year until the week of May 5 when radioactive iodine originating from the Chernobyl-4 reactor accident was detected.
* Quality Assurance Program PSE&G Research Corporation, Research and Testing Laboratory (RTL), has a quality assurance program designed .to maximize confidence in the analytical procedures used. Approximately 20%
8 . ... , . *-
of the total analytical effort is spent on quality control, including process quality control, instrument quality control, interlaboratory cross-check analyses, and data review. The analytical methods utilized in this program are summarized in Appendix* D.
1---. I * .. -.. <* -)1'
The quality of the results obtained by the RTL is insured by the implementation of the Quality Assurance Program as described in .
: :*, ,* .... .* ;:-; .f: . ; '
the Environmental Division Quality Assurance Plan [19,20] and the Environmental Division Procedures Manual [21]~. The internal
* I .. :*-, I I I . I ' '. *! .. . ' **j *: I l ,* '' Iod.ine-131 was* detected at all locations during the three w.e::k<I.y*
* quality control activity of the Laboratory includes the quality control of instrumentation, equipment and reagents; the use of reference standards in calibration, documentation of established procedures and computer programs, and analysis of duplicate and spiked samples. The external quality control activity is imple-mented through participation in the USEPA Laboratory Intercom-par ison Studies Prog*ram. These results are listed in Tables E-1 through E-5 in Appendix E
sampling periods starting on May 5 I l-986 ending on May* '2:.7?, .. 1986. Elevated.
* I        '*
levels p.ersisj:ed at. several locations du:ing the
          '-.-----:_,,..,~-.,.---:-:----:-_--:--*.--, -~-.~-~~-
* last. week. in May and. the . first* week in June. Levels as high as:. '320 x lo-3 pCi/m3 were detected at two locations.*
                                                                    -~,,..,..-~---.-*""7""'~~-~~""'7~':~-..,..-;_. -*-:-.*----":"7.-**;*.*--...*--:**~-,.-----.*o---*-*-;- ..-*- *-- --
A value of :610 x io-3 pCi/m3 was measured in one of our management audit samples but was not used in calculating any of our av*ezra:.q-as be&#xa2;ause of the short sampling period. During the remainder:
 
Q;f 'the year I-131 levels remained at levels below our LLD. The r.L.O sensitivities ranged from* <7. 7 x io-3 to <40 x io-3 pCi/u3: .. The :increased I-131 levels are not, attributable to the i; ofi the Salem or Hope Creek Generating Stations.
Program*changes*
Based om th:eii.r respective effluent release reports, there was no significaint of during the second quarter [22,23]. All of the I-131 results are attributable to the Chernobyl-4 .teactor accident.  
Location 2F4 from which milk~.fodder crops and soil were collected, terminated milk production in Sept~mber and was.
: '. ' r r * ;
replaced by location 2F7. No samples were missed due to this change.                         :
tat ion (Tables c-6, C-7) .. ' i :: : !iAlthough not required by the technical specifications,  
RESULTS AND DISCUSSION The analy:ticai: results of the 1986 REMP samples are divided into categories ~a~ed on exposure pathways~ atmospheric, direct, terrestrt;al ~ .. ~nd aquatic. The analytical results for the 1986 REMP are *;summarized in Appendix A. The* data for individual sample~ ~r~*presented in Appendix Co This i~c~~~n discusses the data for samples colle~ted under the REMP. ;;ri:~:does not include the data from the quality assurance program ~~sc~ssed previously.
,: tation samples were collected at location 2F2 in the town o*! !Salem. Monthly samples were analyzed for gross alpha, gl'OS/$ *.beta, tritium, and gamma emitters.
                                                      !:   J. !! .
Gross alpha  
AtmosPheric
: were detected in four of the. twelve samples analyzedo The *results detected were 0.6, Oo9, 1.2 and 1.3 pCi/L. These ?"esults :: were within the* variation of the LLD sensitivities for the ' .remaining samples which ranged from <O. 3 to <l. 7 pCi/L. Beta activity was detected in all twelve monthly samples and ranged from 1.9 to 15 pCi/L, with an average of 5.5 pCi/L. Tritium Nas not detected in any of the twelve samples analyzed; LLD tivities ranged from <130 to <140 pCi/L. Gamma analysis was performed on each of the monthly samples except for January, 1986 when there was insufficient tion. Detectable levels of and cs-137 were found in one sample during May 1986 at a concentration of 7.4 and 4.8 pCi/L respectivelyo The increase in I-131 and Cs=l37 levels was attributed to the Chernobyl-4 accident since levels of iodine and cesium were measured in precipitation collected at the Research and Testing Laboratory location 3H3v located 110 miles away from the Salem and Hope Creek Stations&
                                        . Air Part!culates (Tables C-1, C-2, C-3)
Otherwise levels of and Cs-137 were below detectable levelsQ Levels of other gamma emitters were comparable to levels in previous years. The presence of Be=7 was detected in each sample at concentrations ranging from 35 to 71 pCi/L. Radium-226 was detected in three samples at a concentration of and 4.8 pCi/L. These values are within the variations of the LLD sensitivities for the other samples which ranged-from <4.i to *1 "" 'l . l ., .: *1 **.  
The.* weekl:y air particulate samples were analyzed for gross alpha and gros$ beta. Quarterly composites of the weekly samples from each* station, were analyzed for specific gamma emitters and a
--..
                                          .single quarterly composite sample was analyzed for Sr-89 and sr~90.            Total data recovery for the eight sampling stations du~in$ 1986 was 98.4 percent.
**:-----*:-* . -----*---.-*--
Concentrations were detected in 359 of the 416 weekly samples analy~ed for gross alpha emitters (Table C-1).                                                                                                       Alpha concentra~
.. ...,, ------*-*--:**-----*.--... -.... -----. ------------.
tions: ranged from 0.8 x io-3 to 22 x lo-3 pCi/m3 with the gr~n~ average for all stations being 2.6 x lo-3 pCi/m3.
. *' ,-:-.. ***.: ... :! * <13 pCi/L.
i Analysis of weekly air p~rticulate                                                                  samples for gross beta (Table
* A slightly detectable leyel of. .
                                ..... --C=2) , indicated concentrations were                                                                   detected in 410 of the 416
                                  .";**samples ranging from 6.7 x io-3 to                                                                       370 x io~3 pCifm3, with
                                      * ~he grand average for a11* stations                                                                   being 41 x io-3 pCi/m3.
I Figure 1 indicates the relation between gross beta activity in
                            ~      .' . ~ir particulates and precipitation for the preoperational and f'.*'.
f
: *~
operational periods, including the effects of atmospheric weapons
*.:..  .-  .. *;:                          testing and the accident at the Chernobyl-4 nuclear power*
t!
reactor.'
Strontium~89 and sr-90 analyses are no longer required by the T*chnical Specifications for the Salem or Hope Creek Generating s.tat:ions. In order to maintain documentation of the ambient
  *-. . 1l i               r       *
      -* .     -~---~-.---- ..! _,, --'-;:*.::-~-----~--- --*--------*-----**** --*-:---:*-----..--:-~ -~ ----~~--:-*--* - -..---- --- . *-~-*- *-* .. *- *-**- .---- **, _,______ --**-;- -------- **-- ... - . . . - --*--- *--- =--- .* ***-- - --.-- .*.-
 
levels of sr~a~ and .sr-90*in_the*air~surrounding tha stations,: . .
strontium analyses are performed on.the -.lst quarterly: sarnpl~ from each location as a management* audit . sampl:e. : Strontium::-89 and
* Sr-90 was not detected in any of the e:l.ghtmorithly composited samples analyzed; LLD sensitivities ranged from <0*~3      x io-3 to
                  <2.0 x lo-3 pCi/m3 and from <0.2 x io-3 to <0.3 x lo-3 pCi/m3 for sr-89 and sr-90 respectively.
Results of gamma spectrometry indicated detectable levels o~ Be-7 in all of the 32 monthly composites, with a maximum of 110 x lo-3 pCi/m3. Berylium-7 is a naturally-occurring radionuclide attributed to cosmic ray activity in the atmosphere. During this reporting period detectable levels of Ru-103, Ru-106, cs-134, Cs-137, Ra-226, and Th-232 were noted in many of the locations sampled. Ruthenium-103 levels ranged from 7.5 x lo-3 to 9.2 x lo-3 pCi/m3. Ruthenium-106 levels ranged from 4.0 x lo-3 to 8.3 x lo-3 pCi/m3. Cesium-134 levels ranged from 8.4 x lo-3 to 10 x lo-~ pCi/m3. Cesium-137 levels ranged from 16 x lo-3 to 18 x lo-3 pCi/m3.
In reviewing the data it is noted that Ru-103, Cs-134 and cs-137 levels increased significantly during the second quarter of 1986.
The Ru-103; Cs-134 and cs-137 increased levels are not attribut-able to the operation of the Salem or Hope Cr~ek Generating
    -"    *. i Stations. Based on their respective effluent release reports, there were no releases of Ru-103, Cs-134 or Cs-137 during the second quarter (22,23]. The increased levels are attributable to the Chernobyl-4 reactor accident. since similar concentrations existed at indicator arid control station locations
* Radium-226 was also detected in one of the samples at a concen-tration of 1.2 x lo-3 pCi/m3, which is within the variations
                  *of the LLD sensitivities for the ~ther samples which.ranged from
                  <0.3 x lo-3 to <10 x lo-3 pCi/m3. Thorium-232 was detected
* in one of the samples at a concentration of 1.7 x la-3 pCi/m3.
      .. : . ~
This value* is within the variations of the LLD sensitivities for the other samples which ranged from <l.l x l0-3 to <2.7 x lo-3 pCi/m3.
Air Iodin&* (Table c-4)
  .  ;;-:      ~
            .,.,  cartridges for the adsorption of air*iodine were connected in
                  *series after each of the air particulate filters. The adsorption media in these cartridges is triethylenediamine (TEDA) impregnated charcoal.
Iodine-131 was below detectable levels for the first four months of the year until the week of May 5 when radioactive iodine
              -    originating from the Chernobyl-4 reactor accident was detected.
        ~  ..'
8
.,   -..                     . :~ . .. , . *-
 
I Iod.ine-131 was* detected at all locations during the three w.e::k<I.y*
sampling periods starting on May 5 I l-986 ~nd. ending on May* '2:.7?, ..
1986. Elevated. levels p.ersisj:ed at. several locations du:ing the
* last. week. in May and. the . first* week in June. Levels as high as:.
                                      '320 x lo-3 pCi/m3 were detected at two locations.* A value of :610 x io-3 pCi/m3 was measured in one of our management audit samples but was not used in calculating any of our av*ezra:.q-as be&#xa2;ause of the short sampling period. During the remainder: Q;f
                                    'the year I-131 levels remained at levels below our LLD. The r.L.O sensitivities ranged from* <7. 7 x io-3 to <40 x io-3 pCi/u3: ..
The :increased I-131 levels are not, attributable to the ope*ra~t::iia11 i;   ofi the Salem or Hope Creek Generating Stations. Based om th:eii.r respective effluent release reports, there was no significaint rel~ase of I~l31 during the second quarter [22,23].                                                                                         All of the
                                        ~levated I-131 results are attributable to the Chernobyl-4
                                      .teactor accident.
: ~
                            ' r
                                    ~;    r
                          *   ; !:Pr~cipi tat ion (Tables c-6, C-7) i ::
: !iAlthough not required by the technical specifications, pre~:n.jpli-
                                  ,: tation samples were collected at location 2F2 in the town o*!
                                  !Salem. Monthly samples were analyzed for gross alpha, gl'OS/$
                                  *.beta, tritium, and gamma emitters. Gross alpha concentratic~s
: were detected in four of the. twelve samples analyzedo The
                                  *results detected were 0.6, Oo9, 1.2 and 1.3 pCi/L. These ?"esults
:: were within the* variation of the LLD sensitivities for the
                                  ' .remaining samples which ranged from <O. 3 to <l. 7 pCi/L. Beta activity was detected in all twelve monthly samples and ranged from 1.9 to 15 pCi/L, with an average of 5.5 pCi/L. Tritium Nas not detected in any of the twelve samples analyzed; LLD sensi-tivities ranged from <130 to <140 pCi/L.
Gamma analysis was performed on each of the monthly samples except for January, 1986 when there was insufficient precipita~
tion. Detectable levels of I~l31 and cs-137 were found in one sample during May 1986 at a concentration of 7.4 and 4.8 pCi/L
  - -~..<*
            ..                        respectivelyo The increase in I-131 and Cs=l37 levels was
              -)1'
    -~T:?~~~-*~ :
attributed to the Chernobyl-4 re~ctor accident since simila~
:*,    ,*  ....                  levels of iodine and cesium were measured in precipitation
    .* ;:-; .f:                        collected at the Research and Testing Laboratory location 3H3v
        '  ,~
* I I
located 110 miles away from the Salem and Hope Creek Stations&
Otherwise levels of I~l31 and Cs-137 were below detectable I
                  . I I
levelsQ Levels of other gamma emitters were comparable to levels observed-in previous years. The presence of Be=7 was detected in each
                  '. ~
sample at concentrations ranging from 35 to 71 pCi/L. Radium-226
                    ! .              was detected in three samples at a concentration of 7.0~ ~.l and
                    .  '              4.8 pCi/L. These values are within the variations of the LLD sensitivities for the other samples which ranged- from <4.i to
              **j *:
I l
              'l*1                                                                                             ""
                                                                                                                ~
              .l
    ., .: *1                                                                                                                                                                             **.
  <f:'.t~*~:JT--*-*~-----~------------~~*--*-.----------*- - . ----*;::--*--:~ ~.--*---.---- **:-----*:-* . -----*---.-*-- .. ...,, ------*- *--:**-- - --*.-- ... - .... -- --- . ------- -- ---.
 
                <13 pCi/L.
* A slightly detectable leyel of. natural*ly~qccurring
* K-40 .was dete.cted in one 'sample ,a:-t *a* level df
* K-40 .was dete.cted in one 'sample ,a:-t *a* level df
* pCi/L du;r.ing*
* s~t pCi/L du;r.ing* t*he
t*he
* September ~ampling periotj. Hbwever, this .value wa~ ~ith~n the ..
* September periotj. Hbwever, this .value the .. variations of .the LLD sensitivities measured throughqut.the year. Thorium-232 was detected in orte period at a concentration of 7.5 pCi/L. This value is within the variations of the LLD sensitivities for the other samples which ranged from <7.2 to <21 All other gamma emitters searched for were below the LLD. Direct Radiation (Tables t-8, c-9) A total of 41 locations were monitored for direct radiation during 1986, including 6 on-site locations, 29 off-site locations within the 10 mile zone, and 6 control locations beyond 10 miles. Monthly and quarterly measurements were made at the 6 on-site stations and at 15 off-site indicator and 3 control. stations.
variations of .the LLD sensitivities measured throughqut.the year.
An additional 14 quarterly measurements were taken at* schools and population centers with 3 additional controls beyond the 10 mile zone in Delaware.
Thorium-232 was detected in orte sam~le ~u;ring th~ A~guit ~a~pling
:- ..      period at a concentration of 7.5 pCi/L. This value is within the variations of the LLD sensitivities for the other samples which ranged from <7.2 to <21 pCi/L~ All other gamma emitters searched for were below the LLD.
Direct Radiation   (Tables t-8, c-9)
A total of 41 locations were monitored for direct radiation during 1986, including 6 on-site locations, 29 off-site locations within the 10 mile zone, and 6 control locations beyond 10 miles.
Monthly and quarterly measurements were made at the 6 on-site stations and at 15 off-site indicator stations~ and 3 control.
stations. An additional 14 quarterly measurements were taken at*
schools and population centers with 3 additional controls beyond the 10 mile zone in Delaware.
Fou*r readings for each TLD at each location were taken in order to obtain a more statistically valid result. The average dose
Fou*r readings for each TLD at each location were taken in order to obtain a more statistically valid result. The average dose
* rate for the 15 monthly off-site indicator Ttn*s was 5.8 milli-ra:ds per standard month, and the corresponding averaged control. dose rate was 6.4.millirads per standard month. The average dose rate for the 29 quarterly off-site indicator TLD's was 5.1 millirads per standard month, and the averaged control rate was 5.6. For these measurements, the rad is considered equivalent to the rem, in accordance with 10CFR20.4.
* rate for the 15 monthly off-site indicator Ttn*s was 5.8 milli-ra:ds per standard month, and the corresponding averaged control.
In Figure 2, the average radiation levels are plotted for the 13 year period through 1986. Figure 2A shows the* monthly averages of the indicator stations and the control stations for 1982 through 1986. Ambient radiation levels during 1986 were comparable to those obtained during 1985. Terrestrial Milk (Tables c-11, C-12) Milk samples were collected in accordance with the Salem and Hope Creek Technical Specifications at six local dairy farms. During this reporting period, one dairy operator terminated operations (location 2F4) and,
dose rate was 6.4.millirads per standard month. The average dose rate for the 29 quarterly off-site indicator TLD's was 5.1 millirads per standard month, and the averaged control rate was 5.6. For these measurements, the rad is considered equivalent to the rem, in accordance with 10CFR20.4.
In Figure 2, the average radiation levels are plotted for the 13 year period through 1986. Figure 2A shows the* monthly averages of the off-sit~ indicator stations and the control stations for 1982 through 1986. Ambient radiation levels during 1986 were comparable to those obtained during 1985.                                            I Terrestrial Milk  (Tables  C~lO, c-11, C-12)
Milk samples were collected in accordance with the Salem and Hope Creek Technical Specifications at six local dairy farms. During this reporting period, one dairy operator terminated operations (location 2F4) and, as required by the SGS and HCGS Technical                .
Specification, a replacement location (lbcation 2F7) was found and added to.the surveillance program. Samples were collected semi-monthly* when cows were on pasture and monthly when cows w e r .
...            not on pasture. .        .      .                  .      .    .
* Each sample was analyzed. for .I:""l31 and gamma emi t.ters. I.n. addi-tion, aithough not* sp.ecif ic~lly required by the SGS and. liCGS Technical* Specifications,*~ne sample from each location was analyzed for:: -Sr..
* i * * * * * *. * . I. * * *
* i * * * * * *. * . I. * * *
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* 4.I*. * * * * *. * *. * * * * * * * * .. * * * * * * .N.
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'** ******* *.*. + 10 8\ t ......................................................................................................
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I~; ~    .                                              ~
f I / I I T Ki . \ "Ji iC 0 ' 8 1 I' -.-\ I I i\ I' I 6 -4 \ \ 0 \ 8 % T \ I 8 s, " I I 0 i \I\ \ 6 -\-* 8 I I \ I '+ I \ / I f' ,+-\ O ..J iii .{. \ D &#xa5; i B + I I \ IB I 'a 'a no* + V S .\t oD \ f il! 80 \ I I 5 1JfMAMJJASDNDJFMAMJJASONDJFMAMJJASONDJrMAMJJA5PNP 488"4 tsee 
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*1 -.: 1 . ' .. , 1 I I *1 i . J ;; *. i . ' .. i : ..... :.*.*. L: FIGURE 2 AVERAGE AMBIENT RADIATION LEVELS FROM QUARTERLY TLDS IN THE VICINITY OF ARTIFICIAL ISLAND 1973 THROUGH 1986 LEGEND ALL STATIONS o CONTROL STATIONS ..... -----+ 9.
I         -~ID l                                              m sa c1i       ,..
7 c 0 E n IO ' Ill E 5 E 4 3 3 2 2 112341234123412341234123412341234123412341234123412341234 tS74 !9715 :f.978 1977 1978 1979 1.1981 1982 1983 1984 19BB 1988
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* I I : .c .&#xb5; c 0 E n ..,i II) ' U) E I> L E
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* FIGURE 2A OF AMBIENT RADIATION LEVELS OF OFF-SITE INDICATOR STATIONS VS. CONTROL STATIONS 1982 THROUGH 1986
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30 28 . ' 26 24 22 20 18 16 14 12 10 8 6 4 ,) I ! j 1 ! l I : ........ . FIGURI: 3 AVERAGE CONCENTRATIONS OF IODINE-131 IN MILK IN THE VICINITY OF ARTIFICIAL ISLAND 1974 THROUGH 1986 ' . ................................ , ...................................................................
FIGURE iA COMPAAISION OF AVERAGE CONCENTRATIONS OF BETA EMITTERS IN PAECIPITATION AND IN AIR PARTICULATES ftOOo--~~~~~~~~~~~~~~~~~~~~~~~~~~~~~._.~~~~~~~-.
***********************
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_._ **-**-*-. **-* -. --..... . FIGURE 3A AVERAGE CONCENTRATIONS OF IODINE-131 IN MILK IN THE VICINITY OF ARTIFICIAL ISLAND 1983 THROUGH 1986 28 . 26 24 22 *****. .*. . . . . . . . . . . . .  
                                                                  +
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                                                                                                                                                  /                    I                                               I     T
* AVERAGE CONCENTRATIONS OF BETA EMITTl::RS
                                                                                                                                                                                                                                    -4 i .{. \        \
--&*-K-40 IN THE DEL. RIVER IN THE VICINITY OF ARTIFICIAL ISL. 1973 THROUGH 1986 LEGEND GROSS BETA e o POTASSIUM-40
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.. FIGURE "4A AVERABE CONCENTAATXONS OF BETA EMXTTERS Q K-40 XN THE DEL. RIVER IN THE VICINITY OF ARTIFICIAL ISL. 1983 THROUGH 1986 LEGEND GROSS BETA e e PIJTASSXUM-40
                                                                                                                                                                                                                  ~                  IB S
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FIGURE 2 AVERAGE AMBIENT RADIATION LEVELS FROM QUARTERLY TLDS IN THE VICINITY OF ARTIFICIAL ISLAND 1973 THROUGH 1986 LEGEND ALL STATIONS s--~~~~~~~~~~~~~~~~~~~~~~~~~~~~~-o                                                                o      9.
* j . *i . * .. .. PIGURE B . AVERAGE .. . Qf_ ..
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IN THE DELAWARE RIVER IN THE. VICJ:NITY-
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FIGURE 2A
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                    ~OMPAA,SON OF AMBIENT RADIATION LEVELS OF OFF-SITE INDICATOR STATIONS VS. CONTROL STATIONS 1982 THROUGH 1986 iO--~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~--~~~~~~~~.-
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. .' . ::*. .. -*.. ) -. ,.: .. *; ' . *: *'*-*-.--... REFERENCES.
1 I
[l] Radiation Management Corporation.. "Artific.:ial Island Radiological.
 
[2] [3] Environmental*
                                        ..' ' !j ' .*.c,*          ... '  .     -- .- -
Monitoring l?rogram -Annual Reports 1973 through 1962" *. ' ' Radiation Management corporation.
*r*)
Environmental l?rogram -1976".* RMC-TR-77_;.03
                                    ....~.-.* \ . '*~-*.                                                                     ..         ___ ....,.. .. - .. --* - ... -.. -
,; 1978. Radiation Management:corporation.
                                                                                                                      . -. _ . *r ."-'-"""-';._.,__c"'*'---;-.,_,..__
Environmental Monitoring l?rogram -RMC-TR-77-02, i97.7. ; . \ ! l "Artificial Island Radiological.
                                                                                                                                          ~~--
Preoperation summary -1973 through "Artificial Island Radiological Deceml:Jer ll to Deceml:Jer 31, 1976". [4] PSE&G Research and Testing LaJ:>oratory.  
                                                                                                                                                                -~  ~      . -- . . . -
[5] [6] "Artificial Island Radiological Environmental Monitoring l?rogram -1983 Annual
                                                ,)
; R'+'L-ENV-84-0l, 1984. ' .. *; ; :r PSE&G Corporation, Research and Testing LaJ:>oratory
:                                               --~ ~ ........ .
*. "Artificial Iialand* Radiological Environmental Monitoring l?rogram -1984 Annual Report:*!.  
  . *n I!
;
      ... 1 j
1985.
I                                  1
* Ii : *1* * . I ' PSE&G Research &#xa2;orporation, Research and Testing LaJ:>oratory. "Artificial Island Radiological..
        *I l'
Environmental Monitoring Program -1985 Annual.
l FIGURI: 3 l                                  I            AVERAGE CONCENTRATIONS OF IODINE-131 IN MILK I                                                                    IN THE VICINITY OF ARTIFICIAL ISLAND
* 1986 * [7] Public service Ele_ctric and Gas company. "Environmental Report, Operating License* Stage -* Sal.em Nuclear Generating Station Units l and 2". 197le': " [8] Public Service Electric and*Gas Company. "Environmental Report, Operating
      **1                                                                                                      1974 THROUGH 1986
*.License Stage -Hope creek Generating Station. 1983. : ' * [9] United Atomic Energy commission. "Final Environmental Statement
      /1                            30
-Salem Nuclear Generating Station, Units l and 2 11* Docket No. 50-272 and 50-311.  
        . *~
[10] . United Atomic Energy commission. "Final Environmental Statement
  'j                                28                                                                                                                                                                                                28
-Hope creek Generating Station, Docket.No.
      *:j                      . ' 26                                                                                                                                                                                                26
50-354. 1983. ' . ' . [ll] Public Servi,ce Electric and Gas. Company. "Updated Final. Safety Analysis.  
  *..i
[12] [13] Report -Salem Nuclear Generating Station, Units l and 2". 1982 * . . ' Public Service Electric and Gas Company. "Final Safety Analysis Report Hope*creek Generating Station. 1984. * ' ' Pubiic :Service Electric and Gas Company. "Salem Nuclear Generating Stat+/-od Unit l -Technical.
    .*.1
Specifications", AppendiX A to Operating License No. DPR-70, 1976, sections 3/4.12 and 6.9.l.lO (Amendment 59
          *j                        24                                                                                                                                                                                                24 1
..... --; ---***.,;:-I"',' . . 
        .{                        22                                                                                                                                                                                                22 l                      20              ................................ , ...................................................................
* . . *.I ** J .... . ; ...... 1 ' REFERENCES.  
                                                                                                                          '                                          .                             ***********************          20 .
{cont id) .. [14] Public Service Electric and Gas Company. "Salem Nuclear Generating Station Unit 2 -Technical Specifications", Appendix *A t_o Operating License No. DPR-75, 1981, Sections 3/4.12 and 6.9.lolO (Amendment 28
* 1 l                      18                                r::
[15] PUblic Service Electric and Gas company. "Hope creek Generating Station Unit l -Technical Specifications", Appendix A to Facility Operating License No. NPF-57, 1986, Sections 3/4.12 and 6.9.1.10.  
                                                                      ~
[16] Pu.blic Service Electric and Gas company. "Offsite Dose calculation
18
-Hope creek Generating Station. [17] PUblic:: service Electric and Gas Company. "Offsite Dose calculation Manual" -Salem Generating Station. [18] u. s. Environmental Protection Agency. "Prescribed Procedures for Measurement of Radioactivity in Drinking Water.11 EPA-600/4-80-032, August, 1980. [19] PSE&G Research corporation, Research and.Testing Laboratory. mental Division Quality Assurance Manual." September, 1980. [20] PSES!G Research corporation, Research and Testing Lanoratory.
  .. ~1                  _J      16 g---
mental Division Quality Assurance Plan.n (supereedes Quality Assurance Manual)f January6 1987. [21] PSE&G Research corporationu Research and Testinq Laboratory.
H 16
mental Division Procedures Manual." February, 1981. [22] PUblic Service Electric and Gas Company. "Radioactive Effluent Release Reports, RERR-l and RERR-2 -Hope creek Generating Station. 1986. [23] PUblic Service Electric and Gas Company. "Radioactive Effluent Release Reports, RERR-20 RERR-21 -Salem Generating Station. 1986. [24] Nuclear Newso "Chernobyl:
.* **1                    'u
The Soviet Reporte" October 1986. [25] The Heal.th Physics Society Newsletter. "Preliminary Dose Assessment of the Chernobyl Accident.
                          ..-1 1<1.
Part January 1987 * 
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FIGURE "4A AVERABE CONCENTAATXONS OF BETA EMXTTERS Q K-40 XN THE DEL. RIVER IN THE VICINITY OF ARTIFICIAL ISL.
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                                  . *1.
    *- __ ....... -* - . - .       . -~
l
*i I
I
                                      !                                AVERAGE CONCENTRATIONS OF TRITIUM IN THE FIGURE BA DELAWARE R,IVEA IN THE VICINITY OF ARTIFICIAL ISL.
1983 THROUGH 1986 5000      ****** ****************************************** ........................................................................... .
AOOC      * * * * * * * * * * * * * * * * * * * * ** ** ** * *************************************************************************************************
500      ** ******** ** * ... * *                * ** ........ ***** *** * . * . *** * * ** * *** * *** * * ***** ** ** * * *****.   * *******************************.*.**********
100      .****..... : .********.**.*******.......**..*....*.*. *............................................... *.* * . . * * . . . . ..........**..
50                                                                                            ~
                                        ******************************************** ******* ..................... .'.****.********************* *-;.;***                                        ~- .***.**.*****..
                                                                                                                                                                                          ;1
                                                                                                                                                                                                ~
Jl  IF  ft.fi A li4    J J        A S 0 N D J F MA MJ                    J    A S 0 N D JI f 114 A M J                J  A S 0 H D J f MA MJ
                                                                                                                                                                                        *I ~I      J AS 0 ND i'.B83                                                  !'!98~                                      ~lil-~                                UJB~
 
[l]
REFERENCES.
Radiation Management Corporation.. "Artific.:ial Island Radiological.
Environmental* Monitoring l?rogram - Annual Reports 1973 through 1962" *.
[2]   Radiation Management corporation. "Artificial Island Radiological.
Environmental Monito~ing l?rogram - Preoperation summary - 1973 through 1976".* RMC-TR-77_;.03 ,; 1978.
[3]   Radiation Management:corporation. "Artificial Island Radiological Environmental Monitoring l?rogram - Deceml:Jer ll to Deceml:Jer 31, 1976".
RMC-TR-77-02, i97.7. ; .
                                                              \  !   l
[4]  PSE&G Research:Cqrpora~ion, Research and Testing LaJ:>oratory.
                        "Artificial Island Radiological Environmental Monitoring l?rogram - 1983 Annual Report*~:. ; R'+'L-ENV-84-0l, 1984.
                                                *;          ; :r
[5]  PSE&G Researc~ Corporation, Research and Testing LaJ:>oratory *.
                        "Artificial Iialand* Radiological Environmental Monitoring l?rogram - 1984 Annual Report:*!. ; ~TL-ENV-85-0l, 1985.
* Ii          : *1*      *      .
I      '
[6]  PSE&G Research &#xa2;orporation, Research and Testing LaJ:>oratory.
                        "Artificial Island Radiological.. Environmental Monitoring Program - 1985 Annual. Report"~ ~TL-ENV-86-0l, *1986 *
      ..'  ~  .
[7]  Public service Ele_ctric and Gas company. "Environmental Report, Operating License* Stage -* Sal.em Nuclear Generating Station Units l and 2". 197le':                            "
::*.          [8]  Public Service Electric and*Gas Company. "Environmental Report, Operating *.License Stage - Hope creek Generating Station. 1983.
[9]  United state~' Atomic Energy commission. "Final Environmental Statement -
Salem Nuclear Generating Station, Units l and 2 11
* Docket No. 50-272 and 50-311. 1973~
[10] . United State~ Atomic Energy commission. "Final Environmental Statement -
Hope creek' Generating
                                            .                            Station, Docket.No. 50-354. 1983.
[ll] Public Servi,ce Electric and Gas. Company. "Updated Final. Safety Analysis.
Report - Salem Nuclear Generating Station, Units l and 2". 1982 *
    .. -*..  )                    .      . '
          ,.:    [12]  Public Service Electric and Gas Company.                            "Final Safety Analysis Report Hope*creek Generating Station. 1984. *
[13]  Pubiic :Service Electric and Gas Company. "Salem Nuclear Generating Stat+/-od Unit l - Technical. Specifications", AppendiX A to Operating License No. DPR-70, 1976, sections 3/4.12 and 6.9.l.lO (Amendment 59
                        ~:~),.,:
          ' ~
                                                                                                                        ..... --; - --***.,;:-I"','
                                                                                                                        . -~    .
 
REFERENCES. {cont id) ..
[14] Public Service Electric and Gas Company. "Salem Nuclear Generating Station Unit 2 - Technical Specifications", Appendix *A t_o Operating License No. DPR-75, 1981, Sections 3/4.12 and 6.9.lolO (Amendment 28
                      &#xa3;~).
[15] PUblic Service Electric and Gas company. "Hope creek Generating Station Unit l - Technical Specifications", Appendix A to Facility Operating License No. NPF-57, 1986, Sections 3/4.12 and 6.9.1.10.
[16] Pu.blic Service Electric and Gas company.    "Offsite Dose calculation Manual~ - Hope creek Generating Station.
[17] PUblic:: service Electric and Gas Company.    "Offsite Dose calculation Manual" - Salem Generating Station.
[18] u. s. Environmental Protection Agency. "Prescribed Procedures for Measurement of Radioactivity in Drinking Water. 11 EPA-600/4-80-032, August, 1980.
[19] PSE&G Research corporation, Research and.Testing Laboratory.      "Environ-mental Division Quality Assurance Manual." September, 1980.
[20] PSES!G Research corporation, Research and Testing Lanoratory. ~Environ=
mental Division Quality Assurance Plan.n (supereedes Quality Assurance Manual)f January6 1987.
[21] PSE&G Research corporationu Research and Testinq Laboratory.      ~Environ=
mental Division Procedures Manual." February, 1981.
[22] PUblic Service Electric and Gas Company. "Radioactive Effluent Release Reports, RERR-l and RERR Hope creek Generating Station. 1986.
[23] PUblic Service Electric and Gas Company. "Radioactive Effluent Release Reports, RERR-20 an~ RERR Salem Generating Station. 1986.
[24] Nuclear Newso    "Chernobyl: The Soviet Reporte"  October 1986.
[25] The Heal.th Physics Society Newsletter. "Preliminary Dose Assessment of the Chernobyl Accident. Part II.~ January 1987 *
.    . *.I
    ** J ....
  ...... 1
            .-~
 
*     . :, i APPENDIX A PROGRAM  


==SUMMARY==
==SUMMARY==
.. ' .. . . .. . "" .. . . ,,,."':"_._  
 
-*----.--:-, --*--*. *-.___,. *-;-* --*-----*--. ...... --*-* . -----.... -*-.. , --**-**;* -.. r*----*---*-----** -.-*-******.--:  
                                                                                                                                                                                                                                                                                      . . . ."" . ~ .
-::--* -----*. -----., .... -------***---<--*-*-:*  
                                                                                                                                                                                                                                                                                                        . I
.... -** --.*-* .. ... . .. -* ********--*  
                . ,,,."':"_._ -*----.--:-, --*--*. *- .___,. *-;- * --*- ---- *--. *-~ ...... -- *-* . ----- .... -*- .. , -- **- **;* -.. r*--- -*---*-- ---** -.-*-******.--: -::- -* - ----*. ----- .,.... -- ---- -***---<--*-*-:* .... -** -- .*-* .. ... . .. -* ********--* --- - -- . -*     ..
------. -* .. . I ! 
 
;' * .. * * "* .. \. ,;:'. .. ' . .. .. . .. . ' . . ,* .. ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  
                        \. ,;:'. .. ' . .. .. . .. .   '
                                                                  ~
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  


==SUMMARY==
==SUMMARY==
SALEM GENERATING STATION DOCKET NOS. 50-27Z/-3H HOPE CREEK GENERATING STATION DOCKET NO. 60-364 SALEM COUNTY, NEW JERSEY JANUARY 1, !986 to DECEMBER 31, 1986 ANALYSIS AN!li LOWER NUMBER Of OR PATHWAY TOTAL NUMBER UNIT Of Al I IUDICAIOB IOC!IXOUS IOC!IIOU WIIU UI6UESI COUIHOI 1 llC!IIOU NON ROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED <<UNIT Of MEASUREMENT)
 
PERFORMED (HO)* (RANGE) !HSTANC*E AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Air Part iculi!hs Aiphm 416 0.8 Z.8 (311/364) zsz 0.4 ml NNE 3.1 (46152) Z.8 (48/62) 0 00-3 pCt/m3) (0.8-Z2) (0.9-22) (1.0-20) Beh '316 41 (369/364) 2S2 0.4 mi NNE 46 (li0/62) 42 (61162) 0 (6.7-370) ( 9. 4-360) (11-330) Sr-89! 8 0.3 <UD <HD <LLD 0 oj:b Sr-90 s 0.2 <Lrn <LLD 0 . II-" Gillmla Be-7 3Z 77 (28/28} !iDl 3.li mi E 91 (4/0 76 (4/4) 0 (60-110) (80-110) (64-90) Ru-1031 :ilZ 0.1 8.6 p12a) !iDl 3.6 mi E 9.2 014) 7.6 (114) 0 (7  
SALEM GENERATING STATION                           DOCKET NOS. 50-27Z/-3H HOPE CREEK GENERATING STATION                     DOCKET NO. 60-364 SALEM COUNTY, NEW JERSEY           JANUARY 1, !986 to DECEMBER 31, 1986 ANALYSIS AN!li               LOWER                                                                                       NUMBER Of
{9.Z) (7 .6) lllu-106 32 1.6 6.6 (3/28) lFl 6.8 mi U 8.3 (114) 4.0 (114) 0 (4.0-8.:ll)  
      ~EDIUM  OR PATHWAY                       TOTAL NUMBER UNIT Of Al I IUDICAIOB IOC!IXOUS                       IOC!IIOU WIIU UI6UESI ~E!U      COUIHOI 1llC!IIOU NON ROUTINE SAMPLED                             OF ANALYSES DETECTION                           MEAN**                     NAME               MEAN         MEAN         REPORTED
(8.3) ( 4 .0) CsHM 312 0.31 9. 3 (7 /28) lfl 6.8 ml N 10 010 9. z (1/4) 0 (8.4-10) (10) ( 9. 2) 2fZ 8.7 mi NNE 10 (114) ( 10) <<:s-137 312 0.3 17 (7 /28) zsz 0.4 mi NNE 18 (114) 17 (114} 0 (16-18) (18) ( 11) lliDl 3.6 ml E aa ( .. OR) !lili-Z26 32 0.3 1. 2 ( 11211) .. If l 6.8 mi N l.2 0/4) <LLP 0 ( 1.2) {1,2) Jh-232 28 a.! l. 7 0120 lf l 6.8 mi N !.7 01.i) <LLP 0 ( 1. 7) ( l. 7)
    <<UNIT Of MEASUREMENT) PERFORMED                                         (HO)*               (RANGE)         !HSTANC*E AND DIRECTION     (RANGE)       (RANGE)     MEASUREMENTS Air Part iculi!hs                         Aiphm               416       0.8           Z.8 (311/364)           zsz   0.4 ml NNE   3.1 (46152)   Z.8 (48/62)           0 00-3 pCt/m3)                                                                             (0.8-Z2)                                   (0.9-22)       (1.0-20)
.. , " ., ..::* J ' . i. \ *1 *.i ' J ' .. ! . j MEDIUM OR PATHWAY SAMPLED . . (UNIT OF MEASUREMENT)
Beh               '316                     41 (369/364)             2S2 0.4 mi NNE     46 (li0/62)   42 (61162)           0 (6.7-370)                                   ( 9. 4-360)   (11-330)
Atr lodtne (10-3 pCt/m 3) . Preclpttatlon (pCi/L) .. ' '* _,., ..... ,. 1.: ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  
Sr-89!                 8     0.3                 <UD                                       <HD             <LLD             0 oj:b II-"
Sr-90                   s     0.2                 <Lrn                                       ~no            <LLD             0 .
Gillmla Be-7               3Z                     77 (28/28}             !iDl 3.li mi E       91 (4/0       76 (4/4)             0 (60-110)                                   (80-110)         (64-90)
Ru-1031           :ilZ     0.1           8.6 p12a)               !iDl 3.6 mi E       9.2 014)       7.6 (114)           0 (7 .6-9.2~                                    {9.Z)           (7 .6) lllu-106           32       1.6           6.6 (3/28)             lFl   6.8 mi U       8.3 (114)     4.0 (114)           0 (4.0-8.:ll)                                   (8.3)           ( 4 .0)
CsHM               312     0.31           9. 3 (7 /28)           lfl   6.8 ml N       10   010       9. z (1/4)           0 (8.4-10)                                       (10)           ( 9. 2) 2fZ 8.7 mi NNE       10 (114)
( 10)
                                                  <<:s-137           312     0.3             17 (7 /28)             zsz   0.4 mi NNE     18 (114)       17 (114}             0 (16-18)                                     (18)           ( 11) lliDl 3.6 ml E       aa ( u~)
OR)
                                                  !lili-Z26         32       0.3           1. 2 ( 11211)           If l 6.8 mi N       l.2 0/4)         <LLP             0
( 1.2)                                     {1,2)
Jh-232             28       a.!           l. 7 0120               lf l 6.8 mi N       !.7 01.i)         <LLP             0
( 1. 7)                                     ( l. 7)
 
                                                                              ~.   '
        ..::* J '                                                     _,., ..... ,. '* 1.:                                                                                                                           ' J::_ ..
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  


==SUMMARY==
==SUMMARY==
SALEM GENERATING STATION HOPE CREEK GENERATING STATION SALEM COUNTY, NEW JERSEY ANALYSIS AND LOWER DOCKET Nos: 60-272/-311 DOCKET NO. 60-354 JANUARY 1, 1986 to DECEMBER 31, 1986 TOTAL NUMBER LIMIT OF ALL IUDIC:AIOH I llC:AIIllU5 lllC:AIIllU WIIU Ul6UESI' MEAU OF ANALYSES DETECTION PERFORMED . (LLD)* I-131 416 7.7 Alpha 12 0.3 Beta . I .12 1.6 . --.... -.:_ -MEAN*f (RANGE) 160 (27/364) (26.:.320) 1.0 (4/12) (0.6-1.3) 6.6 (11/12) NAME DISTANCE AND DIRECTION 16El 4 .1 ml NNW 2F2 8.7 mt NNE 2F2 8.7 mi NNE MEAN (RANGE) 190 (3/62) (70-300) 1.0 (4112) (0 .6-1. 3) 6.6 (11/12) C:DUUDf I DC:6IIDU MEAN (RANGE) 170 (4/61) (64-320) ----* -H-3-,. . 12 130. (1.9-16) <LLD (1.9-16) <LLD No Control Locatton No Control Location No Control *location Be-7 li -47 (11/.H) * * *.zn .... 8.7 mL.HNE 47 (11/11) No Control  
 
... ---.... '* .::: : : * ( 35-71) . Location K-40 11 1-131 11 26 69 (1/ll)c -*.,,::.*._
SALEM GENERATING STATION                                               DOCKET Nos: 60-272/-311 HOPE CREEK GENERATING STATION                                          DOCKET NO. 60-354 SALEM COUNTY, NEW JERSEY                      JANUARY 1, 1986 to DECEMBER 31, 1986 ANALYSIS AND            LOWER                                                                                                                              . NUMBER OF MEDIUM OR PATHWAY        TOTAL NUMBER LIMIT OF ALL IUDIC:AIOH I llC:AIIllU5                               lllC:AIIllU WIIU Ul6UESI' MEAU                         C:DUUDf I DC:6IIDU NONROUTINE SAMPLED .          OF ANALYSES DETECTION                           MEAN*f                                  NAME                                MEAN              MEAN            REPORTED
_,_00._  
                  . (UNIT OF MEASUREMENT) PERFORMED                 . (LLD)*                   (RANGE)                DISTANCE AND DIRECTION                              (RANGE)          (RANGE)      MEASUREMENTS Atr lodtne                I-131         416             7.7           160 (27/364)                        16El 4.1 ml NNW                        190 (3/62)          170 (4/61)
.. ., -69 .. (1111) No Control (69) * * . -... ,, ..  
(10- 3 pCt/m3)                                                           (26.:.320)                                                                 (70-300)           (64-320)            '.;.
... o .... * (69) iocatfori 7.4 (1/11) 2F2 NNE 7:*f(l*/U*)--
                  . Preclpttatlon              Alpha          12          0.3              1.0 (4/12)                         2F2 8.7 mt NNE                         1.0 (4112)           No Control            0 (pCi/L)                                                                 (0.6-1.3)                                                                 (0 .6-1. 3)           Locatton Beta        . I .12          1.6              6.6 (11/12)                       2F2 8.7 mi NNE                        6.6 (11/12)         No Control            0 (1.9-16)                                                                   (1.9-16)           Location
-*. No.Contr.q\
                                      --- - * -H ,. . 12                 130.               <LLD                                                                       <LLD             No Control             0
1.6 ( 7. 4) -{-7.4) . . Location .. , Cs-137 11 0.8 4.8 (1/11) 2F2 8.7.mi NNE . 4.8 (1/11) No Control (4.8) (4.8) Location Ra-226 11
. .,                                                                                                                                                                                          *location
* 4.2 6.6 (jJ1i) 2F2 8.) mi NNE li.6 (3/11) No Control (4.8-7.0)  
  .,"                                          Gamn~
(4.8-7.0)
  . i.                                          Be-7         li                           -47 (11/.H)               **   *.zn....8.7 mL.HNE                         47 (11/11)           No Control             Q
Location Th-232 11 7.2 7.6 (1/11) 2F2 8.7 mi NNE 7.5 (1/11) No Control (7.5) (7.5) Location ' J::_ .. . NUMBER OF NONROUTINE REPORTED MEASUREMENTS
      \                                                                                          (3~-71)                              ... -- -.... '* .::: : : ~ * ( 35-71)           .       Location
'.;. 0 0 0 Q 0 .. 0 0 0 0 
    *1                                          K-40         11               26           69 (1/ll)c - *.,,::.*._ _,_ ~F_z*a~TmTNNE .. ., - 69.. (1111)                                 No Control
. . . ' . *-.....
    *.i                                                                                                                    00
' ; .... * ,* .. ARTifICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  
                                                                                                                              ._                                                                                    0
      '                                                                                          (69)       **             . - ... ,, ..*:..*o.c::.~~---.*,... o . . . . * (69)               iocatfori 1-131        11            1.6              7.4 (1/11)                         2F2 8*.1~mi NNE                       7:*f(l*/U*)-- - *. No.Contr.q\           .. 0
( 7. 4)                                                                   -{-7.4) . .       Location .. ,
Cs-137         11           0.8               4.8 (1/11)                         2F2 8.7.mi NNE . 4.8 (1/11)                                 No Control             0 (4.8)                                                                     (4.8)             Location Ra-226       11
* 4.2               6.6 (jJ1i)                         2F2 8.) mi NNE                         li.6 (3/11)         No Control             0 (4.8-7.0)                                                                 (4.8-7.0)           Location Th-232       11           7.2               7.6 (1/11)                         2F2 8.7 mi NNE                         7.5 (1/11)           No Control             0 (7.5)                                                                     (7.5)             Location J
. j
 
                                      ~*
                                                      ***~ ' ; ....*,* ..
ARTifICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  


==SUMMARY==
==SUMMARY==
SALEM GENERATING STATION DOCKET NOS. 60-UZ/-311 HOPE CREEK GENERATING STATION DOCKET NO. 60-364 SALEM COUNTY, NEW JERSEY JANUARY 1, ,1986 to DECEMBER 31, 1986 ANALYSIS AND LOWER NUMBER Of MEDIUM OR IPAiHWAY TOTAL NUMBER UNIT OF 611 IUDIC6IQH IOC6IIOUS IOC6IlOU Ul6UESI HE6U COUIBOI iQC6IIOU NONROUHNE SAMPLED Of ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED <<UNIT OF MEASUREMENT)
 
PERFORMED (HD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Direct Rild1iltton Gillllllil 287 6.9 (Z61IZ61) 7Sl 0.1 mt SE 6.9 (lZ/12) 6.4 (36/36) ' . 0 (mrad/std.
SALEM GENERATING STATION                                     DOCKET NOS. 60-UZ/-311 HOPE CREEK GENERATING STATION                                 DOCKET NO. 60-364 SALEM COUNTY, NEW JERSEY               JANUARY 1, ,1986 to DECEMBER 31, 1986 ANALYSIS AND                           LOWER                                                                                           NUMBER Of MEDIUM OR IPAiHWAY TOTAL NUMBER UNIT OF 611 IUDIC6IQH IOC6IIOUS                                     IOC6IlOU ~lIU Ul6UESI HE6U         COUIBOI iQC6IIOU NONROUHNE SAMPLED     Of ANALYSES DETECTION                                 MEAN**                           NAME               MEAN           MEAN         REPORTED
month) Dose (monthlll)  
    <<UNIT OF MEASUREMENT) PERFORMED                         (HD)*             (RANGE)             DISTANCE AND DIRECTION         (RANGE)       (RANGE)     MEASUREMENTS Direct Rild1iltton   Gillllllil         287                           6.9 (Z61IZ61)                   7Sl 0.1 mt SE       6.9 (lZ/12)     6.4 (36/36)       ' .0 (mrad/std. month)   Dose (monthlll)                                   (3.8 - 1.7)                                         (6.9-7.1)       ( 6.1_-1.6)
(3.8 -1.7) (6.9-7.1) ( 6 .1_-1.6) Gilllllla 164 6. 0 (140/140) 751 0 .1 mt SE 6.0 (4/4) 6.6 (Z4/Z4) 0 Dose (qtr]lf. b (3.4-6.1) (Ii .6-6 .6) (4. 9-6.4) ir'1 l)Ulk 1-131 122 0.1 10 ( 16/ 103) 3Gl 17 mi NE 19 (3119) 19 (3/19) 0 (111Ct/L) (O.Z-47) (0.3-li3)  
Gilllllla         164                           6. 0 (140/140)                 751 0 .1 mt SE       6.0 (4/4)       6.6 (Z4/Z4)         0 Dose (qtr]lf. b                                   (3.4-6.1)                                           (Ii .6-6 .6)     (4. 9-6.4)
(0.3-63) Sr-89 7 0.8 <LLD <HD <LLD 0 Sr-90 7 z.o (6/6) 6FZ 1.0 mt E 3.0 (lll) Z.1 (111) ii (l.Z-3.0)  
~
(3.0) (Z. 7) Sillmlil Na-ZZ lZ! 1.0 4.6 (11102) 6FZ 7 .o mi E 4.6 (!/20) <LLD 0 (4.6) (4.6) K-40 121 1400 ( 102/ lOZ) .* ...... 2F4 6.3 mi NNE 1400( 13113) 1300 ( 19/19) 0 (lZOO-l!iOO)  
ir'1 l)Ulk                 1-131             122                     0.1     10 ( 16/ 103)                 3Gl 17 mi NE         19 (3119)       19 (3/19)           0 (111Ct/L)                                                               (O.Z-47)                                         (0.3-li3)         (0.3-63)
** /-:=:. -(1300-1600) ( 1100-1400)  
Sr-89                     7                 0.8         <LLD                                               <HD             <LLD           0 Sr-90                     7                         z.o (6/6)                   6FZ 1.0 mt E         3.0 (lll)       Z.1 (111)           ii (l.Z-3.0)                                             (3.0)           (Z. 7)
'* Mn-54 121 0.7 2.9 (lllOZb 13E3 4.9 mi W z. 9 ( 1120) <LLD 0 (Z.9) ( z. 9) Zn-61i 12ll 1.8 11 (11102) llf3 6.3 mi SW 11 (1/ZO) <LLD 0 ( U) (U) Il-Ul !Zll 0.6 20 (8/102) 31H 17 ml NE (2./19) 0 (7,4,,66)  
Sillmlil Na-ZZ             lZ!                     1.0   4.6 (11102)                   6FZ 7.o mi E       4.6 (!/20)           <LLD           0 (4.6)       .*......                              (4.6)
<<:s-U7  
K-40             121                           1400 ( 102/ lOZ)   ** /- :=:. -
'Z.3 4 .1 (li/aOZ) fiU 7 .o mi E 4.fi UW)) @  
2F4 6.3 mi NNE     1400( 13113)   1300 ( 19/19)         0 (lZOO-l!iOO)     '*                               (1300-1600)     ( 1100-1400)
(:il.9-t:i.
Mn-54             121                     0.7   2.9 (lllOZb                   13E3 4.9 mi W       z. 9 ( 1120)         <LLD           0 (Z.9)                                             (z. 9)
0 Ra-226 RZil 6. l 6.6 (31102) 14fl 5.5 mi WNW 5 .s ( zr20 > 6.5 (1119) 0 (4.4-7.3)  
Zn-61i           12ll                     1.8   11 (11102)                   llf3 6.3 mi SW       11 (1/ZO)           <LLD           0
(5.5)
( U)                                               (U)
.**_J-. ";j':. *,. 'J" . 1 I j l _j j ! .*:; .. /. ,. \,'; *::.... .. , *.: .. :. ,,._. .... . . . ::... . . *' .. . . .ARTIFICIAL iSLAND RADIOLOGICAL ENVIRONMENTAL MONITORING*
Il-Ul             !Zll                   0.6   20 (8/102)                     31H   17 ml NE       3~    (2./19)   ~P. (Z/~f))          0 (3.8~49)                                          (7,4,,66)        (7.4~6&sect;)
PROGRAM  
                            <<:s-U7             U~ll                'Z.3       4 .1 (li/aOZ)                 fiU   7.o mi E     4.fi UW))             ~HP              @
(l.3~1i.l)                                        (:il.9-t:i. 0 Ra-226             RZil                   6. l   6.6 (31102)                   14fl   5.5 mi WNW   5 .s   (zr20 >   6.5 (1119)           0 (4.4-7.3)                                         (4.~-1'.3)          (5.5)
 
                                /.   ,.                                                 \,';
                      *::.... .. , *.: . .:. ~-. ~-. ,,._. ~;,:,..,: .:,._;,~ .~ .... -~ -~, . .                                               .::... -~: ..   *' ..
                                                                                                    .ARTIFICIAL iSLAND RADIOLOGICAL ENVIRONMENTAL MONITORING* PROGRAM  


==SUMMARY==
==SUMMARY==
MEDIUM OR PATHWAY SAMPLED (UNIT OF MEASUREMENT)
 
Wel 1 Water (pC 1/L) Potable Water Raw-Treated
SALEM GENERATING STATION                                                   DOCKET NOS. 60-272/-311 HOPE CREEK GENERATING STATION                                              DOCKET NO. 60-364 .
__ (pCi/L) SALEM GENERATING STATION HOPE CREEK GENERATING STATION DOCKET NOS. 60-272/-311 DOCKET NO. 60-364 .
SAL~M  COUNTY, NEW JERSEY             .JANUARY 1, 1986 to DECEMBER 31, 1986 ANALYSIS AND                           *LOWER                                                                                                                                                    NUMBER OF MEDIUM OR PATHWAY                                      TOTAL NUMBER LIMIT OF All INDICATOR \OCAllONS                                                  IOCATION WITH HIGHEST MEAN                                                CONTROi IOCATION      NONROUHNE SAMPLED                                          OF ANALYSES. DETECTION                                      MEAN**                                           NAME                                      MEAN                    MEAN            REPORTED (UNIT OF MEASUREMENT) PERFORMED                                                                (LLD)*                 (RANGE)              DISTANCE AND DIRECTION                                                (RANGE)                (RANGE)         MEASUR~MENTS Wel 1 Water                                              Alpha                          36      0.6             1.2. (~/24)                           2S3 700 ft NNE                                    1.2. (4112)                   <LLD               0 (pC 1/L)                                                                                                           (0.6-2.0)                                                                                 (0. 7-1. 7)
COUNTY, NEW JERSEY . JANUARY 1, 1986 to DECEMBER 31, 1986 ANALYSIS AND TOTAL NUMBER OF ANALYSES.
Beta                            36      1.0***          7.6 (24/Z4)                           6Dl 3.6 mi E                                       10 (lZ/lZ)                 7.4 ( 12/12)          0 (2.0-16)                                                                                  (Z.0-l!i)                 (Z.!i-9.li)
PERFORMED Alpha 36 Beta 36 K-40 36 H-3 36 Sr-89 12 Sr-90 12 GaRJna K-40 36
K-40                            36                      8. 7 (24/24)                          liDl 3.6 mi E                                       13 (12112)                 9.4 (12/12)            0 (2.7-16)                                                                                  (8.8-16)                 (7 .4-17)
**'-36 Tti-z3z-36 Alpha 24 Beta Z4 *LOWER LIMIT OF DETECTION (LLD)* 0.6 1.0*** 130 0.4 0.3 21. 3.3 4.6 0.6 1.0*** All INDICATOR
H-3                            36      130                  <LLD .                                                                                  <LLD                     <LLD              ii Sr-89                          12      0.4                  <LLD                                                                                    <LLD.                    <LLD              *o      '*
\OCAllONS MEAN** (RANGE) 1.2.
Sr-90                          12      0.3                  '<LLD                                                                                     <LLD                      <LLD            -* 0 GaRJna K-40                        36        21.              42 (4/24)                          liDl 3.6 mi E                                         42 (4/lZ)                   <LLD            . p
(0.6-2.0) 7.6 (24/Z4) (2.0-16) 8. 7 (24/24) (2.7-16) <LLD . <LLD '<LLD 42 (4/24) (36-47) .* Z9 (17124) (3.3-96) .9.Z (2/Z4) -: -(8. 4-10) IOCATION WITH HIGHEST MEAN NAME MEAN DISTANCE AND DIRECTION (RANGE) 2S3 700 ft NNE 1.2. (4112) (0. 7-1. 7) 6Dl 3.6 mi E 10 (lZ/lZ) (Z.0-l!i) liDl 3.6 mi E 13 (12112) (8.8-16) <LLD <LLD. <LLD liDl 3.6 mi E 42 (4/lZ) (36-47) 3El 4.1 mi NE 69 (11112) (2.9-170) 601 3.6 mi E 9.Z (2/lZ) (8.4-10) ... -. *.-* .. -... ZF--3 -8.0 .11),i NNE 0.8 ( 11_/24) * --** ft-.. ..:...-_ --:. .!  
.**_J-.                                                                                                                        (36-47) .*                                                                                (36-47)
** ;..-.*-**--... (iL6:.:t.  
                                                                      ~a-:22~                **'- 36      3.3            Z9 (17124)                            3El           4.1 mi NE                           69 (11112)                 69 ( 11112) .          0
: 6) 2F3 8.0 mi NNE CONTROi IOCATION MEAN (RANGE) <LLD 7.4 ( 12/12) (Z.!i-9.li) 9.4 (12/12) (7 .4-17) <LLD <LLD <LLD <LLD 69 ( 11112) . (Z.9-170)
";j':.                                                                                                                      (3.3-96)                                                                                  (2.9-170)                 (Z.9-170)
<LLD No Control *Local ion . No Control o.8 <11/.?H (0.6-1.6) 3.6 (1.7-13).
*,. 'J"                                                              Tti-z3z-                    36      4.6            .9.Z (2/Z4)                            601 3.6 mi E                                       9.Z (2/lZ)                     <LLD              0
1.8 (24124) (1.3-4.9) l!iO ( 1/24) ( l!iO) .3.6._(24/24)  
  . 1                                                                                                                - : - (8. 4-10)
** ,_P"*** *** *
I j
* K-40 24  
(8.4-10) l                                                                                                                                                              ... -. *.- *..- ...
[a canon 2F3 8.0 mi NNE 1.8 {i4i24) No Contra l * --H-3 24 130 * (l.3-4.9)
_j j  Potable Water                                          Alpha                            24      0.6            o.8 <11/.?H                          ZF--3 -8.0 .11),i NNE             * -- *
Location 2F3 8.0 mi NNE 1.!iO ( l / 24) No Control ( 150) Location NUMBER OF NONROUHNE REPORTED 0 0 0 ii *o -* 0 . p 0 0 0 0 0 0 '* 
* f t - ..
'.:. AR!XF!CIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  
0.8 ( 11_/24)               No Control            0 Raw-Treated                                                                                                        (0.6-1.6)                    ..:...-_ -- :. .! -*----~  ** ;..- ~
                                                                                                                                                                                                  .*-**-- ... (iL6:.:t. 6)                       *Local ion .
__ (pCi/L)                                                Beta                            Z4      1.0***          3.6 (~4/24)                           2F3 8.0 mi NNE                                    .3.6._(24/24)               No Control            0
                                                                                                                                                                                                                              ** ,_P"*** *** * *
(1.7-13).                                                                                l~.:7-13)                  [a canon K-40                             24                       1.8 (24124)                          2F3 8.0 mi NNE                                     1.8 {i4i24)                 No Contra l * --     0 (1.3-4.9)                                                                                (l.3-4.9)                 Location
* H-3                              24      130            l!iO ( 1/24)
( l!iO) 2F3 8.0 mi NNE                                     1.!iO ( l / 24)
( 150)
No Control Location 0
 
AR!XF!CIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  


==SUMMARY==
==SUMMARY==
SALEM GENERATING STATION DOCKET NOS. 60-2721-311 HOPE CREEK GENERATING STATION DOCKET NO. 60-364 SAllEM COUNTY, NEW JERSEY JANUARY 1, 1986 to DECEMBER 31, 1986 ANAa.YSIS AND lOWEI! NUMBER OF OH PATHWAY TOTAL NUMBEl.l UMH Of IUDICAIDR  
 
!DC!IIDUS I OCAII!lU kiIIU. Ul6UE51 l:IEAU COIHROI I OCAIIOU NONROUHNE SAMPlfl> OF ANAIL lfSES . DEJIECHON MEANH NAME MEAN MEAN REPORTED <<UNIT Of MEASUREMENT)
SALEM GENERATING STATION                                 DOCKET NOS. 60-2721-311 HOPE CREEK GENERATING STATION                             DOCKET NO. 60-364 SAllEM COUNTY, NEW JERSEY           JANUARY 1, 1986 to DECEMBER 31, 1986 ANAa.YSIS AND       lOWEI!                                                                                                 NUMBER OF
PE!lfORNED  
    ~EDIUN  OH PATHWAY TOTAL NUMBEl.l UMH Of       ~II IUDICAIDR !DC!IIDUS             I OCAII!lU kiIIU. Ul6UE51 l:IEAU         COIHROI I OCAIIOU NONROUHNE SAMPlfl>     OF ANAIL lfSES . DEJIECHON             MEANH                           NAME                   MEAN             MEAN         REPORTED
{U.D)"' (RANGE) DXSTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS Water cont'd Sr-89 0 .6 o.e (1/8) 2f3 8.0 mi NNE 0.6 (118) No Control 0 hw-Tuahdl (0.8) (0.8) locatton (pCW.) Sr-90 8 <<) .4 <LLD <LUI No Control 0 location Gillll!llill l<-40 Z4 zz Z6 (2124) 2F3 8.0 mi NNE 26 (2124) No Control 0 on (Z6-Z6) (26-26) location Ru-103 24 <<1.6 Z.6 (1124) Zf3 8.0 mi NNE 2.6 (1124) No Control 0 (Z.6) .. (2.6) locatlorn lhl-226 24 SJ. 7 6.9 (3/Z4) . . *-. -2f3 8.0 ml NNE 6.9 {3124) No Control 0 (Z.6-8.4)  
  <<UNIT Of MEASUREMENT) PE!lfORNED         {U.D)"'             (RANGE)           DXSTANCE       AND DIRECTION       (RANGE)           (RANGE)     MEASUREMENTS Pot~ble  Water cont'd Sr-89         ~        0 .6         o.e (1/8)                   2f3 8.0 mi NNE         0.6 (118)           No Control         0 hw-Tuahdl                                                   (0.8)                                               (0.8)             locatton (pCW.)             Sr-90         8       <<) .4           <LLD                                                 <LUI           No Control         0 location Gillll!llill
(2.6-8.4) location Th-232 24 . 4.9 6.1 (3/24) 2f3 8.0 mi NNE 6.A (3/24) No Control 0 (6.7-6.8)  
~
(6.7-6.8)
on l<-40       Z4         zz           Z6 (2124)                 2F3 8.0 mi NNE         26 (2124)           No Control         0 (Z6-Z6)                                             (26-26)           location Ru-103     24       <<1.6         Z.6 (1124)                   Zf3 8.0 mi NNE         2.6 (1124)           No Control         0 (Z.6)         ..                                   (2.6)             locatlorn
Loe at fon fruit & Vegetabie$
                                                                              . .*-. ~ -
Ganma { pC I/kg-wet)
lhl-226     24       SJ. 7       6.9 (3/Z4)                   2f3 8.0 ml NNE         6.9 {3124)           No Control         0 (Z.6-8.4)                                         (2.6-8.4)             location Th-232     24     . 4.9         6.1 (3/24)                   2f3 8.0 mi NNE         6.A (3/24)           No Control         0 (6.7-6.8)                                         (6.7-6.8)             Loe at fon fruit &Vegetabie$     Ganma
Be-7 20 H 24 (1/12} 4fl 6.1 mi ENE 24 ( 112) <LLD 0 ( 24) (24) l<-40 20 z 100 (1ZI 12) 2Gl 12 mi NNE 3400 (111) 2100 (8/8) 0 ( 910-2600)  
{pC I/kg-wet)         Be-7       20           H           24 (1/12}                 4fl 6.1 mi ENE         24 ( 112)               <LLD           0
(3400) (1600-3400)
( 24)                                               (24) l<-40       20                   z100 (1ZI 12)                 2Gl   12 mi NNE       3400 (111)         2100 (8/8)           0
I-i31 20 2.3 33 (1112) 2Gl 12 ml NNE 62 (AH) 62 ( 118) 0 (33) (62) (62) Cs-U7 20 A.6 <LLD 3H6 26 ml NE 2.1 (1!4) 1.8 (218) 0 ( 2 .1) (l.6-2.1)
( 910-2600)                                             (3400)         (1600-3400)
Ra-226 20 l.8 8.3 (1112) AGl 10.3 mi N 68 (1/3) 63 (218) 0 (8.3)  
I-i31     20       2.3           33 (1112)                 2Gl   12 ml NNE       62 (AH)             62 ( 118)         0 (33)                                               (62)               (62)
(58-68) Ho-2?:? :w B.8 5.4 mi WNW t?"B t.UO 0 (Vq 1\ & . ;; -----
Cs-U7       20         A.6             <LLD                     3H6 26 ml NE           2.1 (1!4)           1.8 (218)         0
. . '* .. * ::* ,. ., .* -*' . ..;. : .. ." .... ..:...::*
( 2 .1)         (l.6-2.1)
.. . -
Ra-226     20       l.8         8.3 (1112)                     AGl   10.3 mi N       68 (1/3)             63 (218)           0 (8.3)                                               (68~              (58-68)
**-* l . I I .j >1 .*.1 .*;, *., i ., I .I I.*.* .! . i i *i .I .j i l . l *I i .. , ...... J. i j ".j i :i .I *1 '*:l . i i ! . -. . . < J *,1,.* .*.; 1 i , MEDIUM OR PATHWAY SAMPLED (UNIT OF MEASUREMENT)
Ho-2?:?   :w       ~.IS        B.8 P.tfi.2~                ~t'.\f~  5.4 mi WNW       t?"B {L/2i~            t.UO           0 (Vq                                                 1\ &. rl~ ;
Game (pCi/kg-wet) Beef (pC i /kg-wet) Fodder Crops ( pC I /kg-wet) * , .. .,:: . *. -.  
 
... _' ....  
                                                                                            **.-~;;~ ..._'.... --~~~~~;'::~: -~ ':_:....~ /*:*. *.*
.... /*:*. *.* ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  
                  -,.::.~::* ~*~..'..*--~: . ..;. :. ... ...:...::*..
                                                    ."                  . - ---*~ **-*
      . I  l I
          .j
      >1
      .*.1
        .,i I
            .I ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  


==SUMMARY==
==SUMMARY==
: SALEM GENERATING.STATION DOCKET NOS. 60-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 60-364 SALEM COUNTY, NEW JERSEY JANUARY 1; 1986 to DECEMBER 31, 1986 ANALYSIS AND LOWER NUMBER OF TOTAL NUMBER LIMIT OF All IUDICAIOB IOCAIIOUS IOCAIIOU UI6UESI MEAU COUIBOI IOCAIIOU NONROUTINE OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS  
 
'. Ganmil K.:.40 2 2400 ( 1/1) 4Cl 2.8 mi ENE 2400 ( 1/1) 2200 ( 1/1) o*. (2400) ( 2400) ( 2200) Gilnmil K-40 1 2600 (.1/1) 3El 4.1 mi NE 2600 (1/1) No Control 0 (2600) ( 2600) Lociltion Cs-137 1 7.3 (111) 3El 4.lmiNE 7.3 (111) No Control 0 (7.3) (7.3) Lociltion Ganma Be-7 9 140 880 (4/7) 14Fl 6.6 mi WNW 1400 (Ill) 1100 (l/Z) 0 (370-1400)  
      . i i                                                                                                                                                                                                                                                                            :
(1400) ( 1100) K-40 9 6600 (717) 3El 4.lmiNE 16000 (1/1) 8600 (212) .0 (2300-16000) ( 16000) (3000-14000)
I
Cs-137 17 <LLD 361 17 mi NE 13 (1/2) 13 (1/Z) 0 --(13) (13) Ra-226 9 36 36 (117) 2F7 5. 7 mi NNE 36 (1/1) <LLD 0 (36) (35) Th-232 9 69 170* ('lt7) 14fl 5.6 mi WNW -170 (111) <LLD () ( 170) ( 170) -* * '*  
        *i                                                                                                      SALEM GENERATING.STATION                                                     DOCKET NOS. 60-272/-311
.. -::r*: * .. -*
            .I                                                                                                                                                                                  DOCKET NO. 60-364
* _,: :.*.* -.. ... . .. *--. . .. . . .::-*:. *-!. !._* __  
        .j                                                                                                      HOPE CREEK GENERATING STATION i
.. '.,: .. *-. :**. . ..
SALEM COUNTY, NEW JERSEY                           JANUARY 1; 1986 to DECEMBER 31, 1986 ANALYSIS AND                               LOWER                                                                                                                                       NUMBER OF MEDIUM OR PATHWAY      TOTAL NUMBER LIMIT OF All IUDICAIOB IOCAIIOUS                                           IOCAIIOU ~IIU UI6UESI MEAU                                                   COUIBOI IOCAIIOU NONROUTINE SAMPLED          OF ANALYSES DETECTION                                           MEAN**                                   NAME                                     MEAN                   MEAN         REPORTED l                                        (UNIT OF MEASUREMENT) PERFORMED                                       (LLD)*                   (RANGE)           DISTANCE               AND             DIRECTION               (RANGE)                 (RANGE)     MEASUREMENTS
* ro *** * *
      .l                                                                                                                                                                                                                                                                        '.
****** ' * >* *' * ..;. ' ,,' * ' ,* * -' * * * "* * : ' '* *** * *"""* '* *c*> *  
        *I
';,. \ j '** .. , : ' . ,. *** I AR1If ICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  
        ..i,                                                                          Ganmil Game
        . . . J.
i                                          (pCi/kg-wet)                K.:.40                     2                                 2400 ( 1/1)               4Cl 2.8 mi ENE                                       2400 ( 1/1)               2200 ( 1/1)           o*.
j (2400)                                                                         ( 2400)                   ( 2200)
        ".j
:i i
          .I                                          Beef                            Gilnmil
      '*:l
              *1
                                        ~                  (pC i /kg-wet)              K-40                       1                                 2600 (.1/1)               3El 4.1 mi NE                                       2600 (1/1)                 No Control           0
        . i                                                                                                                                                                                                                            ( 2600)                   Lociltion i                                                                                                                                      (2600)
              !                                                                        Cs-137                     1                                 7.3 (111)                 3El 4.lmiNE                                           7.3 (111)                 No Control           0 (7.3)                                                                           (7.3)                   Lociltion Fodder Crops                  Ganma
( pC I /kg-wet)            Be-7                       9                     140         880 (4/7)               14Fl 6.6 mi WNW                                       1400 (Ill)               1100 (l/Z)           0 (370-1400)                                                                       (1400)                     ( 1100)
K-40                       9                                 6600 (717)                 3El 4.lmiNE                                         16000 (1/1)               8600 (212)           .0 (2300-16000)                                                                       ( 16000)               (3000-14000)
    . -. .;*~1-                                                                        Cs-137                 '*~                          17           <LLD                   361 17 mi NE                                         13 (1/2)                 13 (1/Z)             0
        . <                                                                                                  --                                                                                                                         (13)                     (13)
          *,1,.*
J                                                                      Ra-226                     9                       36       36 (117)                   2F7 5. 7 mi NNE                                     36 (1/1)                     <LLD             0
          .*.;                                                                                                                                          (36)                                                                             (35)
                                                                                                                                                                                                                                                                    <LLD Th-232                   9                       69       170* ('lt7)             14fl 5.6 mi WNW - 170 (111)                                                                           ()
( 170)                                                                           ( 170)
                                                                                                                                                                                  -* * '* ,.~---- ..-::r*: *..~ - **_,: :.*.*
        ~
1
                ,i                                            *                                                                                               - .. .       .
                                                                                                                                                                              .::-*:. *- !. !._* __ ~:.:...:-.. '.,: .. *-. : * * .
ro *** * *
 
            * ~ >* *'     * ..;. ' ,,' * '
:~    '
                                            ,* * - ' * * * "* * : ' '* *** * * " " " * '* *c*>
                                                                                                * **~<,. ';,. \ j ~ '** .. ,
AR1If ICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  


==SUMMARY==
==SUMMARY==
SALEN GENERATING STATION DOCKET NOS. li0-27Z/-3U HOPE CREEK GENERATING STATION DOCKET NO. 60-364 SALEM COUNTY, NEW JERSEY JANUARY 1, 1986 to DECEMBER 31, 1986 ANALYSIS AND LOWER NUMBER Of MEDIUM OR PATHWAY TOTAL NUMBER UNIT OF AIL IUDI&AIOH LO&AIIOU5 IO&AIIOU UIGUESI MEAU &OUIHOI IOCAIIOU NONROUTUIE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN . REPOUEO (UNIT Of MEASUREMENT)
 
PERFORMED (LLD)* (RANGq DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMfNTS 1 Soil Sr-90 16 2Z 91 (13114) Zfl 6.0 mt NNE 140 (Rli) 93 (Z/Z) 'o (pCi/kg-dry) (Z7-140) (140) (66-130).
SALEN GENERATING STATION                                 DOCKET NOS. li0-27Z/-3U HOPE CREEK GENERATING STATION                             DOCKET NO. 60-364 SALEM COUNTY, NEW JERSEY                 JANUARY 1, 1986 to DECEMBER 31, 1986 ANALYSIS AND                                   LOWER                                                                                     NUMBER Of MEDIUM OR PATHWAY                             TOTAL NUMBER UNIT OF AIL IUDI&AIOH LO&AIIOU5                                         IO&AIIOU ~IIU UIGUESI MEAU         &OUIHOI IOCAIIOU NONROUTUIE SAMPLED                                 OF ANALYSES DETECTION                                         MEAN**                     NAME                   MEAN         MEAN       . REPOUEO (UNIT Of MEASUREMENT) PERFORMED                                                                 (LLD)*             (RANGq           DISTANCE AND DIRECTION         (RANGE)       (RANGE)   MEASUREMfNTS 1
Gillmli8 . '\ l'(-40 ll.6 7800 (14/H) .*.* 11F3 6.3 ml SW 13000 011) 8600 (Z/Z) . '*0* ( lZ00-13000) ( UOOO) ( 7900-9200) l)(!:h Nb-96 16 4.li 48 (Z/14) ZF7 6.7 mi NNE 63 (111) <LLD 0* (34-63) (63) Cs-U1 X6 390 ( 14/R4) lfl 6.8 mt N lliOO (111) 460 (2/Z) 0 (78-UiOO}  
Soil                                               Sr-90                         16                     2Z     91 (13114)               Zfl 6.0 mt NNE       140 (Rli)       93 (Z/Z)           'o (pCi/kg-dry)                                                                                                   (Z7-140)                                         (140)       (66-130).
(1600) (210-690) lllin-226 16 680 (14/n-0 16El 4.1 mi NNW 1000 UH) 810 (2/2) 0 (260-1000) ( 1000) ( 770-860) Hf3 6.3 mi SW 1000 (111) (1000) 'H'h-232 16 710 (14/14) 16El 4.1 ml NNW 1200 ( 111) 800 (212) 0 (ZJ0-1200) ( 1200) (780-810) i Surface Water Alpha 60 0.6 3 .1 ( 19/48) lfZ 7 .1 mi N 6.6 (3112) 3.li (4112) 0 (pC i IL) (0.7-12) (2.6-12) ( 1. 8-8. 3) Beh 611 3.8*** 61 (48/48) 7El 4.6 ml SE 76 (12112) 46 ( 12/12) 0 (2.4-130)  
                                                                                                                                                                                                                    . '\
(16-130) (7.li-81)
Gillmli8 7800 (14/H)     .*.*     11F3 6.3 ml SW                                           . '*0*
H-3 zo !30 160 (8/16) UAl 0.2 ml SW 210 (214) 160 (1/4) 0 ( 130-270) ( ili0-270) ( 160)
l'(-40                      ll.6                                                                        13000 011)       8600 (Z/Z)
'* : .. . *, ;<. :* 1'-....... C.*._,_.::
( lZ00-13000)     :~*-                            ( UOOO)     ( 7900-9200) l)(!:h                                                           Nb-96                       16                   4.li       48 (Z/14)               ZF7 6.7 mi NNE       63 (111)             <LLD             0*
__ , __ ,; .... -* . ........ *'-*-.. : :'. : :*_,._ .. *-: .. * ...... ... . . . --........ .. .. ; '. *i *-.! *1 .*j \ . :j '.'l .*1 n ;1 I I I I .*; . *i ,j 'i . 'l l *-1 *; I ' l *:i -.i *I :l I :.".j '-.1 *.i :**:j .\ .j I I 1 I '.i *l *I .: .*'.j . .. . I *:. :1 ' I <<>> MEDIUM OR PATHWAY SAMPLED (UNIT OF MEASUREMENT)
  ~                                                                                                                              (34-63)                                         (63)
Surface Water cont'd. Edible Fhh ( pC 1/kg-dr y) (pC1/kg-wet)
Cs-U1                       X6                             390 ( 14/R4)             lfl 6.8 mt N       lliOO (111)       460 (2/Z)           0 (78-UiOO}                                       (1600)         (210-690) lllin-226                   16                             680 (14/n-0             16El 4.1 mi NNW     1000 UH)           810 (2/2)           0 (260-1000)                                       ( 1000)       ( 770-860)
ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  
Hf3 6.3 mi SW       1000 (111)
(1000)
                                                                    'H'h-232                   16                             710 (14/14)             16El 4.1 ml NNW     1200 ( 111)       800 (212)           0 (ZJ0-1200)                                       ( 1200)       (780-810) i             Surface Water                                       Alpha                         60                   0.6       3.1 ( 19/48)             lfZ   7.1 mi N     6.6 (3112)       3.li (4112)             0 (pC i IL)                                                                                                     (0.7-12)                                       (2.6-12)       ( 1. 8-8. 3)
Beh                           611                 3.8***   61 (48/48)               7El 4.6 ml SE       76 (12112)       46 ( 12/12)             0 (2.4-130)                                     (16-130)       (7.li-81)
H-3                           zo                   !30       160 (8/16)             UAl 0.2 ml SW           210 (214)       160 (1/4)             0
( 130-270)                                     ( ili0-270)         ( 160)
 
                                                                                  '* :. ~
1'- ~.......C.*._,_.::__ , __ ,; .... - * ~ ~..... . ........ *'- *- .. : :'. : :*_,._ .. *- : .. * ...... ... . . . - - ........ ..
          *i
    *1
    .*j
            \
. :j
        '.'l
    .*1 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  


==SUMMARY==
==SUMMARY==
SALEM GENERATING STATION HOPE CREEK GENERATIN.G STATION SALEM COUNTY, NEW JERSEY ANALYSIS AND LOWER DOCKET NOS. 60-272/-311 DOCKET NO. 60-364 JANUARY*l, 1986 to DECEMBER 31, 1986 TOTAL NUMBER LIMIT OF Al I IUDICAIOH IOCAIIOUS IOCAIIOU WIIU UI6UESI YEAU Of ANALYSES DETECTION MEAN** NAME MEAN PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) Ganma K-40 60 24 88 (34/48) 7El 4.6 m1 SE 100 (lZ/12)' (33-160) (66-160) Ra-226 60 3.3 6.6 (7148) l2Cl 2.6mi WSW 26 (1/12) ( 2 .6-11) (26) Th-232 60 4.9 7.4 (6/48) 12Cl 2.6 m1 WSW 9.2 (1/12) (6.3-9.3)  
 
(9. 2) Sr-89 6 40 <LLD 12Cl 2.6 m1 WSW 330 (1/2) (bones) (330) Sr-90 6 24 140 (214) 12Cl 2.6 mi WSW 1600 (112) (bones) (34-240) ( 1600) H-3 6 60 <LLD <LLD (aqueous)
n
Ganma K-40 6 3000 (4/4) llAl 0.2 mi SW 3000 (Z/2) (2700-3300) ( 2700-3300) 12Cl 2.6 mi WSW 3000 (2/2) (2700-3300)
      ;1 I                                                                                                                  SALEM GENERATING STATION                         DOCKET NOS. 60-272/-311 I                                                                                                                  HOPE CREEK GENERATIN.G STATION                    DOCKET NO. 60-364 II
Cs-137 6 12 8.3 (1/4) llAl 0.2 m1 SW 8.3 (1/2) (8. 3) (8. 3) Ra-226 6 20 37 (2/4) llAl 0.2 mi SW 41 (1/2) (33-41) . ( 41) -* .. _ --_ -. Th--2-32 -._ 6 31 <LLD 12Cl 2.6 mi WSW 29 (1/2) (29) '/'* NUMBER OF COUUOI I OCAIIOU NON ROUTINE MEAN REPORTED (RANGE) MEASUREMENTS . . :* 70 (9/12) 0 (29-96) 26 (1112) 0 (26) 9.2 (1112) 0 (9.2) 330 (1/Z) 0 (330) 1600 (1/2) 0 ( 1600) <LLD 0 3000 (212) *O ( 2700-3300)
  . *i                                                                                                                        SALEM COUNTY, NEW JERSEY            JANUARY*l, 1986 to DECEMBER 31, 1986
<LLD 0 <LLD 0 29 (112) 0 (29)
                                                                                                                                                                                                            '/'*
* I l j *1 " ' . i 1)(11. w MED!UN OR PATHWAY . SAMPLED (UNIT OF MEASUREMENT)
      ,j
Blue Cubs {pC I/kg-dry)
      'i
<<l>C i/kg-weit)
. 'l                                                MEDIUM OR PATHWAY ANALYSIS AND                    LOWER TOTAL NUMBER LIMIT OF Al I IUDICAIOH IOCAIIOUS                       IOCAIIOU WIIU UI6UESI YEAU     COUUOI IOCAIIOU NUMBER OF NON ROUTINE SAMPLED                                                                              MEAN**                   NAME                 MEAN l                                    (UNIT OF MEASUREMENT) PERFORMED Of ANALYSES DETECTION (LLD)*           (RANGE)         DISTANCE AND DIRECTION       (RANGE)
Benth1c Organ1sms (pCHkg-dry)
MEAN (RANGE)
ARTIFICIAL ISLAND RADIOLOGICAL ENViRONNfNTAl MONITORING PROGRAM  
REPORTED MEASUREMENTS
    *-1 I                                                                                                                                                                                                                        . ~ . :*
      *:i
    -.i l                                    Surface Water cont'd. Ganma K-40                 60             24     88 (34/48)
(33-160) 7El 4.6 m1 SE     100 (lZ/12)'
(66-160) 70 (9/12)
(29-96) 0
    *I
:l                                                                                                  Ra-226               60           3.3       6.6 (7148)             l2Cl 2.6mi WSW       26 (1/12)         26 (1112)        0 I                                                                                                                                        ( 2.6-11)                                     (26)              (26)
      '~~                                                                                              Th-232               60           4.9       7.4 (6/48)             12Cl 2.6 m1 WSW     9.2 (1/12)
:.".j                        ~                                                                                                                                                                                9.2 (1112)        0
                                <<>>                                                                                                                  (6.3-9.3)                                     (9. 2)            (9.2)
  '-.1
  *.i
:**:j
    .\
        .j                                    Edible Fhh                                            Sr-89                   6           40         <LLD               12Cl 2.6 m1 WSW       330 (1/2)         330 (1/Z)        0 I
I
( pC 1/kg-dr y)                                     (bones)
Sr-90                   6           24       140 (214)             12Cl 2.6 mi WSW (330) 1600 (112)
(330) 1600 (1/2)        0 1
I                                                                                            (bones)                                     (34-240)                                     ( 1600)           ( 1600)
(pC1/kg-wet)                                      H-3                     6           60         <LLD                                         <LLD             <LLD          0 (aqueous)
Ganma K-40                   6                   3000 (4/4)             llAl   0.2 mi SW   3000 (Z/2)         3000 (212)        *O
  '.i                                                                                                                                              (2700-3300)                               ( 2700-3300)       ( 2700-3300)
      *l                                                                                                                                                                  12Cl 2.6 mi WSW     3000 (2/2)
    *I
  .*'.j (2700-3300)
. .. ~~ .                                                                                              Cs-137                 6           12       8.3 (1/4)             llAl 0.2 m1 SW       8.3 (1/2)             <LLD          0 I                                                                                                                                              (8. 3)                                       (8. 3)
Ra-226               6             20       37 (2/4)             llAl 0.2 mi SW       41 (1/2)             <LLD          0
      ~;-
(33-41)                                     . ( 41)
    *:.                                                                                   - -_ -. Th--2 ._ 6                         31         <LLD               12Cl 2.6 mi WSW       29 (1/2)           29 (112)         0
:1 (29)             (29)
        'I
 
I l
j                                            ARTIFICIAL ISLAND RADIOLOGICAL ENViRONNfNTAl MONITORING PROGRAM  


==SUMMARY==
==SUMMARY==
SALEM GENERATING STATION HOPE CREEK GENERATING STATION COUNTY, NEW JERSEY DOCKET NOS. 60-272/-3Rl DOCKET NO. 60-364 JANUARY l, 1986 .to DECEMBER 31, 1986 ANALYSES AND TOVAL illlUNBER OF AAALYSES LOWER UD@!T OF DETECTION (LLD)* ALI IUOICATOR IOCAIIOUS  
 
!OCATIOU WITH HIGHEST HEAM PERFORMED .fl (shei]h) Sr-90 4 <<sheH:s) H-3 4 (aqueous)
*1                                            SALEM GENERATING STATION                             DOCKET NOS. 60-272/-3Rl HOPE CREEK GENERATING STATION                        DOCKET NO. 60-364 SA~EM  COUNTY, NEW JERSEY          JANUARY l, 1986 .to DECEMBER 31, 1986 ANALYSES AND       LOWER                                                                                      NUMBER OF MED!UN OR PATHWAY . TOVAL illlUNBER UD@!T OF ALI IUOICATOR IOCAIIOUS             !OCATIOU WITH HIGHEST HEAM     CONTROi IOCATIOU NONROUTXNE SAMPLED      OF AAALYSES DETECTION                MEAN*>!!                     NAME                MEAN          MEAN        REPORTED (UNIT OF MEASUREMENT) PERFORMED        (LLD)*              (RANGE)     '.~*~RSTANCE AND DIRECTION        (RANGE~        (RANGE)   MEASU.REMENTS
Sr-89 (flesh) Sr-90 4 (f1HDll>> Ganma !C-40 . l& Ra-226 4 G11nm11 8 67 60 28 18 28 MEAN*>!! (RANGE) 300 (l/Z) (300) 260 (212) (160-380)
: . '~ -
<HD <LLD <LLD 1800 (212) ( 1700-2000) . <LLD <LLD NAME MEAN AND DIRECTION
Blue Cubs            Sr-8~        .fl    67            300 (l/Z)              11Al 0.2 m1 SW       300 ( H2)         <LLD          0
: . -11Al 0.2 m1 SW 300 ( H2) (300) 12Cl 2.6 ml WSW 400 (212) (320-i&90)  
{pC I/kg-dry)        (shei]h)                              (300)                                        (300)
<LLD 'LLD <LLD llAl 0.2 ml SW 1800 (212) ( 1700-2000) 12Cl 2.6 mi WSW 1800 (212) ( 1700-2000) 12Cl 2.6 mi WSW 20 (212) (19-20) <LLD NUMBER OF CONTROi IOCATIOU NONROUTXNE MEAN REPORTED (RANGE) MEASU.REMENTS
Sr-90        4                      260 (212)              12Cl 2.6 ml WSW     400 (212)      400 (212)       :  o*
<LLD 0 400 (212) : o* ( 320-490) <LLD 0 <LLD 0 <LLD 0 1800 (212) 0 ( 1700-2000) 20 0 (19-20) <LLD 0 
                                  <<sheH:s)                            (160-380)                                    (320-i&90)    ( 320-490)
. r I i *\ . I i . ;) . I l .;*, **1 :1 l J , I .I *.I .j i *i .. , *J *J :,[ .I .j i I I i ' l :.J *1 .,\ 'J ,,j <1 'i ; *l I **:.; ,i .*1 "1. 1
            <<l>C i/kg-weit)      H-3          4      60                <HD                                          <LLD            <LLD          0 1)(11.                        (aqueous) w                            Sr-89        ~      28                <LLD                                         'LLD             <LLD         0 (flesh)
* I I *I ' i . * .. l : .. J .. . 'j ! .. .:..:::.; (JI 0 "*'* . ... *-: .. *:: .. ** * ................
Sr-90        4      18                <LLD                                        <LLD            <LLD          0 (f1HDll>>
!, .' MEDIUM OR PATHWAY . SAMPLED (UNIT OF MEASUREMENT)
Ganma
Sediment (pC1/k9-dry)
                                  !C-40      . l&                  1800 (212)                llAl 0.2 ml SW     1800 (212)     1800 (212)          0
ARTIFICIAL ISLAND RADl_OLQGICAL ENVIRONMENTAL MONITORING PROGRAM  
( 1700-2000)                                  ( 1700-2000)  ( 1700-2000) 12Cl 2.6 mi WSW     1800 (212)
( 1700-2000)
Ra-226      4      28              . <LLD                12Cl 2.6 mi WSW       20 (212)       20 (212~          0 (19-20)         (19-20)
Benth1c Organ1sms    G11nm11      8                        <LLD                                         <LLD           <LLD           0 (pCHkg-dry)
. i
 
.r I
i
      . I
      ;)
        *\
i                                                                               ARTIFICIAL ISLAND RADl_OLQGICAL ENVIRONMENTAL MONITORING PROGRAM  


==SUMMARY==
==SUMMARY==
SALEN GENERATING STATION HOPE CREEK GENERATING STATION SALEM COUNTY, NEW JERSEY ANALYSIS AND LOWER DOCKET NOS, 60-272/-311 DOCKET NO, 60-364 JANUARY 1, 1986 to DECEMBER 31, 1986 TOTAL NUMBER LIMIT OF ALL IUDICAIDB IDCAIIDUS IDC6IIDU UIGUESI YEAU OF ANALYSES DETECTION MEAN** NAME MEAN PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) Sr-90 lZ 19 <LLD <LLD Gillllllil K-40 lZ 9600 (10/10) 16Fl 6.9 mi NNW 16000 (212) (3600-16000)  
 
(16000-16000)
  .        I
Mn-64 12 18 26 (3/10) llAl 0.2 ml SW 27 (212) (24-29) (26-29) Co-68 12 23 67 (4110) 16Al 0.3 mi NW 80 (1/2) (31-80) (80) Co-60 lZ 36 72 (8/10) llAl 0.2 mi SW 100 (212) (37-11_0)  
  .;*,l                                                                                    SALEN GENERATING STATION                             DOCKET NOS, 60-272/-311
(92-110) C5-134 12 16 61 (3/10) 16Al 0.7 mi NNW 82 (1/Z) (46-82) (82) Cs-137 12 16 61 (3/10) llAl 0.2 ml SW 82 (1/2) (49-82) (82) . Ril-2Z6 12 610 (10110) 16Al O. 7 mi NNW 780 (212) (330-810)  
      **1 HOPE CREEK GENERATING STATION                        DOCKET NO, 60-364
(760-810)
:1 J
Th-232 12 720 ( 10/10)
l                                                                                SALEM COUNTY, NEW JERSEY            JANUARY 1, 1986 to DECEMBER 31, 1986
* 16Fl 6,9 mi NNW 970 (212) (300-1000) ( 940-1000)  
    , I
' LLD listed is the lowe5t calculated LLD during the reporting period . **Mean calculated using values above LLD only. Fraction of meaGurement*
    *.I
Above LLD are in parentheses. Typical LLD value.
        .I
* NUMBER OF CDUIBDI IDCAIIDU NONROUTINE MEAN REPORTED (RANGE) MEASUREMENTS
          .j i                                                                  ANALYSIS AND    LOWER                                                                                        NUMBER OF
' <LLD 0 16000. (212) 0 (14000-16000)
    ..*i,                      MEDIUM OR PATHWAY . TOTAL NUMBER LIMIT OF ALL IUDICAIDB IDCAIIDUS                                         IDC6IIDU ~IIU UIGUESI YEAU       CDUIBDI IDCAIIDU  NONROUTINE SAMPLED                                  OF ANALYSES DETECTION             MEAN**                       NAME               MEAN         MEAN          REPORTED
<LLD 0 <LLD 0 <LLD 0 60 ( 112) 0 (60) 20 (1/2) 0 (20) 700 (212). 0 * ... ' .. (670-840) 880 (212) 0 (870-880)
  *J  *J
* 
:,[                    (UNIT OF MEASUREMENT) PERFORMED                                  (LLD)*             (RANGE)           DISTANCE AND DIRECTION       (RANGE)     (RANGE)      MEASUREMENTS
' . ' . _ .. , ' ' " * -r ' * *: . *; ........ *. *. **.*'*. APPENDIX 8 SAMPLE DESIGNATION ANO LOCATIONS 51
            .I                                                                                                                                                                                    ' -~
--**--  
      .j i                  Sediment                                        Sr-90     lZ     19               <LLD                                           <LLD         <LLD              0 I
* ; ! *'? ., . I .-J APPENDIX B SAMPLE DESIGNATION.*: . The PSE&G Research.Corporation identifies samples by a three part code. The first two letters are the power station identification code, in this cas.e '9 SA". The next three letters are for tl'l.e media sampled. AIO = Air Iodine IDM = Immersion Dose (TLD) APT = Air Particulates MLI< = Milk ECH = Hard Shell Blue Crab PWR = Potal:lle Water (Raw) ESB = Benthic organisms PWT = Potable Water (Treated)
I                  (pC1/k9-dry)                                    Gillllllil i
ESF = EdilJle Fish
K-40     lZ                 9600 (10/10)               16Fl 6.9 mi NNW     16000 (212)   16000. (212)        0
* RWA = Rain Water ESS = Sediment SOL = Soil FPB = Beef SWA = surface Water FPL = Green Leafy Vegetacles VGT = Fodder crops (Various)
:.J l'                                                                                                  (3600-16000)                                   (16000-16000)  (14000-16000)
FPV = Vegetables (Various)
        *1                                                                      Mn-64   12     18           26 (3/10)               llAl 0.2 ml SW         27 (212)       <LLD              0
WWA = Well Water GAM = Game The last four symbols are a location code based on direction and distance from the site. Of these, the first two represent each of tl'l.e sixteen angular sectors of 22.5 degrees centered about the reactor site. Sector one is divided evenly by the north axis and other sectors are numbered in a directioru i.e. Q 2=NNEP 3=NE, etc;. The next digit .. is a letter which represents the radial distance from the
      .,\
* s = on-site location E = Dci.les off-site A = DU.les off-site F = 5-10 miles Off=site .B = l-2 miles off-site G =
      'J (JI                                                                                    (24-29)                                       (26-29) 0
miles off-site c = miles off-site H = <20 miles off-site D = 3-4 miles off-site The last number is the station numerical designation within each sector and zone; e.g., l,2,3, *** For example, the designation SA-WWA-SDl would indi.cate a sampie in the SGS program (SA), consisting of well water (WWA), whi.ch had been collected in sector number 5, centered at 90' (due east) with respe<;t.
      ,,j                                                                        Co-68   12     23           67 (4110)               16Al 0.3 mi NW         80 (1/2)       <LLD              0
to the reactor site at a radial distance of 3 to 4 miles off-site, (therefore, radial, distance*
    <1                                                                                                            (31-80)                                         (80)
D). The number l indicates that this is sampling station #l in that particular sector * .. _ --------------.
      'i                                                                        Co-60   lZ     36           72 (8/10)               llAl 0.2 mi SW         100 (212)       <LLD              0
-*-* ._----
  ; *l                                                                                                          (37-11_0)                                       (92-110)
-------
I
.-, ' -.* *! . -. ' J .. J l .. . '* '* .... SAMPLING LOCA'rIONS . All 1986. sampling location's and specific.
  **:.;                                                                          C5-134   12     16           61 (3/10)               16Al 0.7 mi NNW       82 (1/Z)       60 ( 112)          0
information about the individual locations are given in Table B-l. Maps B-l and B-2 show the locations of sampling stations with respect to the site. STATION CODE 2S2 2S3 SSl 6Sl 6S2 7Sl lOSl llSl ll.Al lSAl l6Al 4Cl 12Cl 4D2 5Dl TABLE B-1 STATION LOCATION o.4 mi. NNE of vent. 700 ft. NNE of vent; fresh water holding tank 1.0 mi. E of vent; site access road 0.2 mi. ESE of vent; observation .building area 0.2 mi. ESE of vent; observation b&#xb5;ilding 0.12 mi. SE of vent; station personnel gate 0.14 mi. SSW of vent; site shoreline 0.09 mi. SW of vent; site shoreline 0.2 mi. SW of vent; outfall area 0.3 mi. NW of vent; cooling tower blowdown discharge line outfall 0.7 mi. NNW of vent; south storm drain discharge line 2.a mi. ENE of vent 2. 5 mi. WSW of vent; west bank of Delaware l:U ver 3.7 mi. ENE of vent; Alloway Creek Neck Road 3.5 mi. E of vent; local farm SAMPLE TYPES AIO,APT,IDM WWA AIO,APT,IDM SOL IDM IDM IDM IDM' ECH,ESB,ESJ", ESS,SWA ESS ESS GAM ECH,ESB,ESF, ESS,SWA IDM AIO,APT,IDK, SOL,WWA
        ,i                                                                                                        (46-82)                                         (82)         (60)
* lODl 3. 9 mi.. SSW of vent; Taylor's Bridge Spur AIO,APT,IDJ!,SOL llDl 3.S.mi. SW Of vent GAM l4Dl 3.4 mi. WNW of vent;. Bay View, Delaware IDM
    .*1 "1.                                                                          Cs-137   12     16           61 (3/10)               llAl 0.2 ml SW       82 (1/2)       20 (1/2)            0 1I                                                                                                      (49-82)                                         (82)         (20)
* 54  
I
-...  
        *I
-.. -.. -.  
                                                                                . Ril-2Z6 12                   610 (10110)
..  
(330-810) 16Al O. 7 mi NNW       780 (212)
--
(760-810) 700 (212).
*. ;* ..
(670-840) 0        ..
* .. ! STATION CODE 2El 3El 7El 9El llE2 12El 13El l3E3 16El lFl lF2 1F3 2Fl 2F2 2F3 2F4 2F5 2F6 2F7 3F2 3F3 4Fl 5Fl 5F2 TABLE (cont'd} STATION LOCATION 4.4 mi. NNE of vent; local farm 4.l mio NE of vent; loca.1 farm 4.5 mi. SE of vent; l mi. W of Mad Horse creek 4.2 mi. S of vent SoO mi. SW of vent 4*4 mi. WSW of vent; Thomas Landing 4.2 mi. W of vent; Diehl House Lab 4.9 mi. W of vent; local farm 4ol mi. NNW of vent; Port Penn s.a mi. H of vent; fort 7ol mi.. N of vent; midpoint of Delaware River 5o9 mi. N of local farm 5.0 mi" NNE of vent; local farm 807 mi. NNE of vent; Salem SUbstation 800 mi. NNE of vent; Sal.em Water Company 6.3 mi. NNE of vent; local farm 7.4 mi.. NNE of vent; Salem High School 7o3 mi. NNE of vent; Southern Training Center 5o7 m.i,. NNE of local farm 5.l mi. NE of vent; Hancocks Bridge Municipal Bui.ldinq 8.6 mi.. NE of vent; Quinton Township School Sol mi. ENE of vent; local. farm 605 mi. E of vent .SAMPLE TYPES FPV,IDM,SOL FPB,FPV,IDM, VGT,WWA ESB,ESF,ESS,SWA IDM IDM IDM IDM Mr..K,VGT AIO,APT,IDM,SOL AIO,APT,IDM,SOL SWA FPL,FPV SOL AIO,APT,IDM, RWA,SOL PWR,PWT MLK,SOL !DH IDM ML&'.,SOL,VGT IDM IDM FPL,FPV FPV,IDM,sor..  
  ' i Th-232   12                   720 ( 10/10)
--.-. *---,-
* 16Fl 6,9 mi NNW       970 (212)     880 (212)          0 (300-1000)                                     ( 940-1000)    (870-880)
-*--.--'--*.
  . *.. l                        ' LLD listed is the lowe5t calculated LLD during the reporting period .
-*---... -. -**.**: ******-----
                                **Mean calculated using values above LLD only. Fraction of meaGurement* Above LLD are in parentheses.
---...... --.----. ----*-----* -
                              ~** Typical LLD value.
* I . J .--! '
: ..J
' ' .* :1 *, STATION CODE 6Fl 7F2 lOF2 llFl llF3 l2Fl l3F2 .13F3 13F4 14Fl 14F2 14F3 15F3 16Fl 16F2 lGl 1G3 2Gl 3G1 lOGl 16Gl -3H1 3H3 3HS TAELE B-1 .(cont'd)
      .. ~ .
STATION LOCATION 6.4 mi. ESE of vent; Stow Neck Road 9.1 mi. SE of vent; Bayside, New Jersey 5.8 mi. SSW of vent 6.2 mi. SW of vent; Taylor's Bridge Delaware 5.3 mi. SW of vent; Townsend, Delaware 9.4 mi. WSW of vent; Townsend Elementary 6.5 mi. W of vent; Odessa, Delaware 9.3 m+/-. w of vent; Redding Middle School, Middletown, Delaware 9.8 mi. w of vent; Middletown, Delaware 5.5 mi. WNW of vent; local farm 6.6 mi. WNW of vent; Boyds corner 5.4 .. mi. WNW Of vent; local farl!l 5.4 mi. NW of vent 6.9 mi. NNW of vent; C&D canal School 8.1 mi. NNW of vent; Delaware City PUblic School 10.3 mi. N of vent; local farm 19 mi. N of vent; Wilmington, Delaware 12 mi. NNE of vent; Mannington Township, NJ 17 mi. NE of vent; local farm 12 mi. SSW of vent; Smyrna, Delaware 15 mi. NNW of vent; Greater Wilmington Airport 32 mi. NE of vent; National Park, New Jersey 110 mi. NE of vent; Research and Testing Laboratory 25 mi. NE of vent; local farm 56 . ,' .
      'j
* SAMPLE TYPES IDM IDM IDM IDM MI.I<, SOL ,.VGT IDM IDM IDM IDM MLK,SOL,VGT IDM
 
* FPV IDM ESB,ESS,SWA IDM FPV IDM FPV IDM,MLK,SOL,VGT IDM IDM IDM AIO,APT,IDM,SOL FPL ,FPV --*'* .--*.-*-;-
APPENDIX 8 SAMPLE DESIGNATION ANO LOCATIONS
-;* .. **..-.   
                                                        ~ -r 51
. ! :, . ! .. ; .j ., . _*: 1 -. 'l '. . Cl ON SITE SA . MPl ING AJUIFICJAL . \ 57 . -* ----  
        ----~-~ ----._.-.-...-*---------,,,****-,.**-------~---:-------* *--.---.._.---...,.....,..---.-----~---,:--:-*----*-~ *-:--**-----~---.-------- -- **--
....... ,. MAP S-2 0 FF-SITE SAMPLING LOCATIONS ARTIFICIAL ISLAH D , 58 * 
 
. i i ; * ' .I i l i .. I APPENDIX C DATA TABLES _._.,...--------.---.-.-------*---***'"<---
APPENDIX B SAMPLE DESIGNATION.*: .
---*----:.--------
The PSE&G Research.Corporation identifies samples by a three part code. The first two letters are the power station identification code, in this cas.e
-------*----.-----
        ' SA".
-.-7-___________  
9 The next three letters are for tl'l.e media sampled.
!. *. ---,-----.. ;-------*. ------*-*--.. -----------------***--* -----.-*---*****-* -* -.* .,. *** --** -*: -  
AIO  = Air Iodine                  IDM  =   Immersion Dose (TLD)
* * &deg;:-j ... I *; . . ' . .. -i * . i .*:* 1 i *.*.1 ' **i : ...... '.! *; .; DATA TABLES Appendix c presents the analY.tical results <Jf. the 1986 Artificial Island Radiological Environmental Monitoring Program for the period of January l to December 31, 1986 *. TABLE NO. c-2 C-3 C-4 C-5 TABLE OF CONTENTS TABLE DESCRIPTION ATMOSPHERIC ENVIRONMENT AIR PARTICULATES 1986 Concentrations Of Gross Alpha Emitters ********************
APT  = Air Particulates            MLI<  =   Milk ECH  = Hard Shell Blue Crab        PWR  =   Potal:lle Water (Raw)
1986 concentrations of Gross Beta Emitters.c:1****o*o*cio******oo*
ESB  = Benthic organisms          PWT  =   Potable Water (Treated)
1986 Concentrations of Strontium-89 and Strontiwn-90 and Gamma Emitters in Quarterly Composites
ESF  = EdilJle Fish
*******************.
* RWA  =  Rain Water ESS  =  Sediment                    SOL  =   Soil FPB  = Beef                        SWA  =   surface Water FPL  =  Green Leafy Vegetacles      VGT  =  Fodder crops (Various)
* AIR IODINE 1986 Concentrations of
FPV  =  Vegetables (Various)        WWA  =  Well Water GAM  =  Game The last four symbols are a location code based on direction and distance from the site. Of these, the first two represent each of tl'l.e sixteen angular sectors of 22.5 degrees centered about the reactor site. Sector one is divided evenly by the north axis and other sectors are numbered in a clock-w~e: directioru i.e. 2=NNEP 3=NE, 4=ENE~ etc;. The next digit . is a letter Q
************* ****************
which represents the radial distance from the plant~
DATES 1986 Sampling Dates for Air Samples ****************************
* s = on-site location                  E =  4~5 Dci.les off-site A = 0~1 DU.les off-site                F =  5-10 miles Off=site
PRECIPITATION C-6 1986 concentrations of Gross Alpha and Gross Beta Emitters and PAGE 64 66 68 '10 Tritium ** Cl ******* Clo.., e Cl. Cl *** Cl. c ** o. Cl. e ***** Q e *** o **** " *** o o 77 1986 concentrations of Gamma 11:mitters  
              .B = l-2 miles off-site                G =  io~20 miles off-site c = 2~3 miles off-site                H =  <20 miles off-site D = 3-4 miles off-site The last number is the station numerical designation within each sector and zone; e.g., l,2,3, *** For example, the designation SA-WWA-SDl would indi.cate a sampie in the SGS program (SA), consisting of well water (WWA), whi.ch had been collected in sector number 5, centered at 90' (due east) with respe<;t. to the reactor site at a radial distance of 3 to 4 miles off-site, (therefore, radial, distance* D). The number l indicates that this is sampling station #l in that particular sector *
*******************.*******  
**'?
'18 DIRECT RADIATION TBERMCLUMINESCEN'r DOSIMETERS 1986 Quarterly TLD Results *** Cl Cl o Cl Q c '&deg; o = Cl o
. I
* c o G:I
  .-J
                                                                  .. _ --------------. -*-* ._---- --*-**---.~------.,. ----- - -
 
SAMPLING LOCA'rIONS
                                . All 1986. sampling location's and specific. information about the individual locations are given in Table B-l. Maps B-l and B-2 show the locations of sampling stations with respect to the site.
TABLE B-1 STATION CODE                                                STATION LOCATION                                                                        SAMPLE TYPES 2S2            o.4    mi. NNE of vent.                                                                                               AIO,APT,IDM 2S3            700 ft. NNE of vent; fresh water holding tank                                                                          WWA SSl            1.0 mi. E of vent; site access road                                                                                    AIO,APT,IDM 6Sl            0.2 mi. ESE of vent; observation .building area                                                                        SOL 6S2            0.2 mi. ESE of vent; observation b&#xb5;ilding                                                                                IDM 7Sl            0.12 mi. SE of vent; station personnel gate                                                                              IDM lOSl            0.14 mi. SSW of vent; site shoreline                                                                                    IDM llSl            0.09 mi. SW of vent; site shoreline                                                                                      IDM' ll.Al            0.2 mi. SW of vent; outfall area                                                                                        ECH,ESB,ESJ",
ESS,SWA lSAl            0.3 mi. NW of vent; cooling tower blowdown                                                                              ESS discharge line outfall l6Al            0.7 mi. NNW of vent; south storm drain                                                                                  ESS discharge line
  .-, '                               4Cl            2.a    mi. ENE of vent                                                                                                GAM 12Cl              2. 5 mi. WSW of vent; west bank of Delaware l:U ver                                                                    ECH,ESB,ESF, ESS,SWA 4D2            3.7 mi. ENE of vent; Alloway Creek Neck Road                                                                            IDM 5Dl            3.5 mi. E of vent; local farm                                                                                          AIO,APT,IDK, SOL,WWA lODl             3. 9 mi.. SSW of vent; Taylor's Bridge Spur                                                                           AIO,APT,IDJ!,SOL llDl             3.S.mi. SW Of vent                                                                                                     GAM l4Dl             3.4 mi. WNW of vent;. Bay View, Delaware                                                                               IDM J                                                                                                              54
  .. J l
    .**-t~.-...-_-.-:-:-_-.-~~------.--.:-*--*:-:*;*:-~~-::-::-~:*-::-:--:::--~~--.-.. -  ..-.~::-;---~=-:-~--....,-7"-*~~:---:--~-.,...-:...-~-- -~--.':--:~---~;;-:----;._-:----~.;~ -.---~-- - -    ";--*.*--*--~---- '":~-- :***~-,.-*-.;-*:-
* STATION CODE TABLE STATION LOCATION s~1        (cont'd}
                                                                                                                                                                        .SAMPLE TYPES 2El            4.4 mi. NNE of vent; local farm                                                                                             FPV,IDM,SOL 3El            4.l mio NE of vent; loca.1 farm                                                                                              FPB,FPV,IDM, VGT,WWA 7El            4.5 mi. SE of vent; l mi. W of Mad Horse creek                                                                              ESB,ESF,ESS,SWA 9El            4.2 mi. S of vent                                                                                                           IDM llE2            SoO mi. SW of vent                                                                                                          IDM 12El            4*4 mi. WSW of vent; Thomas Landing                                                                                          IDM 13El            4.2 mi. W of vent; Diehl House Lab                                                                                          IDM l3E3            4.9 mi. W of vent; local farm                                                                                               Mr..K,VGT 16El            4ol mi. NNW of vent; Port Penn                                                                                              AIO,APT,IDM,SOL lFl            s.a    mi. H of vent; fort                        ~lfsborq                                                                AIO,APT,IDM,SOL lF2            7ol mi.. N of vent; midpoint of Delaware River                                                                              SWA 1F3            5o9 mi. N of               vent~        local farm                                                                        FPL,FPV 2Fl            5.0 mi" NNE of vent; local                              farm                                                                SOL 2F2            807 mi. NNE of vent; Salem SUbstation                                                                                      AIO,APT,IDM, RWA,SOL 2F3            800 mi. NNE of vent; Sal.em Water Company                                                                                  PWR,PWT 2F4            6.3 mi. NNE of vent; local farm                                                                                            MLK,SOL 2F5            7.4 mi.. NNE              of vent; Salem High School                                                                        !DH 2F6            7o3 mi. NNE of vent; Southern Training Center                                                                              IDM 2F7            5o7    m.i,. NNE of        vent~        local farm                                                                    ML&'.,SOL,VGT 3F2            5.l mi. NE of vent; Hancocks Bridge Municipal                                                                              IDM Bui.ldinq 3F3            8.6 mi.. NE of vent; Quinton Township School                                                                                IDM 4Fl            Sol mi. ENE of vent; local. farm                                                                                            FPL,FPV 5Fl            605 mi. E of vent                                                                                                          FPV,IDM,sor..
5F2
    *------*--**-----***-~--.-. ---.;-*---**~-.--. -----.~---"'7""---~------..--- *-:-----~- --.-. *---,- :------~ -*--.--'--*. -*-- - ... -. -**.**: ******----- ---.. . . --.- -- - . ~ ----*-- ---* -
 
STATION CODE TAELE B-1 .(cont'd)
STATION LOCATION                SAMPLE TYPES 6Fl  6.4 mi. ESE of vent; Stow Neck Road              IDM 7F2  9.1 mi. SE of vent; Bayside, New Jersey          IDM lOF2  5.8 mi. SSW of vent                              IDM llFl  6.2 mi. SW of vent; Taylor's Bridge Delaware    IDM llF3  5.3 mi. SW of vent; Townsend, Delaware          MI.I<, SOL ,.VGT l2Fl  9.4 mi. WSW of vent; Townsend Elementary School IDM l3F2  6.5 mi. W of vent; Odessa, Delaware             IDM
            .13F3  9.3 m+/-. w of vent; Redding Middle School,        IDM Middletown, Delaware 13F4  9.8 mi. w of vent; Middletown, Delaware       IDM 14Fl  5.5 mi. WNW of vent; local farm                  MLK,SOL,VGT 14F2 14F3 15F3 6.6 mi. WNW of vent; Boyds corner 5.4 ..mi. WNW Of vent; local farl!l 5.4 mi. NW of vent IDM FPV IDM 16Fl  6.9 mi. NNW of vent; C&D canal                  ESB,ESS,SWA 16F2  8.1 mi. NNW of vent; Delaware City PUblic School IDM lGl  10.3 mi. N of vent; local farm                   FPV
* I 1G3  19 mi. N of vent; Wilmington, Delaware          IDM 2Gl  12 mi. NNE of vent; Mannington Township, NJ      FPV
  . J
    .--!      3G1  17 mi. NE of vent; local farm                    IDM,MLK,SOL,VGT lOGl  12 mi. SSW of vent; Smyrna, Delaware            IDM 16Gl  15 mi. NNW of vent; Greater Wilmington Airport  IDM
            -3H1  32 mi. NE of vent; National Park, New Jersey  IDM 3H3 110 mi. NE of vent; Research and Testing        AIO,APT,IDM,SOL Laboratory 3HS 25 mi. NE of vent; local farm                    FPL ,FPV          --*'*
--*--~
    .* :1
      *,                                            56
 
AJUIFICJAL l.SLA~~OCATIONS .
ON SITE. SA MPl ING
                  \
          .j Cl
  . _*: 1
        - -~                      57
      . 'l
      .    ~-
                                                  . -* -~~ ----
 
MAP S-2 0FF-SITE SAMPLING LOCATIONS ARTIFICIAL ISLAH D 58
 
APPENDIX C DATA TABLES
  . i i;
    .I i
l i
.. I
_._.,...--------.---.-.-------*---***'"<--- ---*----:.-------- -------*----.----- -. ___________ !. *. - - -,---- - .. ; - - - - - - - * . - - - - - - * - * - - .. - - - - - - - --- -- --- --***--* --~ --- --.-*- -- *****-* - * - .* .,. *** - -* * - * : -
* DATA TABLES Appendix c presents the analY.tical results <Jf. the 1986 Artificial Island Radiological Environmental Monitoring Program for the period of January l to December 31, 1986 *.
TABLE OF CONTENTS TABLE NO.                                               TABLE DESCRIPTION                                                                                                                  PAGE ATMOSPHERIC ENVIRONMENT AIR PARTICULATES 1986 Concentrations Of Gross Alpha Emitters ********************                                                                                                                   64 c-2        1986 concentrations of Gross Beta Emitters.c:1****o*o*cio******oo*                                                                                                                  66 C-3         1986 Concentrations of Strontium-89 and Strontiwn-90 and Gamma Emitters in Quarterly Composites *******************.*                                                                                                               68 AIR IODINE C-4        1986 Concentrations of                   Iodine~l3l                ************* ~ ****************                                                                               '10 DATES C-5        1986 Sampling Dates for Air Samples ****************************
PRECIPITATION C-6       1986 concentrations of Gross Alpha and Gross Beta Emitters and Tritium **   Cl * * * * * *
* Clo.., e Cl. Cl * *
* Cl. c *
* o . Cl. e * * * *
* Q e *** o **** "                   *** o o                             77 1986 concentrations of Gamma 11:mitters *******************.*******                                                                                                               '18 DIRECT RADIATION TBERMCLUMINESCEN'r DOSIMETERS 1986 Quarterly TLD Results ***                         Cl Cl o Cl Q c '&deg; o = Cl o
* c o   G:I
* c * "
* c * "
* o
* o
* c. c Cl
* c. c      Cl
* Cl* Cl o Cl o o " c 79 1986 Monthly TLD Results 0
* Cl* Cl  o Cl o o " c                          79
* Cl 0 0 0 0 0 0 0 0 _o Cl 0 C) Cl g C> Q 0 0 c 0 &deg;0 Cl e
      * &deg;:-j
* 0 0 Cl 0 e S!J .o G 0 Cl 0 0 so_ 61 -. ------.--*----------
... I
        *;                                1986 Monthly TLD Results                  0
* Cl 0 0 0  0  0  0  0 0 _o  Cl 0 C) Cl g C> Q  0  0 c 0 &deg;0 Cl  e
* 0  0  Cl 0    e    S!J .o G  0 Cl  0  0                      so_
  .. '  .  ~
..- i
        . i
      *.*.1
        **i 1
i 61
              - .------.--*----- ~------*** -~ - - - --*-- - - .--~--- .--r-*-      *-------~ ~~---:-*-- .~----~.-*----~...-~          -- ---- --    ~*----- - - - .-* .. ~-*** ****- ~ ... *****- ~  --;- -, **--*. w , - ....... - - - - - * **-
 
TABLE NO.
OA'l'A 'l'ABLES ' (cont 1. c1. )
TA5LE DESCRIPTION PAGE
                                      'l'ERRES'l'RIAL ENVIRONMENT MILK C-10  1986 concentrations of Iodine-131 **************.****************          82 C-ll  1986 Concentrations of Strontium-89 and Strontium-90 ***********            83 c-12  1986 Concentrations of Gamma Emitters **************************            84 C-13  1986 Sampling Oates for Milk Samples ***


---------,. *
__-:_ **~--~L-."~ . :*,_ . . -. . ~e:.:. -* - ~:':*.
-"' * ** ''* ''" r ** "** .,.. *. TABLE C-3 . 1986 CONCENTRATIONS Of STRONTIUM-89*
I . .                                                  -      .
ANO STRONTIUM-90 AND GAMMA EMITTERS**
                                                                                    "p , **
IN QUARTERLY COMPOSITES Of AIR PARTICULATES
                                                                                                                                                          ~ '*. '
*i .'1 m O> STATION IO COLLECTION PERIOD SA-APT-2S2 12-30-85 to 03-31-86 03-31-86 to 06-30-86 06-30-86 to 09-29-86 09-29-86 to 12-29-86 SA-APT-6Sl 12-30-86 to 03-31-86 03-31-86 to 06-30-86 06-30-86 to 09-29-86 09-29-86 to J2-29-86 SA-APT-601 (1) 12-30-85 to 03-31-86 03-31-86 to 06-30-86 06-30-86 to 09-29-86 09-29-86 to 12-29-86 SA-APT-1001 12-31-86 to 04-01-86 04-01-86 to 07-01-86 07-01-86 to 09-30-86 09-30-86 to 12-30-86
i 1
* Sr-89*** <0.4 <0.4 *-<2.0 -<0.4 Results In Units of 10-3 pCl/m 3 +/- 2 sigma Sr-90*** Be-7 Ru-103 Ru-106 <0.3 64+/-5 <0.4 <3.1 96+/-7 8.8+/-0.8 <7.7 89+/-6 <0.5 <4.4 66+/-6 <0.6 <5.9 <0.2 66+/-5 ' <0.3 <4 .1 ..: 77:tli 7.8+/-0.6 4.0:tZ. l 88:tli <0.3 <4.3 66:tli <0.3 <6.3 <0.3 86+/-8 <0.8 <6.0 110+/-12 9.2+/-1.3 <7.0 89+/-11 <1.0 <8.0 80+/-6 <0.6 <3.0 <0.3 71+/-5 <0.4 <4.7 88+/-6 8.7+/-0.7 <7.0 76:tli <0.6 <4.3 60+/-4 <0.6 <2.7
l TABLE C-9 (COBlt 9 d)
* Cs-134 Cs-137 Ra-226 Th-232 <0.6 <0.6 ( 1.0 <Z.2 9.8+/-0.9 18+/-1 < 1.8 <2.6 <0.6 <0.4 <l.O < l. 7 <0.5 <0.7 <l.2 <2.7 <0.6* <0.4 ( 1.1 ( l. 9 9.3+/-0.8 17+/-1 <l. 3 ( 1.6 <O .Ii <0.4 <0.3 ( i .2 <0.6 <0.6 <1.0 <2.1 <0.6 <0.6 <9.0 (2) 8.4+/-1.1 18+/-2 <10 (2) <l.O ( 1.0 <10 (2) '<0.3 <0.4 <6.0 (2) <0.6 <0.3 ( 1.0 <2.3 9.ilt0.9 17+/-1 ( 1.6 <2;4 <0.6 <0.4 ( 1.0 ( 1. 2 <0.5 <0.4 <0.7 ( 1.6 ., ***.* * 
*.*1 1986 DIRECT RADIATION MEASUREMENTS - MONTHLY TLD RESULTS l                                                                                          Results in mrad/standard month*
.,' * !! . . ... . . .. .... **--'. .... .... :, ..... .. *** /: . I TABLE C-3 (cont'd)*
(Results by Teledyne Isotopes)
1986 CONCENTRATIONS Of STRONTIUM-89*
STATION ID                                    JULY        AUGUST      SEPTEMBER        OCTOBER  NOVEMBER    DECEMBER          AVERAGE SA-IDH-282                              -. 5.9+/-0.3        5.7+/-0.5      5.3+/-0.5        5.4+/-0.3  4.9+/-0.4      '7.1+/-0. 7        5.8+/-1.4
AND STRONTIUM-90 AND GAMMA EMITTERS**
*1                              SA-IDH-5Sl                                5.5+/-0.4        5.9+/-0.7      4.9+/-0.7        5.3+/-0.3  4.6+/-0.3      6.2+/-0.5          5.4+/-1.2
IN QUARTERLY COMPOSITES OF AIR PARTICULATES Results In Units of 10-3 pCl/m 3 :1: 2 sigma STATION ID COLLECTION PEMIOD Sr-89*** Sr-90*** Be-7 Ru-103 Ru-106 Cs-134 Cs-137 Ra-226 lh-232 SA-APT-16El 12-31-86 to 041-01-86
    *I                            SA-IDH-6S2                                6~1+/-0.5        6.1+/-0.4      5.5+/-0~4        5.7+/-0.4  4.9+/-0.5      6.6+/-0.6          5.9+/-L2 SA-IDM-7Sl                                7.0+/-0.8        6.9+/-0.4      6.6+/-0.8        6.5+/-0.9  5.9+/-0.7      7.7+/-1.0          6.9+/-1.2, 1l                            SA- IDH-lOSl                              6.5+/-0.6        6.5+/-0.4       5.7+/-0.5        6.4+/-0.6  5.5+/-0.3     7.6+/-0.9          6 .4+/-1.4 I I
<I!. 41 <0.3 64:1:4 <0.4 <3.9 <0.4 <0.4 ( 1.0 (I. 6 l 04-01-86 to 07-01-86 83:1:!5 1.6:1:0.6 4.2:1:2.1 8.411:0.8 16tl ( 1.4 '( i .6 1 01-01-86 to 09-30-86 83tli <0.3 <4.2 <0.6 <0.4 <0.'11 *< 1.1 J 09-30-86 to 12-30-86 64t4 (0,3 <2.6 <0.4 <0.4 <0.6 < 1. l J I I l SA-APT-lfl l .! 12-30-86 to 03-31-86 <0.6 <0.3 66:1:6 <<C. n <4.6 <0.6 <0.6 l.Zt0.6 <2.2 03-31-86 to 06-30-86 86:1:6 8.8+/-!1. 7 8.3t3.3 lOtl 17tl ( 1.4 <2.3 06-30-86 to 09-29-86 79:1:6 <<0.4 <4.6 <0.6 <0.5 <0.9 1. 7+/-1.0 09-29-86 to 12-H-186 64tE <0.2 <3.6 <0.6 <0.4 <0.8 <l. 3 Cll co SA-APT.:.2f2
SA- IDM-llSl                              6.4+/-0.6        6.1+/-0.5      5.0+/-0.2         5.4+/-0.3 5.0+/-0.l      6.9+/-0.9          5.9+/-1.8 i'
.. , AZ-30-85 to 03-31-86 <G.3 <0.2  
SA-IDM-5Dl                                6.2+/-0.5        6.0+/-0.7      5.5+/-0.5        5.5+/-0.5  4.8+/-0.4      6.5+/-0.6          5.8+/-1.l SA- IDH-lODl                              5. 7+/-1.l      6.3+/-0.5      5.8+/-0.4        6.1+/-0.5  5.3+/-0.4      6.9+/-0.6          6.2+/-1.3 SA- IDH-1401                              6.8+/-0.l       6.2+/-0.3      5.7+/-0.5        6.0+/-0.8 5.2+/-0.4      6.9+/-0.6          6.2+/-1.2 SA-IDM-2El                                6.0+/-0.7        6.0+/-0.3      5.5+/-0.3         5.6+/-0.5  4.9+/-0.6     6.5+/-0.9           5.8+/-1.2 SA-IDH-3El                                6.0+/-0.4       5.9+/-0.5      5.1+/-0.3        5.5+/-0.3  4:8+/-0.4      6.3+/-0.5          5.?+/-1.2 SA-IDM-13El                                5.9+/-0.4        5.9+/-0.4      5.2+/-0.6        5.7+/-0.4  4.8+/-0.5      6.6+/-0.6          5. 7+/-1.2
<<lli.3l <Z.8 <0.6 <0.3 <0.3 <L2 to 06-30-86 80:1:6 9.0tG.8 <7.2 lOti Htl < 1.1 <2.3 06-30-86 to 09-29-86 78t6 <0.6 <3.0 <0.6 <0.4 < 1. R <2.2 09-29-86 to iZ-29-86 6h6 <<0.6 ( 1.6 <0.4 <0.4 <L 1 <LB SA-AP1f-3H3
                  ~              SA-IDM-16El                                6.4+/-0.5        6.1+/-0.4      5.8+/-0.6        5.9+/-0.5  5.1+/-0.4      7.1+/-0.7          6.1+/-1.4 l}-<l
'Contiro])
_SA- IDM-lFl                                6.3+/-0.5        6.2+/-0.3      5.5+/-0.3        5.9+/-0.5  5.1+/-0.5      6.7+/-0.4          6.0+/-1.2 SA-IDM-2F2                                ~-4+/-0.4        5.3+/-0.2      4.7+/-0.2        4.8+/-0.2  4.2+/-0.2      5.9+/-0.3          5.1+/-1.2 SA-IDH-2F6                                6.0+/-0.6       6.1+/-0.3      5.6+/-0.3        5.6+/-0.3 5.0+/-0.5      1.-uo.6          6.o'+/-L3
12-30-6 to 03-31-86 <O.:ll <0.2 64t4 <0.31 <3.9 <0.4 <0.4 <0.9 (l, l 03-31-86 to 06-30-86 83t6 7.6t<<l.li 4.0tl.9 9.2:1:0.7 17tl <0.3 ( 1.1 06-30-86 to '09-29-86
    '!                            SA-IDM-5Fl                                6.1+/-0.3       5.9+/-0.2       5.5+/-0.3        5.6+/-0.4 5.0+/-0.3      6.4+/-0.6          5. 7+/-1.l SA-IDM-6Fl                                5.6+/-0.3        5.3+/-0.2      4.8+/-0.3        5.0+/-0.3  4.3+/-0.2      6.1+/-0.5          5. 3+/-1.0 SA-IDM-7F2                                5.0+/-0.3        4.9+/-0.l      4.2+/-0.2        4.6+/-0.3  3.8+/-0.2     5.5+/-0.6           4.7+/-1.2 SA-IDM-llFl                                6. 8+/-1. 0      6.7+/-0.4      6.2+/-0.8        6.2+/-0.5  5.6+/-0.5      7.2+/-0.8          6-5+/-1. 3 SA- IDM-13F4                              6.5+/-0.4        6.1+/-0.2       5.7+/-0.4        6.0+/-0.5  5.3+/-0.4     6.9+/-0.5          6.2+/-1. 3 SA-IDM-3Gl (C)                            6.7+/-0.5        6.6+/-0.7      6.1+/-0.4         6.3+/-1. 3 5.1+/-0.3      7.2+/-0.3         6. 3+/-1.4 SA-IDM-3Hl (C}                            6.7+/-0.9       6.7+/-0.4       5.6+/-0.6        6.0+/-0.5  5.4+/-0.2      7_.2+/-0.5        6.3+/-1.3 '
* 90t7 <0.1 <7.6 (0,6 (0,6 < 1. R <2.1 09-29-86 to lZ-29-86 64+/-6 ((),6 <6.8 (0,3 (0,6 ( 1.3 ( 1. 9 AVERAGE 76tU u Sr-89 results are corrected for decay to &ample stop dmts. =* AJl ganma emitters searched for were <LLD; llDs given In Table C-33. aaa Management audit anaUyses, required by specAflcilijons or by specific conmitments to Joe al off ic iii Iii. (1) Results by Veledyne Isotopes.  
SA-IPM-383 (C)                            6.9+/-0.5        6.9+/-0.4      6.3+/-0.8        6.5+/-0.3 5.9+/-0.4      7.4+/-0.6          6. 7+/-L 3 AVERAGE                                    6.2+/-1.0        f).1+/-1.0      5.5:1:1.l      5.7+/-1.0  5.0+/-1.0      6.8+/-1.l Grand  Av~rng~        ~rQ!l.6 Ill The standard month * .3o.4 daye.
<<Z) Not analyzed by Te]edyne 
                                  <<c> Control station U) TLD missing from field Jocat!on.
,*
 
.... '--*' ... -* *--.. **--*** ...... . I l ; . l* _i. ., *1 ,j *.1 I . ! I *1 I i .1 I I *J I :j .\ i .1 .J j .! i ! j 1 ! :I **! oj 1 I ! i *, J .. j I :,1 .. ! ..... j .., 0 *MONTH** SA-AIO-ZSZ JANUARY <19 <14 <140 (1) <17 <16 FEBRUARY <Zl <19 <16 <16 MARCH <Z6 . <16 <19 ( 13 APRIL <18 <16 <19 <16 MAY <20 310t34 230t30 8ltl4 48tZO JUNE 26tll <16 <17 ( 17 ... *.* SA-AI0-651
.. :~ *_ :*. :.:- - ..*..... .:... -**~ ,_ ~.   ..
<16 <Z6 <13 <23 <16 <Z4 <10 <41 <Z4 <Zl <17 <14 <16 < 8.7 <20' <30 ( 9.9 <16 310t32 180t28 66t16 <32 33t13 <22 <22 <14 TABLE C:-4 1986 CONCENTRATIONS OF IODINE-131*
 
IN FILTERED AIR Results 1n Units of 10-3 pCt/m 3 t Z sjgma STATION ID SA-AI0-6Dl***
    *'\    .   -  -- . J      .
SA-AIO-lODl SA-AI0-16El SA-AIO-lfl
TABLE C-11 1986 CONCENTRATI0NS OF STRONTIUM-89* ANrr STRONTIUM-90 IN' MILK**
<ZO <33 <ZZ ( 9.3 <20 <14 <17 ( 8.0 <20 <23 <18 <22 <20 <27 <18 <16 <10 <11 <26 <16 <20 <23 <18 <21 <10 <11 <14 ' <17 <30 <13 <28 <30 <10 <28 <20 <18 <30 < 14 <14 <19 <10 <26 <20 <16 <20 <17 <19 <19 <10 <13 <12 <16 <40 <19 <22 <18 <20 <21 <16 <18 <30 <18 <Zl <17 <40 ( 16 <13 <23 <40 <16 <26 <20 280t60 310t29 300t32 320t36 610t220 (2) 180t28 190t29 220t28 73t16 60tl7 70t18 76t16 <60 46t20 <390 (1) 42t23 <30 <28 <28 32tl6 <40 <29 <19 <18 <20 <14 ( 8.9 <28 <30 <14 <18 <14 SA-AIO-ZFZ
Results in Units of pCi/L +/- 2 sigma STATION ID                                              COLLECTION PERIOD                                                                                Sr-89  sr-90 SA=MLK;,.,13E3                                                        07/06-07/86                                                                        <0.9  1.9+/-0.3 SA~MLK~2F4                                                              07/06~07/86                                                                        <0.8 l.St0.3 SA~MLK-2F7                                                            08/03-04/86                                                                        <l.5  2.4+/-0.6 SA-MLK-5F2                                                              07/05-07/86                                                                        <l.l 3.0+/-0.4 SA-MLK-llF3                                                            07/07-08/86                                                                        <0.8 1.7+/-0.3 SA-MLK-l4Fl                                                            07/06-07/86                                                                        <0.8 1.2+/-0.3 SA~MLR~3Gl                                                            07/07=08/86                                                                        <0.9  2.7+/-0.3
<Z4 <14 <17 <17 <22 <19 <11 <21 <14 <ZZ <18 ( 11 <20 <26 <17 <39 <13 <26 270t32 220t28 73tl8 62t22 <30
<20 <21 <22 SA-AI0-3H3
<16 <13 <22 <16 <29 <16 <16 <13 <17 <U <18 <18 <16 <20 <14 <12 <16 <22 320t32 230t30 65t16 64t20 (3) < 16 .. < 19 . <20 AVERAGE 300t37 210t46 69tl7 48t20 .-
' ...... _ *... lABlf C-4 (cont'd) 1986 CONCENTRATIONS Of IODINE-131*
IN FILTERED AIR Re5ults in Units of 10-3 pCi/m 3 +/- 2 sigma SJAHOU rn lllONJH**
SA-Al0-2S2 SA-AR0-551 SA-AI0-501***
SA-AI0-1001 SA-Al0-16El SA-AIO-lfl SA-AI0-2f2 SA-AI0-3H3 AVERAGE JULY <24 <A4 <20 <26 <20 <19 <26 <l8 <22 <U <30 <16 <21 <18 <20 <16 <20 <!4 <20 <22 <19 <16 <30 <17 <19 <!2 <20 < 1l <13 <20 <16 <20 AUGUST ( 9.4 <H <30 ( 9.9 <28 <14 <18 <15 <26 <n9 <20 <22 <23 <12 <21 <15 <14 <Il6 <20 <30 ( 8.0 <21 < lO . <24 <U <18 <30 <19 <lJ <23 <!6 <18 <16 <12 <20 <14 <13 <20 <iii <16 SEPTEMBER
<22 <24 <30 <21 <27 <23 <17 <20 < 9.1 ( 7.7 <20 <26 <16 <19 <21 <22 ..;ii <26 <24 <20 <H <25 <33 ( 11 <12 If-' <18 <32 <20 <14 <25 < 13 <22 <19 OCIOBER <20 <10 <20 <36 <20 <21 < 11 <17 <R4 <H <10 <14 ( 9.0 <16 <22 <18 <23 <H <30 <22 <31 <33 <26 <19 <18 <A9 <20 <H ( 8.6 <20 <30 <20 <16 < 9.6 <20 <26 <14 <12 ( 8.5 <18 NOVEMBER <20 <Ali <20 ( 19 <15 <20 <24 <15 <21 <28 <10 <21 ( 17 <17 <231 <26 <!9 <Ui <30 <21 <H <16 <14 <18 < lOOO (1} <17 <10 <19 <21 <28 <25 <21 DECEMBER ( 9.2 <18 <20 < 8.1 * <12 <13 <19 ( 120 0) <22 <16 <10 < 19 <16 <21 <22 <18 <20 <H ( 1000 ( 1) <20 <R3 <16 ( 1. 9 ( 17 <23 <2! <10 <29 <AB <29 ( 36 <30 I-131 results are corrected for decay to sample stop date. ** Sampling date$ be ffound Table C-6. *** Results by Te]edyne Isotopes.
ll) High LLD due to sample volume. 2) High uncertainty due to low samp]e volume. Result not included any averages. No results due to sampiing assembly. 
.. ...... .. _* ...
... '_.: ._ * . ..:..:.. .. _ ' .. * **--" ****-"' ... ,; '. * .,.., * *: o >'
* M,o/ ... i-. *"*' ... .. .. * .... :.:. *. "***-*** . , .. I. *I :) i l ., ! *l TABLE C-6 i ' i . j 1986 SAMPLING DATES FOR AIR SAMPLES I l. 1
* STATION ID :1 MONTH zsz 6Sl 601 1001 16El lfl ZFZ 3H3 JANUARY lZ-30-86 lZ-30-86 lZ-30-86 JZ-31:-86 lZ-31-86 lZ-30-86 lZ-30-86 12-30-86 "i ! to to to to to to to to J Ql-06-86 01-06-86 01-06-86 01-06-86 01-06-86 01-06-86 01-06-86 01-06:...86 I i 01-06-86 01-06-86 01-06-86 01-06-86 01-06-86 01-06-86 01-06-86 . 01-06-86 i to to to to to to to to I 01-13-86 01-13-86 01-13-86 01-14-86 01-14-86 01-13-86 01-13-86 01-13-86 ! 01-13-86 01-13-86 01-13-86 01-14-86 01-14-86 01-13-86 01-13-86 01-13-86 . i *.] to to to to to to to to 01-14-86*
01-Z0-86 01-Z0-86 01-Zl-86 01-21-86 01-20-86 01-20-86 01-20-86 I .J 1 01-20-86 01-20-86 01-20-86 01-Zl-86 Ol-Zl-86 01-20-86 01-20-86 01-20-86 I to to to to to to to to I 01-27-86 01-27-86 01-27-86 01-28-86 01-28-86 01-27-86 01-27-86 01-27-86 ' . : *! . *. *1 01-27-86 01-27-86 01-27-86 01-28-86 01-28-86 01-27-86 01-27-86 01-27-86 . . *) ..;z .j (\) to to to to to to to to r 02-03-86 02-03-86 02-03-86 02-03-86 02-03-86 OZ-03-86 02-03-86 02-01-86*
.* .. i FEBRUARY 02-03-86 OZ-03-86 OZ-03-86 02-03-86 02-03-86 02-03-86 02-03-86 02-03-86 .i to to to to to to to to ..I OZ-10-86 02-10-86 OZ-10-86 OZ-11-86 02-11-86 OZ-10-86 02-10-86 02-10-86 ., *, J l !>2-10-86 02-10-86 02-10-86 02-11-86 02-10-86 02-10-86 02..:10-86 . *,I 1 to to to to to to to to .* . , 02-18-86 02-18-86 02-18-86 OZ-19-86 02-19-86 02-18-86 02-18-86 02-18-86 .. I .I OZ-18-86 OZ-18-86 02-18-86 02-19-86 02-18-86 02-18-86 02-18-86 '.I I to to to to to to to th ; . ( .. . : 02-24-86 02-24-86 02-24-86 02-25-86 02-24-86 02-24-86 02-24-86 j .. . 02-24-86 02-24-86 02-24-86 02-26-86 02-25-86 02-24-86 02-24-86 02-24-86 I *:i to to to
* to to to to to 03-03-86 03-03-86 03-03-86 03-03-86 "03-03-86 03-03-86 03-03-86 03-03-86 .;j MARCH 03-03-86 03-03-86 03-03-86 03-03-86 03-03-86 03-03-86 03-03-86 03-03-86 .. 1 to to to to to to to ta* * *1 03-10-86 03-10-86 03-10-86 03-11-86 03-11-86 03-10-86 03-10-86 03-10-86 *;;'J :-:*" :; 03-10-86 03-10-86 03-10-86 03-11-86 03-11-86 03-10-86 03-10-86
., .l . i
* to .to to to to to to to ::,I 03-17-86 03-17-86 03-17-86 _03-1. 03-18-86 03-17-86 03-17-86 OJ:.. lJ-86 *1 .. ; . j '"! 
.. . , . !, ... : ... ,
... . ...:..:--...:, ....
.. * ... : ...
.* .:i. .... *.-....
*.
.. . <.** J ,. .* "" .*.* ( " ; ..... ' i I I I. TABLE C-6 (cont'd) 1986 SAMPLING DATES FOR AIR SAMPLES STATION ID MON!H 252 651 6Dl 1001 16El lf! 2F2 3H3 MA!ICH 03-17-86 03-U-86 03-17-86 H-nll-86 03-18-86 03-17--86 03-17-86 03-17-86 to to to to to to to to @3-24-86 03-24-86 03-24-86 03-25-86 03-26-86 03-24-86 03-24-86 03-24-86 03-24-86 03-24"-86 03-24-86 03-26-86 03-26-86 03-24-86 03-2'4-86 03-24.-86 to to to h to to to to 03-3R-86 031-31-86 03-31-86 04-01-86*
04-01-86 03-31-86 03-31-86 03-31-86 APIUL <<>3-:U-86 03-31-86 03-31-86 04-01-86 04-01-86 03-31-86 03-31:-86 03-31-:86 to to to to to to to to 04-07-86 04-01'-86 04-07-86 04-01-86 04-07-86 04-01'-86 04-07-86 04-07-86 04-07-86 04-07-86 04-07-86 04-07-86 <<>4-0?-86 04-07-86' 04-07-86 Q:.o to to to to to to to o4-a4-86 ID4-!C-86 04-14-86 04-16-86 04-16-86 04-14-86 04-14-86 04-14-86 04-14-86 04-14-86 04-14-86 04-16-1116 04-16-86 04-14-86 04-14-86 04-14-86 to to to to to to to to 04-21-86 04-21-86 04-21-86 04-U-86 04-21-86 04-21-86 04-18-86*
04-21-86 04-U-86 04-21-86 04-21-86 04-21-86 04-21-86 04-21-86 04-21-86 04-2*i-86 to to to
* to to to to to 04-28-86 04-28-86 04-28-86 04-29-86 04-29-86 04-2!1-86 04-28-86 04-28-86 MAY 04-28-86 04-28-86 04-28-86 04-29-86 04-29-86 04-28-86 04-28-86 04-28-86 to ta to to to to to to Oli-06-86 Oli-05-86 06-06-86 06-0li-86 06-06-86 06-06-86 06-06-86 06-06-86 06-06-86 l!lli-06-86 06-06-86 Oli-06-86 06-0!i-86 06-06-86 O!i-O!i-86 O!i-06-86 to to to to to to to to Oli-12-86 06-12-86 06-12-86 06-12-86 06-12-86 Ol:i-12-86 06-12-86 05-12-86 \ 06-12-86 Olii-ll2-86 O!i-12-86 06-12-86 O!i-12-86 06-12-86 i 06-12-86 06-12-86 . to to to to to to to to 06-19-86 06-19-86 06-14-86*
06-19-86 O!i-19-86 06-19-86 06-19-86 06-19-86 ' 06-19-86 06-19-86 Oli-H-86 06-19-86 Oli-19-86 06-19-ij6 06-19-Bfi to to to to to t.9 t9 tq Oli-27-86 06-27-86 06-27-86 Oli-27-86 Oli-U-86 Ofi-i1-116 Oli-Z7-86 06-Z?-86 06-U-86 C16-n-e6 (lij,.iHlfi to to to to to to to ' 06-02-86 06-0Z-86 06-02-86 06-02-86 06-28-86*
06-02-86 06-02-86 06-02-86 I 1 
**::_;
.. =.! ** :.&.:.. ... h ... .... * ...........
.. ;... ... -* * ., . ....:...J.-'
.. *.-
,;, .... ***.!; **-** ' ..... ,.
**-.. , .. ****-** . *--... *-* ..... l \. I j I I .i j TABLE C-6 (cont'd) I :1 1986 SAMPLING FOR AIR SAMPLES .j I 1* j STATION ID ! MONTH 252 601 1001 16El lfl 2F2 3H3 06-02-86 06-02-86 06-02-86 i" JUNE 06-02-86 06-02-86 06-02-86 06-02-86 06-03-86 to to to to to to to to r. 06-09-86 06-09-86 06-09-86 06-09-86 06-09-86 . 06-09-86 06-09-86 06-09-86 ) *1 06-09-86 06-09-86 06-09-86 06-09-86 06-09-86 06-09-86.
06-09-86 i 1 to to to to to to to to -I 06-16-86 06-16-86 06-16-86 06-16-86 06-16-86 06-16-86 06-16-86 06-16-86 I J 06-16-86 06-16-86 06-16-86 06-16-86 06-16-86 06-16-86 06-16-86 06-16-86 i to to to to to to to to ' i 06-23-86 06-23-86 06-23-86 06-23-86 06-23-86 06-23-86 06-23-86 06-23-86 i 06-23-86 '.j 06-23-86 06-23-86 06-23-86 06-23-86 06-23-86 06-23-86 ! to to to to to to . to to I 06-30-86 06-30-86 06-30-86 07-01-86 07-01-86 06-30-86 06-30-86 06-30-86 I JULY 06-30-86 06-30-86 06-30-86 07-01-86 07-01-86 06-30-86 06-30-86 ' 06-30-86 . ..,, I to to to to to to to to . . t . -3 07-07-86 07-07-86.
07-07-86 07-07-86 07-07-86 07-07-86 07-07-86 07-07-86 I j 07-07-86 07-07-86 07-07-86 07-07-86 07-07-86 07-07-86 07-07-86 07-07-86 j to to to to to to to to **I 07-14-86 07-16-86 07-16-86 07-16-86 07-16-86 07-14-86 07-16-86 07-14-86 .j 07-14-86 07-16-86.
07-16-86 07-16-86 07-16-86 07-14-86 07-16-86 07-14-86 '1 to to to to to . to to *to I 07-21-86 07-21-86 07-21-86 07-21-86 07-21-86 07-21-86 07-21-86 07-21-86 .. , i i 07-21-86 07-21-86 07-21-86 07-21-86 07-21-86 07-21-86 07-21-86 07-21-86 1 to to to to to to to to I 07-28-86 07-28-86 07-28-86 07-29-86 07-29-86 07-28-86 07-28-86 07-28-86 l .*I AUGUST 07-28-86 07-28-86 07-28-86 07-29-86 07-29-86 07-28-86 07-28-86 07-28-86 j i to
* to to to to to to to .. ' 08-04-86 08-04-86 08-04-86 08-04-86 08-04-86 08-04-86 08-04-86 08-04-86. . . I 08-04-86 08-04-86 08-04-86 08-04-86 08-04-86 08--04-86 08-04-86 08-04-86 to to to to to to to to _, 08-11-86 08-11-:86 08-11-86 08-12-86 08-12-86 08-11-86 08-11-86 08-11-86 1 . ' .. t 08-11-86 08-11-86 08-12-86 08-12-86*'*
08-11-86 08-11-86 .... i *:' .. *.**1 to to to to to to to ***\ 08-19-86 08-19-86 08-19-86 08-19-86 08-19-86 08-19-86 08-18-86 * . :1 ... *<1! *. j ., ;,j :--;* --------------
;, ',J* ,'.' *. *-** .. ..... ...... ** .. :: .. ..; ;. * .......* *:.' ... TABLE C-6 (cont'd) 1986 SAMPLING DATES fOR AIR SAMPLES S'H"ATION ID . ', flCOtHH 252. 6Sl 6Dl lODl l6El lfl 2.fZ 3H3 AUGUST 08-19-86 08:..19-86 08-19-86 08-H-86 08-19-86 08-19-86 08-19-86 08-18-86 to to to to to to to to 08-2.6-86 08-26-86 08-26-86 08-26-86 08-26-86 08-26-86 08-26-86 08-2.6-86 08-2.ii-86 08-26-86 08-2.6-86 08-26-86 08-2.6-86 08-26-86.
08-2.6-86 08-2.6-86 Q:o to to to to to to to 09-02-86 09-02-86 09-02-86 09-03-86 09-03-86 09-02-86 09-02-86 09-02.-86 SEPTEMBER 09-02-86 09-()2-86 09-0Z-86 09-03-86 09-03-86 09-02.-86 09-02.-86 . 09-02.-86 to to to to to to to to 09-08-86 09-08-86 09-08-86 09-08-86 09-08-86 09-08-86 09-08-86 09-08-86 09-08-86 09-08-86 09-08-86 09-08-86 09-08-86 09-08-86 09-08-86 to to to to to to to to 09-16-86 09-16-86 09-16-86 09-16-86 09-16-86 09-16-86 09-16-86 09-16-86 09-16-86 09-16-86 09-16-86 09-16-86 09-16-86 09-16-86 09-16-86 IO!I to to to to to to to to 09-22-86 09-22-86 09-2.2-86
<<19-22-86 09-2.2.-86 09-22-86 09-22.-86 09-2.2.-86 09-22-86 09-22-86 09-22.1-86 09-22-86 09-2.2.-86 09-2.Z-86 09-22.-86 09-22.-86 to to to to to to to to 09-29-86 09-29-86 09-29-86 09-30-86 09-30-86 09-29-86 09-29-86 . 09-2.9-86 OCTOBER 09-29-86 09-29-86 09-2.9-86 09-30-86 09-30-86 09-29-86 09-2.9-86 09-29-86 to to to to to to to to 10-06-86 l0-06-86 10-06-86 i0-06-86 10-06-86 10-06-86 10-06-86 10-06-86 10-06-86 no-06-86 10-06-86 10-06-86 10-06-86 10-06-86 10-06-86 10-06-86 to to to to to to to to 10-14-86 10-14-86 10-14-86 10-16-86 10-16-86 10-14-86 10-14-86 10-14-86 10-14-86 . 10-14-86 10-14-86 10-16-86 10-16-86 10-14-86 . 10-14-86 10-14-86 to .to to to to to lo t'o 10-20-86 10-20-86 10-20-86 !0-20-Si>
10-20-86 A0-20-116 10-20-96 lO-i0-.1i6 tO-tlHl6 HH!!l-8!>
U!-Z0-86 10-Z0-86 10-20-86 10-Z0-86 10-20-86 ! to to to to to to to I to=-n=s6 H)-U:-@li 10-28-86 10-27-86 10-27-86 10-27-86 ' RG-27-86 Ull-27-86 i0-27-86 10-28-86 10-28-86 10-27-86 10-27-86 10-27-86 to to to to to to to to 11-03-86 U-031-86 11-03-86 H-03-86 11-03'-86 11-03-86 11-03-86 11-03-86 I .j j *I *1 I l J :j j I l --1 * :\ . :*J1 **. . *-1 *.:1 **; J *' ; 'i . I i I I l. 1 I l i . *. :j "{ I l . I ". -*-**-**-*---*--*--*-
*-* *. _, .... :_. TABLE C-6 (cont'd) 1986 SAMPLING DATES FOR AIR SAMPLES STATION ID MONTH 252 651 6Dl 16El 11-03-86 11-03-86 11-03-86 11-03-86 11-03-86 to to to to to 11-10-86 11-10-86 11-10-86 11-10-86 11-10-86 NOVEMBER 11-10-86 11-10-86 11-10-86 . 11-10-86 to to to to to 11-17-86 11-17-86 11-17-86 11-17-86
* 11-17-86 11-17-86 11-17-86 11-17-86 11-17-86 11-17-86 to to to to to 11-24-86 11-24-86 11-24-86 11-24-86 11-24-86 11-24-86 11-24-86 11-24-86 11-24-86 11-24-86 to to to to to 11-24:..86*
12-01-86 12-01-86 12-02-86 12-02-86 12-01-86 12-01-86 12-01-86 12-02-86 12-02-86 to to to to to 12-08-86.
12-08-86 12-08-86 12-09-86 12-09-86 DECEMBER 12-08-86 12-08-86 12-08-86 12-09-86 12-09-86 to to to to to 12-16-86 12-16-86 12-16-86 12-16-86 12-16-86 12:..16-86 12-16-86 12-16-86 12-16-86 12-16-86 to to to to to 12-22-86 12-22-86 12-16-86*
12-22-86 12-22-86 12-22-86 12-22-86 12-22-86 12-22-86 12-22-86 to to to to to 12-29-86 12-29-86 12-29-86 12-30-86 lZ-30-86 *Reduced sampling period due to instrument malfunction.
** Start date was delayed by one day due to instrument malfunction at time of startup. This required replacement of the air sampler. lfl 2F2 3H3 11-03-86 11-03-86 11-03-86 to to to 11-10-86 11-10-86 11-10-'86 11-:10-86 11-10-86 11-10-86 to to to 11-17-86 11-17-86 11-17-86 11-17-86 11-17-86 11-17-86 to to to 11-24-86 11-24-86 11-24-86 11-24-86 11-24-86 11-24-86 to to to 12-01-86 12-01-86 12-01-86 12-01-86 12-01-86 12-01-86 to to to 12-08-86 12-08-86 12-03-86*
12-08-86 12-08-86 12-08-86 to to to
* 12-16-86 12-16-86 12-15-86 12-16-86 12-16-86 12-Ui-86 to to to
* 12-22-86 12-22-86 12-22-86 12-22-86 12-22-86 12-22-86 to to to 12-29-86 12-29-86 12-29-86
* 
* * . *, . .. .. '! .' . .. .i *' **t .. *.**I w * ** ' .. . . :.. ' ._. ;: * .. *' .. : .. I * ! ; * 'i : .'. ;;.::! .. * ' '._; . f .. -. ; .*
-TABLE C-6 1986 CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMITTERS, AND TRITIUM IN PRECIPITATION STATION ID: SA-RWA-2F2 Results in Units of pCi/L +/- 2 sigma COLLECTION PERIOD ALPHA BETA TRI TI OM 12-31-85 to 01-27-86 <l. 6 <l.6 <140 01-27-86 to 02-25-86 <1.5 1.9+/-1.2 <130 02-25-86 to 03-31-86 <l. 6 4.4+/-1.4 <140 03-31-86 to 04-28-86 <0.3 3.7+/-0.8 <140 04-28-86 to
<0.3 lStl <140 to 07-01-86 1.J+/-Oo7 8.4:H.O <140 07-01=86 to
<l.l 3.8:!::0.8
<140 to 09-03-86 1. 2:t:l.l 12+/-1 <130 09-03-86 to 09-30-86 0.9+/-0.5 3.8+/-0.8 <140 09-30-86 to 10-27-86 <l. 2 2.2+/-0.6 <140 10-27-86 to 12-01-86 0.6+/-0.6 3.5+/-0.7 <140 12-01-86 to
<l. 7 l.9:!::0.6
<130 AVERAGE 5.2+/-8.6 77 .. **-.. ----;--.. --...-.,--;-*............-,
...........
*-*--------
.. *----**----*-**-;-....... ----.,.----*-----.. -*-**.-------
-. .. I I " i ' "" . .. ,*, .. .. ** TABLE-C-7.
* 1986 CONCENTRATIONS OF GAMMA EMITTERS*
IN PRECIPITATION STATION ID: SA-RWA-2F2 Results.in Units of pCi/L +/- 2 sigma. COLLECTION PERIOD Be-7 K-40 I-131 cs-137 Ra-226 Th-232 12-31-85 to 01.-27-860 Ol-27-86 to 02-25-86 35+/-12 <39 <2.4 <2.4 7.0+/-3.0 <7.2 02-25-86 to 03-31-86 71+/-21 <57 <4.7 " <2.9 <6.7 <12 03-31-86 to 04-28-86 64+/-15 <32 <2.6 <2.0 <4.6 <8.0 04-28-86 to 06-03-86 41+/-23 <81 7.4+/-3.5 4.8+/-3.0 <13 <21 06-03-86 to 07-01-86 54+/-13 <40 <3.4 <3.2 <6.4" <11 07-01-86 to 07-29-86 52+/-14 <42 <4.8 <3.2 <6.4: <ll 07-29-86 to 09-03-86 42+/-10 <25" <l.6 <0.8 <4.2 7.5+/-4.l 09-03-86 to 09-30-86 35+/-14 59+/-25 <3.8 <3.7 <7.7 09-30-86 to 10-27-86 36+/-12 <40 <3.4 <2.6 5.1+/-2.4 <ll 10-27-86 to 12-01-86 43+/-12 <41 <l.5 <2.l 4.8+/-2.7 <7.6 12-01-86 to 12-29-86 42+/-13 <29 <4.8 <2.0 <4.8 <7.4 AVERAGE 47+/-24
* All other gamma emitters searched for were <LLDJ typical LLDs are given in Tal:>le C-33. **Not analyzed.due to insufficient during sampling period. 78
___ .. _._. 
* : . .. . . " . ,, ' * . '. . . ....... . TABLE 1986 DIRECT RADIATION MEASUREMENTS
-QUARTERLY TLD : RESUL'.l'.S . .Rasul.ts in mrad/standard month* (.Resul.ts by Teledyne Isotopes)
JANUARY APRIL JULY OCTOBER STATION ID to to to to MARCH JUNE SEPTEMBER DECEMBER SA-IOM-2S2 5.3+/-0.3 4.4+/-0.2 5.2.:1:0.3 4.7+/-0.6 S.l:!:0.2 4.0+/-0.3 4.9:t0.3 4.2:t:0.3 5.3:!:0.3 4.3+/-0.2 5.4:t:0.2 4.6:!:0.3 SA-IDM-7Sl 6.6+/-0.7 5.6+/-0.S 6.2+/-0.4 5.6:t:0.5 SA-IOM-lOSl s.a+/-o.5 5.0:t0.3 4.8:t0.2 5.1+/-0.3 SA-IOM 00 llSl 5.0+/-0.2 S.2:t:0.3 5.2:t0.3 4.7+/-0.3 SA-IOM 00 402 5.0:1:0.2 4.9+/-0.4 6.7:t:l.8 5.1+/-0.5 SA-IDM-501 5.5+/-0.2 4.6:1:0.l 5 .4::!:0.3 4.6+/-0.3 SA-IOM-1001 5.4+/-0.4 5.0+/-0.3 5.7+/-0.5 4.8+/-0.4 SA-IDM-1401 5.4+/-0.6 4.5:1:0.2 5.5+/-0.3 4.9:1:0. 7 SA-IDM-2El 4.2:1:0.5 5.5+/-0.4 4.7+/-0.5 SA-IOM-3El 5 .2:.1:0 .4 4.4+/-0.2 5.3+/-0.3 4.5+/-0.5 SA-IDM-9El 6.3+/-0.8 5.4+/-0.3 6.2:.1:0.5 5.7+/-0.9 SA-IDM-11E2 5.9+/-0.6 5.2:1:0.7 6.3+/-0.5 5.5+/-0.7 SA-IDM-l2El 5.7+/-0.5 4.8+/-0.3 6.0+/-0.4 5.4+/-0.8 SA-IDM-13El 4.9+/-0.l 4.2+/-0.2 5.0:1:0.3
: 4. 3:t:O .4 SA-IDM-16El 5.5+/-0.2 4.8+/-0.5 5.6+/-0.3 5.0+/-0.5 SA-IOM-lFl 5.4:.l:0.5 4.3:1:0.4 5 .5:.1:0 .4 SA-IOM 00 2F2 4.5:1:0.7 3.6+/-0.3 4.4:1:0.3 3.7+/-0.3 SA-IDM-2F5 5.4+/-0.l 4.6:1:0.2 5.4+/-0.4 4.8+/-0.5 SA-IOM-2F6 5.1+/-0.2 4.4+/-0.4 5.4:1::0.4 4.8:t0.2 SA-IOM-3F2 5.Sil.2 4.2:1:0.3 4.9:!:0.2 4.1:1:0.3 SA-IOM-3F3 5.0+/-0.2 4.3:t:0.2 s.o:to.2 4.3:t:0.3 SA-IOM-5Fl 5.2:t:0.7 4.3:!:0.5 5.l+/-0.3 4.6:!:0.S SA-IDM-6Fl 4.7+/-0.3 3 .6:1:0.,l 4.6:1:0.2 3.8:!:0.3 SA-IOM-7F2 4.6:t0o2 3.4:1:0o2 4.3:1:0.2 3.5:1:0.1 SA-IOM-10F2 5.7:1:0.5 5.1+/-0.4 5.9:1:0.3 5.l.+/-0.5 SA-IOM-llFl 5.0:1:0.5 5.2:1:0.4 5.8:1:0.5 5.3:!:0.6 SA-IDM-12Fl 5.7:!:0.3 4.7+/-0.3 5.7+/-0.l 4o9:!:0.4 SA-IDM-13F2 5.3+/-0.4 4.6+/-0.4 5.4:1:0.3 4.8+/-0.4 SA-IDM-13F3 5.7+/-0.4 4.8+/-0.3 5.7:1:0.4 5.0:!:0.5 SA-IOM-13F4 5.7:1:0.2 4e6:1:0.S 5.6:1:0.3 4.9:1:0.5 SA-IOM-14F2 5.3:1:0.l 4o5:1:0.4 5.5+/-0.4 5.1:1:0.1 SA-IOM-l5F3 6.0:1:0.5
.5.2:1:0.2 6.3:1:0.4 5.4:1:0.4 SA-IDM-16F2 5.2:1:0.1 4.3:1:0.2 5.4:1:0.3 4.S:t:0.4 SA-IOM-lG3 5.8:!:0.4 5.5:1:0.8 6.4:1:0.4 5.7:1:0.4 SA-IOM-3GJ.
C 5.8:!:0.4 4.9:1:0.3 5.8:1:0.3 5.1:1:0.6 SA-IDM-lOGl C 6.l:!:0.6 s.1:1:0.s 5.9:t:O.S 5.3:t0.5 SA-IDM-16Gl C 6.l.+/-0.6 S.3:1:0.5 6.3:1:0.6 S.8+/-0.7 6.0+/-0.5 5.0+/-0.3 5.0+/-0.2 5o2:!:0.5 SA-IDM-3H3 C 5.9:!:0.S s.o:t:o.2 5.9:1:0.3 5.2:1:0.s AVERAGE 5.s:ta.9 4.6il.O 5.5:!:1.l 4.9:!:1.l Grand Average The standard month = 30.4 da.ys * (C) Control station \ 79 AVERAGE 4.9+/-0.8 4.6:tl..l 4.9:t.l.l 6.0+/-1..0 5.2+/-0.9 5.o:to.s 5 .6:t;l..6 5.0:l:l..O 5.2:!;0.8 5.1:.1:0.9 S.O:.l:l.3
.9 5.9+/-0.8 5.7+/-1.0 5.5:t:J..O 4.6+/-0.8 5.2:!:0.8
: 5. O:.l:l..l 4.0+/-0.9 s.o+/-o.a 4.9+/-0.8 4. 7+/-1..2 4.6:1:0o7 4.8:1:008 4.2+/-1.l 4.0:Uo2 5.4:1:0.8 5.5+/-0.6 5.2:!:1.0 5.0:1:0.a 5.3:!:0.9 5.2:1::J..l S.l:!:0.9 4.9:!:1.0 5.8:!:0.8 5.4:!:0.9 5.6:1:1.0 5.9+/-0.9 S.5:t:l.O 5.5:1:0.9 5.l:!::l.3
-----***,--
-.--:.,.-**-*-.
* --.-. *
*
..* --**-*-* ----. *-** ...... --..
... -...
I ' .. -*
----.... . TABLE C-9 1986 DIRECT RADIATION MEASUREMENTS
-MONTHLY TLO RESULTS Results in mrad/standard month* (Results by Teledyne Isotopes)
STATION ID ' JANUARY FEBRUARY MARCH APRIL MAY JUNE SA-IDM-2S2 5.3+/-0.3 6.6+/-0.l 5.2+/-0.4 6.6+/-1.2 6.7+/-0.8 5.6+/-0.5 SA-IDM-5Sl 5.2+/-0.4 5.9+/-0.l 4.5+/-0.2 6.2+/-0.7 5.9+/-0.6 5.0+/-1.2 SA-IDM-6S2 5.6+/-0.4 6.4+/-0.4 4.9+/-0.5 6.8+/-0.5 6.3+/-0.4 5.9+/-0.5 SA-IDM-7Sl 6.5+/-0.6 7.5+/-0.7 6.0+/-0.7 7.7+/-0.6 7.3+/-0.6 7.0+/-0.9 SA-IDM-lOSl 5.9+/-0.6 6.8+/-0.2 5.4+/-0.5 7.4+/-0.7 6.9+/-0.6 6.4+/-0.7 SA-IDM-llSl 5.2+/-0.4 6.1+/-0.3 4.7+/-0.2 6.9+/-0.4 7. 7+/-1.0 6.0+/-0.9 SA-IDM-501 5.5+/-0.5 6.1+/-0.l 5.0+/-0.5 6.6+/-0.8 6.1+/-0.4 5.8+/-0.6 SA-IDM-1001 5.7+/-0.5 6.6+/-0.3 5.3+/-0.4 7.2+/-0.6 6.9+/-0.6 6.7+/-0.7 SA-IDM-1401 5.6+/-0.4 6.6+/-0.4 5. 5+/-1. 3 6.9+/-0.5 6.9+/-0.7 6.2+/-0.7 SA-IDM-2El 5.5+/-0.3 6.2+/-0.4 4.9+/-0.5 6.6+/-0.6 6 .7+/-1.0 5.6+/-0.6 SA-IDM-3El 5.5+/-0.5 6.1+/-0.3 4.7+/-0.1 6.5+/-0.5 6.4+/-0.6 5.2+/-0.8 . ' SA-IDM-13El 5.3+/-0.8 6.2+/-0.2 4.7+/-0.3 6.5+/-0.4 5.8+/-0.7 5.9+/-0.7 Q) SA-IDM-16El 5.6+/-0.6 6.7+/-0.6 5.0+/-0.2 7.0+/-0.4 6.8+/-0.7 6.3+/-0.9 0 SA-IDM-lFl 5.7+/-0.3 6.4+/-0.6 5.1+/-0.3 6.9+/-0.6 6.5+/-0.6 6.3+/-0.8 SA-IDM-2F2 4.8+/-0.4 5.8+/-0.3 4.1+/-0.2 6.0+/-0.5 5.4+/-0.3 5.0+/-0.4 SA-IDM-2F6 5.9+/-0.6 6.6+/-0.5 5.0+/-0.6 6.8+/-0.6 5.9+/-0.5 6.0+/-0.9 SA-IDM-5Fl 5.5+/-0.6 5.9+/-0.3 4.6+/-0.3 6.5+/-0.5 6.1+/-0.4 5.6+/-0.7 SA-IDM-6Fl 5.0+/-0.3 5.7+/-0.1 (1) 5 .* 9+/-0.4 5.4+/-0.3 5.0+/-0.3 SA-IDM-7F2 4.3+/-0.3 5.4+/-0.3 3.8+/-0.3 5.5+/-0.7 5.1+/-0.4 4.5+/-0.7 SA-IDM-llFl 5.8+/-0.4 7 .0+/-1.0 5.5+/-0.5 7.4+/-0.6 7.1+/-0.9 6.5+/-0.6 SA-IDM-13F4 5.8+/-0.6 6.9+/-0.7 4.9+/-0.3 7.0+/-0.5 6.6+/-0.6 6.2+/-0.4 SA-IDM-3Gl (C) 5.5+/-0.2 6.3+/-1.0 5.3+/-0.4 7.4+/-1.5 6.8+/-0.8 6.1+/-0.4 SA-IDM-381 (C) 5.9+/-0.2 6.8+/-0.3 5.3+/-0.4 7.2+/-0.4 6.7+/-0.7 6.3+/-0.8 SA-IDM-383 (C) 6.3+/-0.6 7.4+/-0.4 5.6+/-0.3 7.6+/-0.6 7.3+/-0.6 6.6+/-1.0 AVERAGE 5.5+/-0.9 6.4+/-1.0 5. 0+/-1.0 6.8+/-1.1 6.5+/-1. 3 5.9+/-1. 2
* I:
__ -: __
.. :*,_ .... -. ..
-;*' ... : __ . : ... * "p , ** '*. ' I . . i l
* 1 TABLE C-9 (COBlt 9 d) *.*1 1986 DIRECT RADIATION MEASUREMENTS
-MONTHLY TLD RESULTS l Results in mrad/standard month* (Results by Teledyne Isotopes)
STATION ID JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER AVERAGE SA-IDH-282
-. 5.9+/-0.3 5.7+/-0.5 5.3+/-0.5 5.4+/-0.3 4.9+/-0.4 '7.1+/-0. 7 5.8+/-1.4
* 1 SA-IDH-5Sl 5.5+/-0.4 5.9+/-0.7 4.9+/-0.7 5.3+/-0.3 4.6+/-0.3 6.2+/-0.5 5.4+/-1.2 *I SA-IDH-6S2 6.1+/-0.4 5.7+/-0.4 4.9+/-0.5 6.6+/-0.6 5.9+/-L2 ! 1 SA-IDM-7Sl 7.0+/-0.8 6.9+/-0.4 6.6+/-0.8 6.5+/-0.9 5.9+/-0.7 7.7+/-1.0 6.9+/-1.2, I l SA-IDH-lOSl 6.5+/-0.6 6.5+/-0.4 5.7+/-0.5 6.4+/-0.6 5.5+/-0.3 7.6+/-0.9 6 .4+/-1.4 I SA-IDM-llSl 6.4+/-0.6 6.1+/-0.5 5.0+/-0.2 5.4+/-0.3 5.0+/-0.l 6.9+/-0.9 5.9+/-1.8 ' i SA-IDM-5Dl 4.8+/-0.4 6.5+/-0.6 5.8+/-1.l 6.2+/-0.5 6.0+/-0.7 5.5+/-0.5 5.5+/-0.5 SA-IDH-lODl 5. 7+/-1.l 6.3+/-0.5 5.8+/-0.4 6.1+/-0.5 5.3+/-0.4 6.9+/-0.6 6.2+/-1.3 SA-IDH-1401 6.8+/-0.l 6.2+/-0.3 5.7+/-0.5 6.0+/-0.8 5.2+/-0.4 6.9+/-0.6 6.2+/-1.2 SA-IDM-2El 6.0+/-0.7 6.0+/-0.3 5.5+/-0.3 5.6+/-0.5 4.9+/-0.6 6.5+/-0.9 5.8+/-1.2 SA-IDH-3El 6.0+/-0.4 5.9+/-0.5 5.1+/-0.3 5.5+/-0.3 4:8+/-0.4 6.3+/-0.5 5.?+/-1.2 SA-IDM-13El 5.9+/-0.4 5.9+/-0.4 5.2+/-0.6 5.7+/-0.4 4.8+/-0.5 6.6+/-0.6 5. 7+/-1.2 SA-IDM-16El 6.4+/-0.5 6.1+/-0.4 5.8+/-0.6 5.9+/-0.5 5.1+/-0.4 7.1+/-0.7 6.1+/-1.4 l}-<l _ SA-IDM-lFl 6.3+/-0.5 6.2+/-0.3 5.5+/-0.3 5.9+/-0.5 5.1+/-0.5 6.7+/-0.4 6.0+/-1.2 SA-IDM-2F2 5.3+/-0.2 4.7+/-0.2 4.8+/-0.2 4.2+/-0.2 5.9+/-0.3 5.1+/-1.2 SA-IDH-2F6 6.0+/-0.6 6.1+/-0.3 5.6+/-0.3 5.6+/-0.3 5.0+/-0.5 1.-uo.6 6.o'+/-L3 '! SA-IDM-5Fl 6.1+/-0.3 5.9+/-0.2 5.5+/-0.3 5.6+/-0.4 5.0+/-0.3 6.4+/-0.6 5. 7+/-1.l SA-IDM-6Fl 5.6+/-0.3 5.3+/-0.2 4.8+/-0.3 5.0+/-0.3 4.3+/-0.2 6.1+/-0.5 5. 3+/-1.0 SA-IDM-7F2 5.0+/-0.3 4.9+/-0.l 4.2+/-0.2 4.6+/-0.3 3.8+/-0.2 5.5+/-0.6 4.7+/-1.2 SA-IDM-llFl
: 6. 8+/-1. 0 6.7+/-0.4 6.2+/-0.8 6.2+/-0.5 5.6+/-0.5 7.2+/-0.8 6-5+/-1. 3 SA-IDM-13F4 6.5+/-0.4 6.1+/-0.2 5.7+/-0.4 6.0+/-0.5 5.3+/-0.4 6.9+/-0.5 6.2+/-1. 3 SA-IDM-3Gl (C) 6.7+/-0.5 6.6+/-0.7 6.1+/-0.4 6.3+/-1. 3 5.1+/-0.3 7.2+/-0.3 6. 3+/-1.4 SA-IDM-3Hl (C} 6.7+/-0.9 6.7+/-0.4 5.6+/-0.6 6.0+/-0.5 5.4+/-0.2 7_.2+/-0.5 6.3+/-1.3 ' SA-IPM-383 (C) 6.9+/-0.5 6.9+/-0.4 6.3+/-0.8 6.5+/-0.3 5.9+/-0.4 7.4+/-0.6 6. 7+/-L 3 AVERAGE 6.2+/-1.0 f).1+/-1.0 5.5:1:1.l 5.7+/-1.0 5.0+/-1.0 6.8+/-1.l Grand Ill The standard month * .3o.4 daye. <<c> Control station U) TLD missing from field Jocat!on. 
.. *_ :*. :.:--..*..... .:...
,_ ,.* .. .:..:. ,* .. -****-*. 
*'\ . ---. J . :* . '* *-.--i .. ' . ; *1 '.: * ... :.
* 1 .. ':.::*::':'.l
'**' ... i . STATION ID SA=MLK;,.,13E3 SA-MLK-5F2 SA-MLK-llF3 SA-MLK-l4Fl
{Control)
{Control)
AVERAGE TABLE C-11 1986 CONCENTRATI0NS OF STRONTIUM-89*
AVERAGE                                                                                                                                                         :ic1:1::1.2
ANrr STRONTIUM-90 IN' MILK** Results in Units of pCi/L +/- 2 sigma COLLECTION PERIOD Sr-89 07/06-07/86
* sr-89 results are corrected for decay to midpoint of collection period.
<0.9
                                                  ** Management audit analyses, not required by Technical Specifications or by specific commitments to local officials.
<0.8 08/03-04/86
:* .-~- '*
<l.5 07/05-07/86
          -~ i
<l.l 07/07-08/86
              *1
<0.8 07/06-07/86
~ *.. .:. ~ *1                                                                                                                                                                                                                  i
<0.8 07/07=08/86
.. ':.::*::':'.l                                                                                                                                                83
<0.9
          ...i
* sr-89 results are corrected for decay to midpoint of collection period. sr-90 1.9+/-0.3 l.St0.3 2.4+/-0.6 3.0+/-0.4 1.7+/-0.3 1.2+/-0.3 2.7+/-0.3 :ic1:1::1.2
          . '~
** Management audit analyses, not required by Technical Specifications or by specific commitments to local officials.
___ .,.. __ . __, ___ ., _____ ~- ---- ... ~ ------*-* --.-...-;--v----*---------*** -*-- -.-,.......... -... -.**-*.---*-~:---:--*-**--**7--*<-*:-*--*-..---*-* ,- ----- --*-*-*--*.......
83 ___ .,.. __ . __ , ___ ., _____ ----... ------*-*  
 
--.-.. .-;--v----*---------***  
TABLE C-lZ 1986 CONCENTRATIONS OF GAMMA EMITTERS* IN. MILK' Results in Units of pCi/L :1: Z sigma .*
-*---.-,. .........  
STATION ID**                                 NUCLIDE                             JANUARY                                     FEBRUARY                                           MARCH MONTHLY                                     MONTHLY                                           MONTHLY SA-MLK-13E3                                 Na-ZZ                                   <3.4                                         <3.9                                           <4.0 K-40                                 1400:1:75                                   1400:1:79                                         1400:1:98 Mn-54                                   <Z.5                                         <3.4                                           <4.0 Zn-65                                   <1.Z                                         <1.7                                           <10 I-131                                   <3.0                                         <Z.5                                           <4.7 Cs-137                                 <Z.7                                         <Z.8                                           <4.9 Ra-ZZ6                                 <5.9                                         <1.Z                                           <9.4 SA-MLK-ZF4 (1)                               Na-ZZ                                   <3.7                                         <5.6                                           <3.4 K-40                                 1400+/-74 .                                   1400+/-98                                           1400:1:76 Mn-54                                   <Z.5                                         <4.1                                           <Z.3 Zn-65                                   <5.9                                         <6.3                                           <6.9 I-131                                   <3.0                                         <3.8                                           <3.0 Cs-137                                 <Z.9                                         <4.6                                           <Z.7 Ra-ZZ6                                 <5.5                                         <7.4                                           <5.9 SA-MLK-ZF7 (2)                               Na-ZZ K-40 Mn-54 Zn-65 I-131 Cs-137 Ra-ZZ6 SA-MLK-5FZ                                   Na-2Z                                   <3.5                                         <2.Z K-40                                 1300+/-72                                     1300+/-81                                           1300:1:82
-...  
                                                                                'Mn-64                                   <2.5                                         <3.3                                           <Z.7 Zn-66                                   <5.9                                         <9.1                                           <1.8 I-131                                   <3.Z                                         <3.8                                           <0.6 Cs-137                                 <2.9                                         <2.9                                           <3.6 Ra-Z26                                 <6.2                                         <1.7                                           <5.9 SA-MLK-11F3                                   Na-22                                   <4.6                                         <4.5                                           <3.6 K-40                               1300:1:90                                   1300:!:82                                         1300+/-74 Mn-54                                   <3.2                                         <Z.O                                           <Z.3 Zn-65                                   <8.7                                         <7.3                                           <5.9 I-131-                                 <3.3                                         <0.6                                           <3.3 Cs-137                                 <3.3                                         <3.7                                           <Z.9 Ra-226                                 <6.6                                         <6.8                                           <6.Z SA-MLK-14Fl                                   Na-22                                   <Z.4                                         <3.6                                           <3.5 K-40                               1300+/-81                                     1400+/-77                                           1400:t77 Mn-54                                   <3.8                                         <2.6                                             <3.Z Zn-66                                   <9.1                                         <6.9                                             <1.8 I-131                                   <4.7                                         <3.l                                             <4.7 Cs-137                                 <3.9                                         <Z.6                                             <3.7 Ra-Z26                                 <6.1                                         <S.6                                             <7.9 SA-MLK-361                                   Na-Z2                                   <4.Z                                         <6.Z*                                           <4.9 (Control)                                     K-40                               1300+/-92                                     1300:t9Z                                         1400:1:92 Mn-64                                   <3.Z                                         <3.S                                             <3.Z Zn-65                                   <8.7                                         <8.7                                             <8.Z
,--------*-*-*--*  
    .;.*                                                                         I-131                                   <3.1                                         <3.4                                             <3.6
....... i .' .
- ,:*:j                                                                           Cs-137                                 <3.3                                         <3.5                                             <3.3 0                                                                         Ra-226                                 <7.0                                         <7.0                                             <6.6
TABLE C-lZ 1986 CONCENTRATIONS OF GAMMA EMITTERS*
    .-(                           AVERAGE                                       K-40                               1300+/-100                                   1400+/-110                                           1400:1:100 84
IN. MILK' Results in Units of pCi/L :1: Z sigma .* STATION ID** NUCLIDE JANUARY FEBRUARY MARCH MONTHLY MONTHLY MONTHLY SA-MLK-13E3 Na-ZZ <3.4 <3.9 <4.0 K-40 1400:1:75 1400:1:79 1400:1:98 Mn-54 <Z.5 <3.4 <4.0 Zn-65 <1.Z <1.7 < 10 I-131 <3.0 <Z.5 <4.7 Cs-137 <Z.7 <Z.8 <4.9 Ra-ZZ6 <5.9 <1.Z <9.4 SA-MLK-ZF4 (1) Na-ZZ <3.7 <5.6 <3.4 K-40 1400+/-74 . 1400+/-98 1400:1:76 Mn-54 <Z.5 <4.1 <Z.3 Zn-65 <5.9 <6.3 <6.9 I-131 <3.0 <3.8 <3.0 Cs-137 <Z.9 <4.6 <Z.7 Ra-ZZ6 <5.5 <7.4 <5.9 SA-MLK-ZF7 (2) Na-ZZ K-40 Mn-54 Zn-65 I-131 Cs-137 ,,:,. Ra-ZZ6 SA-MLK-5FZ Na-2Z <3.5 <2.Z K-40 1300+/-72 1300+/-81 1300:1:82  
          - ---- -----------.--,- -- *-....,--..,*-~.7*-:-*-,-~----------~.--:--**-*-****-*-**-*-*r'.*~---~-~~----~-.,,.--..v.-,-~-*- ......-*-*-*-------- *----;--*.--,~---*: * -*---- * ** *- *--~-***-* * * '* *.
'Mn-64 <2.5 <3.3 <Z.7 Zn-66 <5.9 <9.1 < 1.8 I-131 <3.Z <3.8 <0.6 Cs-137 <2.9 <2.9 <3.6 Ra-Z26 <6.2 <1.7 <5.9 SA-MLK-11F3 Na-22 <4.6 <4.5 <3.6 K-40 1300:1:90 1300:!:82 1300+/-74 Mn-54 <3.2 <Z.O <Z.3 Zn-65 <8.7 <7.3 <5.9 I-131-<3.3 <0.6 <3.3 Cs-137 <3.3 <3.7 <Z.9 Ra-226 <6.6 <6.8 <6.Z SA-MLK-14Fl Na-22 <Z.4 <3.6 <3.5 K-40 1300+/-81 1400+/-77 1400:t77 Mn-54 <3.8 <2.6 <3.Z Zn-66 <9.1 <6.9 < 1.8 I-131 <4.7 <3.l <4.7 Cs-137 <3.9 <Z.6 <3.7 Ra-Z26 <6.1 <S.6 <7.9 SA-MLK-361 Na-Z2 <4.Z <6.Z* <4.9 (Control)
 
K-40 1300+/-92 1300:t9Z 1400:1:92 Mn-64 <3.Z <3.S <3.Z Zn-65 <8.7 <8.7 <8.Z .;.* I-131 <3.1 <3.4 <3.6 -,:*:j Cs-137 <3.3 <3.5 <3.3 0 Ra-226 <7.0 <7.0 <6.6 .-( AVERAGE K-40 1300+/-100 1400+/-110 1400:1:100  
.. ; 84 ----------------.--,-
--
...... -*-*-*--------
* -*----* ** *-
* * '* *.
TABLE C-12 (cont'd.)
TABLE C-12 (cont'd.)
1986 CONCENTRATIONS OF GAMMA EMITTERS*
1986 CONCENTRATIONS OF GAMMA EMITTERS* IN MILK
IN MILK
* Results in Units of pCIJL                                 ~      2     sigm~
* Results in Units of pCIJL 2 STATION ID"'"' NUCLIDE APRIL MAY JUNE SEMI-MONTHLY SEMI-MONTHLY SEJfI-MONTHL Y SA-MLK-l3E3 Na-ZZ <4.9 <4.5 <4.6 <4.Z <4.9 <4. 5 . K-40 1400:100 1400+/-83 1300+/-76 1300+/-77 1300.:1:92 1400+/-79 Mn-54 <4.9 z. 9+/-1. 7 <2.8 < 1.8 <3.IJ <1.4 Zn-65 <8.6 <7.4  
STATION ID"'"'                 NUCLIDE                                   APRIL                                                         MAY                                               JUNE SEMI-MONTHLY                                           SEMI-MONTHLY                                             SEJfI-MONTHL Y SA-MLK-l3E3                     Na-ZZ                             <4.9                   <4.5                           <4.6                           <4.Z                     <4.9               <4. 5 .
<9.7 <7.3 <9.5 <8.3 I-131 <0.8 '<1. 9 <3. 9 13+/-Z 3.S:tZ.3 <4.4 Cs-137 <4.S <3.6 <3.6 <3.4 <l.6 <4.Z Ra-ZZ6 <8.6 <7.0 <7.4 <S.O <7.0 <6.Z. SA-MLK-Zf4 Na-ZZ <6.Z <4.4 <4.8 <4.6 <3.1 <4.6 K-40 1400:1:99 1400+/-77 1400:1:99 1400+/-92 1400+/-77 1400:1:93 Mn-54 <3.8 <LB <4.4 <3.5 <Z.5 <3.l . Zn-65 <11 <6.9 <8.8 <8.7 <6..6 <8;z I-131. <Z.3 <3.4 <3.5 3Z.t3 <l.5 <4.0 Cs-137 <4.Z <4.2 <3.0 <3.8 g <3.6 Ra-2Z6 <9.Z <8.3 <7.9 <7.0 <5.9 <6.Z SA-MLK-ZF7 Na-2Z K-40 Mn-54 Zn-65 I-131 Cs-137 Ra-Z26 SA-MLK-6FZ Na-ZZ <2.8 <4.5 <4.0 4.6:1:2.3 d .* 6 <3.6 K-40 1ZOO:t74 1300:1:96 1300+/-74 13Cl0:1:76 1200:s:94 1300:t7Z Mn-54 <2.9 <3.8 <Z.9 <3.S <4!.Q <2.3 Zn-65 <7.D <U <6.4 <6.2 <l*.a <6.7 I-131 * <3.D <3.7 <3.Z 49:!:4 7.M.T <3.4 C:s-137 <3.0 <4.7 <3.7 <3.6 5.W.4* 3.9:1.6 Ra-2Z6 <7.6 <6.6 <7.7 <7.7 <3 * .0i <6.Z SA-MLK-l1F3 Na-2Z <1.D <4.9 <4.8 <4.1 <t.3-<3. l K-40 1400+/-77 1400:t9Z 1400:t97 1300+/-83 1ZOO:t:75*
K-40                         1400:100                 1400+/-83                       1300+/-76                       1300+/-77                     1300.:1:92       1400+/-79 Mn-54                           <4.9                 z. 9+/-1. 7                         <2.8                           <1.8                     <3.IJ             <1.4 Zn-65                           <8.6                     <7.4                           <9.7                           <7.3                     <9.5               <8.3 I-131                           <0.8                   '<1. 9                           <3. 9                           13+/-Z                   3.S:tZ.3             <4.4 Cs-137                           <4.S                     <3.6                           <3.6                           <3.4                     <l.6               <4.Z Ra-ZZ6                           <8.6                     <7.0                           <7.4                           <S.O                     <7.0               <6.Z.
1300:1:82 Mn-54 <Z.3 <3.1 <4.6 < 1. 9 <l.3 <3.l Zn-65 <9.1 <8.7 <9.2 11:1:6 <3,7 <8.l I-131 <3.9 <3.7 <3.5 24+/-3 <4.Z <3.0 Cs-137 <2.3 <3.Z <4.3 <3.8 <l.8, <3.3 Ra-ZZ6 <6.3 <7.4 <7.8 <6.7 <1.L <7.l SA-MLK-14F1 Na-2Z <3.8 <5.1 < 1.2 <1.6 <l.7 <4.9 K-40 1300+/-94 1300:t96 1300+/-83 1300:1:95 140G.t76-1:400:t97  
SA-MLK-Zf4                     Na-ZZ                           <6.Z                     <4.4                           <4.8                           <4.6                       <3.1               <4.6 K-40                         1400:1:99               1400+/-77                       1400:1:99                       1400+/-92                     1400+/-77         1400:1:93 Mn-54                           <3.8                     <LB                           <4.4                             <3.5                     <Z.5               <3.l
*,,..., Mn-54 <1.1 <3.6 <2.8 <3.8 <Z.l'.t <3.9 Zn-611 <6.7 <5.0 <4,7 <5.4 <1.Z (, lCI I-131. <4.4 <3.2 <2,8 26:!:4 4.  
                                                                    . Zn-65                           <11                       <6.9                         <8.8                           <8.7                     <6..6               <8;z I-131.                           <Z.3                     <3.4                         <3.5                           3Z.t3                     <l.5               <4.0 Cs-137                           <4.Z                   <4.2                           <3.0                           <3.8                       ~.z. g             <3.6 Ra-2Z6                           <9.Z                   <8.3                           <7.9                           <7.0                       <5.9               <6.Z SA-MLK-ZF7                       Na-2Z K-40 Mn-54 Zn-65 I-131 Cs-137 Ra-Z26 SA-MLK-6FZ                     Na-ZZ                             <2.8                   <4.5                           <4.0                         4.6:1:2.3                   d .* 6             <3.6 K-40                         1ZOO:t74                 1300:1:96                     1300+/-74                       13Cl0:1:76                   1200:s:94       1300:t7Z Mn-54                             <2.9                   <3.8                           <Z.9                           <3.S                     <4!.Q             <2.3 Zn-65                             <7.D                 <U                               <6.4                           <6.2                     <l*.a             <6.7 I-131 *                         <3.D                     <3.7                           <3.Z                           49:!:4                   7.M.T               <3.4 C:s-137                         <3.0                     <4.7                         <3.7                           <3.6                     5.W.4*           3.9:1.6 Ra-2Z6                           <7.6                     <6.6                         <7.7                           <7.7                       <3* .0i           <6.Z SA-MLK- l1F3                   Na-2Z                           <1.D                     <4.9                         <4.8                           <4.1                       <t.3-             <3. l K-40                         1400+/-77                 1400:t9Z                     1400:t97                     1300+/-83                       1ZOO:t:75*     1300:1:82 Mn-54                           <Z.3                     <3.1                         <4.6                           <1. 9                     <l.3               <3.l Zn-65                           <9.1                     <8.7                         <9.2                           11:1:6                     <3,7               <8.l I-131                           <3.9                     <3.7                         <3.5                           24+/-3                       <4.Z               <3.0 Cs-137                           <2.3                     <3.Z                         <4.3                           <3.8                       <l.8,             <3.3 Ra-ZZ6                           <6.3                   <7.4                           <7.8                           <6.7                       <1.L               <7.l SA-MLK-14F1                     Na-2Z                           <3.8                   <5.1                           <1.2                           <1.6                       <l.7               <4.9 K-40                         1300+/-94                 1300:t96                     1300+/-83                       1300:1:95                   140G.t76-       1:400:t97 Mn-54                           <1.1                   <3.6                           <2.8                           <3.8                       <Z.l'.t           <3.9 Zn-611                           <6.7                   <5.0                           <4,7                           <5.4                       <1.Z           (, lCI I-131.                           <4.4                   <3.2                           <2,8                           26:!:4                   4. 7~:1:.!Jl        <4.9
<4.9 -Cs-137 <Z.G <3.1 .. <3.8 . <4.1 3.hl.T <4.l -..... Ra-226 <8.1 <8.8 7.3:!:4.3  
        ..                                                          Cs-137                           <Z.G                   <3.1                           <3.8                         . <4.1                     3.hl.T               <4.l
<7,9 4.4:t.Z. 8< <.8.2 ,',"> ::! SA-MLK-3Gl Na-ZZ (Control)
      - .....                                                         Ra-226                           <8.1                   <8.8                       7.3:!:4.3                         <7,9                     4.4:t.Z. 8<         <.8.2
K-40 :: Mn-54 <4.8 <3.5 <4.8 <5.5 <4.7: <4.8 140Cl:!:93 1400:1:74 140Cl:1:82 14C!O:t97 1300:!:&1.
      ,',">     ::!                   SA-MLK-3Gl                     Na-ZZ                             <4.8                   <3.5                           <4.8                           <5.5                       <4.7:             <4.8 (Control)                      K-40                        140Cl:!:93               1400:1:74                     140Cl:1:82                     14C!O:t97                   1300:!:&1.       ll.4ll0:1:93
ll.4ll0:1:93  
::                                                  Mn-54                            <3.5                   <2.6                           <2.9                           <3.l                     <C.Z*               <3.7
<3.5 <2.6 <2.9 <3.l <C.Z* <3.7 -. *:; Zn-65 . . ' X-131. Cs-137 .. ... ,; Ra-ZZ.6 <8.i <6.7 <4.8 <11
          -. *:;                                                     Zn-65                             <8.i                    <6.7                          <4.8                        <11                          <8~&.               <.i,4
<.i,4 <4,1 <3.4 <4.0 65:t5 7.4t-.L& ,3,3 <-3.8 <Z.9 <Z.7 <4.2 <4.l ,3,9 <7.7 !i.!i:tZ.9  
    . . ' :~                                                          X-131.                           <4,1                    <3.4                          <4.0                          65:t5                     7.4t-.L&             ,3,3
<7,Q <!LB di.i t6.6 .. AVERAGE IC-40 ", . 1400:1:170 1400:d00 1400:1:110 1.300:1:100 1:.100:18@
    ~
Jl4".CtO:i:100 . ; ! ** ! i .: . .;' ;' .. { '-.;.J.";1 . . . *' . * -... :* rt . . *"---*-----*
Cs-137                            <-3.8                   <Z.9                           <Z.7                           <4.2                       <4.l               ,3,9
..
                  ,;                                                Ra-ZZ.6                          <7.7                 !i.!i:tZ.9                       <7,Q                           <!LB                       di.i               t6.6
**-*-****  
              ..                     AVERAGE                         IC-40                       1400:1:170             1400:d00                       1400:1:110                   1.300:1:100                   1:.100:18@       Jl4".CtO:i:100
*  
            ",    .-~
----..*--*-
.: .~:  .;'   ;' ..
-;-**--..-:-* -.--.-** ----.:*******
i
,":  
{
-. -**-*.** ,. ** .. --*
'-.;.J.";1
* TABLE C-lZ (Cont'd;)
  ..     .*' .~";
* . 1986 CONCENTRATIONS*
* -... :* rt           .
OF GAMMA .EMITTERS*
                              -~*--,*--~..-.,-...-.~-~:---,---*-*--* **-*-**** ---:*r--~- * --**--:"'~*--*-.---_--;***-:-.- ----..*--*- -;-**-- ..-:-* -.- -.-** ----.:******* ,": ***~  -. -**- *.** ,. ** .. --* *
IN. MILK Results in Units of*pCi/L :1: Z sigma STATION ID** NUCLIDE JULY AUGUST SEPTEMBER SEMI-MONTHLY SEMI-MONTHLY SEMI-MONTHLY SA-MLK-13E3 Na-ZZ <3.5 <5.0 <4.9 <3.0 <Z.1 <3.3 K-40 1400:1:75 1500+/-97 1400+/-96 1400:1:85 1400:1:78 1400:1:96 Mn-54 <Z.6 <3.8 <Z.8 <0.8 <0.7 <4.4 Zn-65 <5.4 <11 <8.0 <Z.1 <3.6 <9.7 I-131 <3.6 <3.3 <4.0 <Z.9 <3.1 <Z.8 Cs-137 <Z.7 <4.5 <3.9 <4.0 . 3. 7+/-Z.O <4.0 Ra-226 <5.9 <8.4
 
<6.6 <6.0 <8.8 <8.4 SA-MLK-ZF4 Na-ZZ <4.8 <3.7 <Z.9 <5.4 K-40 1300:1:92 1400+/-75. 1400+/-96 1500:1:96 Mn-54 <3.0 <Z.5 <4.1 <3.0 Zn-65 <9.5 <5.9 <9.0 <9.7 I-131 <4.0 <3.4 <0.7 <3.8 Cs-137 <3.8 <3.0 <4.5 <3.3 Ra-2Z6 <7.0 <5.5 <8.0 <7.0 SA-MLK-ZF7 Na-ZZ --<3.7 <3.5 <4.5 <Z.6 K-40 --1400:1:74 1300+/-73 1400+/-78 1400:!:78 Mn-54 --<Z.6 <Z.5 <Z.6 <4.3 Zn-65 --<6.7 <6.9 <8.1 <3.5 I-131 --<3.Z <3.Z <3.Z <Z.3 Cs-137 --<3.Z <Z.7 <3.2 <3.7 Ra-2Z6 --5.l:t:Z.8  
~
<5.5 <8.1 *<8.7. SA-MLK-5F2 Na-22 <3.9 <4.9 <6.4 <3.Z <1.6 <3.9 K-40 1300:1:77 1300:t:92  
TABLE C-lZ (Cont'd;)
.1300:1:95  
1986 CONCENTRATIONS* OF GAMMA .EMITTERS* IN. MILK Results in Units of*pCi/L :1: Z sigma STATION ID**    NUCLIDE                JULY                        AUGUST                                          SEPTEMBER SEMI-MONTHLY                  SEMI-MONTHLY                                      SEMI-MONTHLY SA-MLK-13E3    Na-ZZ          <3.5          <5.0            <4.9              <3.0                           <Z.1                  <3.3 K-40        1400:1:75      1500+/-97        1400+/-96          1400:1:85                      1400:1:78                1400:1:96 Mn-54          <Z.6           <3.8            <Z.8              <0.8                            <0.7                  <4.4 Zn-65          <5.4         <11              <8.0             <Z.1                            <3.6                  <9.7 I-131          <3.6          <3.3            <4.0             <Z.9                           <3.1                  <Z.8 Cs-137        <Z.7          <4.5            <3.9              <4.0                      . 3. 7+/-Z.O                  <4.0 Ra-226        <5.9           <8.4           <6.6              <6.0                           <8.8                  <8.4 SA-MLK-ZF4      Na-ZZ          <4.8          <3.7            <Z.9             <5.4 K-40        1300:1:92      1400+/-75.       1400+/-96        1500:1:96 Mn-54          <3.0          <Z.5            <4.1              <3.0 Zn-65          <9.5           <5.9            <9.0             <9.7 I-131          <4.0           <3.4            <0.7              <3.8 Cs-137        <3.8            <3.0            <4.5             <3.3 Ra-2Z6        <7.0          <5.5           <8.0              <7.0 SA-MLK-ZF7      Na-ZZ                                        <3.7             <3.5                           <4.5                  <Z.6 K-40                                      1400:1:74      1300+/-73                        1400+/-78                1400:!:78 Mn-54                                        <Z.6              <Z.5                            <Z.6                  <4.3 Zn-65                                        <6.7              <6.9                            <8.1                  <3.5 I-131 Cs-137 Ra-2Z6           -              --
.1300:1:72.
                                                                        <3.Z
1ZOO:t91 1ZOO:t7 Mn-54 <0.7 <3.1 <3.9  
                                                                        <3.Z 5.l:t:Z.8
<Z.Z <2.0 <LG Zn-65 <5.5 <8.2 <7.3 <6.4 <lZ <Z.l I-131 <4.1 <3.4 <4.3 <3.Z <Z.3 <4.6 Cs-137 <4.7 <3.9 <3.8 <Z.9 <5.1 <3.8 Ra-226 <7.1 <7.0 <7.Z <5.9 <7.3 <7.7 SA-MLK-llF 3 Na-22 <6.3 <3.Z <6.0 <5.0 <5.9 <4.4 K-40 1500:1:98 1300:1:78  
                                                                                          <3.Z
.1400+/-98 1500+/-100 1300:1:96 1300:1:93 Mn-54 <3.6 <3.1 <Z.9 <3.Z <3.3 <3.1 Zn-65 <14 <9.5 <4.7 <9.0 <8.Z <8.5 I-131 <4.6 <0.6 <4.5 <4.7 <0.8 <3.8 cs..:137 <4.8 <4.0 <3.0 <3.7 <4.4 <3.6 Ra-226 <6.8 <7.3 <8.3 <8.Z <8.Z <6.6 SA-MLK-14Fl Na-22 <5.5 <4.8 <4.1 <3.9 <3.5 <3.3 IC-40 1400:1:80 1400:1:97 1400:1:77 1400+/-78 1400+/-75 1300:1:82 Mn-54 <3.3* <1.8 <3.1 <1.7 <Z.3 <3.1 Zn-65 <9.4 <11 <1.8 <9.3 <6.4  
                                                                                          <Z.7
<8.8 I-131 <Z.l <3.7 <3.7 <4.4 <3.Z <3.6 Cs-137 <3.6 <4.0 <3.7 <Z.9 <2.7 <3.7 Ra.:226 <8.0 <7.5 <6.3 <8. 7 ' <6.Z <6.9. SA-MLK-3Gl Na-22 <3.9* <Z.9 <4.6 <4.5 <3.9 (3) (Control)
                                                                                          <5.5
IC-40 1300:1:73 1400:1:84 1300+/-83 1100:1:86 1300:1:92  
                                                                                                                          <3.Z
**' Mn-54 <Z.5 <2.4 <Z.Z <3.2 <3.5 Zn-65 <6.9 <8.6 <6.3 <7.7 <9.0 I-131 <3.0 <3.7 <3.3 <3.3 <3.7 Cs-137 <Z.9 <3.Z <3.7 <3.8 <3.5 * *,! Ra-226 <5.5 <7.5 <5.8 <6.6  
                                                                                                                          <3.2
<7.0 " AVERAGE K-40 1400:1:160 1400:1:150 1400:1:100 1400:t:Z80 1300:1:160 1300:!:170  
                                                                                                                          <8.1
; *' * ' -86 .--------*---. -;---:-..
                                                                                                                                                <Z.3
-----*-*-*-*--, -, __ --*---*--** 
                                                                                                                                                <3.7
... 'J -* *.* . *.' ' ..... TABLE C-lZ (cont'd.)
                                                                                                                                                *<8.7.
SA-MLK-5F2     Na-22         <3.9           <4.9           <6.4               <3.Z                           <1.6                 <3.9 K-40       1300:1:77     1300:t:92     .1300:1:95     .1300:1:72.                     1ZOO:t91               1ZOO:t7 Mn-54         <0.7           <3.1           <3.9               <Z.Z                           <2.0                 <LG Zn-65         <5.5           <8.2           <7.3               <6.4                         <lZ                     <Z.l I-131         <4.1           <3.4           <4.3               <3.Z                           <Z.3                   <4.6 Cs-137       <4.7           <3.9           <3.8               <Z.9                           <5.1                 <3.8 Ra-226       <7.1           <7.0           <7.Z               <5.9                           <7.3                 <7.7 SA-MLK- llF 3   Na-22         <6.3           <3.Z           <6.0               <5.0                           <5.9                 <4.4 K-40       1500:1:98     1300:1:78     .1400+/-98       1500+/-100                       1300:1:96               1300:1:93 Mn-54         <3.6           <3.1           <Z.9               <3.Z                           <3.3                 <3.1 Zn-65       <14             <9.5           <4.7               <9.0                           <8.Z                 <8.5 I-131         <4.6           <0.6           <4.5               <4.7                           <0.8                 <3.8 cs..:137     <4.8           <4.0           <3.0               <3.7                           <4.4                 <3.6 Ra-226       <6.8           <7.3           <8.3               <8.Z                           <8.Z                   <6.6 SA-MLK-14Fl     Na-22         <5.5           <4.8           <4.1               <3.9                           <3.5                   <3.3 IC-40       1400:1:80     1400:1:97       1400:1:77     1400+/-78                         1400+/-75                 1300:1:82 Mn-54         <3.3*           <1.8           <3.1               <1.7                           <Z.3                   <3.1 Zn-65         <9.4         <11             <1.8               <9.3                           <6.4                   <8.8 I-131         <Z.l           <3.7           <3.7               <4.4                           <3.Z                   <3.6 Cs-137       <3.6           <4.0           <3.7               <Z.9                           <2.7                   <3.7 Ra.:226       <8.0           <7.5           <6.3               <8. 7 '                       <6.Z                   <6.9.
SA-MLK-3Gl     Na-22         <3.9*         <Z.9           <4.6               <4.5                           <3.9                   (3)
(Control)       IC-40       1300:1:73     1400:1:84       1300+/-83       1100:1:86                       1300:1:92
      **'                 Mn-54         <Z.5           <2.4           <Z.Z               <3.2                           <3.5
        ~
Zn-65         <6.9           <8.6           <6.3             <7.7                           <9.0 I-131         <3.0           <3.7           <3.3               <3.3                           <3.7 Cs-137         <Z.9           <3.Z           <3.7               <3.8                           <3.5
  *   *,!                 Ra-226         <5.5           <7.5           <5.8               <6.6                           <7.0 AVERAGE         K-40       1400:1:160     1400:1:150     1400:1:100     1400:t:Z80                     1300:1:160             1300:!:170
        .~                                                      86
                                                                                .----  ----*-- - . -;---:- .. *~---,--***  -----*- *- *- *--,      -, __ --*-- -*- -**
 
  ... 'J TABLE C-lZ (cont'd.)
1986 CONCENTRATIONS OF GAMMA EMITTERS.* .IN MlLK'
1986 CONCENTRATIONS OF GAMMA EMITTERS.* .IN MlLK'
* Results in Units of pCi/L % Z sigma 
* Results in Units of pCi/L %  Z sigma
*.r*' ;_ ,** ... . . .
 
... *. *. :. * *.. . . ,. * * -.1 ** ;. ** ** , * .' **. *. * ** * **.***** . TABLE C-13
                *.r*'                        ;_ ,**
* 1986 SAMPLING
  . . .  --**----~>-'; ...*. ~ *. :. **..          ** -.1 ** ~- ;. ** ** , * .' * * . *. *  **  * **.*****
                                                                                                                                      . TABLE C-13
* 1986 SAMPLING DATES FOR MILK SAMPLES STATION ID MONTH                                                  13E3                ZF4                                    6FZ      llf3      14Fl      361 JANUARY                                        01-06-86                01-06-86                              01-04-86  01-06-86 01-06-86  01-06-86


SA-SOL-2F?
                    *=*.*      - ..
SA-SOL-5Fl SA-SOL-5F2 SA-SOL-llF3 SA-SOL-14Fl SA-SOL-3Gl SA-SOL-3H3 (C) AVERAGE .... ,;* . . : *. * .. . . *;
          *.~ >>. **, .. ;**                                                                      '_.
.. ,., ..........
:* ..~.*.. .:.~.. :.                  . ' * * . *-* -* *****" .......... ., ... ~ ....... -*~ ** ~<-** .... *"
..:.:.:. , ..........
*j 1
: .. * ..... , TABLE C-23 1986 CONCENTRATIONS OF STRONT!UH-90 AND GAMMA EMITTERS*
I
IN SOIL COLLECTION DATE 01-30-86 07-30-86
'j
_i
  )
TABLE C-25*
ii                                                                                                1986 CONCENTRATIONS OF GROSS BETA EMITTERS IN SURFACE WATER I
-1 Results in Units of. pCi/L +/- 2 sigma STATION  :m                                        01-20-86                          02-03-86    03-
* e *
* e *
* o * * * * * * * * * * *
* o * * * * * * * * * * *
* e * * *
* e * * *
* u * *
* u * *
* PSE&G Analysis of Water *************** " ******.*******
* 156 PSE&G                           Analysis                   of         Water *************** " ******.*******                                                                                 c
c
* 157 PSE&G                           Analysis                     of       Solids (combined procedures) ********                                                                                                         158 ENVIRONMENTAL DOSIMETRY TI                               Analysis of Thermoluminescent Dosimeters .*****..                                                                                                                                   160
* PSE&G Analysis of Solids (combined procedures)  
* PSE&G - PSE&G_Research Corporation TI                   - Teledyne Isotopes CEP                   - Controls for Environmental Pollution, Inc *
******** ENVIRONMENTAL DOSIMETRY TI Analysis of Thermoluminescent Dosimeters  
  '  .* ~
.*****..
. --. *. ~
* PSE&G -PSE&G_Research Corporation TI -Teledyne Isotopes CEP -Controls for Environmental Pollution, Inc
      .. -~
* 116
:"-]                                                                                                                                                          116
* PAGE 154 155 156 157 158 160 * * **-,-----;-* -***--*-*-----,.--
          **-,--- - -;-* - ***--*-*-----,.-- *:-;-** ..-~-* -......--7.~---**--**.*:-~ *-:*-- * .,.---,;:---""';"*~**-~--*7.~*---.---;---r- *--:-.,.... - - - . - .- * ---* - - * *- <---- ..,*.~* *--:*-~* -~ ~--,;- --,----* *---- ***--: --** *-.- . -** ** - *- . -*.* *
*:-;-**  
* SYNOPSIS OF.. PSE&G. RESEARCH CORl?ORA'l'ION PROCEDURE GROSS ALPHA.ANALYSIS OF AIR PARTICULATE SAMl?LES After a1low:i.ng at least a three~day (extendi.ng from the sample stop date to the sample count time) period for the short-lived radionuclides to decay out, air particulate samples are counted for gross alpha activity on a low back~
*-:*--*  
ground gas proportiona1 counter. Along with a set of air particulate samples, a clean air. filter is in:luded as a blank with an Am-241 air filter geometry a1pha counting standard.
*--:-.,....  
The specific a1pha activity is computed on the basis of total corrected air flow sampled during the collection period. This corrected air flow takes into*account the air ~ressure correction due to the vacuum being drawn, the correct.ion factor of the temperature-corrected gas meter as well as the gas meter efficiency itself.
---. -.-* ---* --* *-<----.  
caiculation of Gross Alpha Activity:
--,----* *----***--: --** *-.-. -** ** -*-. -*.* * * 
* *1 . ..
SYNOPSIS OF .. PSE&G. RESEARCH CORl?ORA'l'ION PROCEDURE GROSS ALPHA.ANALYSIS OF AIR PARTICULATE SAMl?LES After a1low:i.ng at least a (extendi.ng from the sample stop date to the sample count time) period for the short-lived radionuclides to decay out, air particulate samples are counted for gross alpha activity on a low ground gas proportiona1 counter. Along with a set of air particulate samples, a clean air. filter is in:luded as a blank with an Am-241 air filter geometry a1pha counting standard.
The specific a1pha activity is computed on the basis of total corrected air flow sampled during the collection period. This corrected air flow takes into*account the air correction due to the vacuum being drawn, the correct.ion factor of the temperature-corrected gas meter as well as the gas meter efficiency itself. caiculation of Gross Alpha Activity:
Air flow is corrected first by using the following equations:
Air flow is corrected first by using the following equations:
P = (B-V)/29.92 V =
P = (B-V)/29.92                                                                             P = Pressure correction factor B = Time-averaged barometric pressure during sampling period, ivHq .
E P = Pressure correction factor B = Time-averaged barometric pressure during sampling period, ivHq . V = Time-averaged vacuum during sampling period, "Hg 29.92 = Standard atmospheric pressure at 32&deg;Fu "Hg F = Uncorrected air flow, ft 3 o.946 = Temperature correction factor from 60&deg;F to 32&deg;F 0.0283 = CUlJic meters per cUlJic foot E = Gas meter efficiency  
V = Time-averaged vacuum   during sampling period, "Hg 29.92     = Standard atmospheric   pressure at 32&deg;Fu "Hg V  = F~P~0.946*0.0283 E                                                                              F   = Uncorrected   air flow, ft 3 o.946     = Temperature correction factor from 60&deg;F to 32&deg;F 0.0283       = CUlJic meters per cUlJic foot E   = Gas meter efficiency (= %
(= % efficiency/100) m3 v "" corrected air flow, p = Pressure correction factor Usinq these corrected a.:!.r flows. the gross alpha activity is computed as Result (pCi/m 3) (G--B)/T ( 2 a22) *(E)$1 G = Sample gross counts B = Background counts (from blank filter) 'l' = Count time of sample and blank, minso E = Fractiona1 Am-241 counting efficiency V = corrected air flow of sample, m 3 2.22 = No. of dpm per pCi 117  
efficiency/100) v   "" corrected air flow, m3 p   = Pressure correction factor Usinq these corrected a.:!.r flows. the gross alpha activity is computed as follows~
... **-:-* .... *:***-
Result (pCi/m3 ) ~        (G--B)/T
*-.---  
    *1
.. I . ! . * .;. 2-sigma error (pCi/m 3) = (G-B) caiculation of lower limit of detection:
( 2 a22) *(E)$1 (V~                                                    G   = Sample gross counts B   = Background counts (from blank filter)
A = Gross alpha activity, pCi/m 3 G = Sample gross counts B = Background counts (from blank filter) 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/m 3) = 4.66
                                                                                                      'l' = Count time of sample and blank, minso E = Fractiona1 Am-241 counting efficiency V   = corrected air   flow of sample, m3 2.22   = No. of dpm per pCi 117
* ca)1/2 B = Background counts (from blank filter) E = Fractional Am-241 counting efficiency v = corrected air flow of sample, T. = Count time of blank, mins. 118 l m3 ** 
. .. ...~
* *
                                  .-::~::-*--.....**-:-* ....*:***- :~.,*-----":'"""-* *-.--- --*~-
* SYNOPSIS OF TELEDYNE ISOTOPES **PROCEDURE ANALYSIS OF AIR !?ARTICULATE FILTEHS.FOR GROSS ALPHA AND-BETA The air filter is first stored for 2 to 5 days from date of receipt to allow for decay' of the radon-thoron daughters.
 
It is then placed in a stainless steel planchet which has been coated in the center with ruJ:lber cement. The filter is then counted for.beta activity and suosequently repeat counted for alpha activity (at a different voltage setting) in a Beckman-Sharp Wide Beta II automatic alpha-beta counter. Gross alpha and beta activity (pCi/m 3) are computed as follows: A = {G/T (2.22*V>11Y*D*E)
l
Where G = Total. sample counts %
  .. I 2-sigma error (pCi/m 3 ) = (l.96*(G+B)l/ 2 )~A (G-B)
+B)/T)l/2 (2o22*V'*Y*D*E)
A = Gross alpha activity, pCi/m 3 G = Sample gross counts
B = Background counts per minute T = Sample count time, mins. 2.22 = dpm/pCi v = Sample volume, m 3 Y = Chemical yield (Y = 1 in this case) D = Decay factor from collection to count date (D = 1 in this case) E = Counter efficiency crm ::a* MUl.tiples of ccmntinq error. If the net activity (G/T -B) is equal to or less than the counting error, then the activity is considered to be the minimum detectable level, or MDL. where MDL = 3*(2*B/T)l/2 (2o22*V*Y*D*E)
                                                        =
Varia.l:lles are as previously defined
B Background counts (from blank filter) caiculation of lower limit of detection:
: .. **
A sample activity is assumed to be LLD if the sample net count is less than 4.66 times the standard deviation of the count on the blank.
* SYNOPSIS OF:PSE&G-RESEARCH CORPORATION l?ROCEI;JURE GROSS ALPHA ANALYSIS OF SAMPLES -The sample is thoroughly miXed. Then, a 250ml portion.of sample and an equal volume of deionized water blank are acidified with dilute sulfuric acid. Barium carrier is added and the sample heated to 50&deg;C in order to help cipitate barium sulfate. Maintaining the same temperature for the remainder of the procedure, iron carrier is then introduced.
LLD(pCi/m3 ) =   4.66
After a 30 minute bration period, the sample is neutralized with dilute ammonium hydroxide to precipitate ferric hydroxide.
* ca) 1 / 2
The mixed precipitates are then-filtered onto a membrane filter, dried under -an infrared heat lamp, weighed and mounted on a stainless steel planchete The sample is then alpha-counted for lOO minutes on a low background gas proportional counter, along With a U-238 source of the same geometry.
{2~22)*(E)*(V)*(T)
The blank is treated in the same manner as the sample. Water samples found to be excessively turbid due to the presence of suspended organic material require pretreatment of this material for the purpose of keeping the final sample thickness to a minimum. This is accomplished by filtering a measured aliquot of the sample (while the filtrate is set aside) and ashing the collected residue in a crucible.
B  = Background counts (from blank filter)
A blank of the same volume is handled in the same manner. Whatever leftover sample residue remains,after the ashing,is dissolved in concentrated nitric acid and passed through a hardened fast filter paper and combined with the sample-filtrate.
E  = Fractional Am-241 counting efficiency v = corrected air flow of sample, m3 T. = Count time of blank, mins.
The combined sampl is then neutralized with dilute ammonium hydr'oXide.
118
From this point, both sample and-blank are acidified with dilute sulfuric acid. Barium carrier is added and the sample is heated to so 0 c in order to help.precipitate barium sulfate. Maintaining the same temperature for the remainder of the procedure, iron carrier is then introduced.
* SYNOPSIS OF TELEDYNE ISOTOPES **PROCEDURE ANALYSIS OF AIR !?ARTICULATE FILTEHS.FOR GROSS ALPHA AND-BETA The air filter is first stored for 2 to 5 days from date of receipt to allow for decay' of the radon-thoron daughters. It is then placed in a stainless steel planchet which has been coated in the center with ruJ:lber cement. The filter is then counted for.beta activity and suosequently repeat counted for alpha activity (at a different voltage setting) in a Beckman-Sharp Wide Beta II automatic alpha-beta counter.
After a 30 minute equilibration period, the sample is neutralized with dilute ammonium hydroXide to precipitate ferric hydroXide.
Gross alpha and beta activity (pCi/m3 ) are computed as follows:
The miXed precipitates are then filtered onto a membrane filter, dried under an infrared heat lamp, weighed and mounted.on a stainless steel planchet.
A =     {G/T ~B)    % qm~((G/T +B)/T)l/2 (2.22*V>11Y*D*E)   (2o22*V'*Y*D*E)
The sample is then alpha-counted for the appropriate time on a low -background gas proportional counter,-along with a U-238 source of the same geometry.
Where    G = Total. sample counts B = Background counts per minute T = Sample count time, mins.
The blank is treated in the same manner as the sample. calculation of Gross Alpha Activity:
2.22   = dpm/pCi v = Sample volume, m3 Y = Chemical yield (Y = 1 in this case)
Result (pCi/L) = (G-B)/T (2.22)*(E)*(V)*(S)
D = Decay factor from collection to count     date (D =1 in this case)
G = B = T = E. = v = s = Sample gross counts Background counts (from blank sample) count time of sample and blank Fractional counting efficiency from U-238 source Sample volume, liters Normalized efficiency regression equation as a function of thick-ness 2.22 = No. of dpm per pCi
E = Counter efficiency crm ::a* MUl.tiples of ccmntinq error.
* 120
If the net activity (G/T -B) is equal to or less than the counting error, then the activity is considered to be the minimum detectable level, or MDL.
* error. (pCi/L)-= (l.96*(G+B)l/?)1iA  
where MDL   = 3*(2*B/T)l/2 (2o22*V*Y*D*E)
** * * (G-B) A= Gross alpha activity, pCi/L G = Sample gross counts .. B = Background counts (from blank sample) .. '} : -' .. ... .. * .. -:--,-.* --*-*-.:***--,..  
Varia.l:lles are as previously defined
-.*****-**'7"-*-**," , ___ _ -** *_--..  
 
.........  
SYNOPSIS OF:PSE&G-RESEARCH CORPORATION l?ROCEI;JURE GROSS ALPHA ANALYSIS OF   WATE~  SAMPLES -
,__ .... -.. ---****--* -.
The sample is thoroughly miXed. Then, a 250ml portion.of sample and an equal volume of deionized water blank are acidified with dilute sulfuric acid.
.. :; *j . i ' * ** SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE GROSS BETA ANALYSIS OF AIR PARTICULATE SAMPLES . After allowing at least a three-day (extending from the sample stop date to the sample count time) period for the short-lived radionuclides to decay out, air particulate samples are counted for gross beta activity on a low ground gas proportiona1 counter. Along with a set of air particulate samples, a clean air filter is included as a blank with an sr-90 air filter geometry .beta counting standard.
Barium carrier is added and the sample heated to 50&deg;C in order to help pre-cipitate barium sulfate. Maintaining the same temperature for the remainder of the procedure, iron carrier is then introduced. After a 30 minute equili-bration period, the sample is neutralized with dilute ammonium hydroxide to precipitate ferric hydroxide. The mixed precipitates are then-filtered onto a membrane filter, dried under -an infrared heat lamp, weighed and mounted on a stainless steel planchete The sample is then alpha-counted for lOO minutes on a low background gas proportional counter, along With a U-238 source of the same geometry. The blank is treated in the same manner as the sample.
The gross beta activity is computed on the basis of tota1 corrected air flow sampled during the collection period. This corrected air flow takes into account the air pressure correction due to the vacuum being drawn, the correction factor of the temperature-corrected gas meter as well as the gas meter efficiency itself. calculation of Gross Beta Activity:
Water samples found to be excessively turbid due to the presence of suspended organic material require pretreatment of this material for the purpose of keeping the final sample thickness to a minimum. This is accomplished by filtering a measured aliquot of the sample (while the filtrate is set aside) and ashing the collected residue in a crucible. A blank of the same volume is handled in the same manner. Whatever leftover sample residue remains,after the ashing,is dissolved in concentrated nitric acid and passed through a hardened fast filter paper and combined with the sample- filtrate. The combined sampl is then neutralized with dilute ammonium hydr'oXide. From this point, both sample and-blank are acidified with dilute sulfuric acid. Barium carrier is added and the sample is heated to so 0 c in order to help.precipitate barium sulfate. Maintaining the same temperature for the remainder of the procedure, iron carrier is then introduced. After a 30 minute equilibration period, the sample is neutralized with dilute ammonium hydroXide to precipitate ferric hydroXide. The miXed precipitates are then filtered onto a membrane filter, dried under an infrared heat lamp, weighed and mounted.on a stainless steel planchet. The sample is then alpha-counted for the appropriate time on a low -
background gas proportional counter,- along with a U-238 source of the same geometry. The blank is treated in the same manner as the sample.
calculation of Gross Alpha Activity:
Result (pCi/L) =       (G-B)/T (2.22)*(E)*(V)*(S)
G = Sample gross counts B = Background counts (from blank sample)
T = count time of sample and blank E. = Fractional counting efficiency from U-238 source
: .. **                                            v = Sample volume, liters s = Normalized efficiency regression equation as a function of thick-ness 2.22 = No. of dpm per pCi 120
 
2~sigma. error. (pCi/L)-                                                       = (l.96*(G+B)l/?)1iA ** * *
(G-B)
A= Gross alpha activity, pCi/L G = Sample gross counts ..
B = Background counts (from blank sample)
                                                                                                                                                                        .-.'}   :
                                                                                                                                                                        ... ' ~
..* .. -:--,- ~,- .* - -*- *-.:***--,.. -.*****-**'7"-*-**," , ___ _ -** *_--.. ~--:---.,.---- ......... ,__ .... - ..--- ****--* - .
 
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE GROSS BETA ANALYSIS OF AIR PARTICULATE SAMPLES .
After allowing at least a three-day (extending from the sample stop date to the sample count time) period for the short-lived radionuclides to decay out, air particulate samples are counted for gross beta activity on a low back-ground gas proportiona1 counter. Along with a set of air particulate samples, a clean air filter is included as a blank with an sr-90 air filter geometry
      .beta counting standard.
The gross beta activity is computed on the basis of tota1 corrected air flow sampled during the collection period. This corrected air flow takes into account the air pressure correction due to the vacuum being drawn, the correction factor of the temperature-corrected gas meter as well as the gas meter efficiency itself.
calculation of Gross Beta Activity:
Air flow is corrected first by using the* following equations:
Air flow is corrected first by using the* following equations:
p = (B-V)/29.92 V = F*P*0.946*0.0283 E p = Pressure.
p = (B-V)/29.92                                     p = Pressure. correction factor B = Time-averaged barometric
correction factor B = Time-averaged barometric pressure durinq samplinq period ** "Hg v = Time-averaged vacuum during sampling period, "Hg 29 * .92 = Standard atmospheric pressure 32&deg;F, "Hg F = Uncorrected air flow, ft 3 0.946 = Temperature correction factor from 60&deg;F to 32&deg;F 0.0283 = CUbic meters per cubic foot E = Gas meter efficiency  
..                                                            pressure durinq samplinq period * *
(= % efficiency/100) m3 v = corrected air flow, p = Pressure correction factor at Using these corrected air flows, the gross beta.activity is computed as follows: Result (pCi/m 3) = (G-B)/T ( 2
                                                                "Hg v = Time-averaged vacuum during sampling period, "Hg 29 *.92 = Standard atmospheric pressure at 32&deg;F, "Hg V = F*P*0.946*0.0283 E                                        F = Uncorrected air flow, ft 3 0.946 = Temperature correction factor from 60&deg;F to 32&deg;F 0.0283 = CUbic meters per cubic foot E = Gas meter efficiency (= %
* 22 ) * ( E) * ( V )" G = Sample gross counts B = Background counts (from blank filter) T =Count time.of sample and blank, mins. E = Fractiona1 Sr-90 counting efficiency
efficiency/100) v = corrected air flow, m3 p = Pressure correction factor Using these corrected air flows, the gross beta.activity is computed as follows:
* v =corrected air flow of sample, m 2.22 = No. of dpm per pCi 122 
Result (pCi/m3 ) =       (G-B)/T
* . i i_
( 2
* 1 . ; * . ,j ' 2-sigma. error (pCi/m 3) = (l.96,..(G+B)l/2)*A (G-8)
* 22 ) * ( E) * ( V )"       G = Sample gross counts B = Background counts (from blank
* ca.J..culation of lower limit of detectiong A = Gross beta activity, pCi/m 3 G = Sample gross counts B = Background counts (from blank filter) 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)  
:;                                                              filter)
= 4.66 "' (B)l/2 (2.22)*(E)*(V)*(T}
T =Count time.of sample and blank, mins.
B E v T = = = = Background counts (from blank filter) Fractional Sr-90 counting efficiency Corrected air flow of sample, count time Of blank, mins. ,:.* . " .. * .. *: *:-..;:*.*  
E = Fractiona1 Sr-90 counting efficiency
,* m3 
* v =corrected air flow of sample, m 2.22 = No. of dpm per pCi
.. ,'I .* * . F
*j
* SYNOPSIS OF TELEDYNE I.SOTOPES PROCEDURE* . .._,_ **--* _,__ -* .. ANALYSIS OF AIR PARTICULATE*.
.i
FILTERS* FOR *GROSS ALPHA .AN:El BETA* ---The ai.r filter is .first stored for 2 to 5 days from date of receipt to allow. for decay of the radon-thoron daughters.
  '                                                    122
It is then placed in a stainless steel planchet which has been coated in the center with rUbber cement. The filter is then counted for beta activity and subsequently repeat counted for
* 2-sigma. error (pCi/m3 )   = (l.96,..(G+B)l/2)*A (G-8)
* alpha activity (at a different voltage setting) in a Beckman-Sharp Wide Beta II autQmatic alpha-beta counter. Gross alpha and beta activity (pCi/m 3) are computed as follows: A = (G/T -B) (2.22*V*Y*D*E)  
A = Gross beta activity, pCi/m 3 G = Sample gross counts B = Background counts (from blank filter)
+/-
* ca.J..culation of lower limit of detectiong A sample activity is assumed to be LLD if the sample net count is less than
+B)/T)l/2 (2.22*V*Y*D*E)
  . i 4.66 times the standard deviation of the count on the blank.
Where G = Total sample counts B =Background counts per.minute T = Sample count time, mins. 2.22 = dpm/pCi V = Sample volume, m 3 Y = Chemical yield (Y = l in this case) D = Decay factor from collection to count date (D = l in this case) E = Counter efficiency = Multiples of counting error If the net activity (G/T -B) is equal to or less t.han the counting error, then the activity is considered to be the minimum detectable level, or MDL. where MDL = 3*(2*B/T)l/2 (2.22*V*Y*D*E)
LLD(pCi/m3)   =   4.66 "' (B)l/2 (2.22)*(E)*(V)*(T}
Variables are as defined 124 * . ---..-----.. .,_ ---*-
B = Background counts (from blank filter)
.. ,
E = Fractional       Sr-90 counting efficiency v = Corrected air flow of sample,   m3 T = count time Of blank, mins.
*--.,---. --.... *-*------*-..-::--:-
i_
: .. ----;;;.-**.-
* 1
-**--:*. **-
.    ,j
1*.* .... -:-; *, . . '" .*
 
_>[ . . **.r* -: .: _._.-' l SYNOPSIS OF PSE&G RESEARCH CORl?OaATION PROCEDURE GROSS BETA ANALYSIS OF WATER SAMPLES The sample is m.iXed thoroughly.
SYNOPSIS OF TELEDYNE I.SOTOPES PROCEDURE* .                                                           .._,_ **--* ~ _,__ -* ..
Then, a l.O liter portion is removed from the potal:!le, rain or well water container and 250ml taken from each surface water. A deionized water blank is prepared for each di.fferent volume of sample (e.g. l.O liter blank for l.O liter samples and 2SOml for 250ml samples).
ANALYSIS OF AIR PARTICULATE*. FILTERS* FOR *GROSS ALPHA .AN:El BETA* ---
All samples and blanks are then evaporated on a hotplate until the volume approaches 20 to 25ml. At that point, the samples and blanks are transferred to tared stainless steel ribbed planchets and evaporated to dryness under an infrared heat lamp. They are sUJ:lsequentlY cooled in a desiccator, weighed and counted on a low background gas proportiona.1 counter along with an source of the same geometry.
The ai.r filter is .first stored for 2 to 5 days from date of receipt to allow.
calculation of Gross Beta Result {pCi/L) = (G-B)/T (2.22)*{E)*V)*(S)
for decay of the radon-thoron daughters. It is then placed in a stainless steel planchet which has been coated in the center with rUbber cement. The filter is then counted for beta activity and subsequently repeat counted for
G = Sample gross counts B = Background counts (from blank sample) T = Count time of sample and. blank E. :.:;, Fractional counting efficiency . * . <'*from source v Sample volume, liters S NormaL.ized efficiency regression equation as a function of thick= ness 2.22 = Noe of dpm per pCi 2-sigma error {pCi/L) = (l.96*(G+B)l/2)*A (G--B) ._. .  
* alpha activity (at a different voltage setting) in a Beckman-Sharp Wide Beta II autQmatic alpha-beta counter.
*:---A = Gross beta activity, pCi/L G = Sample qross counts B Background counts (from blank sample) 125 -.,--* ***-*** --, .. ---**,****---*  
Gross alpha and beta activity (pCi/m3 ) are computed as follows:
*-* --  
A=                     (G/T -B)                             +/- ~m*((G/T +B)/T)l/2 (2.22*V*Y*D*E)                                           (2.22*V*Y*D*E)
... ; . ' ' ' SYNOPSIS OF l?SE&G RESEARCH CORPORATION.
Where                 G = Total sample counts B =Background counts per.minute T = Sample count time, mins.
PROCEDURE'"*.
2.22 = dpm/pCi V = Sample volume, m3 Y = Chemical yield (Y = l in this case)
ANALYSIS OF WATER FOR .POTASSIUM 40 A 60 ml aliquot of water sample (with the exception of rain water) received by the Research and Testing Lal:loratory is first acidified to pH <2 With centrated nitric acid and then analyzed.
D = Decay factor from collection to count date (D                                                                                   =l in this case)
for potassiwn by the following Atomic Absorption Spectrophotometry method: potassiwn standards of known tion (similar to that of the unknowns) are first prepared.
E = Counter efficiency
An aliquot of each sample and standard is pipetted into stoppered flasks. In addition, a duplicate sample, ERA standard and blank water sample are likewise pipetted into their respective flasks. A solution consisting of 4% sodiwn is diluted 1:1 with water and then added to all the flasks. Depending on the AA instrument used, a calibration curve is prepared from the standards after which the samples are run. If the al:lsorbance of any sample is higher than the upper standard used, the sample is then either diluted and re-run, the burner head turned 90&deg;, a more concentrated standard added to the calibration curve or a less sensitive wavelength used. Tne results, reported in parts per million (ppm), are converted to pCi/L by means of a computer program. Calculation of K-40 Activity:
                                                              ~m = Multiples of counting error If the net activity (G/T -B) is equal to or less t.han the counting error, then the activity is considered to be the minimum detectable level, or MDL.
K-40 Activity (pCi/L) = 0.85*C 0.85 = Proportionality constant for converting ppm to pCi/L c = Potassium concentration, ppm 126 : " . .
where MDL                     =         3*(2*B/T)l/2 (2.22*V*Y*D*E)
----;---**-
Variables are as                                   previ~usly                        defined 124
----:-----
.. , ' I .* *          .
-. ----*:--.**
F    *
..
                            -~---*-.-**-*--*----;'*-*--*--.-- ~-----~~-     :7-**-*-~,.:-*:----~--.,.-.-~*              -~                                            ----..--------.~
--,---..
 
... ' * 
1*.*
-....... . . , .: ** .. J *i SYNOPSIS . OF' PSE&G RESEARCH CORPORATION . PROCEDURE
SYNOPSIS OF PSE&G RESEARCH CORl?OaATION PROCEDURE GROSS BETA ANALYSIS OF WATER SAMPLES The sample is m.iXed thoroughly. Then, a l.O liter portion is removed from the potal:!le, rain or well water container and 250ml taken from each surface water.
.* ANALYSIS OF WATER FOR TRITIUM ApproXj.mately SOml of raw sample is mixed with sodium hydroxide and potassium permanganate and is distilled under vacuum" Eight mi of distilled sample is mixed with lOml of Instagel liquid scintillation solution, and placed in the liquid scintillation spectrometer for counting.
A deionized water blank is prepared for each di.fferent volume of sample (e.g.
An internal standard is prepared by miXinq Sml of sample, lOml of Instagel, and o.lml of a standard with known activity.
l.O liter blank for l.O liter samples and 2SOml for 250ml samples). All samples and blanks are then evaporated on a hotplate until the volume approaches 20 to 25ml. At that point, the samples and blanks are transferred to tared stainless steel ribbed planchets and evaporated to dryness under an infrared heat lamp. They are sUJ:lsequentlY cooled in a desiccator, weighed and counted on a low background gas proportiona.1 counter along with an sr~90 source of the same geometry.
The efficiency is determined from this. Also prepared is a blank consisting of Sml of distilled water and lOml of Instagel, to be used for a background determination.
calculation of Gross Beta                  Activity~
This is done for each pair of samples to be countedc Activity is computed as follows: A (pCi/L) = (G-B)*(lOOO) 2.22*(E)*(V)*(T)
Result {pCi/L)                =      (G-B)/T (2.22)*{E)*V)*(S)
I " *' Efficiency (E) is computed as followsg E = (N)*(D) .A' N is determined as follows: N =
G    = Sample gross counts B    = Background counts (from          blank sample)
A = Activity B = Background count of sample G = Gross count of sample E = Counting Efficiency v = Aliquot vol.ume (ml,) T = count. time (min) DPM/pCi . 2o22 -1000 = Number of m.l per L N = Net CPM of spiked sample D = Decay factor of spike A' = DPM of spike C = CPM of spiked sample G = Gross counts of sample T = Count time (m.in) The associated error is expressed at 95%-confidence l.imit,.as followsg 2.222 (V) * (E) Samples are designated LLD if the activity is less than the following value: LLD (pCi/L) == (4o66)*(B) 1 12.,ciooo) 2.22*(V)*(E)fl(T)
T = Count time of sample and. blank E. :.:;, Fractional counting efficiency
.. ** ... *.; *. * .. .. .-* _, . ' -. :"j * > '* . . I . *. : ;_**. :) -***.-; ._, . ' *. ,'*. *1 *----*-) ._, SYNOPSIS OF CONTROLS FOR ENVIRONMENTAL .POLLUT.ION, INC., PROCEDURE TRITIUM ANALYSIS OF AQUEOUS FRACTION OF BIOLOGICAL MATERIALS An aliqtlot of fish or cral:J flesh is placed in a round bottom flask, along with 200ml of benzene, and the water removed via azeotropic distillation.
                                                                                                      . * . <'*from sr~9o source v ~ Sample volume, liters S ~ NormaL.ized efficiency regression equation as a function of thick=
ness 2.22    = Noe  of dpm per pCi 2-sigma error {pCi/L)                 = (l.96*(G+B)l/2)*A (G--B)
A    = Gross beta activity,      pCi/L G    = Sample qross counts B     ~  Background counts (from blank
        .... -:-;                                                                                             sample)
            . . ~
:-~
-~{*'.jt'.-~-~ _>[
  . **.r* -: .:
125
_._.-' l
                          ._. ..,....~.,...~:;- .-.~-:- :-:-*-=-~-=- *:---                                                        -.,--* ***-*** - - , .. ---**,****---* *-* --
 
SYNOPSIS OF l?SE&G RESEARCH CORPORATIO
 
==N. PROCEDURE==
ANALYSIS OF WATER FOR .POTASSIUM 40 A 60 ml aliquot of water sample (with the exception of rain water) received by the Research and Testing Lal:loratory is first acidified to pH <2 With con-centrated nitric acid and then analyzed. for potassiwn by the following Atomic Absorption Spectrophotometry method: potassiwn standards of known concentra-tion (similar to that of the unknowns) are first prepared. An aliquot of each sample and standard is pipetted into stoppered flasks. In addition, a duplicate sample, ERA standard and blank water sample are likewise pipetted into their respective flasks. A solution consisting of 4% sodiwn is diluted 1:1 with water and then added to all the flasks. Depending on the AA instrument used, a calibration curve is prepared from the standards after which the samples are ~hen run. If the al:lsorbance of any sample is higher than the upper standard used, the sample is then either diluted and re-run, the burner head turned 90&deg;, a more concentrated standard added to the calibration curve or a less sensitive wavelength used.
Tne results, reported in parts per million (ppm), are converted to pCi/L by means of a computer program.
Calculation of K-40 Activity:
K-40 Activity (pCi/L)                                   = 0.85*C 0.85       = Proportionality                       constant for converting ppm to pCi/L c   = Potassium concentration, ppm
  . ~
    '                                                                                                                                  126
        --------*~* ----;---**- ----:---- - -.-:-*~--:--- ~:--.:------:**-*-:r---:-.,--:--=-;-:-;-**-**.--~----.- .----*:--.**                ..
:----~--.-*--::;---.~: --,---..~*~7*:*-- *-*--***-~ --.-~---~ ...
 
SYNOPSIS . OF' PSE&G RESEARCH CORPORATION . PROCEDURE .*
ANALYSIS OF WATER FOR TRITIUM ApproXj.mately SOml of raw sample is mixed with sodium hydroxide and potassium permanganate and is distilled under vacuum" Eight mi of distilled sample is mixed with lOml of Instagel liquid scintillation solution, and placed in the liquid scintillation spectrometer for counting. An internal standard is prepared by miXinq Sml of sample, lOml of Instagel, and o.lml of a standard with known activity. The efficiency is determined from this. Also prepared is a blank consisting of Sml of distilled low~tritiated water and lOml of Instagel, to be used for a background determination. This is done for each pair of samples to be countedc Activity is computed as follows:
A (pCi/L)  =   (G-B)*(lOOO) 2.22*(E)*(V)*(T)
A = Activity B = Background count of sample G = Gross count of sample E = Counting Efficiency v = Aliquot vol.ume (ml,)
I T = count. time (min)
                                                *'"    2o22 - DPM/pCi .
1000 = Number of m.l per L Efficiency (E) is computed as followsg E = (N)*(D)
                  .A' N = Net CPM of spiked sample D = Decay factor of spike A' = DPM of spike N is determined as follows:
N = C~(G/T)
  - .......                                                 C = CPM of spiked sample G = Gross counts of sample
        .~
T = Count time (m.in)
The associated error is expressed at 95%-confidence l.imit,.as followsg l.96*(G/T2 +B/T 2 ) 1 /2 ~(l000) 2.222 (V) * (E)
*. J
        *i Samples are designated LLD if the activity is less than the following value:
LLD (pCi/L) ==  (4o66)*(B) 112.,ciooo) 2.22*(V)*(E)fl(T)
 
SYNOPSIS OF CONTROLS FOR ENVIRONMENTAL .POLLUT.ION, INC., PROCEDURE TRITIUM ANALYSIS OF AQUEOUS FRACTION OF BIOLOGICAL MATERIALS An aliqtlot of fish or cral:J flesh is placed in a round bottom flask, along with 200ml of benzene, and the water removed via azeotropic distillation.
Three milliliters of the extracted water is then mixed with aquasol cocktail (NEF-934 Aquasol cocktail, manufactured by New England Nuclear corporation).
Three milliliters of the extracted water is then mixed with aquasol cocktail (NEF-934 Aquasol cocktail, manufactured by New England Nuclear corporation).
The resultant miXture is comprised of 19 percent sample in a clear gel-type aquasol and provides a tritium counting efficiency of approXimately 30 percent, when counted on a Beckman Liquid Scintillation Spectrometer.
The resultant miXture is comprised of 19 percent sample in a clear gel-type aquasol and provides a tritium counting efficiency of approXimately 30 percent, when counted on a Beckman r..s~100 Liquid Scintillation Spectrometer.
The efficiency of the counting system is determined by placing 6 tritium standards (certified by NBS) before each set of water samples to be counted. The counting efficiency is determined from these standards which are equal in activity but vary in the amount of quenching.
The efficiency of the counting system is determined by placing 6 tritium standards (certified by NBS) before each set of water samples to be counted.
All samples are counted for 500 minutes each. 128" ' . -
The counting efficiency is determined from these standards which are equal in activity but vary in the amount of quenching. All samples are counted for 500 minutes each.
... -------. --..,. **-* .... , .....
. ' -. -~-- :"j
i l SYNOPSIS OF PSE&G RESEARCH CORPOAA'l'ION'
      .    ~  .  ~
* PROCEDURE  
I
*. GAMMA ANALYSIS OF AIR IOD!NE ApproXiJnately 30om 3 of air is drawn through a SOml
            . *.  ~
* b_ed of triethylenediamine (TEDA)=impreqnated charcoal granules at a rate which closely corresponds to the :breathing rate of an adult male. The contents of the exposed air iodine cartridge are emptied into an aluminum sample can containing SOml of fresh TEDA-impregnated charcoal.
:  ;_**.  :)
The can is hermetically sealed and then counted on a gamma detector.
              -~
ca1culation of Gamma The followinq are the ca.l.culations performed for the gamma activitYr 2 00 sigma error and LLD: Result (pCi/m 3) = N*D = R (2.22}*(E)*(A)*(T)*(V)  
*. ,'*. *1                                                                                                                        128"
' . ._*i : ..
                ._, )
N = Net counts under photopeak D = Decay correction factor Atl.*EXP(At2) l.-EXP(
                          -------~-~~~~------.-----~---~--:--:-*,.........,-.-:----:.---.-*--:--:-***-*--------~-->'--:----:--*:-:-*:::--:~- "":*---:-*""'-"-"7'-.~.-- '""*--:*-~-~:-------- ... ---- ---. --..,. **-* .... , .....
tl. Acquisition live time t2 = Elapsed time from sample collection to start of acquisition = 0.693/nuclide half life E = Detector efficiency A = Gamma al:>undance factor (no. of photons per disintegration)
 
T = Acquisition live time, mins. v = Sample volume, m3 2o22 No. of dpm per pCi error (pCi/m 3) = 1.9S*(GC+Bc) 1 1 2*R N Ge = Gross counts BC Background COW'ltS All other varia.Dles are as defined earlier. The LLD  
SYNOPSIS OF PSE&G RESEARCH CORPOAA'l'ION'
=
* PROCEDURE *.
.. , *I -:.: ... *\ .*, .... . . . ; *1 -.;_ . ; -. i .*_***.*1
GAMMA ANALYSIS OF AIR IOD!NE ApproXiJnately 30om3 of air is drawn through a SOml
.: ....
* b_ed of triethylenediamine (TEDA)=impreqnated charcoal granules at a rate which closely corresponds to the :breathing rate of an adult male. The contents of the exposed air iodine cartridge are emptied into an aluminum sample can containing SOml of fresh TEDA-impregnated charcoal. The can is hermetically sealed and then counted on a gamma detector.
* SYNOPSIS OF TELEDYNE ISOTOPES PROCEDURE ANALYSIS OF CHARCOAL.
ca1culation of Gamma     Activity~
FILTERS FOR. I(JDINE-131 Charcoal are analyzed for I-131 using a lithiwn-drifted germanium detector interfaced With a 2048 channel pulse height analyzer calibrated at l.O Kev per channel. Teledyne Isotopes employs one of three possible data acquisition and computation systems. The first, a Data General NOVA computer, in series with the pulse height analyzer, calculates*
The followinq are the ca.l.culations performed for the gamma activitYr 2 sigma    00 error and LLD:
the number of .counts (and the standard deviation) in the peak region by performing a
Result (pCi/m 3 ) =                 N*D           =R (2.22}*(E)*(A)*(T)*(V)
* linearly-interpolated background subtraction.
N = Net counts under photopeak D = Decay correction factor Atl.*EXP(At2) l.-EXP( 00 ~tl)
If no peak is observed, then only tne background is used (along with sample volume, collection date and length of count) to.determine the detection lilni.t. The activity or MDL of each nuclide is computed on an IBM 360. This semi-automatic system is in contrast with the other two data acquisition*
                            '  .                         Acquisition live time
and computation systems, namely, a Tracor Northern TN-11 and a Nuclear Data 6620, which perform all the above computations automatically.
                        ._*i                        tl. ~
All resultant spectra are stored on magnetic tape.
                        ~: : ..~:.-.                t2 = Elapsed time from sample collection to start of acquisition
* 130 ***----------. ..---..,..--*--*--.*------
                                                      ~ = 0.693/nuclide half life E = Detector efficiency A = Gamma al:>undance factor (no. of photons per disintegration)
.. ----........---,-
T = Acquisition live time, mins.
.. *--.. ----.-----.--.-7*--.---
v = Sample volume, m3 2o22 ~ No. of dpm per pCi 2~sigma error (pCi/m3 )         = 1.9S*(GC+Bc) 112 *R N
--; ;---;--:.--'7  
Ge = Gross counts BC ~ Background COW'ltS All other varia.Dles are as defined earlier.
........ _ -:-:-:-.:--
The LLD (pe1/m~)  =       4.ss~cac) 1 12 ~o (2.22)~(E)~(A)*(T)*(V) i l
--:---*  
 
..  
            *I SYNOPSIS OF TELEDYNE ISOTOPES PROCEDURE ANALYSIS OF CHARCOAL. FILTERS FOR. I(JDINE-131 Charcoal car~ridges are analyzed for I-131 using a lithiwn-drifted germanium detector interfaced With a 2048 channel pulse height analyzer calibrated at l.O Kev per channel. Teledyne Isotopes employs one of three possible data acquisition and computation systems. The first, a Data General NOVA mini-computer, in series with the pulse height analyzer, calculates* the number of
-_-* *--*-------  
                                              .counts (and the standard deviation) in the peak region by performing a linearly-interpolated background subtraction. If no peak is observed, then only tne background is used (along with sample volume, collection date and length of count) to.determine the detection lilni.t. The activity or MDL of each nuclide is computed on an IBM 360. This semi-automatic system is in contrast with the other two data acquisition* and computation systems, namely, a Tracor Northern TN-11 and a Nuclear Data 6620, which perform all the above computations automatically. All resultant spectra are stored on magnetic tape.
.
          .*,*\
: . *. : ' SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE  
        *1
... ANALYSIS OF RAW MILK FOR IODINE-l3l Stable iodine carrier is equil.:U:lra.ted in a volume of raw milk before two separate SOml batches of anion exchange resin are*introduced to extract iodine. After each batch has been stirred in the milk for an appropriate timef both are then transferred to an aluminum sample can where the resins are rinsed with demineralized water several times and any leftover rinsewater removed with an aspirator stick. The can is hermetically sea:led and then counted on a qamma. detector.
  -    ~
C!a.lcUl.ation of Activity:
          .i 130
Results (pCi/L) = (G->B)/T*(l.OS)x(H)  
.*_***.*1
              ***---- ------...---..,..--*--*--.*------.. - - --........---,-..*--..--~ ----.--- - - . - -.-7*--.--- --; ;-- -;--:.--'7 ........_-:-:-:-.:-- -*-**----~...,.--- --:-- - * ----*.~ .. --------~-~--:---:-*" --*-~~-~.--- ~--*-: - -~* _-* * - - * - - - - ---
 
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE ...
ANALYSIS OF RAW MILK FOR IODINE-l3l Stable iodine carrier is equil.:U:lra.ted in a 4~J.iter volume of raw milk before two separate SOml batches of anion exchange resin are*introduced to extract iodine. After each batch has been stirred in the milk for an appropriate timef both are then transferred to an aluminum sample can where the resins are rinsed with demineralized water several times and any leftover rinsewater removed with an aspirator stick. The can is hermetically sea:led and then counted on a qamma. detector.
C!a.lcUl.ation of I~l3l Activity:
I~l3l  Results (pCi/L)   = (G->B)/T*(l.OS)x(H)
(2.22)*(E)*(V)*(Y)
(2.22)*(E)*(V)*(Y)
G = Sample gross counts B = Background counts (from blank sample) 'I' = count time of sample and blank E = Eo*EXP{-A.*M)  
G = Sample gross counts B   = Background counts (from blank sample)
= efficiency equation where Ea countinq efficiency at zero sample thickness A. = M = v :.:: y =
                                                              'I' = count time of sample and blank E = Eo*EXP{-A.*M) = efficiency equation where Ea ~ countinq efficiency at zero sample thickness A. = Self~cwsorption coefficient M = sample thickness, mg/cm2 v :.:: Sample volume, liters y = Chemical recovery =
coefficient sample thickness, mg/cm2 Sample volume, liters Chemical recovery = R Rl+R2 where R = mq of I-recovered Rl = mq of I-carrier. added R2 = mq of intrinsic staole I-measured in sample l.05 = Correction factor for bound iodine H J/(l-K)*EXP(L)  
R
= correction factor for I-131 decay during count.i.nq period J =
                                                                                    ~--
R = count time, minutes l440 = Noc of minutes per day 8c05 =
Rl+R2 where R = mq of I- recovered Rl = mq of I- carrier. added R2 = mq of intrinsic staole I- measured in sample
Of I=l3lf days K ""
        . ~~,_.;
L =
l.05 = Correction factor for protein~
N = Elapsed ti.me (days) from mid= point of collection period to beginning of count time *
: -~                                                    bound iodine H ~ J/(l-K)*EXP(L) = correction factor for I-131 decay during count.i.nq period J   = (Oc693/8.0S)~(R/l440)
. '*, ., i 1 -*\ . ..--.-': ':* *. *1 *.*: ... _ ! _., . . *: .. , .. j ... .. j ., '!; SYNOPSIS OF PSE&G .RESEARCH . BADIOSTRONTIUM* .ANALYSIS OF AIR FILTERS The air filters are placed in a sma1l beaker and just enough fuming nitric acid is added to cover filters. A blank, composed of the same number of clean air filters, is prepared in the same way. Stable strontium carrier is then introduced into each sample and several fuming nitric acid leachings are carried out to remove the radiostrontium from the filter media. once this is done, the resultant nitrates are dissolved in distilled water and the filter residue is filtered out. Radioactive interferences are stripped out by coprecipitation on ferric hydroXide (yttrium strip) followed by a barium chromate strip. The strontium*
                                                                  =
is precipitated as a carbonate, which is dried and weighed. The samples and 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:
R count time, minutes l440 = Noc of minutes per day 8c05   = Hal,f~life Of I=l3lf days K "" EXP(~J)
* sr-90 Results (pCi/m 3) = N4/R (2.22)*(E)*(E(l5)/E')*(S6)*(V)*(U)  
L   = (0~693/8.0S)*N N   = Elapsed ti.me (days)   from mid=
= W2 where SS = A + B*M + (This is the general form of the norma1ized Sr-90 efficiency regression equation for one particular gas proportional counter, where A, B Care regression coefficients.)
point of collection period to beginning of count time *
M = Thickness density of strontium carbonate precipitate, mg/cm 2
. ~- *. : '
* E(l5)/E' = Ratio of sr-90 efficiency at thickness value of l5mg/cm 2 to sr-90 counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples) E = sr-90 counting standard efficiency v = sample quantity (m3) u = Chemical yield N4 = (N2 Fl*Nl)/W1  
 
= net counts due to sr-90 only Il = l -EXP ((-0.693/2.667)*tl)
SYNOPSIS OF PSE&G .RESEARCH                                                   CORPOBATION~-PROCEDURE                              .
I2 = l -EXP ((-0.693/2.667)*t2) tl = Elapsed time from Y-90 strip to first count 132 ** ----* ---*-* ---*-------_ . *-....  
BADIOSTRONTIUM* .ANALYSIS OF AIR FILTERS The air filters are placed in a sma1l beaker and just enough fuming nitric acid is added to cover t~e filters. A blank, composed of the same number of clean air filters, is prepared in the same way. Stable strontium carrier is then introduced into each sample and several fuming nitric acid leachings are carried out to remove the radiostrontium from the filter media. once this is done, the resultant nitrates are dissolved in distilled water and the filter residue is filtered out. Radioactive interferences are stripped out by coprecipitation on ferric hydroXide (yttrium strip) followed by a barium chromate strip. The strontium* is precipitated as a carbonate, which is dried and weighed. The samples and b~ank are then counted on a low background gas proportional counter and, again, at least 14 days later. The basis for this two count method is-that sr-90 and sr-89 are both unknown quantities requiring two simultaneous equations to solve for them. .
-:--* . .
calculation of sr-90 Activity:
---...
* sr-90 Results (pCi/m3 )                         =                                                       N4/R (2.22)*(E)*(E(l5)/E')*(S6)*(V)*(U)
-*  
                                                                                              = W2 where SS           = A + B*M     + C:11M~ (This is the general form of the norma1ized Sr-90 efficiency regression equation for one particular gas proportional counter, where A, B ~d Care regression coefficients.)
.,.-----*------, ... -* --------*:-....... -..... -*. --  
M   = Thickness density of strontium carbonate precipitate, mg/cm2
-! *1 t2 = Elapsed tJ.me from. Y-90 strip* to second count*** -2.667 = Half-life of Y-90, days R1 = D + E*M + F*M 2 (This is the general. form of the regression equation for Y-90 effwy/sr-90 eff'Y ratio for one particular gas proportionaJ.
* E(l5)/E'           = Ratio of sr-90 efficiency at thickness value of l5mg/cm2 to sr-90 counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples)
counter, where D, E and F are regression coefficients.)
E   = sr-90   counting standard efficiency v   = sample     quantity (m3) u = Chemical yield
N2 = X -Y, where X and Y are recount gross counts and background counts, respectively Nl = Xl Ylu where Xl and Yl are initi.a.l gross counts and background counts, respectively 2.22 = No. of dpm per pCi Fl= EXP ((-0.693/2.667)*t2)
              .,                                        N4 = (N2           Fl*Nl)/W1                       = net             counts due to sr-90 only i
R = Count time of sample and blank Using the same variable definitions as above, the 2-sigma error for sr-90 (pCi/m 3) = Again, keeping the same variable definitions, the LLD for sr-90 (pCi/m3) = + (Xl+Yl1*Flj l/:2 Wl . ca.J.culation of sr-89 Activity:
1
sr-89 Results (pCi/m 3) = N6/R . (2.22)*(E)*(E(l5)/E')*(S7)*(V)*(U)*(F9)
          - *\
S7 G + H*M + I*M 2 ('rh.is is the general. form of the normalized efficiency regression equation for one particular gas proportional counter where G, Hand I are regression coefficients.)
              *1 Il = l - EXP ((-0.693/2.667)*tl)
N6 = Nl -N7*(l + Rl*Il) H'1 = (N2 Fl*Nl)/Wl (This represents ec:runts due to Sr=90) E(l5)/Ew = Ratio of sr-89 efficiency at thickness value of l5mq/cm 2 to sr-90 -countinq standard efficiency run at the time of instrument cal.;U:)ration (This standard is run with each group of environmental stront.iwn samples).
I2 = l - EXP ((-0.693/2.667)*t2) tl       = Elapsed     time from Y-90 strip to first count
.--------,--:-*-*....---..------*-
  . *: . ,.. j 132
..  
          .. j
*.-;--o-
                  - - - - * ---*-* - ~--- --*--- ----_~.. *-....--*-----**-~-~-; -:-- *. .-.---'"-~*--::"':' . ,:--~~-"--::--*-;---- - -- --~... -~*--:-:--=*~---~-:* -* :--~--.,---- .,.- ---- *------, ... -* - - - -- - - - *:- ....... - ..... - *. --
**. ,-. -::---:-*:--.--**-****--.
 
*--**** *-----:
t2 = Elapsed tJ.me from. Y-90 strip* to second count*** -
..* , "n ---* -* -... --* -** ** ----.... i 
2.667        = Half-life                              of Y-90, days R1      =D +                  E*M + F*M2 (This is the general. form of the regression equation for Y-90 effwy/sr-90 eff'Y ratio for one particular gas proportionaJ. counter, where D, E and F are regression coefficients.)
. ' '* *. -... *, . *' *i *--* *.; . i *::. : *. j *** t *-.; i .. , . : F9 =EXP t =Elapsed time from midpoint of collection.period.to time of recount for milk samples only. For all other samples, this represents the elapsed time from sample stop date to time of recount. 50.5 = Half-life of Sr-89, days All other quantities are as previously defined. The 2-sigma error for sr-89 (pCi/m 3) = 2* (sa2+s92)2 (Nl -N7*(l+Rl*Il))
N2      =X -                  Y, where X and Y are recount gross counts and background counts, respectively Nl    = Xl              ~ Ylu where Xl and Yl are initi.a.l gross counts and background counts, respectively 2.22        = No.                of dpm per pCi Fl= EXP ((-0.693/2.667)*t2) i R    = Count                        time of sample and blank Using the same variable definitions as above, the 2-sigma error for sr-90 (pCi/m3 ) =
S9 = (Xl+Yl).1/2 All other variables are as previously defined. Keeping the same variable definitions, the LLD for sr-89 (pCi/m 3) = 4.66*(sa 2+s9 2)1 1 2 134
Again, keeping the same variable definitions, the LLD for sr-90 (pCi/m3)                                                 =
... -------____ ..,.....:.
                                                                                                  + (Xl+Yl1*Flj l/:2 Wl        .
__ *-**
ca.J.culation of sr-89 Activity:
--*  
sr-89 Results (pCi/m3 )                                           =                                                 N6/R
---*-___ _,, ___ _,_"""7 -------------_:." ** -** ..-----------*-------* -* ------*':-
                                                                                                    . (2.22)*(E)*(E(l5)/E')*(S7)*(V)*(U)*(F9)
. ! . , .. * *. . I . 'i SYNOPSIS OF *TELEDYNE
S7 ~ G + H*M + I*M2 ('rh.is is the general. form of the normalized sr~89 efficiency regression equation for one particular gas proportional
*ISOTOPES PROCEDURE.*
*1 counter where G, Hand I are regression coefficients.)
ANALYSIS OF COMPOSITED AIR PARTICULATE FILTERS FOR RADIOSTRONTIUM The composited air filters are leached with concentrated nitric acid, with *heating, in the presence of strontiwn carriero After adding deionized water, the sample is gravity filtered through a paper filter and the filtrate diluted further with additional deionized water, cefore ceing split into two equal parts. One part is put aside for gross alpha analysis.
N6    = Nl              - N7*(l + Rl*Il)
and the other part evaporated on a hotplate to a small volume. The sample is transferred to a centrifuge tu.be and fuming nitric acid added to form the strontium nitrate precipitate.
H'1    = (N2                ~      Fl*Nl)/Wl (This represents ec:runts due to Sr=90)
After centrifuging and pouring off the supernate, the precipi= tate is dissolved in deionized water and an iron scavenge performed.
E(l5)/Ew            = Ratio                        of sr-89 efficiency at thickness value of l5mq/cm2 to sr                                                          countinq standard efficiency run at the time of instrument cal.;U:)ration (This standard is run with each group of environmental stront.iwn samples).
This marks the of the ingrowth period. centrifuging and discarding the precipitate, standardized yttr1Wl1 carrier is added to the supernate and the sample is set aside for 5 to 7 days. After this period, the sample is alkalinized with ammonium hydroXide and heated in a hot water oath to form *yttrium hydroxide.
    ---..---.-~*- .--------,--:-*-*....---..------*- :-'..,.........,:--.-0*~**.-.*-:;- -*.....,-.-**-**--~-----------~~ .. -------..-,......-~~-*-- *.-;--o- **-~:-""..,_ **. ,-. -::---:-*:--.--**-****--. *--**** *-----: ~':'"*---*-~* ..* , "n ---* - * - ... - - * - ** ** - - - - ....
After cooling, the sample is centrifuged and the supernate saved for Sr-89 determination.
 
The precipitate is dissolved with dilute nitric and hydrochloric acids, and the yttrium precipitated as oxalate using saturated ammonium oxalate solution.
F9 =EXP _((-0.693/S0.5)~t) t =Elapsed time from midpoint of collection.period.to time of recount for milk samples only. For all other samples, this represents the elapsed time from sample stop date to time of recount.
The yttrium oxalate is mounted on a . tared paper filter, oven dried, weighed and counted on a gas proportional counter. 'l'he sample is then recounted the fol1owing day to confirm the decay of Y-900 The superna.te, saved for sr-89 determination.
50.5 = Half-life of Sr-89, days All other quantities are as previously defined.
is treated with saturated sodium solution to precipitate strontiwn carbonate which is filtered on a tared qlass fil:ler filter, oven-dried and likewise counted 200 minutes on a gas proportional.
The 2-sigma error for sr-89 (pCi/m3 ) = 2* (sa2+s92)2 ~W3 (Nl - N7*(l+Rl*Il))
counter. These samples, however, are covered with an aomq/cm 2 aluminum al:>sorber to stop the beta emissions, thus allowing the Sr-89 betas to be counted aloneo The sr-89 activity (pCi/m 3) is computed as follows: A = (G/T-Bc-Ba)
S9            = (Xl+Yl).1 / 2 All other variables are as previously defined.
+/-
Keeping the same variable definitions, the LLD for sr-89 (pCi/m3 ) =
(2.22*V*Y*D*E)
4.66*(sa2 +s9 2 ) 1 12
(2.22*V*Y*D*E)
      *.   ~:
If the net activity (G/T -a) is less than or equal to the 2a: counting error, the activity is considered MDL where G 'r Be Ba where MDL = 2*(2:eB/T)l/2 (2.22*V*Y:eD:sE)
*--*      *.;*i
= Total. sample counts = sample count time, mins * =Background rate of counter,-cpm 2o22 = Backqround addition from Sr-90 and ingrowth of
          . i
= dpm/pCi v y D = sample volume, m3 = Chemical yield of strontium
*::.:      *. j 134
=
        *** t
decay factor from midpoint of collection period to counting date. E = sr-89 counting efficiency with 80 mq/cm 2 alW!Unum absorber MUl.tiples of counting error a: = m 
      *-.; i
. j : _; . ' ''-.. ____
                  -----.----~ ... - - - - - - - _ _ _ _ ..,.....:. _ _* -
--: .. '! ... *.; . *. * .. The sr-90 activity (pCi/m 3) .is computed as.* fol.lows; A = (G/T-B) (2.22*V*Y*D*E)
                                                                        ** ----.---~.-- - - * --~---------*-:";"".,- ---*- ___ _,, _ _ _ _,_"""7 - ----- - - -----_:." ~ ** - **..-- - --- -- - - -*----- - -* -* -- - - -~. - -
+/-. (2.22*V*Y*D*E)
 
Y = Chemica1 yieJ.d of the mount or sample counted D = Decay factor from the colJ.ection to the counting date E = counter efficiency AJ.1 other variabJ.es are as previousJ.y defined. If the net activity (G/T-B) is less* than or equa1 to the counting error, the activity is considered MDL where MDL = 2*(2*B/T)1/2 (2.22*V*Yi*Y 2*I*D*&) 136
SYNOPSIS OF *TELEDYNE *ISOTOPES PROCEDURE.*
--
ANALYSIS OF COMPOSITED AIR PARTICULATE FILTERS FOR RADIOSTRONTIUM The composited air filters are leached with concentrated nitric acid, with
-----=-
            *heating, in the presence of strontiwn carriero After adding deionized water, the sample is gravity filtered through a paper filter and the filtrate diluted further with additional deionized water, cefore ceing split into two equal parts. One part is put aside for gross alpha analysis. and the other part evaporated on a hotplate to a small volume. The sample is transferred to a centrifuge tu.be and fuming nitric acid added to form the strontium nitrate precipitate. After centrifuging and pouring off the supernate, the precipi=
-------:,.--------"<'"'  
tate is dissolved in deionized water and an iron scavenge performed. This marks the ~eginning of the Y~9o ingrowth period. centrifuging and discarding the precipitate, standardized yttr1Wl1 carrier is added to the supernate and the sample is set aside for 5 to 7 days. After this period, the sample is alkalinized with ammonium hydroXide and heated in a hot water oath to form
--_--:--:,.........-
          *yttrium hydroxide. After cooling, the sample is centrifuged and the supernate saved for Sr-89 determination. The precipitate is dissolved with dilute nitric and hydrochloric acids, and the yttrium precipitated as oxalate using saturated ammonium oxalate solution. The yttrium oxalate is mounted on a .
-**------.,......,,__,
tared paper filter, oven dried, weighed and counted on a gas proportional counter. 'l'he sample is then recounted the fol1owing day to confirm the decay of Y-900 The superna.te, saved for sr-89 determination. is treated with saturated sodium car~onate solution to precipitate strontiwn carbonate which is filtered on a tared qlass fil:ler filter, oven-dried and likewise counted 200 minutes on a gas proportional. counter. These samples, however, are covered with an aomq/cm2 aluminum al:>sorber to stop the sr~90 beta emissions, thus allowing the Sr-89 betas to be counted aloneo The sr-89 activity (pCi/m3 ) is computed as follows:
.* ... **:  
A =    (G/T-Bc-Ba) +/- ~m*((G/T+Bc+Ba)/T)l/2 (2.22*V*Y*D*E)        (2.22*V*Y*D*E)
. l . ' I I. SYNOPSIS OF PSE&G. RESEARCH CORPORATION PROCEDURE
If the net activity (G/T -a) is less than or equal to the 2a: counting error, the activity is considered MDL
*. RADIOSTRONTIUM ANALYSIS.OF*RAW MILK StalJle strontiwn carrier is first introduced into.a nti.lk sample and into a distilled water sample of equal volume to be used as a blank. The sample(s) and blank are passed through cation resin columns which adsorb strontium, calcium, magnesium and other cations. These cations are then e1uted off with a TRIS-buffered 4N chloride solution into a beaker and precipitated as carbonates.
      .!                  where MDL  = 2*(2:eB/T)l/2 (2.22*V*Y:eD:sE) where    G  = Total. sample counts
The carbonates are converted to nitrates with 6N nitric acid and, by aqidifying further to an* overall concentration of 70% nitric acid, strontium is forced out of solution somewhat ahead of calcium. Barium chromate precipitation is then performed to remove any traces of radium and rad.iobarium.e Strontium recrystallization is carried out to remove residual calcium which may have been coprecipitated with the initial strontium itation. Another recrystallization removes ingrown Y=90, marking the time of the yttrium strip *. The strontiwn is precipitated as its carbonate, filtered, dried and to determine strontium recovery.
                    'r = sample count time, mins
The samples and blank are then counted on a low background gas proportional.
* Be =Background rate of counter,-cpm
counter and, again, at least 14 days later. The basis for this two-count method is that sr-90 and sr-89 are both unknown quantities requiring two simultaneous equations to solve for them. caiculation Activity:
..*                Ba = Backqround addition from Sr-90 and ingrowth of Y~90 2o22 = dpm/pCi
Sr-90 Results (pCi/L) = N4/R where SS = A + B*M + C*M 2 (This is the qenera1 form of the norma1ized Sr-90 efficiency regression equation for one particular gas proportional counter, where A, Band care regression coefficients.)
      *.           v = sample volume, m3 y = Chemical yield of strontium D = sr~89 decay factor from midpoint of collection period to counting date.
M = Thickness density of strontium carbonate precipitate, mg/cm2 E(lS)/E' = Ratio of sr-90 efficiency at thickness va.l.ue of l5mg/cm 2 to Sr-90 countinq standard eff icienc:y run at the time of instrument cal.illration (This standard is run with each group of environmental strontium samples)
E = sr-89 counting efficiency with 80 mq/cm2 alW!Unum absorber a:m = MUl.tiples of counting error
* E =
    . I
countinq standard efficiency v .,, Sample quantity (liters) u "" Chemical yiel.d N4 "':! (N2 FlsaNl)/Wl
  .   'i
= net counts due t.o Sr=90 onl.y Wl, "" ((l + R11iI2) (1 + R1*Il}liFl)
 
Il, "" EXP ((=Oo693/2o667)*'t:l}
The sr-90 activity (pCi/m3 ) .is computed as.* fol.lows; A  =                (G/T-B)                    +/-. ~m*((G/T+B)/T) 1 / 2 (2.22*V*Y*D*E)                                  (2.22*V*Y*D*E)
.. --* ... **-* -*
Y = Chemica1 yieJ.d of the mount or sample counted D = Decay factor from the colJ.ection to the counting date E = counter efficiency AJ.1 other variabJ.es are as previousJ.y defined.
..
If the net activity (G/T-B) is less* than or equa1 to the                                                                                  2~    counting error, the activity is considered MDL
**-* ,.  
          . j where MDL                  =              2*(2*B/T) 1 /2 (2.22*V*Yi*Y 2*I*D*&)
-;-*--:-*
      ~ :    _;
-----;
.. ____ :_~--- -
_.. '.*** ' . : "j " -. ; .. I2 = 1 -EXP {(-0.693/2.667)*t2) tl = Elapsed time.from Y-90 strip to first count* t2 = Elapsed time from Y-90 strip to second count 2.667 = Half-life of Y-90, days Rl = D + E*M + F*M 2 (This is the general form of the regression equation for Y-90 eff'y/sr-90 eff'Y ratio for one particular gas proportional counter, where D, E and F are regression coefficients.)
136
H2 = X -Y, *where X and Y are recount gross counts and
                  -----~ -- ---------~---- -----=- -~*- -....---..--,,_-.-,....,--~-- - - -----:,.--------"<'"' --_--:--:,.........- ------~-- -**- ----- .,......,,__, -c------**-.----*.~-
: counts, Hl = Xl -Yl, where Xl and Yl are initial gross counts and background
 
: counts, 2.22 = Ho. of dpm per pCi Fl= EXP ((-0.693/2.667)*t2)
SYNOPSIS OF PSE&G. RESEARCH CORPORATION PROCEDURE                                    *.
R .:. count time of sample and blank Using the same variable definitions as above, the 2-sigma error for Sr-90 (.pCi/L) = 2* lix:u.l + (XJ+Y1}*F12]l/2* (Wl*W2). Lwi 2 Wl J (H2-Fl*Nl)
RADIOSTRONTIUM ANALYSIS.OF*RAW MILK StalJle strontiwn carrier is first introduced into.a nti.lk sample and into a distilled water sample of equal volume to be used as a blank. The sample(s) and blank are passed through cation resin columns which adsorb strontium, calcium, magnesium and other cations. These cations are then e1uted off with a TRIS-buffered 4N sodi~ chloride solution into a beaker and precipitated as carbonates. The carbonates are converted to nitrates with 6N nitric acid and, by aqidifying further to an* overall concentration of 70% nitric acid, strontium is forced out of solution somewhat ahead of calcium. Barium chromate precipitation is then performed to remove any traces of radium and rad.iobarium.e Strontium recrystallization is carried out to remove residual calcium which may have been coprecipitated with the initial strontium precip~
Again, keeping the same variable definitions, the LLD for sr-90 (pCi/L) = 4.66* + (Xl+Yla*n 2J l/2 Lwi wi J calculation of sr-89 Activity:
itation. Another recrystallization removes ingrown Y=90, marking the time of the yttrium strip * . The strontiwn is precipitated as its carbonate, filtered, dried and weighe~ to determine strontium recovery. The samples and blank are then counted on a low background gas proportional. counter and, again, at least 14 days later. The basis for this two-count method is that sr-90 and sr-89 are both unknown quantities requiring two simultaneous equations to solve for them.
sr-89 Results (pCi/L) = N6/R (2.22)*(E)*(E(l5)/E')*(S7)*(V)*(U)*(F9)
caiculation                of 0 Sr~9o    Activity:
= W3 S7 = G + H*M + I*M2 (This is. the general form of the normalized sr-89 efficiency regression equation for one particular gas proportional counter where G, Hand I are regression coefficients.)
Sr-90 Results (pCi/L)                      =                                                             N4/R (2o22)*(E)*(E(l5)/E 9 )~(S6)*(V)li(U) where SS            =A +        B*M + C*M2 (This is the qenera1 form of the norma1ized Sr-90 efficiency regression equation for one particular gas proportional counter, where A, Band care regression coefficients.)
NS = Nl -N7*(l + Rl*Il) N7 = (N2 -Fl*Nl)/Wl (This represents counts due to Sr-90) 138 ---...---*---:------.-'""'*---
M = Thickness density of strontium carbonate precipitate, mg/cm2 E(lS)/E' = Ratio of sr-90 efficiency at thickness va.l.ue of l5mg/cm2 to Sr-90 countinq standard efficienc:y run at the time of instrument cal.illration (This standard is run with each group of environmental strontium samples)
*----:----...----
* E =      sr~90      countinq standard efficiency
*--*-**--
.l                                            v .,,    Sample quantity (liters) u "" Chemical yiel.d N4      "':! (N2 ~      FlsaNl)/Wl               = net              counts due t.o Sr=90 onl.y Wl,
*---.-.-----:--.
                                                  "" ((l + R11iI2)                ~      (1 + R1*Il}liFl)
*-*----
Il,
"'7";"-:-:-
                                                  ""  l~      EXP ((=Oo693/2o667)*'t:l}
... ----:-*.....-........-----_ --* *-.,-. -.--*-*: . **--
I I.
-.-****.--* ----. . ------*-*-*. -  
    - - * ... **-* - * -----~.---: --:--*-:--,------.~~--,* ~*-----~-------. .. -~..,._-o";"..--;-T--*--,*:- **-* ,. ---~***.**-*-:- -;-*--:-* -----;
.. * . ' ', i ' .. E(lS)/Ew = Rat:ro of.Sr;..99 effic.iencyat thickness va.J.ue of lSmq/cm 2 to sr-90 counting standard ef.ficiency run *at the time instrument calibration (This standard is.run with.each grqup of environmental strontiwn samples) .*. t = Elapsed t.ilne from midpoint of collection period to time of recount for milk samples only. For all other samples, this represents the elapsed t.ilne from sample stop date to time of recount. All other quantities are as previously defined. The 2-sigma error for (pCi/L) = 2* (sa2+s92)1/2
 
*W3 (Nl -N7*(l+Rl*Il))
_.. ~
sa =f<x+Yl + l/2 Lw1 2 w1 J S9 = {Xl+Yl)l/2 . All.other varial:Jles are as previously definedQ 
        "j I2 = 1              -   EXP    {(-0.693/2.667)*t2) tl = Elapsed time.from Y-90 strip to first count*
*.: ,. *,<
t2 = Elapsed time from Y-90 strip to second count 2.667 = Half-life of Y-90, days Rl = D + E*M + F*M2 (This is the general form of the regression equation for Y-90 eff'y/sr-90 eff'Y ratio for one particular gas proportional counter, where D, E and F are regression coefficients.)
* SYNOPSIS OF P.SE&G RESEARCH' CORPORATION*  
H2 = X - Y, *where X and Y are recount gross counts and                                                                                                          back~ound counts, respect~vely Hl = Xl - Yl, where Xl and Yl are initial gross counts and background counts, respe~tively 2.22 = Ho. of dpm per pCi Fl= EXP ((-0.693/2.667)*t2)
*PROCEDURE_*:.:*;
R .:. count time of sample and blank Using the same variable definitions as above, the 2-sigma error for Sr-90 (.pCi/L) =
.... -RADIOSTBONTIUMANALYSIS OF WATER Stal:>le strontium carrier is introduced into a water sample and into a distilled water sample of the same volume which is used as a blank. The sample(s) and blank arethen made alkaline and heated to near boiling"before precipitating the carbonates.
2*   lix:u.l      + (XJ+Y1}*F12]l/2*                                             (Wl*W2).
The carbonates are converted to nitrates by fuming acid recrystallization which acts to purify the sample of most of the calcium. Radioactive interferences are stripped out by tion on ferric.hydroxide (yttrium strip) followed by a barilim chromate strip. The strontium is precipitated as a carbonate before being dried and weighed. The samples and blank are then counted on a low background gas proportional counter and, again, at least 14 days later. The basis for this two count. method is that sr-90 and sr-89 are both unknown quantities requiring two simultaneous equations to solve for them. Since surface waters , _ as well as some drinking water samples , have bee*n found to contain significant amounts of siaJ:>le strontium, a separate aliquot from each sample is a.!alyzed for stal:>le strontium.
Lwi2                        Wl                  J                    (H2-Fl*Nl)
These results are used in correcting the chemical recovery of strontium to its true value. Calculation of sr-90 Activity:
Again, keeping the same variable definitions, the LLD for sr-90 (pCi/L) =
Sr-90 Results (pCi/L) = N4/R (2.22)*(E)*(E(lS)/E')*(S6)*(V)*(U)
4.66* ~ + (Xl+Yla*n                                            2J l/2 Lwi                            wi                      J calculation of sr-89 Activity:
:*: = W2 ' . j .. . .
sr-89 Results (pCi/L) =                                                                                                      N6/R (2.22)*(E)*(E(l5)/E')*(S7)*(V)*(U)*(F9)
j .. j ' ' .
                                                                                                                        = W3 S7        =G+          H*M + I*M2 (This is. the general form of the normalized sr-89 efficiency regression equation for one particular gas proportional counter where G, Hand I are regression coefficients.)
NS        = Nl        - N7*(l + Rl*Il)
N7 = (N2 - Fl*Nl)/Wl (This represents counts due to Sr-90) 138
            ---...---*---:------.-'""'*--- * - - - - : - - - - . . . - - - - * - - * - * * - - -;-'~~-~-.---:----~. *---.-.-----:--. *-*---- :-~~---:--:-.,.*---:- "'7";"-:-:- ... -  ---:-*.....-........-----_ -----~-- *~ --* *- .,-. -.--*-*: . **-- --~,---.--:- -.- ****.--* --- - . . ------ *- *-*. -
 
E(lS)/Ew  = Rat:ro of.Sr;..99 effic.iencyat thickness va.J.ue of lSmq/cm2 to sr-90 counting standard ef.ficiency run *at the time ~.of instrument calibration (This standard is.run with.each grqup of environmental strontiwn samples) .*.
t = Elapsed  t.ilne from midpoint of collection period to time of recount for milk samples only. For all other samples, this represents the elapsed t.ilne from sample stop date to time of recount.
All other quantities are as previously defined.
The 2-sigma error for sr~eg (pCi/L)    = 2* (sa2+s92)1/2 *W3 (Nl - N7*(l+Rl*Il))
sa =f<x+Yl + <xi+n~*Fl ~ l/2 Lw1 2          w1    J S9 = {Xl+Yl)l/2
            . All.other varial:Jles are as previously definedQ i
'  ..~
 
SYNOPSIS OF P.SE&G RESEARCH' CORPORATION* *PROCEDURE_*:.:*;.... -
RADIOSTBONTIUMANALYSIS OF WATER Stal:>le strontium carrier is introduced into a water sample and into a distilled water sample of the same volume which is used as a blank. The sample(s) and blank arethen made alkaline and heated to near boiling"before precipitating the carbonates. The carbonates are converted to nitrates by fuming nit~ic acid recrystallization which acts to purify the sample of most of the calcium. Radioactive interferences are stripped out by coprecipita-tion on ferric.hydroxide (yttrium strip) followed by a barilim chromate strip.
The strontium is precipitated as a carbonate before being dried and weighed.
The samples and blank are then counted on a low background gas proportional counter and, again, at least 14 days later. The basis for this two count.
method is that sr-90 and sr-89 are both unknown quantities requiring two simultaneous equations to solve for them.
Since surface waters , _as well as some drinking water samples , have bee*n found to contain significant amounts of siaJ:>le strontium, a separate aliquot from each sample is a.!alyzed for stal:>le strontium. These results are used in correcting the chemical recovery of strontium to its true value.
Calculation of sr-90 Activity:
Sr-90 Results (pCi/L)                    =                                N4/R (2.22)*(E)*(E(lS)/E')*(S6)*(V)*(U)
:*:                                                                      = W2 where SS        =A +      B*M + C*M2 (.This is the general form of the normalized sr-90 efficiency regression equation for one particular gas proportional counter, where A, Band care regression coefficients.)
M = Thickness density of strontium carbonate precipitate, mg/cm2 E(lS)/E'        = Ratio        of sr-90 efficiency at thickness value of 1Smg/cm2 to Sr-90 counting standard efficiency run at the time of instrume.nt calibration (This standard is run with each group of* environmental
  . j'                                                        strontium samples)
      ..                                              E  = sr-90 counting standard efficiency
.. j
    ~-:.
v  = Sample quantity (liters)
  .. j u  = Chemical yield N4    = (N2 - Fl*Nl)/Wl = net counts due to                                  Sr-90 only Wl    = ((l + Rl*I2) - (l + Rl*Il)*Fl)
. ::~::J
.*.*
.*.*
* 1 .. ,.') i where SS = A + B*M + C*M 2 (.This is the general form of the normalized sr-90 efficiency regression equation for one particular gas proportional counter, where A, Band care regression coefficients.)
* 1 Il    = l - EXP ((-0.693/2.667)*tl) 140*
M = Thickness density of strontium carbonate precipitate, mg/cm 2 E(lS)/E' = Ratio of sr-90 efficiency at thickness value of 1Smg/cm 2 to Sr-90 counting standard efficiency run at the time of instrume.nt calibration (This standard is run with each group of* environmental strontium samples) E = sr-90 counting standard efficiency v = Sample quantity (liters) u = Chemical yield N4 = (N2 -Fl*Nl)/Wl
    .. ,.')
= net counts due to Sr-90 only Wl = ((l + Rl*I2) -(l + Rl*Il)*Fl)
i
Il = l -EXP ((-0.693/2.667)*tl)
              -~~~-.--**~---~--*------~--.--~---.-,---~,-.-.:-*--*--.*--,-."""*:-~:---..-.*-*::--:-:_.*-:-*--*-*":'"r---:--.-*-----*-;**-*~v**-~*:-:""'-*"*-:**~,-*-.**-***-:*:-*;******-*-*
* 140* 
 
*, I2 = l -EXP tl =Elapsed time*from Y-90 strip to first count t2 = Elapsed time from Y-90 strip to second count 2.667 = Half-life of Y-90, days R1 = D + E*M + F*M2 (This is the general form of the regression equation for Y-90 eff'y/Sr-90 eff 'Y ratio for one particular gas
I2  =l     - EXP             ((-0~693/2.667)*t2) tl =Elapsed time*from Y-90 strip to first count t2   = Elapsed time                       from Y-90 strip to second count 2.667     = Half-life of                       Y-90, days R1 = D + E*M + F*M2 (This is the general form of the regression equation for Y-90 eff'y/Sr-90 eff 'Y ratio for one particular gas
* proportional counter, where D, E and F are regression c:oeffic.ients.)
* proportional counter, where D, E and F are regression c:oeffic.ients.)
N2 = X -Y, where X and Y are recount gross counts and background counts, respectively Nl = Xl -Yl, where Xl and Yl are initial gross counts and background counts, respectively 2.22 = No. of dpm per pCi Fl= EXP ((-0.693/2.667)*t2)
N2   =X -         Y, where X and Y are recount gross counts and background counts, respectively Nl   = Xl     - Yl, where Xl and Yl are initial gross counts and background counts, respectively 2.22 = No. of dpm per pCi Fl= EXP ((-0.693/2.667)*t2)
R = count time of sample and :blank Using the same variable definitions as anovef the 2=sigma. error for sr-90 (pCi/L) = + (Wl*W2) L Wl Wl (N2-Fl*Nl)
R   = count             time of sample and :blank Using the same variable definitions as anovef the 2=sigma. error for sr-90 (pCi/L)                                                       =
Again, keeping the same variable definitions, the LLD for Sr-90 (pCi/L) = 4.66*[<x+Yl t
2~ r~ + CX1+Yl~*F11l/2 1i (Wl*W2)
l/2 Wl 2 Wl caJ.culation of sr-89 Activityg ResuJ.ts (pCi/L) = N6/R  
LWl                              Wl                                   (N2-Fl*Nl)
= W3 S7 = G + R1iM + I*M 2 (This is the general form of the normalized efficiency regression equation for one particular gas proportional counter wn.ere Gf H and I are regression coefficients  
Again, keeping the same variable definitions, the LLD for Sr-90 (pCi/L) =
* .) N6 = Nl -N7*(l + Rl*Il) N7 = (N2 = Fl*Nl)/Wl (This represents counts due to Sr=90) 141 -*---* --.-,, **-*--:----*--
4.66*[<x+Yl                   t     (Xl+Yl~*Fl] l/2 Wl 2                         Wl caJ.culation of sr-89 Activityg sr~eg      ResuJ.ts (pCi/L)                     =                                                 N6/R
*----*-
*,                                                                                  (2.22)*(E)*(E(l5)/E')*(S7)~(v)~(U)*(F9)
... -------.. . .,...-._,....  
                                                                              = W3 S7 =   G   + R1iM + I*M2 (This is the general form of the normalized sr~89 efficiency regression equation for one particular gas proportional counter wn.ere Gf H and I are regression coefficients * .)
*----*.-*-
N6 = Nl - N7*(l + Rl*Il)
--  
N7   = (N2         =   Fl*Nl)/Wl (This represents counts due to Sr=90) 141
:'_ .* *,: .. **! . I ... ; --. ! . t .. ; .-. E(lS)/E' =Ratio of sr-89 at* thickness of l5mq/cm 2 to sr-90 count.inq standard efficiency run at the time*of i.ns-trument calibration (This standard is. run.with each qroup of environmental strontiuin
  -*---* --.- ,, **-*--:----*-- *----*- --:-*---.*----~ ...-- -----. --.--.---.---~~-..,...-._,.... *- ---*.-*- *--~...--*- --
* F9 = EXl? ((-0.693/50.S)*t) t = Elapsed time from midpoint of collection period to time of recount for milk samples only. For all other samples, this represents the elapsed. time from sample stop date to time of recount.  
 
= Half-life of. sr-89, days All other quantities are as previously defined. The 2-sigma error for sr-89 (pCi/L) = 2* (sa2+592yl/2  
E(lS)/E' =Ratio of sr-89 efficien~y at* thickness valu~ of l5mq/cm2 to sr-90 count.inq standard efficiency run at the time*of i.ns-trument calibration (This standard is. run.with each qroup of environmental strontiuin samp~es)
*W3 (Nl -N7*(l+Rl*Il))
* F9 = EXl? ((-0.693/50.S)*t) t = Elapsed time from midpoint of collection period to time of recount for milk samples only. For all other samples, this represents the elapsed. time from sample stop date to time of recount.
sa =Rx+;) + cx1+na*r1j l/2 Lw1 wi S9 = (Xl+Yl)1/2 All other variables are* as previously defined. Keeping the same variable defini.tions, the LLD for sr-89 (pCi/L) = 4.ss*(sa 2+s9 2)1 1 2 142 -----------
so~s  = Half-life of. sr-89, days All other quantities are as previously defined.
...  
The 2-sigma error for sr-89 (pCi/L) = 2* (sa2+592yl/2 *W3 (Nl - N7*(l+Rl*Il))
-----
sa =Rx+;) + cx1+na*r1j l/2 Lw1             wi S9 = (Xl+Yl) 1 / 2 All other variables are* as previously defined.
.. -
Keeping the same variable defini.tions, the LLD for sr-89 (pCi/L) =
-.---* -------**. ..,.. --*  
4.ss*(sa 2+s9 2 ) 112
---.--._::--.." .** *.*=-. r-****-:---**-.
            . I
'*. *
            .t
* SYNOPSIS OF PSE&G RESEARCH CORPORATION*:
:'_ .*                                                                                            142
l?ROCEDURE  
                ----------- ~-~-~----,-~--- ... ----~-----~---- - - - - - ---,..~------ .. - -~- --~--- ----~ - .-- - * ----- -- **. ..,.. - ~ -* **.---**~ ---.- -._::--.." .** *.*=-. r-****-:---**-.
-RADIOSTRONTIUM ANALYSIS OF VEGETATION, MEAT AND AQUATIC SAMPLES The samples are weighed (recorded as "wet" weight) as received, .before .being placed in an oven to dry at l00&deg;Cc At the completion of the drying period, samples are again. weighed (recorded as "dry" weight) and then pulverized.
 
A measured amount {quantity dependent on desired sensitivity) of the pulverized sample is first charred over a Bunsen .burner and then ashed in a muffle -furnacec The ash is fused with 40g sodium carbonate, along with 20mg strontium carrier, at 90o 0 c for 1/2 hour. After removal from the the melt is cooled, pulverized and added to 500ml distilled water and heated to near boiling for 30 minutes, with stirtingc The sample is filtered (filtrate discarded) and the carbonates on the filter dissolved with lgl nitric acid (HNa 3). The resultant nitrates are heated to dryness and are dissolved in 20ml di,stilled water before adding 60m.J. fuming HN0 3 o After calcium removal with anhydrous acetone, radioactive interferences are stripped out by coprecipitation on ferric hydroXide followed by. coprecipitation on barium chromate.  
SYNOPSIS OF PSE&G RESEARCH CORPORATION*: l?ROCEDURE -
*The strontium is precipitated as its carbonate, which is dried and weighed. The samples are then counted on a low background gas proportional counter and, again, at least 14 days later. The basis for this two-count method is that and sr-89 are .both unknown quantities requiring two simultaneous equations to solve for them
RADIOSTRONTIUM ANALYSIS OF VEGETATION, MEAT AND AQUATIC SAMPLES The samples are weighed (recorded as "wet" weight) as received, .before .being placed in an oven to dry at l00&deg;Cc At the completion of the drying period, samples are again. weighed (recorded as "dry" weight) and then pulverized. A measured amount {quantity dependent on desired sensitivity) of the pulverized sample is first charred over a Bunsen .burner and then ashed in a muffle                                                                                                   -
furnacec The ash is fused with 40g sodium carbonate, along with 20mg strontium carrier, at 90o 0 c for 1/2 hour. After removal from the f~rnace, the melt is cooled, pulverized and added to 500ml distilled water and heated to near boiling for 30 minutes, with stirtingc The sample is filtered (filtrate discarded) and the carbonates on the filter dissolved with lgl nitric acid (HNa 3 ). The resultant nitrates are heated to dryness and are dissolved in 20ml di,stilled water before adding 60m.J. fuming HN0 3 o After calcium removal with anhydrous acetone, radioactive interferences are stripped out by coprecipitation on ferric hydroXide followed by. coprecipitation on barium chromate. *The strontium is precipitated as its carbonate, which is dried and weighed. The samples are then counted on a low background gas proportional counter and, again, at least 14 days later. The basis for this two-count method is that ~r-90 and sr-89 are .both unknown quantities requiring two simultaneous equations to solve for them *
* caicuiation of sr-90 Activity:
* caicuiation of sr-90 Activity:
Sr=90 ResUl.ts (pCi/kq wet) = N4/R ( 2 e 22 ) "' ( E) "' ( E ( 15 ) /E: i ) .... (SS ) "' ( V ) * ( u.) = W2 where SS = A + B*M + C*M 2 (This is the general form of the normalized sr-90 efficiency regression equation for one particular gas proportional counter, where A, Band care regression coefficients.)
Sr=90 ResUl.ts (pCi/kq wet)                                                 =
M = Thickness density of strontiwn carbonate precipitate, mg/cm2  
                                                                                                          = W2
= Ratio of efficiency at tlti.ckness va.J.ue of l5mg/cm2 to.
( 2 e 22 ) "' ( E) "' ( E ( 15 ) /E: i N4/R
counting standard efficiency run at the time of instrument Cal.illration  
                                                                                                                                                                          ) .... (SS ) "' ( V ) * ( u.)
('rhiS Standard is run With each g'I'OUp Of environmental strontiwn samples) E = sr-90 countinq standard efficiency V = Sample quantity (kq wet) u = Chemical yield N4 = (H2 Fl"'Hl)/Wl.  
where SS               =A +           B*M + C*M2 (This is the general form of the normalized sr-90 efficiency regression equation for one particular gas proportional counter, where A, Band care regression coefficients.)
= net counts due to only -*--*-*---------.-*--*--*------........----:---.,.-.-:--
M     = Thickness density of strontiwn carbonate precipitate, mg/cm2 E(l~)/Ev              = Ratio of sr~9o efficiency at tlti.ckness va.J.ue of l5mg/cm2 to. sr~9a counting standard efficiency run at the time of instrument Cal.illration ('rhiS Standard is                                                     run         With each g'I'OUp Of environmental strontiwn samples)
**-:-*-***--,-;7"-''-'"':'"':"  
E     = sr-90               countinq standard efficiency V     = Sample                 quantity (kq wet) u     = Chemical                     yield N4       = (H2                 Fl"'Hl)/Wl. = net counts due to                                                       sr~9o              only
.. -* . --.-----*-----.-* -*--.------****. --..*. ---------.*.
-*-- ---~---*- ~ *-*- - -------.-*--*--*------........----:---.,.-.-:-- **-:-*-***--,-;7"-''-'"':'"':" -~.-- .. -* . --.----- *- - - - - .-* - *- -.------****. - - ..*. --- ----- - .*.
. -! *' -*' : __ ,* ;:*! . . := *** : *:-
 
Il = l -*EXE' ((-0.693/2.667)*'!:1)
Il    = l -*EXE' ((-0.693/2.667)*'!:1)
I2 = l -EXE' ((-0.693/2.667)*t2) tl = Elapsed time from Y-90 strip to first count t2 = Elapsed time from Y-90 strip to second count 2.667 = Ha1f-life of Y-90, days Rl = D + E*M + F*M2 (This is the genera1 form of the regression equation for Y-90 eff'y/Sr-90 eff'Y ratio for one particular gas proportiona1 counter, where D, E and F are regression coefficients.)
I2    = l - EXE' ((-0.693/2.667)*t2) tl    = Elapsed time from Y-90 strip to first count t2   = Elapsed time from Y-90 strip to second count 2.667       = Ha1f-life of Y-90, days Rl   = D + E*M + F*M2 (This is the genera1 form of the                                                                                       regression equation for Y-90 eff'y/Sr-90 eff'Y ratio for one particular gas proportiona1 counter, where D, E and F are regression coefficients.)
N2 = X -Y, where X and Y are recount gross counts and background counts, respectively' Nl = Xl -Yl, where Xl and Yl are initia.J.
N2   =X -         Y, where X and Y are recount gross counts and background counts, respectively' Nl   = Xl       - Yl, where Xl and Yl are initia.J. gross counts and background counts, respectively 2.22     = No.       of dpm per pCi Fl = EXP ((-0.693/2.667)*t2)
gross counts and background counts, respectively 2.22 = No. of dpm per pCi Fl = EXP ((-0.693/2.667)*t2)
R = count time of sample and blank
R = count time of sample and blank Using the same varial:lle definitions as above, the 2-siqma error for Sr-90 (pCi/kg wet) =  
          -~                        Using the same varial:lle definitions as above,
+ (W1*W2l Lw1 w1 (N2-Fl*Nl)
          *'                        the 2-siqma error for Sr-90 (pCi/kg wet) =
Again, keeping the same variable definitions, the LLD for Sr-90 (pCi/kq wet) = 4.66*  
2*r~ + (X1+Y1~*F111/2* (W1*W2l Lw1                     w1                               (N2-Fl*Nl)
+ (Xl+Y1l*F121 l/2 calculation of Activity:
Again, keeping the same variable definitions, the LLD for Sr-90 (pCi/kq wet)                               =
Sr-99 Resul.ts (pCi/kq wet) = N6/R (2.22)*(E)*(E(l5)/E')*(S7)*(V)*(U}*(F9}  
4.66* ~~;> + (Xl+Y1l*F121 l/2 calculation of                 sr~99      Activity:
= W3 * .. S7 = G + H*M + I*M 2 (This is. the genera1 form of the normaJ.ized Sr-89 efficiency regression equation for one particular qas proportional counter where G, Hand I are regression coeff:Lcients.}
Sr-99 Resul.ts (pCi/kq wet)                           =                                                     N6/R
N6 = Nl -N7*(1 + Rl*Il) 144 --_______ + ___ r
        ;:*!                                                                                    (2.22)*(E)*(E(l5)/E')*(S7)*(V)*(U}*(F9}
-******---..-.,....*--*-:----,....---,
          .~
** ****.--
                                                                                            = W3 S7   = G + H*M +               I*M2 (This is. the genera1 form of the normaJ.ized Sr-89 efficiency regression equation for one particular qas proportional counter where G, Hand I are regression coeff:Lcients.}
*-
N6   = Nl     - N7*(1 + Rl*Il)
-**-:; . e-:** ;-
          . ~
*.*-**:-::;.-  
:= ***:
-N7 = (N2 -Fl:s.Nl)/Wl (This represents counts.due to Sr=90) E(lS)/E' = Ratio of sr-89 efficiency at thickness
144
*value of l5rng/crn 2 to sr-90 counting standard efficiency run. at the.time*
          ~--' - - _______ + _ _ _r -,.--------~-.-~-r.*..,__,....__~,.-,-,---. -------~--*-*---;**.-* -******---..-.,....*--*-:----,....---,--~---."""": -*"":-.-:~--" -,...-.~*,...._,***** ** ****.-- -~*-.**-~~; *- --..~-* -**-:; . e-:** ;-  -*t~-
of instrument caJ..il'.>ration (This standard is run with each group of environmental strontium samples) F9 =EXP ((-0.693/50.S)*t) t = Elapsed time from midpoint of collection period to time of recount for milk samples only. For all other samples,_
 
this represents the elapsed time from sample stop date to time of recount. so.s = Half-life of sr-89, days A1l other quantities as previously defined. The 2-sigma error for sr-89 (pCi/kg wet) = (sa 2+s9 2 ll/2 1lW3 (Nl -N7*(l+Rl*Il))
    -N7  = (N2    -  Fl:s.Nl)/Wl (This represents counts.due to Sr=90)
SS = li.x.+/-..tl_
E(lS)/E'  = Ratio      of sr-89 efficiency at thickness *value of l5rng/crn2 to sr-90 counting standard efficiency run. at the.time* of instrument caJ..il'.>ration (This standard is run with each group of environmental strontium samples)
+
F9 =EXP ((-0.693/50.S)*t) t  = Elapsed        time from midpoint of collection period to time of recount for milk samples only. For all other samples,_ this represents the elapsed time from sample stop date to time of recount.
l/2 Wl S9 = (Xl+Yl)l/2 Keeping the same variaJJle definitions, the LLD for sr-89 (pCi/kg wet) = / ***-" *r*-* **--;-**--.--*
so.s = Half-life          of sr-89, days A1l other quantities          ~e    as previously defined.
*-* .... ---
The 2-sigma error for sr-89 (pCi/kg wet)           = 2~ (sa 2 +s9 2 ll/2 1lW3 (Nl - N7*(l+Rl*Il))
-  
SS  =li.x.+/-..tl_ + (XJ+/-yJ~*FJJ l/2
*. -.:. -. -; ! -.i -. t -. -: ! ''-. SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE.*
            ~                  Wl S9  = (Xl+Yl)l/2 Keeping the same variaJJle definitions, the LLD for sr-89 (pCi/kg wet)                          =
RADIOSTRONTIUM.
4.ss~csa 2 +s9 2 > 1 1 2
ANALYSIS OF. BONE AND SHELL The bone or shell is first physically separated from the rest of the sample* before being broken up and boiled in 6N sodiwn hydroXide (NaOH) solution for a brief time to digest remaining flesh/collagen material adhering to the sample. After multiple rinses with distilled water, the bone/shell is then oven dried and pulverized.
                                                                              /
An aliquot of the sample is removed, weighed and ashed in a muffle furnace. Then, in the presence of strontiwn carrier and cesiwn holdl:lack carrier, the radiostrontium is leached out of the ash by boiling in diluted nitric acid, after which the sample is filtered.
                                                                                * * * - " *r*-* **--;-**--.--* *-* .... - - - --~--.,***. -
The sample is then treated with concentrated (70%) nitric acid and boiled until strontiwn nitrate crystallizes out. The strontiwn nitrate is freed of calcium by repeated fwning nitric acid recrystallizations*.
 
From this point on, any radiological impurities are removed by coprecipitation with ferric hydroXide followed by coprecipitation with bariwn chromate.
SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE.*
The strontium is precipitated as strontiwn carbonate, which is dried, weighed, then counted on a low background gas proportional counter. A second count is performed at least 14 days later. The basis for this two-count method is that Sr-90 and Sr-89 are both unknown quantities requiring two simultaneous equations to solve for them. caJ.cuJ.ation of sr-90 Activity:
RADIOSTRONTIUM. ANALYSIS OF. BONE AND SHELL The bone or shell is first physically separated from the rest of the sample*
sr-90 Results (pCi/kg dry) = N4/R (2.22)*(E)*(E(l5)/E')*(S6)*(V)*(U)  
before being broken up and boiled in 6N sodiwn hydroXide (NaOH) solution for a brief time to digest remaining flesh/collagen material adhering to the sample. After multiple rinses with distilled water, the bone/shell is then oven dried and pulverized. An aliquot of the sample is removed, weighed and ashed in a muffle furnace. Then, in the presence of strontiwn carrier and cesiwn holdl:lack carrier, the radiostrontium is leached out of the ash by boiling in diluted nitric acid, after which the sample is filtered.
= W2 where S6 = A + B*M + C*M 2 (This is the general form of the normalized sr-90 efficiency regression equation for one particular gas proportional counter, where A, Band care regression coefficients.)
The sample is then treated with concentrated (70%) nitric acid and boiled
M = Thickness density of strontium carbonate precipitate, mg/cm 2 E(lS)/E' = Ratio of sr-90 efficienC:y at thickness val.ue of l5mg/cm2 to sr-90 counting standard efficiency run at the time of instrwnent Calibration (This' standard is run with each group of environmental strontiwn samples) E = sr-90 counting standard efficiency V = Sample quantity (kg dry) u = Chemical yield N4 = (N2 -Fl*Nl)/W1  
      *. ~
= net counts due to sr-90 only * -*--* ."
until strontiwn nitrate crystallizes out. The strontiwn nitrate is freed of calcium by repeated fwning nitric acid recrystallizations*. From this point on, any radiological impurities are removed by coprecipitation with ferric hydroXide followed by coprecipitation with bariwn chromate. The strontium is precipitated as strontiwn carbonate, which is dried, weighed, then beta.-
** i . l Wl = ((l + Rl*I2) (l + Rl*Il)*Fl)
counted on a low background gas proportional counter. A second count is performed at least 14 days later. The basis for this two-count method is that Sr-90 and Sr-89 are both unknown quantities requiring two simultaneous equations to solve for them.
IJ. = l -EXP ((-0.693/2.667)*tl)
caJ.cuJ.ation of sr-90 Activity:
I2 = l -EXP ((-0.693/2.667)*t2) tJ. = Elapsed time from Y-90 strip to first count t2 = Elapsed time from Y-90 strip to second count 2.667 = Half-life of Y-90, days lU = D + E*M + F*M 2 (This is' the general form of the regression equation for eff 'Y ratio for one particular gas proportional counter, where D, E and F are regression .coefficients. ) N2 = X -Y, wnere X and Y are recount gross counts and background counts, respectively Nl = X1 -Yl, wnere Xl and Yl are initial gross counts and background counts, respectively 2.22 = No. of dpm per pCi Fl= EXP ((-0.693/2.667)at2)
-      . sr-90 Results (pCi/kg dry)   =                 N4/R
R = Count t.ime of sample and :t:llarut Using the same variable definitions as above, the 2-sigma error for sr-90 (pCi/kg dry) = Again, keepinq the same variable definitions, the LLD for sr-90 (pCi/kg dry) = 4.66111 +
    ~.
1/2 caJ.cul.ation of Activityg Results (pCi/kg ctry) = N6/R S7 = G + + I*M2 (This is the general. form of the normalized efficiency regression equation for one particular gas proportional counter where G, Hand I are regression coefficients.)  
(2.22)*(E)*(E(l5)/E')*(S6)*(V)*(U)
**------.----
                                          = W2 where S6   =A + B*M + C*M2 (This is the general form of the normalized sr-90 efficiency regression equation for one particular gas proportional counter, where A, Band care regression coefficients.)
---:---**-------.--*---
M = Thickness density of strontium carbonate precipitate, mg/cm2
.-----..,---
      - .i E(lS)/E'   = Ratio of sr-90 efficienC:y at thickness val.ue of l5mg/cm2 to sr-90 counting standard efficiency run at the time of instrwnent Calibration (This' standard is run with each group of environmental
---;-*--. .,. .*. -**---------------
  -. t strontiwn samples)
..... ,. .. -**-------:_  
E = sr-90 counting standard efficiency V = Sample quantity (kg dry)
-**------****--* ------, ....... *-----.. ---*-*-*c-:-.-----*
*~:    !
... ) 'l .**,! . ; *---.' *_.,. :**i . ' *t N7 = (N2 -Fl1tNl)/Wl (This represents .counts. due to E(lS)/E' = Ratio of Sr-89 efficiency at thickness value of l5mg/cm 2 to sr-90 counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples) F9 =EXP ((-0.693/50.S);tt) t = Elapsed time from midpoint of collection period to time of recount for milk samples only. For all other samples, this represents the elapsed time from sample stop date to time of recount. so.s = Half-life of sr-89, days All other quantities are as previously defined. The 2-sigma error for sr-89 (pCi/kg dry) = 21' (sa2+s92)l/2  
u = Chemical yield N4 = (N2 - Fl*Nl)/W1 = net counts due to   sr-90 only
*W3 (Nl -N71t(l+Rl*Il))
                                                                                                -*- -* ." ~-~'--
SS =  
 
+
**                                                 Wl IJ.
l/2 S9 =* (Xl+!l)l/2 All other varialJles are as previously defined. Keeping the same varialJle definitions,.
                                                            = ((l + Rl*I2) ~ (l + Rl*Il)*Fl)
the LLD for Sr-89 {pCi/kg dry) = 4.66*{S8 2+s9 2)1/2 ..  
                                                            = l - EXP ((-0.693/2.667)*tl)
*-;---,-*-*-'---
I2       = l - EXP ((-0.693/2.667)*t2) tJ.     = Elapsed time from Y-90 strip to                                                                 first count t2       = Elapsed time from Y-90 strip to                                                                 second count 2.667 = Half-life of Y-90, days lU       =D +             E*M + F*M2 (This is' the general form of the regression equation for Y~90 eff'y/sr~90 eff 'Y ratio for one particular gas proportional counter, where D, E and F are regression
----. --..... ' --.. -*
                                                                .coefficients. )
. . ' *
N2       =X -               Y, wnere X and Y are recount gross counts and background counts, respectively Nl       = X1           - Yl, wnere Xl and Yl are initial gross counts and background counts, respectively 2.22         = No.             of dpm per pCi Fl= EXP ((-0.693/2.667)at2)
* SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE' RADIOSTRONTIUM ANALYSIS OF SOIL AND SEDIMENT After the soil or sediment sample has been dried and pulverized, a SOgm aliquot is added to approx:ima.tely 1/3 -liter concentrated hydrochloric acid (HCl), containinq Sml of strontium carrier (lOmq sr++/ml).
R     = Count               t.ime           of sample and :t:llarut Using the same variable definitions as above, the 2-sigma error for sr-90 (pCi/kg dry) =
A blank taininq only 1/3 -liter concentrated and Sml strontiwn carrier is run in parallel with the sample. The samples are stirred viqorously for at least 30 minutes and then filtered.
Again, keepinq the same variable definitions, the LLD for sr-90 (pCi/kg dry) =
The filtrate is then diluted to a known volume and aliquots removed for stable str:ontiwn.
4.66111         ~~p                  +     (Xl+;;:~*Flj 1/2 caJ.cul.ation of                       sr~89          Activityg sr~89      Results (pCi/kg ctry)                                         =                                                     N6/R (2.22)*(E)~(E(l5)/E')*(S7)~(V)*(U)~(F9)
The remaining sample is alka.linizeci with ammonium hydroXide to precipitate all the transitional elements.
S7      =G +             H~N + I*M2 (This is the general. form of the normalized sr~89 efficiency regression equation for one particular gas proportional counter where G, Hand I are regression coefficients.)
After filtering out these interferences, the filtrate is heated and sodium carbonate added to precipitate strontiwn and calciwn carbonate.
i
These carbonates are first filtered and then di.qested with 6N HN0 3* Two _ fwn:i.nq (90%) mro 3 recrystallizations are then performed to remove calcium. Subsequently, radi.oactive impurities are removed by two precipitation steps, using ferric hydroxide and bariwn chromate as carriers.
. l
The strontium is precipitated as strontium carbonate before beinq dried and weighed. The samples are counted for beta activity in a low background gas proportional counter (Count time will vary, depending on the desired sensitivity.).
      **- -----.---- ---:--- * * - - - ----.--*--- .-----..,--- *0*--..~~---* ---;- *--. -~- .,..*. -**- ----- -- --- ---- ---~-;-~----r--- ..... ,. .. -**------ - :_ --~--- -**-- -- -- ****--* ------, ....... *- ---- .. ---*-*- *c-:-.--- --*
There is a second count at least 14 days later. The basis for this two-count method is that sr-90 and Sr-89 are both unknown quantities requiring two simultaneous equations to solve for them. caJ.cUlation of sr-90 sr-90 Results (pCi/kg dey) *= N4/R (2.22)*(E)*(E(lS)/E')*(S6)*(V)*(U)  
 
= W2 where S6 = A + B*M + (This is the genera.I.
N7 = (N2 -       Fl1tNl)/Wl (This represents .counts. due to sr~9a)
form of the normalized sr-90 efficiency reqression equation for one particular gas proportional counter, where A, Band care reqression coefficients.)
E(lS)/E' = Ratio       of Sr-89 efficiency at thickness value of l5mg/cm2 to sr-90 counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples)
M = Thickness density of strontium.
F9 =EXP ((-0.693/50.S);tt) t = Elapsed       time from midpoint of collection period to time of recount for milk samples only. For all other samples, this represents the elapsed time from sample stop date to time of recount.
carbonate precipitate, mq/cm 2 E(l5)/E' = Ratio of Sr-90 efficiency at thickness vaiue of 15mg/cm 2 to Sr=90 countinq standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontiwa samples) E = sr-90 counting standard efficiency v = Sample quantity (kq dry) u = CheliCLcal.
so.s = Half-life       of sr-89, days All other quantities are as previously defined.
yield N4 = (N2 -Fl*Nl)/WJ.  
The 2-sigma error for sr-89 (pCi/kg dry)       = 21' (sa2+s92)l/2 *W3 (Nl - N71t(l+Rl*Il))
= net counts due to Sr-90 only Wl. = ((l + Rl*I2) -(l +  
SS = r~~) +        (X1+~~*Flj l/2 S9 =* (Xl+!l)l/2 All other varialJles are as previously defined.
-.--7*..---.-*-*--..*--*-----------
Keeping the same varialJle definitions,. the LLD for Sr-89 {pCi/kg dry)                               =
-
4.66*{S82 +s9 2 ) 1 / 2
--* -----*---*---*----.-----
  ...    ~
-*  
          )
..  
        'l
*---* 
*_.,. :**i
' .*J . ' -j . i Il = l -EXP ( (-0 .693/2 .667) *tl) . I2 = l -EXP ({-0.693/2.667)*t2)  
. '       ~
.. tl = Elapsed time from Y-90 strip to first count t2 = Elapsed time from Y-90 strip to second count 2.667 = Half-life Of Y-90, days Rl = D + E*M + F*M 2 (This is the general form of the regression equation for Y-90 eff'y/sr-90 eff 'Y ratio for one particular gas proportional counter, where o, E and F are regression*
        *t
                                                                                --.--.--~-""- --.-~-::-**-.--:- *-;---,-*-*-'---  - --      - -~ . - - .....
* SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE' RADIOSTRONTIUM ANALYSIS OF SOIL AND SEDIMENT After the soil or sediment sample has been dried and pulverized, a SOgm aliquot is added to approx:ima.tely 1/3 - liter concentrated hydrochloric acid (HCl), containinq Sml of strontium carrier (lOmq sr++/ml). A blank con-taininq only 1/3 - liter concentrated HC~ and Sml strontiwn carrier is run in parallel with the sample. The samples are stirred viqorously for at least 30 minutes and then filtered. The filtrate is then diluted to a known volume and aliquots removed for stable str:ontiwn. The remaining sample is alka.linizeci with ammonium hydroXide to precipitate all the transitional elements. After filtering out these interferences, the filtrate is heated and sodium carbonate added to precipitate strontiwn and calciwn carbonate.
These carbonates are first filtered and then di.qested with 6N HN0 3
* Two
_fwn:i.nq (90%) mro 3 recrystallizations are then performed to remove calcium.
Subsequently, radi.oactive impurities are removed by two precipitation steps, using ferric hydroxide and bariwn chromate as carriers. The strontium is precipitated as strontium carbonate before beinq dried and weighed. The samples are counted for beta activity in a low background gas proportional counter (Count time will vary, depending on the desired sensitivity.). There is a second count at least 14 days later. The basis for this two-count method is that sr-90 and Sr-89 are both unknown quantities requiring two simultaneous equations to solve for them.
caJ.cUlation of sr-90                     Activity~
sr-90     Results (pCi/kg                     dey)       *=                                   N4/R (2.22)*(E)*(E(lS)/E')*(S6)*(V)*(U)
                                                                              = W2 where S6       =A +       B*M + c~M2 (This is the genera.I. form of the normalized sr-90 efficiency reqression equation for one particular gas proportional counter, where A, Band care reqression coefficients.)
M   = Thickness                 density of strontium. carbonate precipitate, mq/cm2 E(l5)/E'       = Ratio         of Sr-90 efficiency at thickness vaiue of 15mg/cm2 to Sr=90 countinq standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontiwa samples)
E = sr-90           counting standard efficiency v = Sample quantity                           (kq dry) u = CheliCLcal. yield N4   = (N2       - Fl*Nl)/WJ.                   = net         counts due to Sr-90 only
* Wl. = ((l       + Rl*I2) - (l +                         Rl~Il)~Fl)
*-.--~---~--*-:--:---*--::___,,....-.-~ -.--7*..---.-*-*--..*--*----------- - --~*~,...--..,~--~~---***--*----~---~-- --* ----- *--- *- - -*----.----- -* ----~...,..--- .. ~---~ *---*
 
Il =  l -  EXP  ( (-0 .693/2 .667) *tl) .
I2 =l  - EXP ({-0.693/2.667)*t2) tl = Elapsed time from Y-90 strip to first count t2 = Elapsed time from Y-90 strip to second count 2.667 = Half-life Of Y-90, days Rl =D +   E*M + F*M2 (This is the general form of the regression equation for Y-90 eff'y/sr-90 eff 'Y ratio for one particular gas proportional counter, where o, E and F are regression*
coefficients.)
coefficients.)
N2 = X -Y, where X and Y are recount _gross counts and background counts, respe(:tively Nl = Xl -Yl, where Xl and Yl are initial gross counts and background counts, respectively 2.22 = No. of dpm per pCi Fl = EXP ((-0.693/2.667)*t2)
N2 =X -   Y, where X and Y are recount _gross counts and background counts, respe(:tively Nl = Xl - Yl, where Xl and Yl are initial gross counts and background counts, respectively 2.22 = No. of dpm per pCi Fl = EXP ((-0.693/2.667)*t2)
R = Count t;Lme* of sample and blank*
R = Count   t;Lme* of sample and blank*
* Using the same varial:lle definitions as aJ:>ove, the 2-sigma error for sr-90 (pCi/kq dry) = 2*[CX+Y) + .. (Wl*W2) [ Wl2 Wl (N2-Fl*Nl)
  .*J
Again, keeping the same varial:lle definitions, the LLD for sr-90 (pCi/kq dry) = 4.66* Rx+;p + [wi
* Using the same varial:lle definitions as aJ:>ove, the 2-sigma error for sr-90 (pCi/kq dry)           =
2*[CX+Y)   + on+n~*F11 1 12 ..     (Wl*W2)
[ Wl2           Wl           (N2-Fl*Nl)
Again, keeping the same varial:lle definitions, the LLD for sr-90 (pCi/kq dry) =
4.66* Rx+;p   + cxi+n~*F1J 1 12
[wi
* Wl
* Wl
* calcul.ation of sr-89 Activity:
* calcul.ation of sr-89 Activity:
sr-89 Results (pCi/kq dry) = NS/R (2.22)*(E)*(E(l5)/E')*(S7)*(V)*(U)*(F9)  
-j sr-89 Results (pCi/kq     dry) =                       NS/R (2.22)*(E)*(E(l5)/E')*(S7)*(V)*(U)*(F9)
= W3 S7 = G + H*M + I*M 2 (This is the general form of the normalized sr-89 efficiency regression equation for one -particular gas.proportional .counter where G, Hand I are regression coefficients.)
                                        = W3
150  
. i S7 =G +   H*M + I*M2 (This is the general form of the normalized sr-89 efficiency regression equation for one -particular gas.proportional
,,.-----:-; -----.-*---.*---
                  .counter where G, Hand I are regression coefficients.)
.... _ -.** -.. --*;
150
* N7 = (N2 = (This represents counts due to E(lS)/E' =.Ratio of sr-89 efficiency at thickness value of 15mg/cm 2 to sr-90 counting standard.efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontiwn samples) F9 =EXP ((-0.693/50.S)*t) t = Elapsed t.ime from midpoint of collection period to time of recount for milk samples only. For all other samples, this represents the elapsed time from sample stop date to time of recount. 50.5 = Half=life of Sr=89, days All other quantities are as previously defined. 2-sigma error for Sr=89 (pCi/kg dry) = 2* (se2+sg2)l/2  
                                                                            *:-~---:* ,,.-----:-; ~ -----.-*---.*--- .... _ -.** -..--*;
*W3 (Nl -N7*(l+Rl*Il))
 
SB = rc.x+/-Y.l +
N7     = (N2       = Fl~Nl)/Wl    (This represents counts due to sr~90)
1/2 [Wi2 Wl sg = All other varial:lles are as previously defined * ..  
E(lS)/E' =.Ratio of sr-89 efficiency at thickness value of 15mg/cm2 to sr-90 counting standard.efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontiwn samples)
*-----.**.---
F9 =EXP             ((-0.693/50.S)*t) t   = Elapsed         t.ime from midpoint of collection period to time of recount for milk samples only. For all other samples, this represents the elapsed time from sample stop date to time of recount.
--*---****  
50.5 = Half=life of Sr=89, days All other quantities are as previously defined.
-***--* -* -,***:i..-*
Th~ 2-sigma error for Sr=89 (pCi/kg dry)                       = 2* (se2+sg2)l/2 *W3 (Nl - N7*(l+Rl*Il))
-c *. ,*.: .** .. ,. .. i . .,
SB     =rc.x+/-Y.l       + (Xl+Yla*Fl~ 1/2
* SYNOPSIS OF PSE&G RESEARCH CORPORATION.PROCEDURE ANALYSIS OF ENVIRONMENTAL SAMPLES FOR It has been the practice of the Environmental Division to perform a stable strontium determination on any samples to be analyzed for strontium 90 and 89, if they are likely* to contain significant amounts of the stable isotopes..
[Wi2                 Wl sg     = cxi~u> 1 1 2 All other varial:lles are as previously defined *
In the case of mineral (soil or sediment) or biological (bone and shell) media, an ashing and/or acid leaching is performed to extract the element{s) of interest.
'.---*----~--.*-..,..---** *-----.**.--- --*---**** -----~-------*-* -                                                            -~* ***--* - * -,***:i..-*
The removal of the aliquot is done early in the course of the radiostrontium analysis and involves the withdrawl of 25 ml of diluted leachate (soil and sediment only) from the regular sample, transferring it to a flask. Bone and shell are prepared by 2 g of sample, digesting in 6N HCl, filtering out insoluble residues and then transferring to a flask. All, the above samples are analyzed by the method of Standard Additions, whereby each sample leachate is spiked with known concentrations of stable strontium.
 
Absorbances for sample, spiked samples and blank are determined by Atomic Absorption Spectroscopy (AAS) and are then plotted graphically and the true concentration is then extrapolated.
SYNOPSIS OF PSE&G RESEARCH CORPORATION.PROCEDURE ANALYSIS OF ENVIRONMENTAL SAMPLES FOR STA~LE STRO~TIUM It has been the practice of the Environmental Division to perform a stable strontium determination on any samples to be analyzed for strontium 90 and 89, i f they are likely* to contain significant amounts of the stable isotopes..                                           In the case of mineral (soil or sediment) or biological (bone and shell) media, an ashing and/or acid leaching is performed to extract the element{s) of interest. The removal of the aliquot is done early in the course of the radiostrontium analysis and involves the withdrawl of 25 ml of diluted leachate (soil and sediment only) from the regular sample, transferring it to a flask. Bone and shell are prepared by ash~ng 2 g of sample, digesting in 6N HCl, filtering out insoluble residues and then transferring to a flask. All, the above samples are analyzed by the method of Standard Additions, whereby each sample leachate is spiked with known concentrations of stable strontium.
Chemical and ionization interferences are controlled by adding 1% or more of lanthanum as chloride to all samples to be analyzed.
Absorbances for sample, spiked samples and blank are determined by Atomic Absorption Spectroscopy (AAS) and are then plotted graphically and the true concentration is then extrapolated. Chemical and ionization interferences are controlled by adding 1% or more of lanthanum as chloride to all samples to be analyzed. Stable strontium is then determined by AAS in the air-acetylene flame at the 460.7 run line.
Stable strontium is then determined by AAS in the air-acetylene flame at the 460.7 run line. For analysis of water, a 60-ml aliquot of sample is removed, acidified to pH<2 with hydrochloric acid and analyzed by AAS as follows: A group of strontium standards (of similar concentration to: the unknowns) is prepared.
For analysis of water, a 60-ml aliquot of sample is removed, acidified to pH<2 with hydrochloric acid and analyzed by AAS as follows: A group of strontium standards (of similar concentration to: the unknowns) is prepared.
Then, to 9 ml of each prepared sample'* blank and standard, is added 1 ml. of lanthanum oxide solution.
Then, to 9 ml of each prepared sample'* blank and standard, is added 1 ml. of lanthanum oxide solution. These are ana,lyzed at 460.1* run by air"".'acetylene AAS, following the manufacturer's recommended instrument parameters.
These are ana,lyzed at 460.1* run by air"".'acetylene AAS, following the manufacturer's recommended instrument parameters.
All. results (calculated as milligrams of strontium per liter) are then used to find the true chemical recovery of strontium based on both the amount of carrier added (only in the case of soil and sediment) and the quantity of strontium intrinsic to the sample.
All. results (calculated as milligrams of strontium per liter) are then used to find the true chemical recovery of strontium based on both the amount of carrier added (only in the case of soil and sediment) and the quantity of strontium intrinsic to the sample. . Sample calculation of corrected Chemical Recovery of Strontium in Soil and Sediment:
                                    . Sample calculation of corrected Chemical Recovery of Strontium in Soil and
  ~ -c *.
Sediment:
Reported concentration of stal:>le strontium (mg/L):ll9 Volume of specimen (mll:2S (removed from lOOOml of diluted leachate)
Reported concentration of stal:>le strontium (mg/L):ll9 Volume of specimen (mll:2S (removed from lOOOml of diluted leachate)
Proportion of sample used for aliquot: 0.025 Milligrams strontium in 25ml flask= (119mg/L) x (.025L/25ml) x (25ml) = 2.98mg sr Since 2.98mg Sr represents the quantity of stable.strontium in 2 1/2 percent of the sample, total strontium (stable + carrier) in the full sample = 2.98mq Sr = 119 mg o.02s 152  
Proportion of sample used for aliquot: 0.025 Milligrams strontium in 25ml flask= (119mg/L) x (.025L/25ml) x (25ml)
-----...
                                                                                                = 2.98mg sr i
.. .. -. . -.  
            .  ~                      Since 2.98mg Sr represents the quantity of stable.strontium in 2 1/2 percent of the sample, total strontium (stable + carrier) in the full sample =
.. -
2.98mq Sr   = 119 mg o.02s 152
*----:--:-;: ----* ._,__:* **_ .. --  
                  -*--*-----*-~-~- ----- ...-.---~~-:"""">"*-:------..,                                                       .. -~- ..- . --~~ . -. .-:-~--.- -~-**.** *- -- -:--:-;:
.. *
* I .. ..
* Net weight of srco 3 precipitate.(mg):
125 Percent of Sr in precipitate:
59.35 Quantity of strontium recovered= (l25mg) x (.5935) = 74.2. corrected chemical recovery of strontiwn
= 74.2 = 0.623 ll.9.0 The calculations f_ollow the same sequence for :bone and shell samples. Sample ca.1.culation of Corrected Chemical Recovery of Strontium in Reported concentrations of stable strontium l.65 *volume of radiochemical water sample (liters):  


===2.0 Stable===
                  ~ ..
strontium in 2 liter sample = (l.65mg/t) x (2.0L) = 3.30mg Quantity of strontium carrier added to sample 20.0 Total amount of strontium in sample (mg): 20.0 + 3.30 = 23.3mg Net weight of srco 3 precipitate (mg): 28.9 Percent of Sr in precipitate:
* Net weight of srco 3 precipitate.(mg): 125 Percent of Sr in precipitate: 59.35 Quantity of strontium recovered= (l25mg) x (.5935) = 74.2.
59.35 Quantity of strontium recovered=  
corrected chemical recovery of strontiwn =                                                                 74.2        = 0.623 ll.9.0 The calculations f_ollow the same sequence for :bone and shell samples.
(28.9mg) x (.5935) = l7.2mg corrected chem.ical.
Sample ca.1.culation of Corrected Chemical Recovery of Strontium in                                                                                                        Water~
recovery of 17.2mq .738 23.3mq --------::----.---'<-*  
Reported concentrations of stable strontium (mq/L)~ l.65
-:----------*--
                                *volume of radiochemical water sample (liters): 2.0 Stable strontium in 2 liter sample                                               = (l.65mg/t)                         x (2.0L)
---------* .  
                                                                                                                  = 3.30mg Quantity of strontium carrier added to sample (mg)~ 20.0 Total amount of strontium in sample (mg): 20.0 + 3.30 = 23.3mg Net weight of srco 3 precipitate (mg): 28.9 Percent of Sr in precipitate: 59.35 Quantity of strontium recovered= (28.9mg) x (.5935)                                                                                     = l7.2mg
----------*  
* corrected chem.ical. recovery of                                       strontium~                      17.2mq 23.3mq
-*-----.. --------.. ------* ------------;----------
                                                                                                                                                                ~      .738 I
.... -----* ----.. -. -*-*-------------  
  *~
-*** _] SYNOPSIS OF PSE&G CORPORATION PROCEDURE GAMMA ANALYSIS OF A.IR PARTICULATE COMPOSITES At the end of each calendar quarter, 13 weekly air filters from a location are stacked in a two inch diameter Petri dish in chronological order, with the oldest filter at the bottom, nearest the detector, and the newest one on top. The Petri dish is closed and the sample counted on a gamma detector.
      --------::----.---'<-* -:----------*-- -- - ----- -* . -:--""7---~--- ----------* - *- --~- ----.. -- ------ .. ----- - * ------ ~ ----- -;---------- .... - ----* -- - - .. - . - *-*-- --- ------ --
The following are the calculations performed for the gamma activity, 2-sigma error and LLD: Result (pCi/m 3) = N*D = R (2.22)*(E)*(A)*(T)*(V)
 
N = Net counts under photopeak D = Decay correction factor .\.tl.*EXP(:\t2) 1-EXP(-.\.tl) tl = Acquisition live time t2 = Elapsed time from sample collection to start of acquisition A. = 0.693/nuclide half life
SYNOPSIS OF PSE&G RES~RCH    CORPORATION PROCEDURE GAMMA ANALYSIS OF A.IR PARTICULATE COMPOSITES At the end of each calendar quarter, 13 weekly air filters from a giv~n location are stacked in a two inch diameter Petri dish in chronological order, with the oldest filter at the bottom, nearest the detector, and the newest one on top. The Petri dish is closed and the sample counted on a gamma detector.
* E = Detector efficiency A = Gamma abundance factor (no. of photons per T = Acquisition live time, mins. V = Sample volume, m3 2.22 = No. of dpm per pCi 2-sigma error (pCi/m 3) = l.96*(GC+Bc)l/2,.a N GC = Gross-counts BC = Background counts All other variables are as defined earlier. The LLD (pCi/m3) = 4.66*(Bc)l/2,.D (2.22)*(E}*(A)*(T)*(V}
The following are the calculations performed for the gamma activity, 2-sigma error and LLD:
154 . ., ... ... . . .. *. -. * 
Result (pCi/m 3 ) =           N*D           =R (2.22)*(E)*(A)*(T)*(V)
*--.* . .*. *1 -*1* ; ... i ' . .
N = Net counts under photopeak D = Decay correction factor
* j ... *,, . -' ::j ; * . ,'I '1".I -. ,1 * .. _.J . . . -l . ' *! . *:_::,.I .*.,. 1 .. ' *. . SYNOPSIS OF TELEDYNE ISOTOPES PROCEDURE:  
                                                                                      .\.tl.*EXP(:\t2) 1-EXP(-.\.tl) tl = Acquisition live time t2 = Elapsed time from sample collection to start of acquisition A. = 0.693/nuclide half life
*. ANALYSIS OF AIR PARTICULATE FILTERS FOR GAMMA . Ai.r particulate filters are analyzed for gamma using a germanium detector interfaced with a 2048 channel pulse height analyzer at 1.0 Kev per channel. Teledyne Isotopes employs one of three possible data acquisition and computation systems. The first, a Data General NOVA minicomputer, in series with the pulse height anaJ.yzer, calculates the _number of counts (and a one standard deviation).
* E = Detector efficiency A = Gamma abundance factor (no. of photons per di~integration)
in the peak region by performing a linearly-interpolated background subtraction.
T = Acquisition live time, mins.
If no peak is observed, then only the background is used (along with sample volumep tion date and length of count) to determine the detection limit. The activity or MDL of each nuclide is computed on an IBM 360. This semi-automatic system is in contrast with the other two data acquisition and computation systems, namely, a Tracor Northern TN-ll and Nuclear Data 6620 which perform all the above computations automatically.
                                                                                    =
All resultant spectra are stored on magnetic tape. ,/
V Sample volume, m3 2.22 = No. of dpm per pCi 2-sigma error (pCi/m3 )   = l.96*(GC+Bc)l/2,.a N
SYNOPSIS OF PSE&G .RESEARCH .COREORl\TION PROCEDURE  
GC   = Gross- counts BC   = Background counts All other variables are as defined earlier.
.*
The LLD (pCi/m3)   =   4.66*(Bc)l/2,.D (2.22)*(E}*(A)*(T)*(V}
* GAMMA ANALYSIS OF.RAW.MILK A well miXed 3.5-liter sample of raw milk is poured into a Marinelli beaker along with 20ml of 37% formaldehyde solution (used as a preservative).
154
After stirring, the sample is allowed to reach ambient temperature and then counted on a gamma detector.*
-*** _]
        . ., ...*-~- ... . ... *. -.
 
SYNOPSIS OF TELEDYNE ISOTOPES PROCEDURE: *.
ANALYSIS OF AIR PARTICULATE FILTERS FOR   GAMMA .
Ai.r particulate filters are analyzed for gamma using a lithium~drifted germanium detector interfaced with a 2048 channel pulse height analyzer calibr~ted at 1.0 Kev per channel. Teledyne Isotopes employs one of three possible data acquisition and computation systems. The first, a Data General NOVA minicomputer, in series with the pulse height anaJ.yzer, calculates the
_number of counts (and a one standard deviation). in the peak region by performing a linearly-interpolated background subtraction. If no peak is observed, then only the background is used (along with sample volumep collec~
tion date and length of count) to determine the detection limit. The activity or MDL of each nuclide is computed on an IBM 360. This semi-automatic system is in contrast with the other two data acquisition and computation systems, namely, a Tracor Northern TN-ll and Nuclear Data 6620 which perform all the above computations automatically. All resultant spectra are stored on magnetic tape.
          . ~ .'~
      .*.        *1
                -*1*
i
.-' ::j
          -~
* j
. *:_::,.I
                ,'I
              '1".I
              -. ,1
          * .. _.J
      .. . -~
l
            .*.,. 1                                                              ,/
.. ' ~ *.      .~
 
SYNOPSIS OF PSE&G .RESEARCH .COREORl\TION PROCEDURE GAMMA ANALYSIS OF.RAW.MILK A well miXed 3.5-liter sample of raw milk is poured into a cal~rated Marinelli beaker along with 20ml of 37% formaldehyde solution (used as a preservative). After stirring, the sample is allowed to reach ambient temperature and then counted on a gamma detector.*
calculation Of Gamma Activity:
calculation Of Gamma Activity:
The following are the calculations performed for the gamma activity, 2-sigma error and LLD: Result (pCi/L) = N*D = R (2.22)*(E)*(A)*(T)*(V)
The following are the calculations performed for the gamma activity, 2-sigma error and LLD:
N = Net counts under photopeak D = Decay correcti.on factor X. tl*EX1?(X.t2) 1-EXP(-x.tl) tl = Acquisition live time
Result (pCi/L) =           N*D           = R (2.22)*(E)*(A)*(T)*(V)
* t2 = Elapsed time from sample tion to start of acquisition  
N = Net counts under photopeak D = Decay correcti.on factor X. tl*EX1?(X.t2) 1-EXP(-x.tl) tl = Acquisition live time t2 = Elapsed time from sample collec-tion to start of acquisition
: x. = 0.693/nuclide half-life *
: x. = 0.693/nuclide half- life
* E = Detector efficiency  
        **                                             E = Detector efficiency A=   Gamma aJJundance factor (no. of photons per disintegration)
.. . . . *' l ' *1 _.. ' . T A = Gamma aJJundance factor (no. of photons per disintegration)
T = Acquisition live time, mins.
T = Acquisition live time, mins. V = Sample volume, liters 2.22.= No. of dpm per pCi 2-sigma error (pCi/L) = l.96*(GC+Bc)l/2*R N GC = Gross counts BC = Background counts All.other variaJJles are as defined earlier. The LLD (pCi/L) = -
V=   Sample volume, liters 2.22.= No. of dpm per pCi 2-sigma error (pCi/L) = l.96*(GC+Bc)l/2*R N
(2.22)*(E)*(A)*(T)*(V)  
GC = Gross counts
*
        ..                                            BC = Background counts
. . .*'    l
          *1 All.other variaJJles are as defined earlier.
The LLD (pCi/L) =   - 4~66*CBc)l/2wo (2.22)*(E)*(A)*(T)*(V)
_.. *~
      . T'


* ;.! '.*i ' .. .* 1* < .-I
~*.       ..~.
* I -I j ., SYNOPSIS OF PSE&G RESEARCH*
SYNOPSIS OF PSE&G RESEARCH* CORPORATION.. PROCEDURE GAMMA ANALYSIS OF WATER After thoroughly agitating the sample container, 3.5 liters of water sample is poured into a calibrated.Marinelli beaker and then counted on a gamma detector.
CORPORATION  
.. PROCEDURE GAMMA ANALYSIS OF WATER After thoroughly agitating the sample container, 3.5 liters of water sample is poured into a calibrated.Marinelli beaker and then counted on a gamma detector.
ca1cu1ation of Gamma Activity:
ca1cu1ation of Gamma Activity:
The following are the calculations performed for the gamma activity, 2-sigma error and IJ:.JJg Result (pCi/L) = Nao = R 2-sigma error (pCi/L) N Net counts under photopeak D = Decay correction factor .\.tl*EXP(.\.t2) 1-EXP(-.\.tl) tl = Acquisition live time t2 = Elapsed time from sample collec-tion to start of acquisition = 0.693/nuclide half life E Detector efficiency A = Gamma. aJJundance factor (no. of *pnotons per disintegration)
The following are the calculations performed for the gamma activity, 2-sigma error and IJ:.JJg Result (pCi/L)                 =                           Nao                             =R (2.22)*(E)~(A)*(T)*(V)
T = Acquisition live time, mins. V = Sample volume, liters 2.22 = No. of dpm per pCi = l.96*(GC+BC)l/2*R N GC = Gross counts BC = Background counts All other variatiles are as defined earlier. The LLD (pCi/L) =
N ~ Net counts under photopeak D = Decay correction factor
157 ..  
                                                                                                                                        .\.tl*EXP(.\.t2) 1-EXP(-.\.tl) tl = Acquisition live time t2 = Elapsed time from sample collec-tion to start of acquisition
.. -..,.  
                                                                                                                            ~ = 0.693/nuclide half life E ~ Detector efficiency A = Gamma. aJJundance factor (no. of
---. ***-------**  
                                                                                                                                      *pnotons per disintegration)
---. -
T = Acquisition live time, mins.
--*  
V = Sample volume, liters 2.22 = No. of dpm per pCi 2-sigma error (pCi/L)                            = l.96*(GC+BC)l/2*R N
... --..... -----.-,-.-..--
GC         = Gross counts BC         = Background counts
*--* ---------... .... :**--------
    ;.!                    All other variatiles are as defined earlier.
""* -. ** .. -., _,.
    '.*i                    The LLD (pCi/L)                 =               4.66~{BC)l/2.o (2.22)~(E)~(A)*(T)~(V)
*.; *':**-*
    .* 1*
* SYNOPSIS.OF PSE&G RESEARCH CORPORATION  
.-    I
*PROCEDURE.
*    -I j
GAMMA ANALYSIS OF SOLIDS several methods are employed in preparing solids for gamma anal.ysis, depending on the type of sample or sensitivity required.
I 157
For high sensitivity anal.ysis of vegetation, meat and seafood, the sample is first weighed, then oven-dried to a constant weight. A ratio of wet-to-dry weight is computed before the sample is ground and compressed to unit density (lg/cm 3), whenever possible, in a tared al.uminum can. The can is weighed and then hermetical.l.y sea.l.ed and counted on a gamma detector.
  .. \------~ .. -..,. -~~-*-* --- . ***-------** - -- . - ---~-------::---*~----,...,.-.-,.--..,.,_... --* ---~-__... ... -- ..... -----.-,-.-..-- *--* - -------- ... ~ .... :**---- -- - - *-*~ ""* -. **.. - *-~ ., _,.
In most cases, a wet sample is prepared (assuming sensitivity can be met) by using a food processor to puree it. The sample is then poured into a brated and tared clear plastic container until. a standard volume is reached. The sample is weighed and then seal.ad with a screw cap before gamma counting.
 
Soil. and sediment samples are first oven dried until. a constant weight is achieved and then pul.verized.
SYNOPSIS.OF PSE&G RESEARCH CORPORATION *PROCEDURE.
The sampl.e is added to a tared al.uminum can, compacted to a standard vol.lime and weighed. It is hermetical.l.y seal.ed and gamma counted. Benthic organisms are oven dried; followed by the physical.
GAMMA ANALYSIS OF SOLIDS several methods are employed in preparing solids for gamma anal.ysis, depending on the type of sample or sensitivity required. For high sensitivity anal.ysis of vegetation, meat and seafood, the sample is first weighed, then oven-dried to a constant weight. A ratio of wet-to-dry weight is computed before the sample is ground and compressed to unit density (lg/cm 3 ), whenever possible, in a tared al.uminum can. The can is weighed and then hermetical.l.y sea.l.ed and counted on a gamma detector.
removal of any * *obvious impurities-(such as shells or twigs). The dried organisms are weigh and then wet-ashed with.concentrated nitric After al.l solids have been digested, the sample is evaporated to near drYt1ess and the residual.
In most cases, a wet sample is prepared (assuming sensitivity can be met) by using a food processor to puree it. The sample is then poured into a cal.i-brated and tared clear plastic container until. a standard volume is reached.
sal.ts taken up with distilled water. The sample is filtered and the filtrate added to an al.uminum can. The* sample volume is brought up to the standard geometry with distilled water and the can hermetical.ly sealed before gamma counting.
The sample is weighed and then seal.ad with a screw cap before gamma counting.
Soil. and sediment samples are first oven dried until. a constant weight is achieved and then pul.verized. The sampl.e is added to a tared al.uminum can, compacted to a standard vol.lime and weighed. It is hermetical.l.y seal.ed and gamma counted.
Benthic organisms are oven dried; followed by the physical. removal of any         *
            *obvious impurities-(such as shells or twigs). The dried organisms are weigh and then wet-ashed with.concentrated nitric acid~ After al.l solids have been digested, the sample is evaporated to near drYt1ess and the residual. sal.ts taken up with distilled water. The sample is filtered and the filtrate added to an al.uminum can. The* sample volume is brought up to the standard geometry with distilled water and the can hermetical.ly sealed before gamma counting.
calculation of Gamma Activity:
calculation of Gamma Activity:
The following are the calculations performed for the gamma activity, 2-siqma error and LLD: Result (pCi/kg) = N*D = R (2.22)*(E)*(A)*(T)*(V)
The following are the calculations performed for the gamma activity, 2-siqma error and LLD:
N = Net counts under photopeak D = Decay correction factor. >..tl.*EXP(>..t2) 1-EXP(->..tl) tl = Acquisition live time t2 = Elapsed time from sample collec-tion to start of acquisition  
Result (pCi/kg) =               N*D           = R (2.22)*(E)*(A)*(T)*(V)
>.. = o.693/nuclide half life E = Detector efficiency A -Gamma abundance factor (no. of photons per disinteqration) v = Sample volume, kiloqrams T = Acquisition live time, mins.
N = Net counts under photopeak D = Decay correction factor.
* 2.22 = No. of dpm per pCi . *-. _ .. , :.-.. . I I I 
                                                                  >..tl.*EXP(>..t2) 1-EXP(->..tl) tl = Acquisition live time t2 = Elapsed time from sample collec-tion to start of acquisition
                                                            >.. = o.693/nuclide half life E = Detector efficiency A - Gamma abundance factor (no. of photons per disinteqration)
T = Acquisition live time, mins.
* v = Sample volume, kiloqrams 2.22 = No. of dpm per pCi


error (pCi/kg) "" l.$l6"'(GC+Bc)l/4,.,e  
2~sigma error (pCi/kg) "" l.$l6"'(GC+Bc)l/4,.,e *.
*. N GC = Gross counts BC = Background counts All other variables are as defined earlier. The LLD (pCi/kg) = 4.661'(Bc)l/2,.,o (2.22)*(E)"'(A)*(T)*(V)  
N GC     = Gross                 counts BC     = Background                           counts All other variables are as defined earlier.
/ .. *, ., *-.i . -; . * ***J ---....-.**  
The LLD (pCi/kg)                     =         4.661'(Bc)l/2,.,o (2.22)*(E)"'(A)*(T)*(V)
--.--,---------.  
                            /
---------*--*-
  *-.i
---*-*.--;**!----*---
****J
--..... 7"'*-----.--"':,-
      ---....-.** --.--,---------. -- -- -- ~-.- ---*--*- -~-;--------~--*.- ---*-*.--;**!----*--- *-""'.!**---~---- -----.-.---.---~-~-*-* -- ..... 7"'*-----.--"':,- ... --..---:-*---:--. *----. --- ' .... --- - - - .* ... *-*-- --**-**
... --..---:-*---:--.  
 
*----. ---' .... ------.* ... *-*----**-**
---~    - -:
' *, --: * ' SYNOPSIS OF TELEDYNE ISOTOPES PROCEDURE, ANALYSIS OF TELEDYNE ISOTOPES THERMOLUMINESCENT.
SYNOPSIS OF TELEDYNE ISOTOPES PROCEDURE, ANALYSIS OF TELEDYNE ISOTOPES THERMOLUMINESCENT. DOSIMETERS These devices are rectangular Teflon wafers impregnated with 25% caso 4 :Dy phosphor. They are first annealed in a 2S0&deg;C oven prior to exposure in the field. Following field exposure (for a 1-month or 3-month period) four separate areas of the dosimeter are read in a Teledyne Isotopes model 8300 TLD reader. The dosimeter is then re-irradiated by a standardized cs-137 source and the four areas are read again. Calculation of the environmental exposure is performed by computer, using the re-irradiation readings to determine the sensitivity of each area of the dosimeter. The readings of control dosimeters are sUbtracted to aJ.1ow for transit dose and system back-ground.
DOSIMETERS These devices are rectangular Teflon wafers impregnated with 25% caso 4:Dy phosphor.
The results are computed as follows:
They are first annealed in a 2S0&deg;C oven prior to exposure in the field. Following field exposure (for a 1-month or 3-month period) four separate areas of the dosimeter are read in a Teledyne Isotopes model 8300 TLD reader. The dosimeter is then re-irradiated by a standardized cs-137 source and the four areas are read again. Calculation of the environmental exposure is performed by computer, using the re-irradiation readings to determine the sensitivity of each area of the dosimeter.
For. any given area of the dosimeter, the dose in mR is calculated by the following formula:
The readings of control dosimeters are sUbtracted to aJ.1ow for transit dose and system ground. The results are computed as follows: For. any given area of the dosimeter, the dose in mR is calculated by the following formula: DOSE = R
DOSE = R *                       (REDOS~/RR)-AVC R = Initial reading of the area RR = Second reading of. the area (after re-irradiation)
* R = Initial reading of the area RR = Second reading of. the area (after re-irradiation)
REDOSE = Re-irradiation dose, mR AVC =Average of control values, mR 4N where AVC =                         ~CDOSE/4H i=l H     = Total           number of control dosi-meters
REDOSE = Re-irradiation dose, mR AVC =Average of control values, mR 4N where AVC =
        *,*,                                                                     CDOSE = CR*(CREDOSE/CRR)
i=l H = Total number of control meters *,*, CDOSE = CR*(CREDOSE/CRR)  
CDOSE *= control area dose, mR CR = Initial reading of control area CRR = Second reading of the control area (after re-irradiation)
' *. *i ' **.l .. . ' CDOSE *= control area dose, mR CR = Initial reading of control area CRR = Second reading of the control area (after re-irradiation)
CREDOSE = Re-irradiation dose of the control dosimeter, mR
CREDOSE = Re-irradiation dose of the control dosimeter, mR
* 160 -----*-.  
'  * . *i
-*"C'-.. -.. --.,  
      **.l '
.. -._ -7'1"----..-::--
      ... '~
......  
160
..
                    --~:---**----------- ....-.---~---:---~.-.-*"C'-..-.. - - .,                         ..-._ -7'1"----..-::-- ......
*----* *-.---.-*
                                                                                  --~*------~...........,**-                            ---.----.--:---~-------------- .. -*~.~-----:--:-*--*-*-, *----* *-.---.-* ---.- - - .. *-:,-- .
---.---.. *-:,--. ...
 
. j .; . I . : ;: * ' l . ' ,: :*::j APPENDIX E  
APPENDIX E


==SUMMARY==
==SUMMARY==
OF USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARISON STUDIES PROGRAM RESULTS
OF USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARISON STUDIES PROGRAM RESULTS
*-! . ; *.* . . ' ! ; '.; :..... .. * . ' 1 i l )'  
      . j
      . I
,: :*::j
        ~
        ~
l
 
            )'


==SUMMARY==
==SUMMARY==
USEPA INTERCOMPARISON PROGRAM_ Appendix E presents a
O~  USEPA INTERCOMPARISON   ~TUDIES  PROGRAM_
* summa.ry of the analytical*
Appendix E presents a
results for the 1986 USEPA Environraental Radioactivity Laboratory Intercomparison Studies Progr*am.
* summa.ry of the analytical* results for the 1986 USEPA Environraental Radioactivity Laboratory Intercomparison Studies Progr*am.
TABLE NO. E-1 E-2 E-3 E-4 E-5 TABLE OF CONTENTS TABLE DESCRIPTION Gross Alpha and Gross Beta Emitters in Water and Air Particulates  
TABLE OF CONTENTS TABLE NO.                         TABLE DESCRIPTION E-1     Gross Alpha and Gross Beta Emitters in Water and Air Particulates *******************************       164 E-2      Gamma Emitters in Milk, Water, Air Particulates and Food Products ***..*..**********.*******.***       165 E-3      Tri ti um in Water ............* o *******************   167 E-4      Iodine in Water and Milk *************************       168 E-5      Strontium-89 and Strontium-90 in Air Particulates, Milk, Water and Food Products ******************       169
*******************************
* ~
Gamma Emitters in Milk, Water, Air Particulates and Food Products ***..*..**********.*******.***
1 i
Tri ti um in Water ............*
l
o *******************
 
Iodine in Water and Milk *************************
TABLE E-l USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM Gross Alpha and Gross .Beta Analysis of Water (pCi/L) and Air Particulate (pCi/filter)
Strontium-89 and Strontium-90 in Air Particulates, Milk, Water and Food Products ******************
DATE     ENV SAMPLE CODE PSE&:G EPA GRAND AVG MM-YY         ENV ID       MEDI-UM ANALYSIS   Mean :!: s.d. Known     Mean :!: s.d.
164 165 167 168 169 
Ol-86     EPA-WAT-ABl69     Water   Alpha       3.6:1:0.3   3.0:!:8.7   3 .6:!:l.4 86-90                     Beta         6.7:1:0.S   7.0:1:8.7   7 .2:1:l.8 03-86     EPA-WAT-ABl75     Water   Alpha         18:1:3     15:1:8.7     13:!:3 86-374                   Beta           8:1:1       8:1:8.7   10:!:3 03-86     EPA-APT-GABSl76   APT     Alpha       . l7:!:l     15+/-8.7       16+/-3 86-660                   Beta           50+/-1       4"1+/-8. 7     51+/-6 04-86     EPA-WAT-Pl78     Water   Alpha         18:!:1     17+/-8.7       15+/-4 86-512                   Beta           29:il     '35:!:8.7     32:!:5 05-86
'. '-i
      .07-86 EPA-WAT-ABl80
* TABLE E-l USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM Gross Alpha and Gross .Beta Analysis of Water (pCi/L) and Air Particulate (pCi/filter)  
                '86-871 EPA-WAT-ABl89 86-1204 Water
* . .. *** DATE ENV SAMPLE CODE PSE&:G EPA GRAND AVG MM-YY ENV ID MEDI-UM ANALYSIS Mean :!: s.d. Known Mean :!: s.d. Ol-86 EPA-WAT-ABl69 Water Alpha 3.6:1:0.3 3.0:!:8.7 3 .6:!:l.4 86-90 Beta 6.7:1:0.S 7.0:1:8.7 7 .2:1:l.8 03-86 EPA-WAT-ABl75 Water Alpha 18:1:3 15:1:8.7 86-374 Beta 8:1:1 8:1:8.7 03-86 EPA-APT-GABSl76 APT Alpha . l7:!:l 15+/-8.7 86-660 Beta 50+/-1 4"1+/-8. 7 04-86 EPA-WAT-Pl78 Water Alpha 18:!:1 17+/-8.7 86-512 Beta 29:il '35:!:8.7 05-86 EPA-WAT-ABl80 Water Alpha 8:1:1 8:1:8.7 '86-871 Beta* 14:1:1 15:1:8.7 .07-86 EPA-WAT-ABl89
                                  *Water Alpha Beta*
*Water Alpha 6:1:1 6+/-8.7 86-1204 Beta lS:!:l 18+/-8.7 08-86 EPA-APT-GABSl92 APT Alpha 24:1:1 22:1:8.7 86-1567 Beta 90:1:2 66:!:8.7 09-86 EPA-WAT-ABl94 Water Alpha 15:1:1 15:!:8.7 86-1766 Beta 8:1:2 8+/-8.7 10-86 EPA-WAT-Pl97 Water Alpha 44:!:1 40:!:8.7 86-2079 . Beta 19:!:1 51:1:8.7 ll-86 EPA-WAT-ABl99 Water Alpha 19:!:2 20:!:8.7 86-2666 Beta 16:!:1 20:1:8.7
Alpha Beta 8:1:1 14:1:1 6:1:1 lS:!:l 8:1:8.7 15:1:8.7 6+/-8.7 18+/-8.7 7:1:2' 15:!:3 6:1:2 18:1:3 08-86    EPA-APT-GABSl92  APT    Alpha          24:1:1      22:1:8.7     22+/-4 86-1567                   Beta         90:1:2       66:!:8.7     71+/-8 09-86     EPA-WAT-ABl94     Water   Alpha         15:1:1       15:!:8.7     15:!:4 86-1766                   Beta           8:1:2       8+/-8.7       10:!:3 10-86     EPA-WAT-Pl97     Water   Alpha         44:!:1     40:!:8.7     36+/-10
* s.d. -one standard deviation of three individual analytical results *** known value with control limits, indicating whether results are in agreement or disagreement 13:!:3 10:!:3 16+/-3 51+/-6 15+/-4 32:!:5 7:1:2' 15:!:3 6:1:2 18:1:3 22+/-4 71+/-8 15:!:4 10:!:3 36+/-10 47+/-6 17+/-5 21:!:3 ***
'. '-i 86-2079 .                 Beta           19:!:1     51:1:8.7     47+/-6 ll-86     EPA-WAT-ABl99     Water   Alpha         19:!:2       20:!:8.7     17+/-5 86-2666                   Beta         16:!:1       20:1:8.7     21:!:3
-one standard deviation of acceptable results of all participating laboratories 164 ... * 
* s.d. - one standard deviation of three individual analytical results
.. \...' J' '_! * * ' 1 i : .? ' TABLE E-2 USEPA ENVIRONMENTAL.
        *** known value with control limits, indicating whether results are in agreement or disagreement
RADIOACTIVITY LABORATORY INTE.RCOMPARSION STUDY PROGRAM Gamma Analysis of Milk, Water (pCi/L), Air Particulate (pCi/filte!->
        *** s.d~ - one standard deviation of acceptable results of all participating laboratories 164
and Food Product_s (pCi/kq)
 
* DATE ENV SAMPLE CODE PSE&G MM-YY ENV ID MEDIUM ANALYSIS Mean +/- s.d.
.. \. .'            J' TABLE E-2 USEPA ENVIRONMENTAL. RADIOACTIVITY LABORATORY INTE.RCOMPARSION STUDY PROGRAM Gamma Analysis of Milk, Water (pCi/L), Air Particulate (pCi/filte!-> and Food Product_s (pCi/kq)
EPA-ORG-GS170 02-86 86-173 Food K(l) Water cr-51 Co-60 Zn-65 .Ru-106 Cs-134 Cs-137 04=86 EPA=APT=GABSl76 APT 86-660 cs-137 04-86 EPA=WAT-Pl78 86=512 06-86 EPA-MLK-GS184 86-1071 06-86 86-921 07=86 86=1205 Water co-60 cs-134 cs-137 Milk I-131 Cs-137 K(l) water cr-51 Co-60 zn-ss .Ru-106 cs-134 CS-137 Food I=l3l CS-137 K(l) oe-es EPA-APT=GABSl92 APT 86-1567 CS-137 <30 14:1:1 922:1:11 42+/-4 18+/-1 41+/-2 <ll 28:1:1 22:tl lOi:l
DATE                ENV SAMPLE CODE                                                                                                  PSE&G                                    EPA                  GRAND AVG MM-YY                        ENV ID                                    MEDIUM                ANALYSIS                    Mean +/- s.d.                                    Known                  Mean +/- s.d.
* 9:!:1 Sil 6+/-1 43:1:1 37+/-1 1660:1:10  
01~86              EPA-ORG-GS170                                        Food                  I~l:U                              <30                                      20:1:10.4                      21+/-2 86~100                                                                    c:s~l37                              14:1:1                                15+/-8.7                          17+/-2 K(l)                               922:1:11                            950+/-248                        957+/-90 02-86              EPA~WAT-Gl71                                        Water                cr-51                                42+/-4                                  38+/-8.7                        39+/-6 86-173                                                                     Co-60                                 18+/-1                                  18:1:8.7                        18+/-3 Zn-65                                41+/-2                                    40:1:8.7                      41+/-4
<18 66il 87+/-3 43+/-5 46:1:1 lOil 26:ll 2lil l.150:1:30 2lil ** EPA Known 20:1:10.4 15+/-8.7 950+/-248 38+/-8.7 18:1:8.7 40:1:8.7 0 30:1:8.7 22+/-8.7 10:1:8.7 10:.tS.7 5:t8.7 5:!:8.7 41:1:10 .6 31+/-8.7 1600:1:140 0 66:1:8.7 86:1:8.7 50:1:8.7 49+/-8.7 10+/-8.7 30:1:10.4 20:1:s.1-usoiloo 22:1:8.7 *** GRAND AVG Mean +/- s.d. 21+/-2 17+/-2 957+/-90 39+/-6 18+/-3 41+/-4 28+/-4 22+/-3 ll:t2 10+/-2 S:U 6:U 44+/-4 37+/-3 1600:1:110 o 64+/-4 86+/-6 SO:t:ll 46:i:4 11+/-2 28+/-3 21:!:3 llSO:l::l.04 24:M -.  
                                                                                                                              .Ru-106                           <ll                                            0 Cs-134                               28:1:1                                30:1:8.7                        28+/-4 Cs-137                              22:tl                                  22+/-8.7                          22+/-3
....
* 04=86 04-86 EPA=APT=GABSl76 86-660 EPA=WAT-Pl78 86=512 APT Water cs-137 co-60 cs-134 cs-137 lOi:l
.. ..,---...  
* 9:!:1 Sil 6+/-1 10:1:8.7 10:.tS.7 5:t8.7 5:!:8.7 ll:t2 10+/-2 S:U 6:U 06-86              EPA-MLK-GS184                                      Milk                  I-131                                43:1:1                               41:1:10 .6                      44+/-4 86-1071                                                                  Cs-137                                37+/-1                                 31+/-8.7                          37+/-3 K(l)                            1660:1:10                             1600:1:140                      1600:1:110 06-86              EPA-WAT~Gl81                                        water                cr-51                              <18                                            0                                o 86-921                                                                    Co-60                                66il                                66:1:8.7                         64+/-4 zn-ss                                87+/-3                                86:1:8.7                         86+/-6
....  
                                                                                                                            .Ru-106                              43+/-5                                50:1:8.7                         SO:t:ll cs-134                                46:1:1                              49+/-8.7                         46:i:4 CS-137                                lOil                                10+/-8.7                         11+/-2 07=86              EPA~ORG-=GSl90                                      Food                  I=l3l                                26:ll                                30:1:10.4                      28+/-3 86=1205                                                                    CS-137                              2lil                                  20:1:s.1-                      21:!:3 K(l)                            l.150:1:30                          usoiloo                        llSO:l::l.04 oe-es              EPA-APT=GABSl92                                    APT                    CS-137                              2lil                                  22:1:8.7                       24:M 86-1567
...  
* 1 i
-----*
: .?
.._,. ____ ----. ---**-----*-*-**-*-:-
            -. -~---.-..-.----- --""-~- .... ~.---------.,.-----.,.-*----*.-7 ....,---...                         ..
*--* ....* ,._ **-.*
                                                                                          .....--.-,--..,..-.-~.--- -**--:-*--.~~i- ... *-:*~-,..~---------*~*-******-*** -- -- -* ---.---**--~~-*- .._,. ____ - - - - . -- - **--- --*-*-**-*-:- *--* ....* ,._ **-.*
! . ......
 
* TABLE E-2. (cont'd) USEl?A ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMl?ARSION STUDY PROGRAM Gamma Anal.ysis of Milk, Water (pCi/L), Air Particulate (pCi/filter) and Food Products (pCi/kg) "' "'"' "'"'"' DATE ENV SAMl?LE CODE PSE&G El?A GRAND AVG MM-YY ENV ID MEDIUM ANALYSIS Mean :!: s.ci. Known Mean :!: s .ci. 10-86 .EPA-WAT-Gl95 Water cr-51 57:!:8 57:!:8.7 56::1:17 86-1964 Co-60 28::1:2 3l::l:8a 7 31+/-3 Zn-65 79:!:6 85:!:8.7 85+/-7 RU-106 69+/-9 74+/-8.7 68:!:8 cs-134 26+/-2 28:!:8.7 26+/-3 Cs-137 "42:!:2 44:!:8.7 45:!:4 10-86 EPA-MLK-GSl98 Milk I-131 48:!:1 49:!:10.4 . 49+/-5 86-2147 cs-137 44+/-1 39+/-8.7 44+/-3 K(l) 1540:1:20 1565:1:135 1565::1:106 ll-86 El?A-WAT-.E'l97 Water co-60 23il 24:1:8.7 86-2079" CS-134 ll:l:l 12:1:8.7 CS-137 8::1:1 8::1:8.7 "' s.d. -one standarci deviation of three inciiviciual analytical results "'"' known value with control limits, indicating whether results are in agreement or disagreement 24::1:2 11:1:2 9:!:2 "'"'"' s.ci. -one standard cieviation of acceptable results of all participating laboratories (l) Reported as mg/L of Potassium.
TABLE E-2. (cont'd)
166 * . . . .
USEl?A ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMl?ARSION STUDY PROGRAM Gamma Anal.ysis of Milk, Water (pCi/L), Air Particulate (pCi/filter) and Food Products (pCi/kg)
.. --. -.. -....
DATE         ENV SAMl?LE CODE PSE&G El?A GRAND AVG MM-YY             ENV ID                     MEDIUM         ANALYSIS             Mean :!: s.ci.                         Known         Mean :!: s .ci.
**-
10-86       .EPA-WAT-Gl95                   Water         cr-51                       57:!:8                           57:!:8.7           56::1:17 86-1964                                       Co-60                       28::1:2                           3l::l:8a 7         31+/-3 Zn-65                       79:!:6                           85:!:8.7           85+/-7 RU-106                     69+/-9                             74+/-8.7             68:!:8 cs-134                     26+/-2                             28:!:8.7           26+/-3 Cs-137                     "42:!:2                           44:!:8.7           45:!:4 10-86       EPA-MLK-GSl98                   Milk           I-131                       48:!:1                           49:!:10.4         . 49+/-5 86-2147                                       cs-137                     44+/-1                             39+/-8.7             44+/-3 K(l)                   1540:1:20                       1565:1:135           1565::1:106 ll-86       El?A-WAT-.E'l97                 Water         co-60                       23il                             24:1:8.7           24::1:2 86-2079"                                       CS-134                     ll:l:l                           12:1:8.7           11:1:2 CS-137                       8::1:1                             8::1:8.7         9:!:2
......
                                "' s.d. - one standarci deviation of three inciiviciual analytical results
..
                              "'"' known value with control limits, indicating whether results are in agreement or disagreement
*--* ---.,., **::----*-...,., *.---:-:
                            "'"'"' s.ci. - one standard cieviation of acceptable results of all participating laboratories (l) Reported as mg/L of Potassium.
* USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM Tritiwn Anal.ysis of Water (pCi/L) ,,. ** *** DATE ENV SAMPLE CODE PSE&G EPA GRAND AVG MM-YY ENV ID MEDIUM ANALYSIS Mean +/- Sod. Known Mean +/- s.do EPA=WAT-Hl72 Water H=3 5170+/-70 5227:!:906 5105+/-340 06=86 Water H-3 3000:1:80 3125+/-624 3052+/-347 86-981 10-86 EPA-WAT-H196 Water H-3 5890+/-l.OO 5973+/-1.034 5694+/-406 86-1965 ,,. Sodo -one standard deviat.ion of three individual analytical results ** known value with control limits, indicating whether results are in agreement or disagreement
.  *-~-
**a Sodo -one standard deviation of acceptable results of all participating laboratories 167 ---------*
166
-......,.._
  . -----------*---...-:-~*----.-.--.~**--------**---~.. --.- .. -.... -~.,----:--~*----:?-,----. **- -~-...----.--._-~*;"C""~ ...                .
-*-
_,.-.---~-----~- ---:-*-----~--. *--* --- .,., **::-- --*-...,., *.---:-:
-**--**--..----*----.. -.-:--'?""""*
 
.---;'",-*.*--
USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM Tritiwn Anal.ysis of Water (pCi/L)
**--**  
DATE                        ENV SAMPLE CODE                                                                                                      PSE&G        EPA                      GRAND AVG MM-YY                                  ENV ID                                MEDIUM                    ANALYSIS                      Mean +/- Sod.          Known                  Mean +/- s.do 02~86                      EPA=WAT-Hl72                                      Water                      H=3                              5170+/-70          5227:!:906                  5105+/-340 86~244 06=86                      EPA~WAT~Hl82                                      Water                      H-3                              3000:1:80        3125+/-624                    3052+/-347 86-981 10-86                      EPA-WAT-H196                                      Water                      H-3                              5890+/-l.OO        5973+/-1.034                  5694+/-406 86-1965
----,. ***--*----* -----*-*:*-*;
              ,,. Sodo - one standard deviat.ion of three individual analytical results
-
            ** known value with control limits, indicating whether results are in agreement or disagreement
. . . **'; .*. "*" . i *-** ,( ** TABLE E-4 USEPA ENVI*RONMENTAL
        **a Sodo - one standard deviation of acceptable results of all participating laboratories
:RADIOACTIVITY LABORATORY IN'I'ER.:OMPARSION STUDY PROGRAM Iodine Analysis of Water and Milk (pCi/L) " "" """ DATE ENV SAMPLE CODE* PSE&G EPA GRAND AVG MM-YY ENV ID MEDIUM ANALYSIS Mean +/- s.d. Known Mean +/- s.d. 03-86 EPA-MLK-Il 72 Milk(l) I-l3l 2.4+/-1 9::1:10.4 86-245 04-86 El?A-WA'I'-Il 77 Water 8::1:l 9::1:10.4
* 167
*86-424 *08-86 El?A-WA'I'-Il9l Water I-131 39::1:1 45+/-10.4 86-1305 " s.d. -.one standarc1 deviation of three individual analytical results "" known value with control limits, indicating whether results are in agreement or disagreement 9+/-2 9+/-2 42+/-6 """ s.d. -one standarc1 deviation of acceptable results of all participating laboratories (1) Special El?A/NRC low level study
  ~~~ ---------* - ......,.._ -*- ----.,,-.-;.~----.-**--**- -..-- - - *---- .. -.-:--'?""""* .---;'",-*.*-- -~-- ---~-~---, **-- ** ~--**** ---- ----~ -~-- ,.         ***--*--- -* --- - - *-*:*- *; ----~---~---*' -
* 168 .. , *   
 
...: _(\ * ... . ; i ' .j *. i
                                                                                                    ,(
* 1 ' TABLE E-5
TABLE E-4 USEPA ENVI*RONMENTAL :RADIOACTIVITY LABORATORY IN'I'ER.:OMPARSION STUDY PROGRAM Iodine Analysis of Water and Milk (pCi/L)
* USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM* Strontium-89 and Strontium-90 Analysis of Air Particulates (pCi/filter), Milk, Water (pCi/L) and Food Products (pCi/kq) * ** "'** DATE ENV SAMPLE CODE PSE&G EPA GRAND AVG MM-YY ENV ID MEDIUM ANALYSIS Mean :t: s.d. Known Mean +/- s.d. 01=86 EPA-WAT-5168 Water sr-89 24+/-2 31+/-10.4 31+/-5 86-26 Sr-90 12+/-1 15+/-2.6 14+/-2.2 01-86 EPA-ORG-GS170 Food sr-89 (l) 86-108 sr-90 (1) 03-86 EPA-APT-GABSl76 APT sr.:..90 16+/-1 18+/-2.6 17+/-2 86-660 04-86 EPA-WAT-Pl78 Water Sr-89 6:1::1 7+/-8.7 6+/-2 86-512 sr-90 6:t::l 7+/-2.6 7+/-1 05=86 EPA-WAT-SJ.79 water Sr=89 -4:tl S:t8.7 5+/-2 86-675 Sr=90 4::1::1 5:1::2.6 5+/-1 EPA-MLK-GS184 Mi.lk. Sr=89 <4 o 0 86-1071 sr-9o l2il 16+/-2.6 15+/-3 07-86 EPA-ORG-GSl90 Food sr-89 24+/-2 30+/-8.7 25+/-3 86-1205 sr-90 16+/-2 19+/-2.6 19+/-7 08-86 EPA-WAT-GABSl92 APT sr-90 22+/-1* 22+/-2.6 22+/-3 86-1567 10-86 EPA-MLK-GSl98 Milk sr-89 8:t:l. 9+/-8.7 9+/-3 86 00 2147 sr-90 <l.6 0 1+/-0.S l.l-86 EPA-WAT-Pl97 Water sr-89 10+/-1 10+/-8.7 9+/-3 86-2079 sr-90 3:t:l 4+/-2.6 4:.t:l
DATE     ENV SAMPLE CODE*
* s.d ... one standard deviation of three incli.vidual analytical results_ ** known value with control l.i.mits, whether results are in agreement or disagreement a*a s.d. -one standard deviation of acceptal::lle results of all.
PSE&G EPA GRAND AVG MM-YY         ENV ID         MEDIUM ANALYSIS     Mean +/- s.d. Known     Mean +/- s.d.
laboratories (l) Not analyzed by PSE&G.
03-86   EPA-MLK-Il 72        Milk(l) I-l3l          2.4+/-1        9::1:10.4     9+/-2 86-245 04-86    El?A-WA'I'-Il 77    Water  I~131            8::1:l    9::1:10.4    9+/-2
.. .,-.-.,.-.,-*--****-***-.  
                          *86-424
*-**--*-*--
                *08-86    El?A-WA'I'-Il9l      Water  I-131          39::1:1    45+/-10.4      42+/-6 86-1305
-*----*-***------*----"'
                    " s.d. -.one standarc1 deviation of three individual analytical results
.. -*-,-**. c ... ,_. __ '**-* --*. -*--* .. . .* I 
                  "" known value with control limits, indicating whether results are in agreement or disagreement
* : . '.j J *' ' ., *i -' :_* :.1 . I . . :. . *.} .. * '. ; ,.: -" APPENDIX F SYNOPSIS OF LAND USE CENSUS 171 
                  """ s.d. - one standarc1 deviation of acceptable results of all participating laboratories (1) Special El?A/NRC low level study *
* * : *; *. 1 * . . . . I ., .. *l .. ; *_
    . /~ **';
APPENDIX F SYNOPSIS OF l986&deg;LAND USE CENSUS A land use census was conducted to identify, within a distance of 8 km (5 miles), the location of the nearest milk animal, the nearest residence and the nearest garden of greater than 5om2 (500ft2) producing broad leaf vegetation in each of the 16 meteorological sectors.
            *-~
* Tabulated below are the results of these surveys: Meteorological Sector N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW Milk Animal Aug., 1986 km (miles) None None None None None None None None None None None None 7.8 (4.9) None None None Nearest Residence Aug., 1986 km (miles) None 6.9 (4.3) 6.4 (4.0) 6.1 (3.8) 5.4 (3.4) None None None 6.1 (4.1) 5.5 (3.4) 6.9 (4.3) 7.1 (4.4) 6.5 (4.0) 5.5 (3.4) 5.9 (3.7) 6.8 (4.2) Vegetable Garden Aug., 198 6 km (miles) None None None None None None None None None None None None None None None None}}
.*. ~ "*" . i 168
 
...:          _(\
TABLE E-5
* USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM*
Strontium-89 and Strontium-90 Analysis of Air Particulates (pCi/filter),
Milk, Water (pCi/L) and Food Products (pCi/kq)
DATE      ENV SAMPLE CODE                                                              PSE&G                                EPA                       GRAND AVG MM-YY            ENV ID                        MEDIUM          ANALYSIS          Mean :t: s.d.                            Known                    Mean +/- s.d.
01=86     EPA-WAT-5168                        Water          sr-89                    24+/-2                               31+/-10.4                        31+/-5 86-26                                              Sr-90                   12+/-1                              15+/-2.6                         14+/-2.2 01-86      EPA-ORG-GS170                      Food            sr-89                      (l) 86-108                                              sr-90                      (1) 03-86     EPA-APT-GABSl76                    APT             sr.:..90               16+/-1                               18+/-2.6                         17+/-2 86-660 04-86     EPA-WAT-Pl78                      Water            Sr-89                     6:1::1                            7+/-8.7                         6+/-2 7+/-1 86-512                                              sr-90                     6:t::l                             7+/-2.6 05=86     EPA-WAT-SJ.79                      water            Sr=89 -                   4:tl                              S:t8.7                         5+/-2 86-675                                              Sr=90                     4::1::1                            5:1::2.6                      5+/-1 os~ss      EPA-MLK-GS184                      Mi.lk.           Sr=89                    <4                                      o                            0 86-1071                                            sr-9o                  l2il                              16+/-2.6                          15+/-3 07-86      EPA-ORG-GSl90                      Food            sr-89                  24+/-2                                30+/-8.7                        25+/-3 86-1205                                            sr-90                  16+/-2                                19+/-2.6                        19+/-7 08-86      EPA-WAT-GABSl92                    APT              sr-90                  22+/-1*                             22+/-2.6                          22+/-3 86-1567 10-86      EPA-MLK-GSl98                      Milk            sr-89                      8:t:l.                            9+/-8.7                          9+/-3 86 2147 00 sr-90              <l.6                                        0                            1+/-0.S l.l-86    EPA-WAT-Pl97                      Water            sr-89                  10+/-1                              10+/-8.7                            9+/-3
        ;                        86-2079                                            sr-90                      3:t:l                              4+/-2.6                          4:.t:l i
* s.d ... one standard deviation of three incli.vidual analytical results_
                        ** known value with control l.i.mits, inclicat~ng whether results are in agreement or disagreement a*a  s.d. - one standard deviation of acceptal::lle results of all.                                                                  part~cipating laboratories (l) Not analyzed by PSE&G.
    .j
  *. i
    *1
        '-o.---~~*---***~-----~--**;--~-~---.-- ...,-.-.,.-.,-*--****-***-. -~ -*-----*~-**.---*-*****--*--*-.  *-**--*-*-- -*---- *-***-- ----*----"' .. - *-,-**. c ... ,_. __ '**-*    -- *.-*--* .. . .* I
 
APPENDIX F SYNOPSIS OF LAND USE CENSUS
: . '.j J
                *i
-    :_* :.1 .
        . . :. ~
            . *.}
                  '~
I 171
* APPENDIX F SYNOPSIS OF l986&deg;LAND USE CENSUS A land use census was conducted to identify, within  a distance of 8 km (5 miles), the location of the nearest milk  animal, the nearest residence and the nearest garden of greater  than 5om2 (500ft2) producing broad leaf vegetation in each of  the 16 meteorological sectors.
* Tabulated below are the results of these surveys:
Milk        Nearest      Vegetable Animal      Residence        Garden Meteorological    Aug., 1986      Aug., 1986    Aug., 198 6 Sector          km (miles)     km (miles)    km (miles)
N                None            None          None NNE              None          6.9 (4.3)       None NE                None          6.4 (4.0)       None ENE              None          6.1 (3.8)       None E                None         5.4 (3.4)      None ESE              None           None         None SE                None           None         None SSE              None           None         None s                None         6.1 (4.1)        None SSW              None          5.5 (3.4)      None SW                None         6.9 (4.3)        None WSW              None        7.1 (4.4)        None w              7.8 (4.9)      6.5 (4.0)        None WNW              None        5.5 (3.4)        None NW                None        5.9 (3.7)        None NNW              None        6.8 (4.2)        None
        *. 1
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      .. *l
          ~
I
      *_~-*~}}

Latest revision as of 17:46, 28 February 2020

Artificial Island Radiological Environ Monitoring Program, 1986 Annual Radiological Environ Operating Rept.
ML18092B555
Person / Time
Site: Salem, Hope Creek, 05000000
Issue date: 12/31/1986
From:
PSE&G RESEARCH CORP.
To:
Shared Package
ML18092B554 List:
References
RTL-ENV-87-01, RTL-ENV-87-1, NUDOCS 8705070117
Download: ML18092B555 (169)
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Text

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RTL-ENV-"'87-01 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Fc.w Salem Generating Stat.icn. Unit i: Doc:l<et No. 50=272 Salem Generating Staticmo Unit 2: Docket No. 50-<:H,,1 Hope Creel< Generating Stat ion: Doc:l<et No. 50-354 I 1986 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 

                                                                        ..JANUARY                      1      TO DECEMBER 31, 1986 PUBLIC SERVICE ELECTRIC ANO GAS COMPANY Sy
                                                                                       ~SE&G               RESEARCH CORPORATION
     ;                                                                          RESEA~CH                     ANO TESTING LABORATOR~

. *-.j APRIL 1987 I 

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TABLE OF CONTENTS

SUMMARY

o***** *0*111e1oocieo11e1e1c()CDeoc**g****C11E10***C1**0*0C ' 1' 1 INTRODUCTION. eC1eeeC1Geeeeee*eeeeeeGeeeee *'. 0 ****** Cl

  • 2 THE PROGRAM ** **oc*C1*e*****oeeeec1>eo1:1t1* 3 Objectives. c o o o e o o E> o o o o o o o Cl e o o o o *
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OOOCIOCCCICO 3 sample Collection. oeooo0ceGeoooeoe O.eOCCICI000CO 4 Data Interpretation. e e e e Cl o Cl Cl* e e 0 G e e Cl e D. O Cl e !I* O G Cl e Cl Cl Cl Cl 0 e Cl Cl 5 Quality Assurance Program. 6 Program Changes~ *** . '** 

                                                                                                                                           .  *t ID !~   e  e e                                       7 RESULTS AND DISCUSSION.                                                                                                          efloeooo1D*eoo                                7 Atmospherieo       0 0 0 0 D 0  e cc c     0 Cl) 0  0 0  0   0 0 0   0  0    c' 0   (!) 0 *11 o'   0   0  C>    ~;o     0. e  Cl 0  0.0   0  0 Cl 0  0            7 Direct Radiation ***               OCODOCCIC8()0000000                                                                                                             10 Terrestrial ** " o e       OG   Cl 0 00    00    OC!IOGGOO           0   0   0   Cl                                                                                10 Aquatic *****            * * *  *  * *. *  * *   *
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  • 0 16 PROGRAM DEVIATIONS. e e Cl e e e e e G Cl G Cl e e e e e e e e e ,e e e e e e e e e e Cl e e ID 8 e e e Cl e 19 CONCLUSIONS ****** ************cioeoeeooocoe C1eeeOGCOGeC1eee 19 PROGRAM OVERVIEW. 0000CICIOOCICOCICI080000DOCI
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  • 21 REFERENCES. ooocaooooeeeoccooooocociao eaeooooocoeooeeoooo 36 APPENDIX A PROGRAM

SUMMARY

. () ... 'ci. 0 0 Cl c Cl 0 39 APPENDIX B SAMPLE DESIGNATION AND:LOCATIONS. 51 APPENDIX C DATA TABLES ********** Q 0 '* . '* CIOOOOOOOOCCCOCIOCIOCOOO 59 APPENDIX D SYNOPSIS OF ANALYTICAL'PROCEDURESo Cl Cl 0.0. Cl 0 0 cc 0 113 

    "'                     APPENDIX E

SUMMARY

OF USEPA ENVIRONMENTAL RADIOACTIVITY 

     "                                            LABORATORY INTERCOMPARISON STUDIES PROGRAM RESULTS      0°0  Cl c Cl* 0 . 0   0. c  G   G. 0° 0   0 . :0      0   0                                                                      161 APPENDIX F             SYNOPSIS OF LAND USE CENSUS.                                                 0  0    0   o_o      0   0   0  0  0  0  0  0. 0  0 .-0    ... 171
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                                                                                                                                                                                                                ~

LIST OF. FIGU.RES .. *.. FIGURE* NUMBER. . FIGURE DESCRIPTION. 

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

PAGE 

                                                                                                                    ~
1. Comparison of Average Concentrations of Beta Emitters in Precipitation and in Air Particulates,.

1973 through 1986.................................. 26 lA. Comparisbn of Average Concentrations of Beta Emitters in Precipitation and in Air Particulates, 1983 th~ough 1986 ********* ~........................ 27

2. Average Ambient Radiation* Levels from Quarterly TLDs in the Vicinity of Artificial Island, 1973 through 1~86 .......* ** . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 28 2A. Comparison of Ambient Radiation Levels of Off-Site Indicator Station~ vs. Cont~ol Stations, 1982 through 1986 *************************************** 29
3. Average Concentrations of Iodine-131 in Milk in the Vicinity of Artificial Island, May 1974 through December 1986 **********.** :.- *.*************** * *******. 30 ~

3A. Average Concentrations of Iodine-131 in Milk in the Vicinity of Artificial Island, 1983 througn 1986 ... 31 

    *.**;          4.      Average Concentrations of Beta Emitters and Potassium-40 in the Delaware River in the Vicinity
*.*   . *'                 6f Artificialjisland, 1973 through 1986 ****** ~ *****                                      32 4A.      Average Concen~rations of Beta Emitters and Potassium-40 in the Delaware River in the Vicinity of Artificial Island, 1983 through 1986 ************                                         33
s. Average Concentrations of Tritium in the Delaware River in the Vicinity of Artificial Island, 1973 through 1986* ..*.....*..*. *............*. *...*... :. ..... 34
/ ..

SA. Average Concentrations of Tritium in *the Delaware River in the Vicinity of Artificial Island, 1983 

  *.. ,.j                   through 1986 *************************** ~ ***********

1:1.

SUMMARY

During the per.iod from January l through December* 31, 1986;. the*. Research* and Testing Laboratory (RTL), PSE&G Research Cor.po-ration, has been responsible for the collection and analysis of all samples and the maintenance of sampling equipment connected with the Radiolog_ical Environmental Monitoring Program (llEMP'); at Artificial Island, Salem County, New Jersey. This program was designed to identify .and quantify concentra~ tions of radioactivity in various environmental media and ta quantify ambient radiation levels in therenvirons of Artificial Island. Due to the proximity of the Salem~and Hope Creek Gener-ating Stations a common REMP is beinci' co.hducted. Salem Gene.r-ating Station (SGS) Unit One became* crit:ic!al on December 11., 1976, thereby initiating the operational phase of the REBPo Data collected during the operaJ:,ion,al! phase served as a sourc:e.- of preoperational data for Salem Uqit ~wo and the Hope Creek Generating Station. Salem Unit Two achieved initial criticality on August 2, 1980 and the Hope Cre~k :G:enerating Station achieved initial criticality on June 28, 19:~6 ~ '! This report presents the results of thermoluminescent dosi~~t~i arid radiological analyses of environmental samples collected~d~iing 1986. A total of 4091 analyses were perf'ormed on 1615 environment.al samples during the period covered' by .this report.- Samples of air particulates, air iodine, surface, ground and drinking water, benthic organisms, sediment, milk, fish, crabs, vegeta-bles, game, fodder crops, meat, soi1,:* and precipitation were r: collected. Thermoluminescent dos~meter$ were* used to measure ambien~ radiation levels. Ambient radiation levels remained .at normal levels observed in previous years until May 9, 19~~ when radioactivity from the Chernobyl-4 reactor accident wa~ detected. According to reports provided to Western scientists at:the International Atomic Energy Agency conference on Chernc;>byl held in Vienna, Austria, it is now known that the accident occurred as a result of a 

     -~

poorly planned reactor experiment. Soviet plant personnel I deliberately took actions which blocked the plant's safeguard 

      .   '        systems that would have automatically prevented the accidento
**: .. i This action resulted in a reactivity excursion accident in which the reactor became prompt c;ri.tical [ 24 I. The excursion resulted in a power escalation which resulted in fuel melting and finally
         -,        a steam explosion which prdp~lled fuel fragments, activation products and burning graphite into the environmente The intense heat of the graphite fire.provided a mechanism for the radio~

active fission products and activation products to_ become_. sufficiently buoyant to enter :the upper atmosphere [ 25]. 

     '.*:~         Actions taken to fight the fire resulted in additional destruc~

tion of.the core which caused*airborne releases into the environment to fluctuated by several orders of magnitude for several days after the accident~

Estimates*: of projected :I-131 concentrations :i;n milk*. in the. town .... of Pr ipyat, . USSR. were .'reported*. as :high as 10 3, 700 ,*ooo pCi/L [ 25 l ~.

  • The Soviets arid the Scandariavian countries.also.repcirted measur--

ing excessive concentrations of radioactivity in.soiis,, reindeer flesh, fish, wells, rainwater and goat milk.* .Since all releases from*our nuclear stations were within our technical -specifica-tions, the increases in radioactivity a~ measured in various environmental media in the vicinity of the Artificial Island were due to the accident at Chernobyl-4 and not to the operation of the Salem or Hope Creek. Generating Stations *. INTRODUCTION Artificial Island is the site of Salem and Hope Creek Generating Stations. The Salem -Generating Station (SGS) consists of two operating pressurized water nuclear power reactors. Salem Unit One has *a net rating of 1090 MWe (3338 MWt), and Salem Unit Two is rated at 1115 MWe (3411 MWt). The Hope Creek Generating Station (HCGS) is a boiling water nuclear power reactor which achieved initial criticality on June 28, 1986. The Hope Creek Unit has a* net rating of 1067 MWe (3293 MWt). Artificial .Island is a* man-made peninsula on the east bank of th Delaware River and was created by the deposition of hydraulic fill from dredging operations. It. is located in Lower Alloways Creek Township, Salem County, New Jersey *. The environment

  • surrounding Artificial Island is characterized mainly by the Delaware River and Bay, extensive tidal marshlands, and low-lying meadowlands. These land types make up approximately 85% of the land area within five miles of the site. Most of the remaining land is used for agriculture [7,8]. More specific informatfon
                                                         .on the demography, hydrology, meteorology, and land use of the area may be found *in the Environmental Beports [7,8], Environ-mental Statements [9,10], and the Updated Final Safety Analysis Report for SGS [11] and the Final Safety Analysis .Report for HCGS
                ..                                         [ 12].                                                                                            /

Since 196a an off-site Radiological Environmental M6nitoring Program (REMP) has beeri conducted at the Artificial Island Site. 

                                                       *Starting in December* 1972, more extensive radiological monitoring programs were. initiated. The operational REMP. was initiated in December 1976 when Salem Unit 1 achieved criticality. The
                 .. t.                                    Research and Testing Laboratory (RTL), PSE&G Research Corpo-ration, a wholly-owned subsidiary of Public Service Electric and

. ~ .. *: . ~ 

             .. *.                                        Gas Company,. has been involved in the REMP since its inception
  • The RTL is responsible for the collection of all radiological environmental samples, and, from 1973, through June, 1983, conducted a quality assurance program in which duplicates of a portion of those samples analyzed by the primary laboratory were also analyzed by the RTL. *
  • 2
                    '-.~._..-...,."'."'-, ---*~-:**.---;--~ - : : : - - :-     *. - : . : - - *~
                                                                                               ... _,-~-                                                                                         ...
                                                                                                                                 ..... - . * - -- .. - .~*-::~-:-'-. -:~*-7""-~~--~---~~-~~.--:-: ~:---:*--~*-*.
                                                                                                       .. - - - - - .- .- . "-;-"?-                                                                              ------ ---** -*--;--* *--- -*--- -*-**
    • From January1 1973, through. June, ,.1983 1.. Radiation Management
  • Corporation (RMC) had primary responsib-ility. for _the analysis of all samples under the Artificial. Island REMP and the annual reporting of* results.
  • RMC reports for the *the preopera tional phase from* 197 3 to 1976 and for *the operational phase from 1976 through 1982 are referenced in this report [l-3]. On July 1, 1983, the RTL assumed primary responsibility.for the analysis of all samples (except TLD's) arid the reporting of results.

Teledyne Isotopes (TI), Westwoo9, NJ, at that time was made responsible for third-party QA analyses and TLD's *. RTL reports for the operational phase from i983 to 1985 are refere~ced in this report [4~6]. 

                                                                                                          ' "          t     ;

This report summarizes the r.esu:lts from January l through December 31, 1986, for the* A;rtffi!cial Island Radiological Environmental Monitoring ~r~gram

  • I: **
                                                                                                       '1 THE PROGRAM                                                  t;    r .t~
                                                                                                            ~    :-;

The operational phase of !th~ :;REMP was conducted in accordance with Section Sections 3/4~l~~and 6.9.1.10 of Appendix A to SGS Oper*ting Licenses DPR-7& and DPR-75 [14,15] and. Sections 3/4.12 and 6c9.l *. ~. of Appendix A to:HCGS Operating License NPF=57 [lSlo An overview of the program is provided in Table 1 (page 21). Radioanalytical data from samples collected under this program were compared with results from the preoperational phase. Differences between these periods were examined statistically, where applicable, to d~te~mine the effects, if any, of station operations. * *

  • The REMP for the Artii~cial Island Site includes additional samples and analyses not specifically required by the Salem and Hope Creek Generating :Stations Technical Specifications. The summary tables in this r~port include these additional samples and analyses
  • Objectives
          . .,                                                                   *. '
  • l
         ' .; .~

i The objectives bf'.: th'e Operational Radiological* Environmental i Monitoring Program ~re: 

                  !                          1. To fulfill.~h~ obligations of the Radiological surveillance

_,' sections of the Technical Specifications for the Salem 

                  .                                Generating"Station 1SGS) and the Hope Creek Generating
            *.    *j Station (HCGS).
2. To determine whether any significant increase occurs in the concentration'of radionuclides in critical pathways *
           .. ~ I
    . :. j

.******. . \'!'

. j
                    ~
                '*1
                    *~--- *---~-;""'r~- ,---------**---~
                         ...          .. - .             .. ,-.... c7 .. *--,..,..,*~~~~.;.;.,~.:- -- **-----..-- .. - _.... *----.----, ..... _ .*---.,:--*~~--- * ******-*r,***- -i-*-*

4. To determine-if SGS or HCGS has*~caused :an increase*in radidactive,inventory.of;long~lived radionuclides~. To detect any change .in ambient gamma.radiation.levels. 

                                                                                       ~he
5. To verify that SGS and HCGS operations have no detrimental effects on the health and safety of the public or on. the environment.

This report, as required by Section 6.9.1.10 of the Salem Technical Specifications, and Section 6.9.l.,6 of the Hope Creek Technical Specifications summarizes the findings of the 1986 REMP. Results of the four-year preoperational program which was conducted prior to the operation of any reactors on the Arti-ficial Island have been summarized for purposes of comparison with subsequent operational reports [2]. Sample Collection In order to meet the stated objectives, an appropriate opera-tional REMP .was developed." samples of var.ious media were selected to obtain data for the evaluation of the radiation dose to man and other organisms *. The selection of sample types was bas~d on: (1) established critical pathways for the transfer of radionuclides through the environment to man, and .(2) experience gained during the preoperat.ional phase. Sampling l.ocations were determined from site meteorology,* Delaware estuarine hydrology, local demography, and land uses~ Sampling locations were divided into two classes - indicator and control. Indicator statioris are those which are expected to manifest station effects, if any exist; control samples are collected at locations which are believed to be unaffected by station operations. Fluctuations in the le~els of radionuclides and direct radiation at indicator stations are evaluated with respect to analogous fluctuations at control. stations. Indicator and control station data.are also evaluated relative to preoper-ational data. Air particulates were 'collected on Schleicher-Schuell No. 25 glass fiber filters with low-volume air samplers. Iodine was collected from air by adsorption on TEDA-impregnated charcoal cartridges connected -in series after the air particulate filters. Air sample volumes were measured with calibrated dry-gas meters and were corrected to standard temperature and pressure. * . . . - : :**. ~ 

                -~

Precipitation was collected in a. Wong Laboratory Automatic Precipitation Collector having a 95 square inch collection area. The collector is automatically covered during periods of* no precipi. ta ti on to exclude fallout resulting from dry. deposition *

  • Samples were collected monthly and transferred to new polyethyle
  • ' .1 4

bottles~ The collecto~~as rinsed~with distilled watet to ... include residual particulates-in the precipitation samples * 

                                               . Tritium results were corrected. f.or. the tritium. content *o*f the.

distilled water. Ambient radiation levels in the environs were measured with energy-compensated CaS04 (Dy) thermoluminescent dosimeters (TLD's) supplied and riead by Teledyne Isotopes. Packets for monthly and quarte~ly:exposure were placed on and around the Artificial Island Sit~ at various distances. Well water samples. were. collected monthly by PSE&G personnel and separate raw and ~~ea~ea potable water samples were composited daily by personnel.of~ the City of Salem water treatment plant. 

                                                  *New two~gallon polyethy!lene containers were used .for all water samples.                                       ;

I All estuarine sa,mples were collected by V. J. Schuler Associates f Inc. and delive~ed ~y PSE&G personnel. surface water samples were collected ~n!n~w containers which were rinsed twice with the sample medium p~i~rj t~ collection. Edible fish and crabs were taken by net, and~ f..rozen in sealed polyethylene containers. Benthos and sedim*it samples were taken with a bottom grab sampler. Milk samples were taken semi-monthly when cows were on pasture and monthly when cows were not grazing on open pasture. Samples were collected in hew polyethylene containers. Food products, fodder crops, game;~ and beef were sealed in new plastic bags or jarso All perishable samples were transported in ice chests, and no preservative$ wer~'added. Soil samples:.wh~ch *are collected once every three years were collected at several locations in New Jersey and Delaware. Appendix A describes and summarizes, in accordance with Section

6. 9. l ~ 10 of .the Salem TS and Section 6. 9 .1 *. 6
  • of the Hope Creek TS, the enti~e*operational program as performed in 1986.

Appendix B.des~ribes the coding system which identifies sample 

             .'                                    type and location. Table B-1 lists the sampling stations and the
            .,                                     types of. samples collected at each station. These sampling 1                                   stations are indicated on maps B~l and B-2.

Data Inter~retation 

  *** .....    :                                   Results. 0~*~11 analyses were grouped according to the analysis.

performed for each type of sample and are presented in the data tables : in :Appendix c. All results above the lower limit of detection (:LLD) are at a confidence level of +/- 2 sigma. This 1 represents: *the range of values into which 95% of repeated analyses of the same sample should fall. As defined in Regula-tory Guide:4.8, LLD is the smallest concentration of radioactive 

 *'"         .J
  • .**:Z

... -j 

            *j
               .                                                           ..:~  .* .

l 

                 -,....----;-***--;--*---*-- *--- -----.-~----**.:. --.-~.*.~r,f~
                                                                        ..      ..j--*-** *-* --*- -*---.*.*-*- *--.-*-**-*---.-*,-----.**---.- -- -- * --**--****.-**-**-.-- --*.**** .,. .. ______ ;-*---* -- --*---- .... - - - .- . I

I. 

                                         . material.* in *a sample that* will. yie-ld a' net count (above system*.
                                        . backgrouIJ,dJ that wil,l. be detected* wi-.th 95% probabi*li°ty with only 5% probability of falsely concluding that a *blank observation represents a. "real signal". LLD i~ normally calculated as 4~66
                                                                                                                                                                                        *~

times one standard deviation of the background count or of the blank sample count as appropriate. The grouped data were averaged and standard deviations calculated in accordance with Appendix B of Reference 18. Thus, the 2 sigma deviation* of the averaged data represent sample and not analytical variability. When a group of d~ta was composed Of 50%* or more LLD values, averages were not calculated. Grab sampling is a useful and acceptable procedure for taking environmental samples of a medium in which the concentration of radionuclides i~ expected to vary slowly with time or where intermittent sampling is deemed sufficient to establish the radiological characteristic~ of the medium. This method, however, is only representative of the sampled medium for that specific location and instant of time. As a result, variation in the radionuclide concentrations of the samples will normally occur. Since these variations will tend to counterbalance one another, the extraction of averages based upon repetitive grab samples is considered valid.

  • Quality Assurance Program PSE&G Research Corporation, Research and Testing Laboratory (RTL), has a quality assurance program designed .to maximize confidence in the analytical procedures used. Approximately 20%

of the total analytical effort is spent on quality control, including process quality control, instrument quality control, interlaboratory cross-check analyses, and data review. The analytical methods utilized in this program are summarized in Appendix* D. The quality of the results obtained by the RTL is insured by the implementation of the Quality Assurance Program as described in . the Environmental Division Quality Assurance Plan [19,20] and the Environmental Division Procedures Manual [21]~. The internal

  • quality control activity of the Laboratory includes the quality control of instrumentation, equipment and reagents; the use of reference standards in calibration, documentation of established procedures and computer programs, and analysis of duplicate and spiked samples. The external quality control activity is imple-mented through participation in the USEPA Laboratory Intercom-par ison Studies Prog*ram. These results are listed in Tables E-1 through E-5 in Appendix E
  • I '*
         '-.-----:_,,..,~-.,.---:-:----:-_--:--*.--, -~-.~-~~-
                                                                    -~,,..,..-~---.-*""7""'~~-~~""'7~':~-..,..-;_. -*-:-.*----":"7.-**;*.*--...*--:**~-,.-----.*o---*-*-;- ..-*- *-- --

Program*changes* Location 2F4 from which milk~.fodder crops and soil were collected, terminated milk production in Sept~mber and was. replaced by location 2F7. No samples were missed due to this change.  : RESULTS AND DISCUSSION The analy:ticai: results of the 1986 REMP samples are divided into categories ~a~ed on exposure pathways~ atmospheric, direct, terrestrt;al ~ .. ~nd aquatic. The analytical results for the 1986 REMP are *;summarized in Appendix A. The* data for individual sample~ ~r~*presented in Appendix Co This i~c~~~n discusses the data for samples colle~ted under the REMP. ;;ri:~:does not include the data from the quality assurance program ~~sc~ssed previously. 

                                                      !:    J.  !! .

AtmosPheric 

                                       . Air Part!culates (Tables C-1, C-2, C-3)

The.* weekl:y air particulate samples were analyzed for gross alpha and gros$ beta. Quarterly composites of the weekly samples from each* station, were analyzed for specific gamma emitters and a 

                                         .single quarterly composite sample was analyzed for Sr-89 and sr~90.             Total data recovery for the eight sampling stations du~in$ 1986 was 98.4 percent.

Concentrations were detected in 359 of the 416 weekly samples analy~ed for gross alpha emitters (Table C-1). Alpha concentra~ tions: ranged from 0.8 x io-3 to 22 x lo-3 pCi/m3 with the gr~n~ average for all stations being 2.6 x lo-3 pCi/m3. i Analysis of weekly air p~rticulate samples for gross beta (Table 

                                ..... --C=2) , indicated concentrations were                                                                   detected in 410 of the 416
                                 .";**samples ranging from 6.7 x io-3 to                                                                       370 x io~3 pCifm3, with
                                      * ~he grand average for a11* stations                                                                    being 41 x io-3 pCi/m3.

I Figure 1 indicates the relation between gross beta activity in 

                           ~       .' . ~ir particulates and precipitation for the preoperational and f'.*'.

f

*~

operational periods, including the effects of atmospheric weapons

  • .:.. .- .. *;: testing and the accident at the Chernobyl-4 nuclear power*

t! reactor.' Strontium~89 and sr-90 analyses are no longer required by the T*chnical Specifications for the Salem or Hope Creek Generating s.tat:ions. In order to maintain documentation of the ambient 

 *-. . 1l i               r        *
     -* .     -~---~-.---- ..! _,, --'-;:*.::-~-----~--- --*--------*-----**** --*-:---:*-----..--:-~ -~ ----~~--:-*--* - -..---- --- . *-~-*- *-* .. *- *-**- .---- **, _,______ --**-;- -------- **-- ... - . . . - --*--- *--- =--- .* ***-- - --.-- .*.-

levels of sr~a~ and .sr-90*in_the*air~surrounding tha stations,: . . strontium analyses are performed on.the -.lst quarterly: sarnpl~ from each location as a management* audit . sampl:e. : Strontium::-89 and

  • Sr-90 was not detected in any of the e:l.ghtmorithly composited samples analyzed; LLD sensitivities ranged from <0*~3 x io-3 to
                  <2.0 x lo-3 pCi/m3 and from <0.2 x io-3 to <0.3 x lo-3 pCi/m3 for sr-89 and sr-90 respectively.

Results of gamma spectrometry indicated detectable levels o~ Be-7 in all of the 32 monthly composites, with a maximum of 110 x lo-3 pCi/m3. Berylium-7 is a naturally-occurring radionuclide attributed to cosmic ray activity in the atmosphere. During this reporting period detectable levels of Ru-103, Ru-106, cs-134, Cs-137, Ra-226, and Th-232 were noted in many of the locations sampled. Ruthenium-103 levels ranged from 7.5 x lo-3 to 9.2 x lo-3 pCi/m3. Ruthenium-106 levels ranged from 4.0 x lo-3 to 8.3 x lo-3 pCi/m3. Cesium-134 levels ranged from 8.4 x lo-3 to 10 x lo-~ pCi/m3. Cesium-137 levels ranged from 16 x lo-3 to 18 x lo-3 pCi/m3. In reviewing the data it is noted that Ru-103, Cs-134 and cs-137 levels increased significantly during the second quarter of 1986. The Ru-103; Cs-134 and cs-137 increased levels are not attribut-able to the operation of the Salem or Hope Cr~ek Generating 

    -"    *. i Stations. Based on their respective effluent release reports, there were no releases of Ru-103, Cs-134 or Cs-137 during the second quarter (22,23]. The increased levels are attributable to the Chernobyl-4 reactor accident. since similar concentrations existed at indicator arid control station locations
  • Radium-226 was also detected in one of the samples at a concen-tration of 1.2 x lo-3 pCi/m3, which is within the variations
                 *of the LLD sensitivities for the ~ther samples which.ranged from
                  <0.3 x lo-3 to <10 x lo-3 pCi/m3. Thorium-232 was detected
  • in one of the samples at a concentration of 1.7 x la-3 pCi/m3.
      .. : . ~

This value* is within the variations of the LLD sensitivities for the other samples which ranged from <l.l x l0-3 to <2.7 x lo-3 pCi/m3. Air Iodin&* (Table c-4) 

  .  ;;-:      ~
            .,.,  cartridges for the adsorption of air*iodine were connected in
                 *series after each of the air particulate filters. The adsorption media in these cartridges is triethylenediamine (TEDA) impregnated charcoal.

Iodine-131 was below detectable levels for the first four months of the year until the week of May 5 when radioactive iodine 

             -    originating from the Chernobyl-4 reactor accident was detected.
        ~  ..'

8 ., -.. . :~ . .. , . *-

I Iod.ine-131 was* detected at all locations during the three w.e::k<I.y* sampling periods starting on May 5 I l-986 ~nd. ending on May* '2:.7?, .. 1986. Elevated. levels p.ersisj:ed at. several locations du:ing the

  • last. week. in May and. the . first* week in June. Levels as high as:.
                                      '320 x lo-3 pCi/m3 were detected at two locations.* A value of :610 x io-3 pCi/m3 was measured in one of our management audit samples but was not used in calculating any of our av*ezra:.q-as be¢ause of the short sampling period. During the remainder: Q;f
                                    'the year I-131 levels remained at levels below our LLD. The r.L.O sensitivities ranged from* <7. 7 x io-3 to <40 x io-3 pCi/u3: ..

The :increased I-131 levels are not, attributable to the ope*ra~t::iia11 i; ofi the Salem or Hope Creek Generating Stations. Based om th:eii.r respective effluent release reports, there was no significaint rel~ase of I~l31 during the second quarter [22,23]. All of the 

                                       ~levated I-131 results are attributable to the Chernobyl-4
                                     .teactor accident.
~
                            '  r
                                    ~;    r
                          *   ; !:Pr~cipi tat ion (Tables c-6, C-7) i ::
!iAlthough not required by the technical specifications, pre~:n.jpli-
                                  ,: tation samples were collected at location 2F2 in the town o*!
                                  !Salem. Monthly samples were analyzed for gross alpha, gl'OS/$
                                  *.beta, tritium, and gamma emitters. Gross alpha concentratic~s
were detected in four of the. twelve samples analyzedo The
                                  *results detected were 0.6, Oo9, 1.2 and 1.3 pCi/L. These ?"esults
were within the* variation of the LLD sensitivities for the
                                 ' .remaining samples which ranged from <O. 3 to <l. 7 pCi/L. Beta activity was detected in all twelve monthly samples and ranged from 1.9 to 15 pCi/L, with an average of 5.5 pCi/L. Tritium Nas not detected in any of the twelve samples analyzed; LLD sensi-tivities ranged from <130 to <140 pCi/L.

Gamma analysis was performed on each of the monthly samples except for January, 1986 when there was insufficient precipita~ tion. Detectable levels of I~l31 and cs-137 were found in one sample during May 1986 at a concentration of 7.4 and 4.8 pCi/L 

 - -~..<*
            ..                         respectivelyo The increase in I-131 and Cs=l37 levels was
              -)1'
    -~T:?~~~-*~ :

attributed to the Chernobyl-4 re~ctor accident since simila~

  • , ,* .... levels of iodine and cesium were measured in precipitation
   .* ;:-; .f:                         collected at the Research and Testing Laboratory location 3H3v
        '   ,~
  • I I

located 110 miles away from the Salem and Hope Creek Stations& Otherwise levels of I~l31 and Cs-137 were below detectable I 

                 . I I

levelsQ Levels of other gamma emitters were comparable to levels observed-in previous years. The presence of Be=7 was detected in each 

                 '. ~

sample at concentrations ranging from 35 to 71 pCi/L. Radium-226 

                    ! .               was detected in three samples at a concentration of 7.0~ ~.l and
                    .   '              4.8 pCi/L. These values are within the variations of the LLD sensitivities for the other samples which ranged- from <4.i to
              **j *:

I l 

              'l*1                                                                                             ""
                                                                                                               ~
              .l
   ., .: *1                                                                                                                                                                              **.
 <f:'.t~*~:JT--*-*~-----~------------~~*--*-.----------*- - . ----*;::--*--:~ ~.--*---.---- **:-----*:-* . -----*---.-*-- .. ...,, ------*- *--:**-- - --*.-- ... - .... -- --- . ------- -- ---.

               <13 pCi/L.
  • A slightly detectable leyel of. natural*ly~qccurring
  • K-40 .was dete.cted in one 'sample ,a:-t *a* level df
  • s~t pCi/L du;r.ing* t*he
  • September ~ampling periotj. Hbwever, this .value wa~ ~ith~n the ..

variations of .the LLD sensitivities measured throughqut.the year. Thorium-232 was detected in orte sam~le ~u;ring th~ A~guit ~a~pling

- .. period at a concentration of 7.5 pCi/L. This value is within the variations of the LLD sensitivities for the other samples which ranged from <7.2 to <21 pCi/L~ All other gamma emitters searched for were below the LLD.

Direct Radiation (Tables t-8, c-9) A total of 41 locations were monitored for direct radiation during 1986, including 6 on-site locations, 29 off-site locations within the 10 mile zone, and 6 control locations beyond 10 miles. Monthly and quarterly measurements were made at the 6 on-site stations and at 15 off-site indicator stations~ and 3 control. stations. An additional 14 quarterly measurements were taken at* schools and population centers with 3 additional controls beyond the 10 mile zone in Delaware. Fou*r readings for each TLD at each location were taken in order to obtain a more statistically valid result. The average dose

  • rate for the 15 monthly off-site indicator Ttn*s was 5.8 milli-ra:ds per standard month, and the corresponding averaged control.

dose rate was 6.4.millirads per standard month. The average dose rate for the 29 quarterly off-site indicator TLD's was 5.1 millirads per standard month, and the averaged control rate was 5.6. For these measurements, the rad is considered equivalent to the rem, in accordance with 10CFR20.4. In Figure 2, the average radiation levels are plotted for the 13 year period through 1986. Figure 2A shows the* monthly averages of the off-sit~ indicator stations and the control stations for 1982 through 1986. Ambient radiation levels during 1986 were comparable to those obtained during 1985. I Terrestrial Milk (Tables C~lO, c-11, C-12) Milk samples were collected in accordance with the Salem and Hope Creek Technical Specifications at six local dairy farms. During this reporting period, one dairy operator terminated operations (location 2F4) and, as required by the SGS and HCGS Technical . Specification, a replacement location (lbcation 2F7) was found and added to.the surveillance program. Samples were collected semi-monthly* when cows were on pasture and monthly when cows w e r . ... not on pasture. . . . . . .

  • Each sample was analyzed. for .I:""l31 and gamma emi t.ters. I.n. addi-tion, aithough not* sp.ecif ic~lly required by the SGS and. liCGS Technical* Specifications,*~ne sample from each location was analyzed for:: -Sr..;.89 and Sr-90 in order to maintain the data base developed *in prior years. All sr-89 results were below detect-*

able levels. Strontium-90 results were comparable at indicatar and control locations and averaged 2.1 pCi/L. Following the nuclear accident at the Chernobyl-4 reactor in the Soviet Onion,* iodine-131 levels increased significantly. Esti-mates of the quantity of I-131 released from the Chernobyl-4 

                ..      reactor indicate that as much as 20% of the core inventory of
             '          I-131 could have been discharged (25]. Samples collected during the third week in May and analyzed for I-131 using an ion
                      ' exchange resin method, ranged between 11 and 53 pCi/L with the highest result obtained at the control station location. The elevated levels persisted during June and the first week of July.

The mean of the indicator locations which had detectable levels of I-131 was 10 pCi/L while the mean at the control locations 

  ;'        :           which had detectable concentrations of I-131 was 19 pCi/L.

Levels of I-131 iri milk did not return to normal levels until the 

 ..                     third week of July. All other samples collected during the year
                 *,     indicated no discernible I-131 activity. Figure 3 and 3A shows 11 the average I-131 activity measured during this year compared to results obtained in.previous yearso Table c~10 lists the results and shows that sensitivities ranged from <Ogl to <0.8 pCi/t. ..

Gamma spectrometry showed detectable concentrations of naturally= occurring K-40 in all samples. The annual mean concentration measured at indicator locations averaged 1400 pCi/L, and the annual mean concentration measured at control locations averaged 1400 pCi/L~ Sodium-22 was detected in one sample in May at a concentration of 4.6 pCi/L. The Na-22 LLDs for all stations ranged from <l.O to <6.4 pCi/L. Manganese-54 was detected in only one sample at a l~vel of 2.9 pCi/L. The Mn-54 LLDs for all stations ranged from <0.7 to <4.9 pCi/L. Zinc-65 was detected in only one sample ~t a concentration of 11 pCi/L. Cesium-137 was detected in six samples at levels which ranged from 3.3 to 5.1 pCi/L. Since the cs~l37 LLDs for all stations ranged from 

                        <2.3 to <5.l pCi/L the positive results are not considered as being significant. Levels as high as 14 pCi/L ~ere detected during the preoperational program [2]e Radium~226 was detected in four samples at concentrations comparable to levels observed

.... . during the preopecational program (2]

  • Although not as sensitive as the ion exchange method, I-131 results were also obtained in the gamma scan and .the values *were
          *>.*-*.:      comparable to the results obtained using the anion exchange resin method. Iodine~l31 levels obtained from the gamma scan averaged 20 pCi/L at the indicator locations which had detectable levels and 36 pCi/L at the control locations. All other results searched for were below LLD.

Concentrations of. I-.131 in milk. in* the 2nd .. _quarter* .exceed~d .. the-* values in.Table.3~12~2 of *the SGS and~acGs~TechQical Specifica~

  • tions. These concentrations are not . attributed* to_ the. op~ration.

of the Salem and Hope Creek Generating Stations *... Based up.on their respective effluent release reports, th~re was ~o signifi-cant release of I-131 during the 2nd quarter (22; 23]. Well Water (Tables c-14, C-15, c-16) Although wells in. the vicinity of the Salem and Hope Creek Generating Statiori are not anticipated to be affected by plant operations, water samples were collected monthly from two indi-cator wells and one control well. Each.sample was analyzed for gross alpha, gross beta, tritium, potassium-40 and gamma emitters. Quatterly composites were analyzed for.radiostrontium. Gross ~lpha concentrations from 0.6 to. 2.D pCi/L were de~ected in seven of the.indicator locations, with LLD sensitivities for the other analyses ranging f~om ~0.5 to <3.7 pCi/i. G~o~s beta activity was detected in all of the samples. The mean activity for the iridicator locatio~s wa~ 7.6 pCi/L with a range of 2.0 to ts pCi/L; mean activity for the control location was 7.4 pCi/L with a range of 2.5 to 9.5 pCi/L. PotassiiJ.m-40 in _each monthly

  • sample was-determined by atomic absorption* spectroscopy *. *Mean .

activi~y for the indicator locations was *8.7 pCi/L with a range of 2.7 to 16 pci/L, and mean activity for the control location was 9.4* pCi/L with a range of 7.4 to 17 pCi/L.

  • All tritium results were at LLD levels of <130 to <140 pci/L.. Neither Sr-89 nor sr~90 was dete_cted in any of the samples. The LLD sensi ti v-i ties for Sr-89 ranged from <0.4 to <11 pCi/L, and from <0.3 to
                  <0.6 pCi/L for sr-90.

Gamma spectrometry was performed on each sample. Potassium-40, Ra-226 and Th-232 were the orily gamma emitters detected. 

           *.-j Although not as sensitive-as atomic absorption, K-40 was detected by gamma scan in eight samples at lev*els ranging from 35 to 4 7
                 .pci/L. Radium-226 was detected in seventeen of the twenty four indicator locations and *eleven of the twelve control station
     '***.   **   lbcations at values which rang~d from a low 2.9 pci/L to a *high of 170 pCi/L~ The range of the Ra-226 values were higher than values observed in previous years. We believe that results are
             -,   higher due to a procedural change in which the samples are no
                *longer boiled down to a 100 ml standard geometry. This change results in less radon daughters being removed from the sample.

Since Ra-226 is an alpha emitter, its identificatioh by gamma 

                 -isotopic analysis is obtained by counting the Pb-214 gamma rays
'    ..      .~   from the daughter products. We believe that values currently being observed* are indicative of the concentrations which have
                . always existed. Concentrations of Th-232 were d~tected in two
  • ,.* indicator station samples a*t B. 4 and* 10 pCi/L*; *LLD values for the other thirty f_our samples. ranged. from <4. 6 *to <10 pCi/L.

12 -* + *:;::**,; 

  ;-*. * *:-l

Potable Water. (Tables C"'."'17,

  • C-18, c-19)

Both raw and treat~d water samples were collected from the Salem water treatrnenb.plant. Each consisted. of daily aliquots composited into a monthly sample. The* raw water source for this plant is Laurel Lake and adjacent wells. Each sample was analyzed for gross alpha, gross beta, K-40, tr.itium, and gamma emitters. Quarterly composites of raw and treated water were analyzed for sr-89, sr-90. Detectable alpha activity was noted in eleven water samples at concentrations ranging from 0.5 to 1.5 pCi/L; LLD sensitivities ranged from <0.5 to <2.4 pCi/L (raw), and from <0.5 to <l.9 pCi/L (treated). Beta activity was observed in all of the 24 monthly samples witp ranges of 2.0 to 13 pCi/L (raw), and 1.7 to 8.2 (treated), and averages of 3.6 pCi/L (raw) and 3.6 pCi/L (treated). Potassium-40 concentrations for raw and treated samples *were similar but lower than the gross beta activity in all cases. The K-40 average for the raw and treated samples was 1.6 and 2.0 pCi/L respectively. Tritium activity was observed in one of the twenty-four samples at a concentration of 150 pCi/L. strontium-89 was detected in one of the eight quarterly composite

  • water samples at a concentration of 0.8 pCi/L; LLD sensitivities ranged from <0.5 to <l.6 pCi/L for Sr-89. Strontium-90 was not detected in any of the water samples and the LLDs ranged from
                              <0.4 to <l.O pCi/L for Sr-90. Gamma spectrometry detected Ru-103 in one sample at 2.6 pCi/L; Ra-226 in three samples at concentra~

tions ranging from 2.6 to 8.4 pCi/L; and Th-232 in three samples at concentrations ranging from 5.7 to 6.8 pCi/L. The LLDs ranged from <0.5 to <5.6 pCi/L for Ru-103; .from <3.7 to <5.8 pCi/L for Ra-226 and from <4.9 to <9.6 for Th-232. Food Products (Table C-20) Although vegetables in the region are not irrigated with water in which liquid plant effluents have been discharged, a variety of food products grown in the area for human consumption were sampled. These included sweet corn, peppers, asparagus, cabbage, and tomatoes * 

 .1 All samples contained naturally occurring K-40 at concentrations from 910 to 3400 pCi/kg~wet, with an average for all samples of 2100 pCi/kg-wet. Berylium-7 was detected in one sample at a concentration of 24 pCi/kg=wet. Iodine-131 was detected in one indicator location and one control location at levels of 33 and 62 pCi/kg-wet for samples.collected during May. The increased I-131 levels are not attributable to the operation of the Salem or Hope Creek Generating StationsG Based on their respective f:'

13 . - -~ 

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

      .*.*   ~

effluent releasereports;\:here were no significant release of I-131 during the second quarter [22,23] ... All of ~h~ elevated: I-131 results are attributable to the Chernobyl-4 reactor* accident. A trace of Cs-137 was detected in tomatoes from two control stations ~t 1.5 and 2.1 pCi/kg-wet. Since the LLD sensitivities ranged from <l.6 to <24 pCi/kg-wet, the detectable levels of Cs-137.are not considered as being significant. Concentrations of Ra-226 were detected in three samples ranging from 8.3 to 68 pCi/kg-wet. The two highest concentrations measured occurred at two different control locations at concentrations which were comparable. to *the LLD-values. The LLD values ranged from <1.8 to 

                                       <51 pCi/kg-wet. Thorium-232 was detected i~ one tomato sample at a concentration of s.s*pci/kg-wet~ The LLDs ranged from <5.5 to <110 pCi/kg-wet for a variety of food products collected during the reporting period.

Game (Table C-21) Since muskrats inhabit the marsh lands surrounding the-~ite, and since muskiatsare consumed by local inhabitants,*two muskrat

  • samples were collected and analyzed for gamma emitters. Gamma scans of the. flesh indicated the presence of naturally-occurring K~40 in both. samples at concentrations of 2200 and 2400
        .. i pCi/kg-wet
  • Beef (Table C-21)

Although not required by the SGS or HCGS Technical Specifica-tions, beef sampies are collected, when* available, twice a year. The second semi-annual beef sample was not obtained. Farmers from 

                                      .whose animals the samples are normally obtained did* not slaughter
                                     *from July through December 1986 *.

Analysis of the flesh for gamma emitters indicated the presence of naturally-occurring K-40 at concentrations of 2500 pCi/kg-wet, * .. *.. *: . and Cs-137 at 7.3 pCi/kg-wet

  • Fodder Crops *(Table C-22)
                                     *Samples of *crops normally used as cattle feed were collected at nine locations where these products may be a significant element in the food-chain pathway. Six of the locations are or ~ere mil sampling stations*.
  • Samples collected .for *wet, gamma an*alysis

., .. *-J included barley, feed corn, corn silage and soybeans. - 14

Potassium=40. was detected in all of. the nine samples* at con*cen~ trations. ranging from 2300 to. 15000 pCi/kg-wet, wi_th an average:* af 7000 pCi/kg-wet. Berylium-7, from the atmosphere, was found .. in five of the samples at concentrations. ranging from 37D to 1400 pCi/kg-wet. Cesium-137 was detected in one of our control loca-tions at a concentration of 13 pCi/kg-wet. The LLDs for Cs-137 ranged from <17 to <54 pCi/kg=wet. Radium-226 and Th~232 wer::e detected in two different samples at a concentrations of 35 and 170 pCi/kg-wet. The LLDs for the Ra-226 ranged from <36 tQ <lGO pCi/kg-wet while the LLDs for Th-232 ranged from <59 to <l3U pCi/kg-wet.

  • Soil (Table C-23)

Soil is sampled every three years at 16 locations, including two controls, and analyzed for Sr-90 and gamma emitters. Sanples are collected at each station in areas that have been relatively undisturbed since the last collection in order to determine any change in the radionuclide inventory of the area. The concentrations of sr-90 for the indicator stations ranged from 27 to 140 pCi/kg-dry with an average. of 91 pCi/kg~dry... The two control stations yielded results of 56 and 130 pCi/kq~dry with an average of 93 pCi/kg. Since the purpose of these samples is to determine if the operation of the nuclear stations is resulting in an increase in the inventory of long lived reactor produced radionuclides in the environment, the values obtained were compared to data reported in previous years. Averages for the indicator stations were 220 pCi/kg in 1977, 149 pCi/k~ in 1980, and 125 pCi/kg in 1983. Averages for the control stations were 430 pCi/kg in 1977, 195 pCi/kg, and 93 pCi/kg in 1983. The gradual decrease is perhaps attributable to the wash~out and decay of weapons testing fall-out from the l950's to the 1960 9 s. Gamma spectrometry of these samples showed detectable concentra-tions of the naturally occurring radionuclides (K~40, Ra-226, and_ Th-232) and the fission product Nb-95 and cs~l37. The Nb-95 concentrations found ranged from 34 to 63 pCi/kg with an ave~aqe of 48 pCi/kg. These results are comparable to measurements obtained during the preoperational studies in which levels* of Nb-95 of 90 pCi/kg were observed [2]. The cs-137 at the indicator stations ranged from 78 to 1500 pCi/kg with an average 

 . - -:~

of 393 pCi/kg. The two control stations were 210 and 690 pCi/kg 

        .. with an average of 450 pCi/kg. Averages for the indicator stations were 710 pCi/kg in 1977f 445 pCi/kg in 1980 and 440
. _]
   -.. !   pCi/kg in 1983. Averages for the control stations were 620 pCi/kg in 1977, 650 pCi/kg in 1980 and 615 pCi/kg in 1983.
      .,l
 .. '
  • 0

~  : .. i 

              - Aquatic surface Water   ( Tabies
  • c-24, c-25., c-26, C-27 ).

Surface water samples were collected morithly at five locations in the Delaware estuary. One location is at the outfall area, another is downstream from *the outfall area, and another is directly west of the outfall area at the mouth of the Appoquini-mink River. Two upstream locations are in the Delaware River and at the mouth of the Chesapeake and Delaware Canal, the latter being sampled when the flow is* from the Canal into the river. Station 12Cl, at the mouth of the Appoquinimink River, serves as the operational-control. All surface water samples were analyzed monthly for gross alpha and gross beta emitters, and gamma emitters. Quarterly composites were analyzed for tritium. Alpha concentrations were detected in 19 of the 48 indicator samples and in four of the twelve control samples, with concen-trations for all samples. ranging from 0. 7 to 12 pCi/L; LLD sensitivities which ranged from <0.6 to <4.7 pCi/L. Beta con-centrations for the indicator stations ranged from 2.4 to 130 pCi/L with an average of 51 pCi/L, and for the control statioti, 

      '         from 7.5 to 81 pCi/L with an average of 45-pCi/L. *Nearly all of
     "*         the beta activity* was contributed by K-40, a natural component *

->'. *j::;*. 

              *of salt and brackish waters, as illustrated in Figure 4, which compares averaged gross beta and K-40 concentrations.

Tritium ~onceritrations for the indicate~ statio~s ranged from 130 to 270 pCi/L. The average of the eight indicator samples with detectable *1.evels of tritium was 160 pCi/L. Tritium was detected in one of the four control samples at 150 pCi/L. Levels for the years 1973 through 1986 are plotted in Figure 5. Gamma spectrometric analysis of surface. water samples -showed detectable concentrations of K-40 in 34 of the 48 samples. The average K-40 concentration at the indicator stations was 88 

         --{

pCi/L, .with a range of 33 to 160 pCi/L. Average K~4o concentra-tio~ at the control station, where detectable concentrations 

             *_were found in nine of the twelve samples, was 70 pCi/L with a range of 29 to 95 pCi/L. Radium-226 was detected in seven indicator station samples, with the*values ranging from 2.6 to 11 pCi/L, and one control station sample at 25 pCi/L. Radium-226 concentrations in this year's samples were higher than in      _

j *_previous years due to procedural change in which water samples 

           '    are no longer boiled down to a 100 ml standard geometry. This change results in less radon daughters being removed from the sample. Since Ra-226 is an alpha emitter, its identification by gamma isotopic.analysis is obtained by counting the Pb-214 daughter product. .concentrations of Th-232 in five indicator station samples were detected rangingfrom 5.3 to 9.3 pCi/L and one control sample at 9 .2 pCi/L.. LLD sensitivities for Th-232 ranged from <5.3 to <9.3 pCi/L.

16

Fish (Tables c~28, C~29) Edible species of *fish were collected semi-annually at thre.e locations and analyzed .for tritium and gamma .emitters (flesh~ and for sr-89 and sr-90 (bones). . Samples included channel catfis.hi, summer flounder, weakfish and bluefish. Gamma spectrometry of these samples indicated K-40 in all s.i~ samples at an average concentration of 3000 pCi/kg-wet with a range of 2700. to 3300 pCi/kg-wet. One of the six samples had detectable concentrations of Cs-137 with a value of 8.3 pCi/kg-wet. The LLD sensitivity for the other five samples 

               .~

ranged from <12 to <19 pCi/kg~wet. Radium-226 was detected in the second semi-annual sample at two locations, at concentrations of 33 and 41 pCi/kg-wet. Levels as high as 130 pCi/kg-wet ~ere observed during the preoperational period [2]. Thorium-232 WJas detected in the ~irst semi-annual sample from the control station at a concentration of 29 pCi/kg~wet. LLD sensitivities for Th~232 ranged from <31 to <61 pCi/kg-wet. s~rontium-89 was detected in one of the six bone samples, with a concentration of 330 pCi/kg-dry. The LLD sensitivities for the other six samples ranged from <40 to <75 pCi/kg-dry. Two of the four semi-annual indicator samples analyzed for sr-90 had detect-able concentrations of 34 and 240 pCi/kg~dcyf with an average of 137 pCi/kg~dry. The level seen at the control location fo~ the sample collected during the period from May 12 to May l~, 1986 was 1500 pCi/kg-dry. ~ review of station effluent release records does not indicate any significant quantity of Sr-89 or sr-90 being discharged during the first half of the year [231. Tritium analyses were performed on the aqueous fraction of the flesh portions* of these samples. None of the samples analyzed indicated any detectable concentrations of tritium. Blue Crab (Table C-30) 

.   *. *, . : .~

Blue crab samples were collected semi~annually at two locations, and the edible portions were analyzed for gamma emitters, sr-89 

   ..          -~-

and.Sr~90, and tritium in the aqueous fraction. 

     ***.        )

_- .. The shells were also analyzed for Sr=89 and Sr-900 

     -*.'-~

Potassium-40 was detected in the flesh portion of all four samples. Potassium-40 levels ranged from 1700 to 2000 pCi/kg=wet with an average of 1800 pCi/kg-wet. Radium-226 was detected in two samples from the control location at concentrations of 19 and 20 pCi/kg-wet~ Strontium-89 was not detected in any of the four flesh samples; LLD sensitivities rariged from <28 to <46 pCi/kg-wet. One shell sample from the f i.rst semi-annual set had detectable levels of Sr-89 at 300 pCi/kg~dry; and LLD sensitivities ranging from <67 to <89 pCi/kg-dry. ~imiliar concentrations were observed during the preoperational program [2]. 17 

         *.*.j
               *1
  • ' --* 1
J, -~-~--:---**------:------- ~----*-~*---- -;--*.----:--~-**-:*-:--*- *- -----... -------------* **--. -~*-* *.*----*** ----:- - -**-** ---*- ---------,, -*- .... *--.--- .-* - - - -- *.-.-**- - -- *- . --- -** . -*
  • Strontium-90 was not . detected in any of the edible flesh portion$*'-*

of the blue crab samples. The*LLD.sensitiviti9s.:for these samples ranged from <18 to <24 pCi/kg~wet for *Sr-90. All four shell samples had detectable concentrations of.Sr-90 ranging from 150 to 490 pCi/kg-dry with an average of 340 pCi/kg-dry. - Tritium activity was not detected in the aqueous fraction of any of the edible flesh portion of the four blue crab samples collected. The LLD sensitivity achieved, in all cases was <50 pCi/kg-wet. Benthic Organisms and Sediment . (Tables c-31, C-32) Benthic organisms were separated from the bottom sediment and analyzed for gamma emitters. All gamma emitters searched for 

                                    *were <LLD sensitivities. It should be noted ~hat, due to the very small sample sizes for all samples, satisfactory gamma sensitivities could not be achieved.

Sediment samples of sufficient size were availabla to enable sensitivity requirements for both Sr-90 and gamma emitters to be 

                         ~~ I met. Levels of Sr-90 were* below LLD (<19 to <38 pCi/kg-dry)
' ~~-~'.:. *in all twelve samples. analyzed. Results of gamma spectrometry
  • indicated the presence o~ naturally-occurring K-40, Ra-226, and
               ".                     Th-232 in all twelve samples with averages of 10000, 620, and 740 pCi/kg-dry res'pectively. Concentrations of the .gamma emitters, i

i Mn-54, co-58, co-60, cs-134 and Cs-137 were also detetted. 

                                     *Manganese-54 was detected in three. samples at an average concen-tration of 26 pCi/kg-dry with LLDs ranging from. <18 to <38 pCi/kg-dry. Concentrations of Co-58 were detected in four samples ranging from 31 to 80 pCi/kg-dry, with the average being 57 pCi/kg-dry. Cobalt-58 LLD sensitivities for the remaining four samples ranged from <23 to <38 pCi/kg-dry. .concentrations
                                    *Of co-60 were detected in eight samples *ranging from 37 to 110 pCi/kg-dry, with the average being 72 pCi/kg-dry. Cobalt-60 LLD

.. ' . ~- ' sensitivities for .the remaining four samples ranged from <36 to 

                                      <48 pCi/kg-dry. Cesium-134 concentrations were detected. in four*

samples at levels ranging from 46 to .82 pCi/kg-dry, with LLDs ranging from <16 to <3~ pCi/kg-dry. _Cesium-137 concentrations in four samples ranged from 49* to 82 pCi/kg-dry: LLD sensitiv-ities ranged from <16 to <39 pCi/kg-dry. 

          *.._\
         . I
         . I
       . 1
           *.5
          .-i
        ~   .* i
    . : .i ~~{                                                          lS*
.:.j

PROGRAM DEVIATIONS Air particulate/iodine sampler location 252 for the week be,gim~ *.. > ning January 13, was operational for only 1.2 days out of a 7.d~Y. sampling week due to an instrument malfunction. Direct radiation measurement results from location 6Fl for Mai~~h are unavailable: TLDs were missing from the field location. Air particulate/iodine sampler location 5Dl for the week be~im ning May 12, was operational for only 2ol days out of a 1 da..y sampling week due to an_ instrument malfunction. Air particulate/iodine sampler location 16El for the week begin-ning May 27, was operational for only 0.6 days out of a 1 da~ sampling week due to ari instrument malfunctiono Iodine-131 results from location 3H3 for the week beginnin9 June 2, are unavailable due to a faulty sampling assemblye Milk gamma results from location 3Gl for the September 22-23~ sample are unavailable due to loss of sample during prepara.tian .. Air particulate/iodine. sampler location. 252 for the week begia-ning November 24, was operational for only Oo2 days out of a 1. day sampling week due to an instrument malfunctiono Air particulate/iodine sampler location 3H3 for the week begin= ning December l, was operational for only 2.0 days out of a 7! day sampling week due to an instrument malfunction. Air particulate/iodine sampler location SDl for the week begin-ning December 15, was operational for only 0.3 days out of a 7 day sampling week due to an instrument malfunction. 

  .,        .1 CONCLUSIONS The Radiological Environmental Monitoring Program for Artificial
      ' j
     -.      ;                                   Island was conducted during 1986 in accordance with the SGS and HCGS Technical Specifications. The objectives of the program
.j were met during this periodc The data collected assists in demonstrating that SGS Units One and Two and HCGS were operated in compliance with Technical Specifications.

J The ability of the program to detect radionuclides released from 

                                            *. the accident at the Chernobyl-4 reactor, has demonstrated tbat the program being conducted is effective in sensing small.

increases in radiation levels. It is evident that air, milk, water, food products and soil surrounding the Chernobyl power reactor complex were seriously contaminated as a result of the

  • 0 19
               ;---~--***-*-- ** *.--*- **-:**-* **.,.--*,.--*- -*-*: ~, *-.-*--* -*.,*---*~--****--* *~ .. ,.,..* ,** 7""-;*-;-:-"T:--*o *, .-----*,.- -.--.**** ._ __ , *-*-

accident *.. However~ radiation levels measured.in the United* States due.*to the accident were not affected in*terms of public, health and safety. Ambient radiation le~els as measured .in our program were relatively low, averaging 5.1.mrad/std. month. Although ambient radiation levels remained normal, our surveil-* lance programs were sufficiently sensitive to detect radio-nuclides in the environment which were discharged from the damaged Chernobyl~4 reactor. The concentrations measured and provided in this report although higher than normal were not excessive. In fact, with the exception of I-131 in milk, none of the concentration found exceeded the reporting levels estab-lish~d by the USNRC. The reporting levels establlshed in the Technical Specifications applies only to abnormal environmental measurements caused by the licensed power reactor. None of the I-131 detected in milk was due to the o*peration of the Salem or Hope Creek reactors. The operation of SGS Units One and Two and HCGS had no significant effect on the radiological character-istics of the environs of Artificial Island. 

                                            *~'
     . . ~ .:

20

. -~ ~ .~
  . -- :~:::~~-r:=---~*~*-~-v:--_-:-.:*-;:~:;;.::-*-::--::-~-~,---.-.*.----:--:*--.-~-.-~--~*-:*--:-.-:-.::_--:- ...--_-_--......... -.-.. --~....-~----.--~-~,.---:-*- *-- ------.... --::-*-:--.--* .. -,..-.:;*-::.---~ -7**-*-~--<' ;:-

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

l i 

   *1
 .1 I

TABLE l 1986 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM S!A'.l!IOll CODE COLLECTION MED!Uli INDICATOR CONTROL FREQUENCY TYPE/FREQUENCY* OF ANALYSIS I. ATMOSPHERIC ENVIRONMENT

a. Air Particulate 2S2 501 l6El lFl 3H3 Weekly Gross alpha/weekly 5Sl lODl 2F2 Gross beta/weekly Sr-89 & Sr-90/first quarterly**

Gamma scan/quarterly

b. Air Iodine 2S2 SDl 16El lFl 3H3 Weekly Iodine-131/weekly
            !\'\)                                  5Sl                  1001          2F2 Ii--'
    *i
 *.*1             c. Precipitation                                          2F2                                    ll!onthly  Gross alpha/monthly Gross beta/monthly Tritium/monthly 1                                                                                                                        Gamma scan/monthly i
u. DIRECT RADIATION
a. Thermoluminescent 2S2 501 2El lFl 3Gl :nu Monthly & Gamma dose/monthly Dosimeters 5Sl lODl 3El  :?F2 3H3 Quarterly Gamma dose/quarterly 5S2 HDl 13El 2F6 7Sl 16El 5Fl lOSl 6Fl HS]. 7F2 llFl 13F4 I I
                                                  ... .- .. _ *-*~- **-*-.  ..            .
                                                                                  ~           .

l 

          ..:i
                 ;                                                                                                   TABLE 1 (cont'd)
          .*,\

J .i 1986 ARTIFICIAL. ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 

          *1
            *I
    ..:]                                     MEDIUM ST!T!QH INDICATOR CODE CONTROL COLLECTION
                                                                                                                                     ¥R~QUENCY           TYPE/FREQUENCY* OF ANALYSIS
      .      ~:1
                                                                                                                                   .~:*  .
                                                                                                                                  .~:; :::*--~.
             . J j
 .* . <1                             ~-   Thermoluminescent                                 4D2     ~El   2F5          1G3     . :, Qii_arterly      Gamma dose/quarterly
     .. ]                                  Dosimeters (cont'd)                                           11E2   3F2   lOGl
                 .J                                                                               .12El 3F3           16.Gl
i 10F2
             .l    iI 12Fl
             'I 13F2 I                                                                                    13F3 I
              *'I                                                                                        14F2
      . .I
      . :1                                                                                               15F3
                 ..~
              *.1 j
                              ~

16F2 

            ;!                l\)
              .i.
1. III. TERRESTRIAL ENVIRONMENT
a. Hilk 13E3 2F4 3Gl Monthly Iodine-131/monthly 2F7*** (animals not Gamma scan/monthly
                                                                                                        ~F2                              on pasture) 11F3                            Semi-monthly   Iodine-131/semi-monthly 14Fl                            (animals on    Gamma scan/semi-monthly on pasture) Sr-89 & Sr-90/July, first
  • collection** .
b. Well Water 2s3 5Dl 3El Monthly Gross alpha/m~ntnly Gr-.oss peta/monthly Potassium-40/monthly Tritium/monthly Gamma scan/monthly Sr--89 & Sr--90/quar-ter-ly
                                  -*~ *. .'.. *,..;_...;_.. __ _

TABLE ]. (cont'd) 1986 ARTU'ICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM S'.£~'.l!IQH CODE COLLECTION HEDIUH INDICATOR CONTROL FREQUENCY TYPE/FREQUENCY* OF ANALYSIS Cc Potable Water 2F3 Monthly Gross alpha/monthly (Raw & 'Treated) <<composited Gross beta/monthly daily) Potassium-40/monthly Tritium/monthly Gamma scan/monthly Sr-89 & Sr-90/quarterly 

               ~. Yegetables                                      2El    1F3               lGl 3H5     Annually     Gamma scan/on collection
        !l\'ll                                                    3EJ\. 4Fl               2Gl         (at harvest)
        ~                                                                5Fl 14F3
               @. Game                                               4Cl                    U.Dl       Semi-        Gamma scan/9n collection

'j (Muskrat) annually

f. !Beef 3El Semi- Gamma scan/on collection annually 9* Fodder crops 3El 2F7 3Gl Annually Gamma scan/on collection l3E31 5F2 11F3 14Fl

I- 

                              .'i
                        ............ *- .. - ... - ,._. -~-- ---*--.

I 

  .-<1 l

j i 

     .j TABLE 1 (col)t'd) i I

i 1986 ~RTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM _-:1

  • .:.1
  .I                                                                                                        COLLECTION
STATION CODE
 .. 1
                       . MEDIUM                                          INDICATOR            CONTROL       FREQUENCY          TYPE/FREQUENCY* OF ANALYSIS J  I h *. Soil                                            6Sl  5Dl 2El     lFl     3Gl 3H3       Collected       Sr-90/on collection
.. .. j lODl 16El    2Fl                   from each       Gamma scan/on collection
I
     \I                                                                               2F2                   location 2F4                   once every I

1 2F7 *.* liiree years. I ~~:-* . 5Fl

1 5F2
J1 11F3
 *. 'I l                                                                            14Fl I

l\) I

l. IV. AQUATIC ENVIRONMENT.
        .l
     ;[         a *. surface Water                                     llAl 7El   1F2          l2Cl         Monthly         Gr_oss alpha/monthly
    **1                                                                          16Fl.                                      Gross beta/monthly
      *j Gamma scan/monthly
       *1                                                                                                                   Tritium/quarterly i
        ~
      *1 l
b. Edible Fish llAl 7El_ 12Cl Semi- Tritium (flesh) annually. Aqueous fraction/on collection Sr~89 & Sr-90 (bones)/on ~ollection
     *1                                                                                                                     Gamma scan (flesh)/on collection J
      .~

1

c. Blue Crabs llAl 12Cl Semi- Ttitium (flesh)/on collection 1

I annually Sr-89 & Sr-90 (shell)/on collection Sr-89 & Sr-90 (flesh)/on collection I! Gamma scan (flesh)/on collection I I

TABLE l (cont 0 d) 1986 ARTIFICIAL ISLAND RADIOLOGICA~ ENVIRONMENTAL MONITORING PROGRAM si~irnu CODE COLLECTION HEDIUH INDICATOR COlilTROL FREQUENCY TYPE/FREQUENCY* OF ANALYSIS dl. Benthic Organisms llAl '1El 16Fl 12Cl Semi- Gamma scan/on collection annually

e. Sediment :UAl '1'El l6Fl 12Cl Semi- sr~9o/on collection 15Al annually Gamma scan/on collection l6Al

~ l* Q Except for TLDs. the quarterly analysis is performed on a composite of individual samples collected during the quarter. 

    &c  Management audit analyses, not required by Technical Specifications or by specific commitments to local officials.
  &cc   Station 2F7 replaced station 2F4 (terminated milk production) on September 1 0 1986.

I 

               .. l FIGURE 1 COMPARISON OF AVERAGE CONCENTRATIONS OF BETA EMITTERS IN PRECIPITATION ANO AIR PARTICULATES 1973 THROUGH 1986 LE GENO 500                                                                                                                                                                                               AIR 1E-3 pC1/mHH3 e                        o RAIN pCi/L
                                                                                                                                                                                                             +------+

I I I I I 

          ' 100                                                                          . + ... L ., ******************* * ***

I I I I I I t I I I 

                                                                                                            +

50 ,*. *\. : * ** 1, ********************* 

                                                 "it,                         11 I I I I I I I I I

I 

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                                                      +                            11              11           I I

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                                                                                                                +\

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                                                                                                                    \                                               \
t I

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                                          **********'****I***

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nu I .... \ I ', I~; ~ . ~ iii j!! + \I I v i~! I -~ID l m sa c1i ,.. 1~:1-+--t--ti-+--t-ti-+-+-t-++-tl-+--t-11-+--t-11-+--+-11-+-+-t-+-+-1-+-+-1-+-+-+-+-+-+-+-+-+-+-+-+-+-+--+--4-+-+-l-+-+-l-+-~~ 

                                                                                                                                                                                                                        +

l 1234123412341234123412341234 4123412341234123412341234 

                ~973           1974 1975 i976 1977 1978                                                            ~979            i                 1981 1982                       t983            ~ss4               1985 1986

I 

     ,
  • l- . . -...... *', ,.,.,. . . . . . . . L. *" " * * * "* ...... " ***

FIGURE iA COMPAAISION OF AVERAGE CONCENTRATIONS OF BETA EMITTERS IN PAECIPITATION AND IN AIR PARTICULATES ftOOo--~~~~~~~~~~~~~~~~~~~~~~~~~~~~~._.~~~~~~~-. 1983 THROUGH 1986 LEGEND 500 AXA 1E-3 pCi/mNM3 e e RAIN pC:l/L 

                                                                                                                                                                                                                            +-- - - - -+

i. 100 0 0 oOOO 0.0 0 0 00 0 00 0 O o o 0 0 o 0 0 o 00 0 o o O o oO o o 00 o o O O O o o o oO o o o Oo 00 O O O o 0 0 0 oo oo o O o o o o o o o o o o o o o o o o o o o o o o o o o o o o o o o o o o 0 o o o oo o o o o o o o o oo 0 0 0 0 0 50 ***************************************************************************..******.***** '** ******* *.*. 10 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . y. . . .,. . . . . . . + 8\ t 5 ******************~****************************** ..................../1. ....................... .!. .\.,/.\ t 

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                                             '8
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                                                                                                                                                                                                                                    -4 i .{. \         \

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                                        \ 6            -\-*      8 I I                     \        '+            ~     I \ /                                    I                f' ,+-        \         O                      iii
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I 1JfMAMJJASDNDJFMAMJJASONDJFMAMJJASONDJrMAMJJA5PNP 

       ~se3                                                           488"4                                                          ~~~!!!                                                         tsee

FIGURE 2 AVERAGE AMBIENT RADIATION LEVELS FROM QUARTERLY TLDS IN THE VICINITY OF ARTIFICIAL ISLAND 1973 THROUGH 1986 LEGEND ALL STATIONS s--~~~~~~~~~~~~~~~~~~~~~~~~~~~~~-o o 9. CONTROL STATIONS 

                                                                                                               ..... - - - - -+
    *1
 -.: 1 1

II L: 

                       ~   1--~~~~~~~~~-,--~~~~~~~~~~~~~~~~~~~~~~~~~~~                                                             7
    *1 i               c

.J 0 

     ;;                E n   6-+-~-,--~~~~.--~~~~~~~~~---t-H~r-~-t+~~~~--1r--1----,,r-"'<rtr.-.-r_._~,.----t--+-6
                       ~

IO 

                      'E Ill
                       ~   5-1-~--r'---t-it-t-~"T-;,--"'"'"t--rlR--W----W~----t>t-it't-~~-R-~t--~f-\+t-~---~~~~~---it--~-r-,t---'r 5 E
*. i
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4 3 3 . i

2 2 112341234123412341234123412341234123412341234123412341234
                             ~973  tS74    !9715 :f.978 1977 1978 1979 1 . 1 9 8 1 1982 1983 1984                      19BB 1988

FIGURE 2A 

                    ~OMPAA,SON OF AMBIENT RADIATION LEVELS OF OFF-SITE INDICATOR STATIONS VS. CONTROL STATIONS 1982 THROUGH 1986 iO--~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~--~~~~~~~~.-
   .c
   .µ c

0 E n 

   ..,i II)
   'U)

E I> L E I I : 

                                                                    ---4 2

JFMAMJJASONDJFMAMJJASONDJFMAMJJASONDJFMAMJJASDNOJFMAMJJASOHD-irse ~~~~ 1sa~ ssas i~a6 ' 1 I 

                                       ..' ' !j ' .*.c,*          ... '  .      -- .- -
  • r*)
                                   ....~.-.* \ . '*~-*.                                                                     ..         ___ ....,.. .. - .. --* - ... -.. -
                                                                                                                     . -. _ . *r ."-'-"""-';._.,__c"'*'---;-.,_,..__
                                                                                                                                          ~~--
                                                                                                                                                                -~  ~      . -- . . . -
                                                ,)
--~ ~ ........ .
 . *n I!
      ... 1 j

I 1 

        *I l'

l FIGURI: 3 l I AVERAGE CONCENTRATIONS OF IODINE-131 IN MILK I IN THE VICINITY OF ARTIFICIAL ISLAND 

     **1                                                                                                       1974 THROUGH 1986
     /1                            30
        . *~
 'j                                28                                                                                                                                                                                                28
     *:j                       . ' 26                                                                                                                                                                                                26
  *..i
   .*.1
         *j                        24                                                                                                                                                                                                24 1
        .{                         22                                                                                                                                                                                                22 l                       20              ................................ , ...................................................................
                                                                                                                          '                                          .                             ***********************           20 .
  • 1 l 18 r::
                                                                     ~

18 

  .. ~1                   _J       16 g---

H 16 .* **1 'u 

                          ..-1 1<1.

i~ 

          ~                a.      14                                                                                                                                                                                                14
  .. i
       *1                          12                                                                                                                                                                                                12
   *\. 1*: ,,;
                    .              10              ............................ ****************************** ~-***********-************************** ......... ~.1!...... .                                                       10
        .~}

I m m m m ~ i m ~ ~~ a i~ ~~ ~~~~  !~~IP ~ I. 8 

      . i t*

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                                                                                                                                                                                                                        \
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         *I 4
                                                                                                                                                                                                                    \ \

4 2 

        .,1 O~'f-.111-.lfl-il-'t'-""f&-'!l-lf'~~~-i-ll~olfL-~-t-J~ut'-~ll-'t'-""f&-'f--l+l....~ut'-.lflo-ll~~~-'P-'~~.~~Jtl-l~~!F-4~~
  ,*,*!                                    l 123412341234 1234 1234123412                                                                         . 2 3 4 12 3 4 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 '

0 f97~ ~9715 is7~ ili77 . 1978 197$ f.S~n ~ i982 i983 ~StM £fiHU5 1988

FIGURE 3A AVERAGE CONCENTRATIONS OF IODINE-131 IN MILK 

  'j,                                                                             IN THE VICINITY OF ARTIFICIAL ISLAND I

1983 THROUGH 1986 30 --~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~30 28 28 26 . 26 24 24 22 22 20 *****. .*. . . . . . . . . . . . . .. * ............ .. ...... .. . . . . .* . . . .. . . . . . . . . . . . *. . . . . . . . . . . . . . . .. . . . ... . . . . . .. . .. .. . . . . . . . . . . . . . .. . . .. 20 iB 18 

      <<:ill l!-.il  ....! 16                                                                                                                                                                                                                              16
             'u
              .-II I

a i4 14 

   !                12                                                                                                                                                                                                                              12

. I i

11) .... ...... .. ... ..... .. ...... . .. ..... ....... ... .. . . .. . ... . .. ........ ... ... . .. . . . . .. . . . .. . .. . . . . ...... . . . ... E............ . "' 10 B
                                                                                           .                                                                                                       l8 IO e

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                                                                                                                                                                                                    ~               iii a:

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     '.'I                                                                                                                           *FIGURE 4                                   --*-. ***
  • i AVERAGE CONCENTRATIONS OF BETA EMITTl::RS --&*- K-40 IN
   .j 1

i THE DEL. RIVER IN THE VICINITY OF ARTIFICIAL ISL. I 1973 THROUGH 1986 I 

.* .1 I

LEGEND _*j "I 500 GROSS BETA

I e o
   .;I                                                                                                                                                                            POTASSIUM-40 I                                                                                                                                                                          +----- . :.1;
~
    .,I i

100 50 _J 

            'u rl a.

10 ........... ****************** ..................................................................................... . 5 ...,........................ -~ ................. **********~ ................................ ****************fl*** 

                                                   ~                                                      mi              m ~        ~                     i~                                    iei
                                                   ~~
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                                                                                                                          *a ;a S 1--.to-fo-'"*-4__+-t_ _~_ _+-+__t-+_ _t--+--+-ii-+--f-l~-t-1--+-1--+-+-+-t-t--t-t--+--+-ll--+--+-il--+--+--tf-+--t-l-i-+-1--+-+~
                          ! 12341234123412341234123412341234123412341234123412341234 i'

i;! If Q.. 11lo1 497$ 1974 t975 ~978 1977 1978 i97B 1 1981 1982 1983 ~Be4 ~988 1988 1, 

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

FIGURE "4A AVERABE CONCENTAATXONS OF BETA EMXTTERS Q K-40 XN THE DEL. RIVER IN THE VICINITY OF ARTIFICIAL ISL. 1983 THROUGH 1986 LEGEND 500 GROSS BETA e e PIJTASSXUM-40 

                                                                                                                             +------+

soo 

  ~       50 i ~  _J
                                                                                                                                                      +
    'ua.

rl I

  • i

.j iO ,........................... '....................... .. ..... ........ *,* .... . I 

                                                                    \I 5     ............................................ ~ ........ ................................................ *-;..;*** ~-............... .

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                                                                                                        .. PIGURE B                                         .

.* ****_1 AVERAGE .. CO~f;f:~TRATIONE; . Qf_ ..'!"~ITIUM IN THE ... -1* 

  . . *1                                                DELAWARE . RIVER IN THE. VICJ:NITY-                           .         .  **oF*-:;ART:.I.F:CCl:AL                     .    ..       ISL
  • 1973 THROU.(;H ~:986*:**-- c--------.._. .*-*-**-*
                                                                                                                                                        . . ,.-..-.-   --~~-** - - - - -

I 10000 _ _ _ _ _...._________________________ ~_

  • 1
                                                                                                                                                                        -- ***   r *   * ~ *
        *1                           5000      ********** .-************ ***.*********** *************** ***** **.*******-********* -*.*****.*********************** , ****..*.*********

1000 ****************************************************************************. *********************** ....................... . 

       ~-j 51)0     ********************.* *******************************************************.**.*********.*********.******** , ***************
      *.j
                              ...J
                              'a.

(J 

                                      *:: ::::: :: :::::::: :: :: :: :::::::*.; :: ::: *::: .... ,: :. ::::: .. :::;1 .:* *: :. ::::: ::: ..:* *::* ::::: ::::. ::::::. ::*. ::*:*z:.~ *:

m

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                                                                                                                                                                                                  ' 11 11~
  . . '\
  ' *~t
  • j
 . . *i 12341234123412341234123412341234123412341234123412341234 Ul73 !B74' ta7a iB7B tB77 tS78 tB7S t                                            teat 1982 1983 UH14                                        1988 1988

                                 . *1.
   *- __ ....... -* - . - .       . -~

l 

*i I

I 

                                     !                                 AVERAGE CONCENTRATIONS OF TRITIUM IN THE FIGURE BA DELAWARE R,IVEA IN THE VICINITY OF ARTIFICIAL ISL.

1983 THROUGH 1986 5000 ****** ****************************************** ........................................................................... . AOOC * * * * * * * * * * * * * * * * * * * * ** ** ** * ************************************************************************************************* 500 ** ******** ** * ... * * * ** ........ ***** *** * . * . *** * * ** * *** * *** * * ***** ** ** * * *****. * *******************************.*.********** 100 .****..... : .********.**.*******.......**..*....*.*. *............................................... *.* * . . * * . . . . ..........**.. 50 ~ 

                                       ******************************************** ******* ..................... .'.****.********************* *-;.;***                                        ~- .***.**.*****..
                                                                                                                                                                                          ;1
                                                                                                                                                                                                ~

Jl IF ft.fi A li4 J J A S 0 N D J F MA MJ J A S 0 N D JI f 114 A M J J A S 0 H D J f MA MJ 

                                                                                                                                                                                       *I ~I      J AS 0 ND i'.B83                                                   !'!98~                                       ~lil-~                                 UJB~

[l] REFERENCES. Radiation Management Corporation.. "Artific.:ial Island Radiological. Environmental* Monitoring l?rogram - Annual Reports 1973 through 1962" *. [2] Radiation Management corporation. "Artificial Island Radiological. Environmental Monito~ing l?rogram - Preoperation summary - 1973 through 1976".* RMC-TR-77_;.03 ,; 1978. [3] Radiation Management:corporation. "Artificial Island Radiological Environmental Monitoring l?rogram - Deceml:Jer ll to Deceml:Jer 31, 1976". RMC-TR-77-02, i97.7. ; . 

                                                             \  !   l

[4] PSE&G Research:Cqrpora~ion, Research and Testing LaJ:>oratory. 

                       "Artificial Island Radiological Environmental Monitoring l?rogram - 1983 Annual Report*~:. ; R'+'L-ENV-84-0l, 1984.
                                                *;          ; :r

[5] PSE&G Researc~ Corporation, Research and Testing LaJ:>oratory *. 

                       "Artificial Iialand* Radiological Environmental Monitoring l?rogram - 1984 Annual Report:*!. ; ~TL-ENV-85-0l, 1985.
  • Ii  : *1* * .

I ' [6] PSE&G Research ¢orporation, Research and Testing LaJ:>oratory. 

                       "Artificial Island Radiological.. Environmental Monitoring Program - 1985 Annual. Report"~ ~TL-ENV-86-0l, *1986 *
      ..'  ~  .

[7] Public service Ele_ctric and Gas company. "Environmental Report, Operating License* Stage -* Sal.em Nuclear Generating Station Units l and 2". 197le': "

  • . [8] Public Service Electric and*Gas Company. "Environmental Report, Operating *.License Stage - Hope creek Generating Station. 1983.

[9] United state~' Atomic Energy commission. "Final Environmental Statement - Salem Nuclear Generating Station, Units l and 2 11

  • Docket No. 50-272 and 50-311. 1973~

[10] . United State~ Atomic Energy commission. "Final Environmental Statement - Hope creek' Generating 

                                            .                            Station, Docket.No. 50-354. 1983.

[ll] Public Servi,ce Electric and Gas. Company. "Updated Final. Safety Analysis. Report - Salem Nuclear Generating Station, Units l and 2". 1982 * 

   .. -*..  )                     .       . '
         ,.:    [12]   Public Service Electric and Gas Company.                             "Final Safety Analysis Report Hope*creek Generating Station. 1984. *

[13] Pubiic :Service Electric and Gas Company. "Salem Nuclear Generating Stat+/-od Unit l - Technical. Specifications", AppendiX A to Operating License No. DPR-70, 1976, sections 3/4.12 and 6.9.l.lO (Amendment 59 

                       ~:~),.,:
         ' ~
                                                                                                                       ..... --; - --***.,;:-I"','
                                                                                                                        . -~    .

REFERENCES. {cont id) .. [14] Public Service Electric and Gas Company. "Salem Nuclear Generating Station Unit 2 - Technical Specifications", Appendix *A t_o Operating License No. DPR-75, 1981, Sections 3/4.12 and 6.9.lolO (Amendment 28 

                     £~).

[15] PUblic Service Electric and Gas company. "Hope creek Generating Station Unit l - Technical Specifications", Appendix A to Facility Operating License No. NPF-57, 1986, Sections 3/4.12 and 6.9.1.10. [16] Pu.blic Service Electric and Gas company. "Offsite Dose calculation Manual~ - Hope creek Generating Station. [17] PUblic:: service Electric and Gas Company. "Offsite Dose calculation Manual" - Salem Generating Station. [18] u. s. Environmental Protection Agency. "Prescribed Procedures for Measurement of Radioactivity in Drinking Water. 11 EPA-600/4-80-032, August, 1980. [19] PSE&G Research corporation, Research and.Testing Laboratory. "Environ-mental Division Quality Assurance Manual." September, 1980. [20] PSES!G Research corporation, Research and Testing Lanoratory. ~Environ= mental Division Quality Assurance Plan.n (supereedes Quality Assurance Manual)f January6 1987. [21] PSE&G Research corporationu Research and Testinq Laboratory. ~Environ= mental Division Procedures Manual." February, 1981. [22] PUblic Service Electric and Gas Company. "Radioactive Effluent Release Reports, RERR-l and RERR Hope creek Generating Station. 1986. [23] PUblic Service Electric and Gas Company. "Radioactive Effluent Release Reports, RERR-20 an~ RERR Salem Generating Station. 1986. [24] Nuclear Newso "Chernobyl: The Soviet Reporte" October 1986. [25] The Heal.th Physics Society Newsletter. "Preliminary Dose Assessment of the Chernobyl Accident. Part II.~ January 1987 * . . *.I 

   ** J ....
 ...... 1
            .-~
  • . :, i APPENDIX A PROGRAM

SUMMARY

                                                                                                                                                                                                                                                                                     . . . ."" . ~ .
                                                                                                                                                                                                                                                                                                       . I
               . ,,,."':"_._ -*----.--:-, --*--*. *- .___,. *-;- * --*- ---- *--. *-~ ...... -- *-* . ----- .... -*- .. , -- **- **;* -.. r*--- -*---*-- ---** -.-*-******.--: -::- -* - ----*. ----- .,.... -- ---- -***---<--*-*-:* .... -** -- .*-* .. ... . .. -* ********--* --- - -- . -*     ..

                       \. ,;:'. .. ' . .. .. . .. .   '
                                                                  ~

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM GENERATING STATION DOCKET NOS. 50-27Z/-3H HOPE CREEK GENERATING STATION DOCKET NO. 60-364 SALEM COUNTY, NEW JERSEY JANUARY 1, !986 to DECEMBER 31, 1986 ANALYSIS AN!li LOWER NUMBER Of 

      ~EDIUM  OR PATHWAY                        TOTAL NUMBER UNIT Of Al I IUDICAIOB IOC!IXOUS                        IOC!IIOU WIIU UI6UESI ~E!U       COUIHOI 1llC!IIOU  NON ROUTINE SAMPLED                             OF ANALYSES DETECTION                           MEAN**                      NAME                MEAN         MEAN          REPORTED
    <<UNIT Of MEASUREMENT) PERFORMED                                         (HO)*               (RANGE)         !HSTANC*E AND DIRECTION      (RANGE)       (RANGE)      MEASUREMENTS Air Part iculi!hs                          Aiphm               416        0.8           Z.8 (311/364)            zsz   0.4 ml NNE    3.1 (46152)    Z.8 (48/62)           0 00-3 pCt/m3)                                                                             (0.8-Z2)                                    (0.9-22)       (1.0-20)

Beh '316 41 (369/364) 2S2 0.4 mi NNE 46 (li0/62) 42 (61162) 0 (6.7-370) ( 9. 4-360) (11-330) Sr-89! 8 0.3 <UD <HD <LLD 0 oj:b II-" Sr-90 s 0.2 <Lrn ~no <LLD 0 . Gillmla Be-7 3Z 77 (28/28} !iDl 3.li mi E 91 (4/0 76 (4/4) 0 (60-110) (80-110) (64-90) Ru-1031 :ilZ 0.1 8.6 p12a) !iDl 3.6 mi E 9.2 014) 7.6 (114) 0 (7 .6-9.2~ {9.Z) (7 .6) lllu-106 32 1.6 6.6 (3/28) lFl 6.8 mi U 8.3 (114) 4.0 (114) 0 (4.0-8.:ll) (8.3) ( 4 .0) CsHM 312 0.31 9. 3 (7 /28) lfl 6.8 ml N 10 010 9. z (1/4) 0 (8.4-10) (10) ( 9. 2) 2fZ 8.7 mi NNE 10 (114) ( 10) 

                                                  <<:s-137            312      0.3             17 (7 /28)             zsz   0.4 mi NNE     18 (114)       17 (114}             0 (16-18)                                      (18)            ( 11) lliDl 3.6 ml E        aa ( u~)

OR) 

                                                  !lili-Z26          32       0.3            1. 2 ( 11211)            If l 6.8 mi N        l.2 0/4)          <LLP             0

( 1.2) {1,2) Jh-232 28 a.! l. 7 0120 lf l 6.8 mi N  !.7 01.i) <LLP 0 ( 1. 7) ( l. 7) 

                                                                              ~.   '
        ..::* J '                                                      _,., ..... ,. '* 1.:                                                                                                                            ' J::_ ..

ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM GENERATING STATION DOCKET Nos: 60-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 60-354 SALEM COUNTY, NEW JERSEY JANUARY 1, 1986 to DECEMBER 31, 1986 ANALYSIS AND LOWER . NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF ALL IUDIC:AIOH I llC:AIIllU5 lllC:AIIllU WIIU Ul6UESI' MEAU C:DUUDf I DC:6IIDU NONROUTINE SAMPLED . OF ANALYSES DETECTION MEAN*f NAME MEAN MEAN REPORTED 

                  . (UNIT OF MEASUREMENT) PERFORMED                 . (LLD)*                    (RANGE)                 DISTANCE AND DIRECTION                              (RANGE)           (RANGE)       MEASUREMENTS Atr lodtne                 I-131         416             7.7            160 (27/364)                        16El 4.1 ml NNW                         190 (3/62)          170 (4/61)

(10- 3 pCt/m3) (26.:.320) (70-300) (64-320) '.;. 

                  . Preclpttatlon              Alpha           12           0.3               1.0 (4/12)                         2F2 8.7 mt NNE                         1.0 (4112)           No Control             0 (pCi/L)                                                                  (0.6-1.3)                                                                 (0 .6-1. 3)           Locatton Beta        . I .12           1.6              6.6 (11/12)                        2F2 8.7 mi NNE                         6.6 (11/12)          No Control             0 (1.9-16)                                                                   (1.9-16)            Location
                                      --- - * -H ,. . 12                  130.                <LLD                                                                       <LLD             No Control             0

. ., *location 

  .,"                                          Gamn~
  . i.                                           Be-7          li                            -47 (11/.H)                **   *.zn....8.7 mL.HNE                         47 (11/11)           No Control             Q
     \                                                                                          (3~-71)                              ... -- -.... '* .::: : : ~ * ( 35-71)           .        Location
    *1                                           K-40          11                26            69 (1/ll)c - *.,,::.*._ _,_ ~F_z*a~TmTNNE .. ., - 69.. (1111)                                 No Control
   *.i                                                                                                                    00
                                                                                                                             ._                                                                                     0
      '                                                                                          (69)       **             . - ... ,, ..*:..*o.c::.~~---.*,... o . . . . * (69)               iocatfori 1-131         11            1.6              7.4 (1/11)                         2F2 8*.1~mi NNE                        7:*f(l*/U*)-- - *. No.Contr.q\           .. 0

( 7. 4) -{-7.4) . . Location .. , Cs-137 11 0.8 4.8 (1/11) 2F2 8.7.mi NNE . 4.8 (1/11) No Control 0 (4.8) (4.8) Location Ra-226 11

  • 4.2 6.6 (jJ1i) 2F2 8.) mi NNE li.6 (3/11) No Control 0 (4.8-7.0) (4.8-7.0) Location Th-232 11 7.2 7.6 (1/11) 2F2 8.7 mi NNE 7.5 (1/11) No Control 0 (7.5) (7.5) Location J
. j

                                     ~*
                                                     ***~ ' ; ....*,*  ..

ARTifICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM GENERATING STATION DOCKET NOS. 60-UZ/-311 HOPE CREEK GENERATING STATION DOCKET NO. 60-364 SALEM COUNTY, NEW JERSEY JANUARY 1, ,1986 to DECEMBER 31, 1986 ANALYSIS AND LOWER NUMBER Of MEDIUM OR IPAiHWAY TOTAL NUMBER UNIT OF 611 IUDIC6IQH IOC6IIOUS IOC6IlOU ~lIU Ul6UESI HE6U COUIBOI iQC6IIOU NONROUHNE SAMPLED Of ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED 

    <<UNIT OF MEASUREMENT) PERFORMED                          (HD)*              (RANGE)              DISTANCE AND DIRECTION          (RANGE)        (RANGE)     MEASUREMENTS Direct Rild1iltton    Gillllllil         287                            6.9 (Z61IZ61)                   7Sl 0.1 mt SE       6.9 (lZ/12)      6.4 (36/36)       ' .0 (mrad/std. month)    Dose (monthlll)                                   (3.8 - 1.7)                                         (6.9-7.1)        ( 6.1_-1.6)

Gilllllla 164 6. 0 (140/140) 751 0 .1 mt SE 6.0 (4/4) 6.6 (Z4/Z4) 0 Dose (qtr]lf. b (3.4-6.1) (Ii .6-6 .6) (4. 9-6.4) ~ ir'1 l)Ulk 1-131 122 0.1 10 ( 16/ 103) 3Gl 17 mi NE 19 (3119) 19 (3/19) 0 (111Ct/L) (O.Z-47) (0.3-li3) (0.3-63) Sr-89 7 0.8 <LLD <HD <LLD 0 Sr-90 7 z.o (6/6) 6FZ 1.0 mt E 3.0 (lll) Z.1 (111) ii (l.Z-3.0) (3.0) (Z. 7) Sillmlil Na-ZZ lZ! 1.0 4.6 (11102) 6FZ 7.o mi E 4.6 (!/20) <LLD 0 (4.6) .*...... (4.6) K-40 121 1400 ( 102/ lOZ) ** /- :=:. - 2F4 6.3 mi NNE 1400( 13113) 1300 ( 19/19) 0 (lZOO-l!iOO) '* (1300-1600) ( 1100-1400) Mn-54 121 0.7 2.9 (lllOZb 13E3 4.9 mi W z. 9 ( 1120) <LLD 0 (Z.9) (z. 9) Zn-61i 12ll 1.8 11 (11102) llf3 6.3 mi SW 11 (1/ZO) <LLD 0 ( U) (U) Il-Ul !Zll 0.6 20 (8/102) 31H 17 ml NE 3~ (2./19) ~P. (Z/~f)) 0 (3.8~49) (7,4,,66) (7.4~6§) 

                           <<:s-U7             U~ll                'Z.3       4 .1 (li/aOZ)                  fiU   7.o mi E      4.fi UW))             ~HP              @

(l.3~1i.l) (:il.9-t:i. 0 Ra-226 RZil 6. l 6.6 (31102) 14fl 5.5 mi WNW 5 .s (zr20 > 6.5 (1119) 0 (4.4-7.3) (4.~-1'.3) (5.5) 

                               /.    ,.                                                 \,';
                     *::.... .. , *.: . .:. ~-. ~-. ,,._. ~;,:,..,: .:,._;,~ .~ .... -~ -~, . .                                                .::... -~: ..   *' ..
                                                                                                   .ARTIFICIAL iSLAND RADIOLOGICAL ENVIRONMENTAL MONITORING* PROGRAM

SUMMARY

SALEM GENERATING STATION DOCKET NOS. 60-272/-311 HOPE CREEK GENERATING STATION DOCKET NO. 60-364 . SAL~M COUNTY, NEW JERSEY .JANUARY 1, 1986 to DECEMBER 31, 1986 ANALYSIS AND *LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF All INDICATOR \OCAllONS IOCATION WITH HIGHEST MEAN CONTROi IOCATION NONROUHNE SAMPLED OF ANALYSES. DETECTION MEAN** NAME MEAN MEAN REPORTED (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUR~MENTS Wel 1 Water Alpha 36 0.6 1.2. (~/24) 2S3 700 ft NNE 1.2. (4112) <LLD 0 (pC 1/L) (0.6-2.0) (0. 7-1. 7) Beta 36 1.0*** 7.6 (24/Z4) 6Dl 3.6 mi E 10 (lZ/lZ) 7.4 ( 12/12) 0 (2.0-16) (Z.0-l!i) (Z.!i-9.li) K-40 36 8. 7 (24/24) liDl 3.6 mi E 13 (12112) 9.4 (12/12) 0 (2.7-16) (8.8-16) (7 .4-17) H-3 36 130 <LLD . <LLD <LLD ii Sr-89 12 0.4 <LLD <LLD. <LLD *o '* Sr-90 12 0.3 '<LLD <LLD <LLD -* 0 GaRJna K-40 36 21. 42 (4/24) liDl 3.6 mi E 42 (4/lZ) <LLD . p .**_J-. (36-47) .* (36-47) 

                                                                     ~a-:22~                 **'- 36       3.3             Z9 (17124)                            3El            4.1 mi NE                            69 (11112)                 69 ( 11112) .          0
";j':.                                                                                                                       (3.3-96)                                                                                  (2.9-170)                 (Z.9-170)
  • ,. 'J" Tti-z3z- 36 4.6 .9.Z (2/Z4) 601 3.6 mi E 9.Z (2/lZ) <LLD 0
  . 1                                                                                                                 - : - (8. 4-10)

I j (8.4-10) l ... -. *.- *..- ... _j j Potable Water Alpha 24 0.6 o.8 <11/.?H ZF--3 -8.0 .11),i NNE * -- *

  • f t - ..

0.8 ( 11_/24) No Control 0 Raw-Treated (0.6-1.6) ..:...-_ -- :. .! -*----~ ** ;..- ~ 

                                                                                                                                                                                                 .*-**-- ... (iL6:.:t. 6)                        *Local ion .

__ (pCi/L) Beta Z4 1.0*** 3.6 (~4/24) 2F3 8.0 mi NNE .3.6._(24/24) No Control 0 

                                                                                                                                                                                                                             ** ,_P"*** *** * *

(1.7-13). l~.:7-13) [a canon K-40 24 1.8 (24124) 2F3 8.0 mi NNE 1.8 {i4i24) No Contra l * -- 0 (1.3-4.9) (l.3-4.9) Location

  • H-3 24 130 l!iO ( 1/24)

( l!iO) 2F3 8.0 mi NNE 1.!iO ( l / 24) ( 150) No Control Location 0

AR!XF!CIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEM GENERATING STATION DOCKET NOS. 60-2721-311 HOPE CREEK GENERATING STATION DOCKET NO. 60-364 SAllEM COUNTY, NEW JERSEY JANUARY 1, 1986 to DECEMBER 31, 1986 ANAa.YSIS AND lOWEI! NUMBER OF 

    ~EDIUN  OH PATHWAY  TOTAL NUMBEl.l UMH Of        ~II IUDICAIDR !DC!IIDUS             I OCAII!lU kiIIU. Ul6UE51 l:IEAU         COIHROI I OCAIIOU NONROUHNE SAMPlfl>      OF ANAIL lfSES . DEJIECHON             MEANH                            NAME                    MEAN             MEAN         REPORTED
  <<UNIT Of MEASUREMENT) PE!lfORNED         {U.D)"'             (RANGE)           DXSTANCE       AND  DIRECTION       (RANGE)           (RANGE)      MEASUREMENTS Pot~ble  Water cont'd Sr-89         ~        0 .6          o.e (1/8)                   2f3 8.0 mi NNE          0.6 (118)           No Control          0 hw-Tuahdl                                                    (0.8)                                                (0.8)             locatton (pCW.)             Sr-90         8        <<) .4            <LLD                                                 <LUI            No Control          0 location Gillll!llill

~ on l<-40 Z4 zz Z6 (2124) 2F3 8.0 mi NNE 26 (2124) No Control 0 (Z6-Z6) (26-26) location Ru-103 24 <<1.6 Z.6 (1124) Zf3 8.0 mi NNE 2.6 (1124) No Control 0 (Z.6) .. (2.6) locatlorn 

                                                                             . .*-. ~ -

lhl-226 24 SJ. 7 6.9 (3/Z4) 2f3 8.0 ml NNE 6.9 {3124) No Control 0 (Z.6-8.4) (2.6-8.4) location Th-232 24 . 4.9 6.1 (3/24) 2f3 8.0 mi NNE 6.A (3/24) No Control 0 (6.7-6.8) (6.7-6.8) Loe at fon fruit &Vegetabie$ Ganma {pC I/kg-wet) Be-7 20 H 24 (1/12} 4fl 6.1 mi ENE 24 ( 112) <LLD 0 ( 24) (24) l<-40 20 z100 (1ZI 12) 2Gl 12 mi NNE 3400 (111) 2100 (8/8) 0 ( 910-2600) (3400) (1600-3400) I-i31 20 2.3 33 (1112) 2Gl 12 ml NNE 62 (AH) 62 ( 118) 0 (33) (62) (62) Cs-U7 20 A.6 <LLD 3H6 26 ml NE 2.1 (1!4) 1.8 (218) 0 ( 2 .1) (l.6-2.1) Ra-226 20 l.8 8.3 (1112) AGl 10.3 mi N 68 (1/3) 63 (218) 0 (8.3) (68~ (58-68) Ho-2?:? :w ~.IS B.8 P.tfi.2~ ~t'.\f~ 5.4 mi WNW t?"B {L/2i~ t.UO 0 (Vq 1\ &. rl~ ; 

                                                                                           **.-~;;~ ..._'.... --~~~~~;'::~: -~ ':_:....~ /*:*. *.*
                 -,.::.~::* ~*~..'..*--~: . ..;. :. ... ...:...::*..
                                                   ."                  . - ---*~ **-*
      . I  l I
          .j
     >1
     .*.1
       .,i I
           .I ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

      . i i                                                                                                                                                                                                                                                                             :

I 

        *i                                                                                                       SALEM GENERATING.STATION                                                      DOCKET NOS. 60-272/-311
           .I                                                                                                                                                                                  DOCKET NO. 60-364
        .j                                                                                                       HOPE CREEK GENERATING STATION i

SALEM COUNTY, NEW JERSEY JANUARY 1; 1986 to DECEMBER 31, 1986 ANALYSIS AND LOWER NUMBER OF MEDIUM OR PATHWAY TOTAL NUMBER LIMIT OF All IUDICAIOB IOCAIIOUS IOCAIIOU ~IIU UI6UESI MEAU COUIBOI IOCAIIOU NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN REPORTED l (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS 

      .l                                                                                                                                                                                                                                                                        '.
        *I
       ..i,                                                                           Ganmil Game
       . . . J.

i (pCi/kg-wet) K.:.40 2 2400 ( 1/1) 4Cl 2.8 mi ENE 2400 ( 1/1) 2200 ( 1/1) o*. j (2400) ( 2400) ( 2200) 

       ".j
i i
          .I                                          Beef                            Gilnmil
      '*:l
             *1
                                       ~                   (pC i /kg-wet)              K-40                       1                                 2600 (.1/1)                3El 4.1 mi NE                                        2600 (1/1)                 No Control           0
       . i                                                                                                                                                                                                                            ( 2600)                   Lociltion i                                                                                                                                       (2600)
              !                                                                        Cs-137                     1                                  7.3 (111)                 3El 4.lmiNE                                           7.3 (111)                 No Control           0 (7.3)                                                                           (7.3)                    Lociltion Fodder Crops                   Ganma

( pC I /kg-wet) Be-7 9 140 880 (4/7) 14Fl 6.6 mi WNW 1400 (Ill) 1100 (l/Z) 0 (370-1400) (1400) ( 1100) K-40 9 6600 (717) 3El 4.lmiNE 16000 (1/1) 8600 (212) .0 (2300-16000) ( 16000) (3000-14000) 

   . -. .;*~1-                                                                         Cs-137                 '*~                          17           <LLD                    361 17 mi NE                                         13 (1/2)                  13 (1/Z)             0
       . <                                                                                                   --                                                                                                                          (13)                      (13)
          *,1,.*

J Ra-226 9 36 36 (117) 2F7 5. 7 mi NNE 36 (1/1) <LLD 0 

          .*.;                                                                                                                                          (36)                                                                             (35)
                                                                                                                                                                                                                                                                   <LLD Th-232                    9                        69        170* ('lt7)             14fl 5.6 mi WNW - 170 (111)                                                                            ()

( 170) ( 170) 

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

1 

               ,i                                            *                                                                                               - .. .        .
                                                                                                                                                                              .::-*:. *- !. !._* __ ~:.:...:-.. '.,: .. *-. : * * .

ro *** * * 

           *  ~ >* *'     * ..;. ' ,,' * '
~ '
                                           ,* * - ' * * * "* * :  ' '* *** * * " " " * '* *c*>
                                                                                               * **~<,. ';,. \ j ~ '** .. ,

AR1If ICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

SALEN GENERATING STATION DOCKET NOS. li0-27Z/-3U HOPE CREEK GENERATING STATION DOCKET NO. 60-364 SALEM COUNTY, NEW JERSEY JANUARY 1, 1986 to DECEMBER 31, 1986 ANALYSIS AND LOWER NUMBER Of MEDIUM OR PATHWAY TOTAL NUMBER UNIT OF AIL IUDI&AIOH LO&AIIOU5 IO&AIIOU ~IIU UIGUESI MEAU &OUIHOI IOCAIIOU NONROUTUIE SAMPLED OF ANALYSES DETECTION MEAN** NAME MEAN MEAN . REPOUEO (UNIT Of MEASUREMENT) PERFORMED (LLD)* (RANGq DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMfNTS 1 Soil Sr-90 16 2Z 91 (13114) Zfl 6.0 mt NNE 140 (Rli) 93 (Z/Z) 'o (pCi/kg-dry) (Z7-140) (140) (66-130). 

                                                                                                                                                                                                                   . '\

Gillmli8 7800 (14/H) .*.* 11F3 6.3 ml SW . '*0* l'(-40 ll.6 13000 011) 8600 (Z/Z) ( lZ00-13000)  :~*- ( UOOO) ( 7900-9200) l)(!:h Nb-96 16 4.li 48 (Z/14) ZF7 6.7 mi NNE 63 (111) <LLD 0* 

 ~                                                                                                                              (34-63)                                          (63)

Cs-U1 X6 390 ( 14/R4) lfl 6.8 mt N lliOO (111) 460 (2/Z) 0 (78-UiOO} (1600) (210-690) lllin-226 16 680 (14/n-0 16El 4.1 mi NNW 1000 UH) 810 (2/2) 0 (260-1000) ( 1000) ( 770-860) Hf3 6.3 mi SW 1000 (111) (1000) 

                                                                   'H'h-232                    16                             710 (14/14)             16El 4.1 ml NNW      1200 ( 111)        800 (212)            0 (ZJ0-1200)                                       ( 1200)        (780-810) i             Surface Water                                       Alpha                         60                   0.6       3.1 ( 19/48)             lfZ   7.1 mi N      6.6 (3112)       3.li (4112)             0 (pC i IL)                                                                                                      (0.7-12)                                       (2.6-12)        ( 1. 8-8. 3)

Beh 611 3.8*** 61 (48/48) 7El 4.6 ml SE 76 (12112) 46 ( 12/12) 0 (2.4-130) (16-130) (7.li-81) H-3 zo !30 160 (8/16) UAl 0.2 ml SW 210 (214) 160 (1/4) 0 ( 130-270) ( ili0-270) ( 160) 

                                                                                  '* :. ~

1'- ~.......C.*._,_.::__ , __ ,; .... - * ~ ~..... . ........ *'- *- .. : :'. : :*_,._ .. *- : .. * ...... ... . . . - - ........ .. 

         *i
   *1
    .*j
           \
. :j
        '.'l
   .*1 ARTIFICIAL ISLAND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

n 

      ;1 I                                                                                                                   SALEM GENERATING STATION                          DOCKET NOS. 60-272/-311 I                                                                                                                  HOPE CREEK GENERATIN.G STATION                    DOCKET NO. 60-364 II
 . *i                                                                                                                         SALEM COUNTY, NEW JERSEY            JANUARY*l, 1986 to DECEMBER 31, 1986
                                                                                                                                                                                                            '/'*
     ,j
      'i

. 'l MEDIUM OR PATHWAY ANALYSIS AND LOWER TOTAL NUMBER LIMIT OF Al I IUDICAIOH IOCAIIOUS IOCAIIOU WIIU UI6UESI YEAU COUUOI IOCAIIOU NUMBER OF NON ROUTINE SAMPLED MEAN** NAME MEAN l (UNIT OF MEASUREMENT) PERFORMED Of ANALYSES DETECTION (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) MEAN (RANGE) REPORTED MEASUREMENTS 

    *-1 I                                                                                                                                                                                                                        . ~ . :*
     *:i
   -.i l                                     Surface Water cont'd. Ganma K-40                 60             24      88 (34/48)

(33-160) 7El 4.6 m1 SE 100 (lZ/12)' (66-160) 70 (9/12) (29-96) 0 

    *I
l Ra-226 60 3.3 6.6 (7148) l2Cl 2.6mi WSW 26 (1/12) 26 (1112) 0 I ( 2.6-11) (26) (26)
      '~~                                                                                              Th-232               60           4.9       7.4 (6/48)             12Cl 2.6 m1 WSW     9.2 (1/12)
.".j ~ 9.2 (1112) 0
                                <<>>                                                                                                                  (6.3-9.3)                                      (9. 2)             (9.2)
  '-.1
  *.i
    • j
    .\
        .j                                     Edible Fhh                                            Sr-89                    6            40          <LLD               12Cl 2.6 m1 WSW       330 (1/2)          330 (1/Z)        0 I

I ( pC 1/kg-dr y) (bones) Sr-90 6 24 140 (214) 12Cl 2.6 mi WSW (330) 1600 (112) (330) 1600 (1/2) 0 1 I (bones) (34-240) ( 1600) ( 1600) (pC1/kg-wet) H-3 6 60 <LLD <LLD <LLD 0 (aqueous) Ganma K-40 6 3000 (4/4) llAl 0.2 mi SW 3000 (Z/2) 3000 (212) *O 

 '.i                                                                                                                                               (2700-3300)                                ( 2700-3300)       ( 2700-3300)
     *l                                                                                                                                                                   12Cl 2.6 mi WSW     3000 (2/2)
    *I
  .*'.j (2700-3300)

. .. ~~ . Cs-137 6 12 8.3 (1/4) llAl 0.2 m1 SW 8.3 (1/2) <LLD 0 I (8. 3) (8. 3) Ra-226 6 20 37 (2/4) llAl 0.2 mi SW 41 (1/2) <LLD 0 

     ~;-

(33-41) . ( 41) 

    *:.                                                                                    - -_ -. Th--2 ._ 6                         31          <LLD               12Cl 2.6 mi WSW       29 (1/2)           29 (112)         0
1 (29) (29)
       'I

I l j ARTIFICIAL ISLAND RADIOLOGICAL ENViRONNfNTAl MONITORING PROGRAM

SUMMARY

*1                                             SALEM GENERATING STATION                             DOCKET NOS. 60-272/-3Rl HOPE CREEK GENERATING STATION                        DOCKET NO. 60-364 SA~EM  COUNTY, NEW JERSEY          JANUARY l, 1986 .to DECEMBER 31, 1986 ANALYSES AND        LOWER                                                                                       NUMBER OF MED!UN OR PATHWAY . TOVAL illlUNBER UD@!T OF ALI IUOICATOR IOCAIIOUS              !OCATIOU WITH HIGHEST HEAM      CONTROi IOCATIOU NONROUTXNE SAMPLED      OF AAALYSES DETECTION                 MEAN*>!!                     NAME                MEAN          MEAN        REPORTED (UNIT OF MEASUREMENT) PERFORMED         (LLD)*              (RANGE)      '.~*~RSTANCE AND DIRECTION        (RANGE~        (RANGE)    MEASU.REMENTS
. '~ -

Blue Cubs Sr-8~ .fl 67 300 (l/Z) 11Al 0.2 m1 SW 300 ( H2) <LLD 0 {pC I/kg-dry) (shei]h) (300) (300) Sr-90 4 260 (212) 12Cl 2.6 ml WSW 400 (212) 400 (212)  : o* 

                                  <<sheH:s)                            (160-380)                                     (320-i&90)     ( 320-490)
            <<l>C i/kg-weit)      H-3           4       60                <HD                                          <LLD             <LLD          0 1)(11.                        (aqueous) w                            Sr-89         ~       28                <LLD                                         'LLD             <LLD          0 (flesh)

Sr-90 4 18 <LLD <LLD <LLD 0 (f1HDll>> Ganma 

                                  !C-40      . l&                   1800 (212)                llAl 0.2 ml SW      1800 (212)     1800 (212)          0

( 1700-2000) ( 1700-2000) ( 1700-2000) 12Cl 2.6 mi WSW 1800 (212) ( 1700-2000) Ra-226 4 28 . <LLD 12Cl 2.6 mi WSW 20 (212) 20 (212~ 0 (19-20) (19-20) Benth1c Organ1sms G11nm11 8 <LLD <LLD <LLD 0 (pCHkg-dry) . i

.r I i 

     . I
     ;)
        *\

i ARTIFICIAL ISLAND RADl_OLQGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

  .        I
  .;*,l                                                                                    SALEN GENERATING STATION                             DOCKET NOS, 60-272/-311
      **1 HOPE CREEK GENERATING STATION                        DOCKET NO, 60-364
1 J

l SALEM COUNTY, NEW JERSEY JANUARY 1, 1986 to DECEMBER 31, 1986 

    , I
   *.I
       .I
         .j i                                                                   ANALYSIS AND     LOWER                                                                                        NUMBER OF
    ..*i,                       MEDIUM OR PATHWAY . TOTAL NUMBER LIMIT OF ALL IUDICAIDB IDCAIIDUS                                         IDC6IIDU ~IIU UIGUESI YEAU       CDUIBDI IDCAIIDU  NONROUTINE SAMPLED                                   OF ANALYSES DETECTION              MEAN**                        NAME               MEAN         MEAN          REPORTED
 *J  *J
,[ (UNIT OF MEASUREMENT) PERFORMED (LLD)* (RANGE) DISTANCE AND DIRECTION (RANGE) (RANGE) MEASUREMENTS
           .I                                                                                                                                                                                    ' -~
     .j i                   Sediment                                         Sr-90      lZ      19               <LLD                                           <LLD          <LLD              0 I

I (pC1/k9-dry) Gillllllil i K-40 lZ 9600 (10/10) 16Fl 6.9 mi NNW 16000 (212) 16000. (212) 0

.J l' (3600-16000) (16000-16000) (14000-16000)
        *1                                                                       Mn-64    12      18            26 (3/10)                llAl 0.2 ml SW         27 (212)        <LLD              0
     .,\
     'J (JI                                                                                     (24-29)                                        (26-29) 0
      ,,j                                                                        Co-68    12      23            67 (4110)                16Al 0.3 mi NW         80 (1/2)        <LLD              0
    <1                                                                                                            (31-80)                                         (80)
      'i                                                                         Co-60    lZ      36            72 (8/10)                llAl 0.2 mi SW         100 (212)       <LLD              0
 ; *l                                                                                                           (37-11_0)                                       (92-110)

I 

 **:.;                                                                           C5-134   12      16            61 (3/10)                16Al 0.7 mi NNW       82 (1/Z)       60 ( 112)           0
       ,i                                                                                                         (46-82)                                         (82)          (60)
    .*1 "1.                                                                           Cs-137   12      16            61 (3/10)                llAl 0.2 ml SW        82 (1/2)       20 (1/2)            0 1I                                                                                                       (49-82)                                         (82)          (20)

I 

        *I
                                                                               . Ril-2Z6  12                   610 (10110)

(330-810) 16Al O. 7 mi NNW 780 (212) (760-810) 700 (212). (670-840) 0 .. 

 ' i Th-232   12                   720 ( 10/10)
  • 16Fl 6,9 mi NNW 970 (212) 880 (212) 0 (300-1000) ( 940-1000) (870-880)
 . *.. l                        ' LLD listed is the lowe5t calculated LLD during the reporting period .
                               **Mean calculated using values above LLD only. Fraction of meaGurement* Above LLD are in parentheses.
                              ~** Typical LLD value.
..J
     .. ~ .
     'j

APPENDIX 8 SAMPLE DESIGNATION ANO LOCATIONS 

                                                       ~ -r 51
        ----~-~ ----._.-.-...-*---------,,,****-,.**-------~---:-------*  *--.---.._.---...,.....,..---.-----~---,:--:-*----*-~ *-:--**-----~---.-------- -- **--

APPENDIX B SAMPLE DESIGNATION.*: . The PSE&G Research.Corporation identifies samples by a three part code. The first two letters are the power station identification code, in this cas.e 

       ' SA".

9 The next three letters are for tl'l.e media sampled. AIO = Air Iodine IDM = Immersion Dose (TLD) APT = Air Particulates MLI< = Milk ECH = Hard Shell Blue Crab PWR = Potal:lle Water (Raw) ESB = Benthic organisms PWT = Potable Water (Treated) ESF = EdilJle Fish

  • RWA = Rain Water ESS = Sediment SOL = Soil FPB = Beef SWA = surface Water FPL = Green Leafy Vegetacles VGT = Fodder crops (Various)

FPV = Vegetables (Various) WWA = Well Water GAM = Game The last four symbols are a location code based on direction and distance from the site. Of these, the first two represent each of tl'l.e sixteen angular sectors of 22.5 degrees centered about the reactor site. Sector one is divided evenly by the north axis and other sectors are numbered in a clock-w~e: directioru i.e. 2=NNEP 3=NE, 4=ENE~ etc;. The next digit . is a letter Q which represents the radial distance from the plant~

  • s = on-site location E = 4~5 Dci.les off-site A = 0~1 DU.les off-site F = 5-10 miles Off=site
              .B = l-2 miles off-site                G =   io~20 miles off-site c = 2~3 miles off-site                 H =   <20 miles off-site D = 3-4 miles off-site The last number is the station numerical designation within each sector and zone; e.g., l,2,3, *** For example, the designation SA-WWA-SDl would indi.cate a sampie in the SGS program (SA), consisting of well water (WWA), whi.ch had been collected in sector number 5, centered at 90' (due east) with respe<;t. to the reactor site at a radial distance of 3 to 4 miles off-site, (therefore, radial, distance* D). The number l indicates that this is sampling station #l in that particular sector *
    • '?
. I
 .-J
                                                                 .. _ --------------. -*-* ._---- --*-**---.~------.,. ----- - -

SAMPLING LOCA'rIONS 

                                . All 1986. sampling location's and specific. information about the individual locations are given in Table B-l. Maps B-l and B-2 show the locations of sampling stations with respect to the site.

TABLE B-1 STATION CODE STATION LOCATION SAMPLE TYPES 2S2 o.4 mi. NNE of vent. AIO,APT,IDM 2S3 700 ft. NNE of vent; fresh water holding tank WWA SSl 1.0 mi. E of vent; site access road AIO,APT,IDM 6Sl 0.2 mi. ESE of vent; observation .building area SOL 6S2 0.2 mi. ESE of vent; observation bµilding IDM 7Sl 0.12 mi. SE of vent; station personnel gate IDM lOSl 0.14 mi. SSW of vent; site shoreline IDM llSl 0.09 mi. SW of vent; site shoreline IDM' ll.Al 0.2 mi. SW of vent; outfall area ECH,ESB,ESJ", ESS,SWA lSAl 0.3 mi. NW of vent; cooling tower blowdown ESS discharge line outfall l6Al 0.7 mi. NNW of vent; south storm drain ESS discharge line 

 .-,  '                                4Cl            2.a     mi. ENE of vent                                                                                                 GAM 12Cl              2. 5 mi. WSW of vent; west bank of Delaware l:U ver                                                                     ECH,ESB,ESF, ESS,SWA 4D2            3.7 mi. ENE of vent; Alloway Creek Neck Road                                                                             IDM 5Dl            3.5 mi. E of vent; local farm                                                                                           AIO,APT,IDK, SOL,WWA lODl              3. 9 mi.. SSW of vent; Taylor's Bridge Spur                                                                            AIO,APT,IDJ!,SOL llDl              3.S.mi. SW Of vent                                                                                                     GAM l4Dl              3.4 mi. WNW of vent;. Bay View, Delaware                                                                                IDM J                                                                                                               54
 .. J l
    .**-t~.-...-_-.-:-:-_-.-~~------.--.:-*--*:-:*;*:-~~-::-::-~:*-::-:--:::--~~--.-.. -  ..-.~::-;---~=-:-~--....,-7"-*~~:---:--~-.,...-:...-~-- -~--.':--:~---~;;-:----;._-:----~.;~ -.---~-- - -    ";--*.*--*--~---- '":~-- :***~-,.-*-.;-*:-
  • STATION CODE TABLE STATION LOCATION s~1 (cont'd}
                                                                                                                                                                        .SAMPLE TYPES 2El            4.4 mi. NNE of vent; local farm                                                                                              FPV,IDM,SOL 3El            4.l mio NE of vent; loca.1 farm                                                                                              FPB,FPV,IDM, VGT,WWA 7El            4.5 mi. SE of vent; l mi. W of Mad Horse creek                                                                               ESB,ESF,ESS,SWA 9El            4.2 mi. S of vent                                                                                                            IDM llE2             SoO mi. SW of vent                                                                                                           IDM 12El             4*4 mi. WSW of vent; Thomas Landing                                                                                          IDM 13El             4.2 mi. W of vent; Diehl House Lab                                                                                           IDM l3E3             4.9 mi. W of vent; local farm                                                                                               Mr..K,VGT 16El             4ol mi. NNW of vent; Port Penn                                                                                              AIO,APT,IDM,SOL lFl            s.a     mi. H of vent; fort                         ~lfsborq                                                                AIO,APT,IDM,SOL lF2            7ol mi.. N of vent; midpoint of Delaware River                                                                              SWA 1F3            5o9 mi. N of                vent~        local farm                                                                         FPL,FPV 2Fl            5.0 mi" NNE of vent; local                              farm                                                                SOL 2F2            807 mi. NNE of vent; Salem SUbstation                                                                                       AIO,APT,IDM, RWA,SOL 2F3            800 mi. NNE of vent; Sal.em Water Company                                                                                   PWR,PWT 2F4            6.3 mi. NNE of vent; local farm                                                                                             MLK,SOL 2F5            7.4 mi.. NNE              of vent; Salem High School                                                                        !DH 2F6            7o3 mi. NNE of vent; Southern Training Center                                                                               IDM 2F7            5o7     m.i,. NNE of         vent~        local farm                                                                     ML&'.,SOL,VGT 3F2            5.l mi. NE of vent; Hancocks Bridge Municipal                                                                               IDM Bui.ldinq 3F3            8.6 mi.. NE of vent; Quinton Township School                                                                                IDM 4Fl            Sol mi. ENE of vent; local. farm                                                                                            FPL,FPV 5Fl            605 mi. E of vent                                                                                                           FPV,IDM,sor..

5F2 

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

STATION CODE TAELE B-1 .(cont'd) STATION LOCATION SAMPLE TYPES 6Fl 6.4 mi. ESE of vent; Stow Neck Road IDM 7F2 9.1 mi. SE of vent; Bayside, New Jersey IDM lOF2 5.8 mi. SSW of vent IDM llFl 6.2 mi. SW of vent; Taylor's Bridge Delaware IDM llF3 5.3 mi. SW of vent; Townsend, Delaware MI.I<, SOL ,.VGT l2Fl 9.4 mi. WSW of vent; Townsend Elementary School IDM l3F2 6.5 mi. W of vent; Odessa, Delaware IDM 

           .13F3   9.3 m+/-. w of vent; Redding Middle School,        IDM Middletown, Delaware 13F4   9.8 mi. w of vent; Middletown, Delaware        IDM 14Fl   5.5 mi. WNW of vent; local farm                  MLK,SOL,VGT 14F2 14F3 15F3 6.6 mi. WNW of vent; Boyds corner 5.4 ..mi. WNW Of vent; local farl!l 5.4 mi. NW of vent IDM FPV IDM 16Fl   6.9 mi. NNW of vent; C&D canal                   ESB,ESS,SWA 16F2   8.1 mi. NNW of vent; Delaware City PUblic School IDM lGl  10.3 mi. N of vent; local farm                   FPV
  • I 1G3 19 mi. N of vent; Wilmington, Delaware IDM 2Gl 12 mi. NNE of vent; Mannington Township, NJ FPV
  . J
   .--!       3G1  17 mi. NE of vent; local farm                    IDM,MLK,SOL,VGT lOGl  12 mi. SSW of vent; Smyrna, Delaware             IDM 16Gl  15 mi. NNW of vent; Greater Wilmington Airport   IDM
            -3H1   32 mi. NE of vent; National Park, New Jersey   IDM 3H3  110 mi. NE of vent; Research and Testing         AIO,APT,IDM,SOL Laboratory 3HS 25 mi. NE of vent; local farm                    FPL ,FPV           --*'*

--*--~ 

    .* :1
     *,                                             56

AJUIFICJAL l.SLA~~OCATIONS . ON SITE. SA MPl ING 

                 \
          .j Cl
 . _*: 1
        - -~                       57
      . 'l
      .    ~-
                                                  . -* -~~ ----

MAP S-2 0FF-SITE SAMPLING LOCATIONS ARTIFICIAL ISLAH D 58

APPENDIX C DATA TABLES 

 . i i;
   .I i

l i .. I _._.,...--------.---.-.-------*---***'"<--- ---*----:.-------- -------*----.----- -. ___________ !. *. - - -,---- - .. ; - - - - - - - * . - - - - - - * - * - - .. - - - - - - - --- -- --- --***--* --~ --- --.-*- -- *****-* - * - .* .,. *** - -* * - * : -

  • DATA TABLES Appendix c presents the analY.tical results <Jf. the 1986 Artificial Island Radiological Environmental Monitoring Program for the period of January l to December 31, 1986 *.

TABLE OF CONTENTS TABLE NO. TABLE DESCRIPTION PAGE ATMOSPHERIC ENVIRONMENT AIR PARTICULATES 1986 Concentrations Of Gross Alpha Emitters ******************** 64 c-2 1986 concentrations of Gross Beta Emitters.c:1****o*o*cio******oo* 66 C-3 1986 Concentrations of Strontium-89 and Strontiwn-90 and Gamma Emitters in Quarterly Composites *******************.* 68 AIR IODINE C-4 1986 Concentrations of Iodine~l3l ************* ~ **************** '10 DATES C-5 1986 Sampling Dates for Air Samples **************************** PRECIPITATION C-6 1986 concentrations of Gross Alpha and Gross Beta Emitters and Tritium ** Cl * * * * * *

  • Clo.., e Cl. Cl * *
  • Cl. c *
  • o . Cl. e * * * *
  • Q e *** o **** " *** o o 77 1986 concentrations of Gamma 11:mitters *******************.******* '18 DIRECT RADIATION TBERMCLUMINESCEN'r DOSIMETERS 1986 Quarterly TLD Results *** Cl Cl o Cl Q c '° o = Cl o
  • c o G:I
  • c * "
  • o
  • c. c Cl
  • Cl* Cl o Cl o o " c 79
     * °:-j
... I
        *;                                1986 Monthly TLD Results                   0
  • Cl 0 0 0 0 0 0 0 0 _o Cl 0 C) Cl g C> Q 0 0 c 0 °0 Cl e
  • 0 0 Cl 0 e S!J .o G 0 Cl 0 0 so_
  .. '  .  ~

..- i 

       . i
     *.*.1
       **i 1

i 61 

             - .------.--*----- ~------*** -~ - - - --*-- - - .--~--- .--r-*-      *-------~ ~~---:-*-- .~----~.-*----~...-~           -- ---- --    ~*----- - - - .-* .. ~-*** ****- ~ ... *****- ~  --;- -, **--*. w , - ....... - - - - - * **-

TABLE NO. OA'l'A 'l'ABLES ' (cont 1. c1. ) TA5LE DESCRIPTION PAGE 

                                      'l'ERRES'l'RIAL ENVIRONMENT MILK C-10   1986 concentrations of Iodine-131 **************.****************           82 C-ll   1986 Concentrations of Strontium-89 and Strontium-90 ***********            83 c-12   1986 Concentrations of Gamma Emitters **************************            84 C-13   1986 Sampling Oates for Milk Samples ***************************            88 WELL WATER C-14   1986 concentrations of Gross Alpha and Gross Beta Emitters; Potassium-40 and Tritium..................................            90 C-15   1986 concentrations of Gamma Emitters **************************
  • c-16 1986 Concentrations of Strontiwn-89 and Strontiwn-90 in.

Quarterly *composites.~************************************ 94-POTABLE WA'l'ER C-17 1986 concentrations of Gross Alpha and Gross Beta Emitters; _ Potassium-40 and-Tritiwn.................................. 95 C-18 1986 Concentrations of Gamma Emitters ************************** 96 C-19 1986 Concentrations of Strontium-89 and Strontiwn-90 in Qua.i:-terly composites ..**.... *-* .....*..*...........*........ 97 FOOD PRODUCTS* C"."20 1986 concentrations of Gamma Emitters in VegetalJles ************

  • 98 c-21 1986 Concentrations of Gamma Emitters in Game and Meat ********* 99
 .~
  • . ~

FODDER CROPS c-22 1986 concentrations of Gamma. Emitters *********.**********.******* 100 62

DATA TABLES . ( cont. ' ¢i. ) .. TABLE NO. TABLE DESCRIPTION * *PAGE SOIL C-23 1986 Concentrations of Strontium-90 and Gamma Emitters ********* lOl AQUATIC ENVIRONMENT SURFACE WATER C-24 1986 concentrations of Gross Alpha Emitters ******************** 102 C-25 1986 Concentrations of Gross*aeta Emitters ***** ~*************** 103 C-26 1986 Concentrations of Gamma Emitters ************************** 104 C-27 1986 concentrations of Tritium in Quarterly Composites ******* :. lO;i EDIBLE FISH C-28 1986 Concentrations of Strontium~89 and strontium-90 and Tritium. o . o o . o o . o o e e o o o o a o a o o o o o o o o" ~. o o o . o o . Clo o o o . o . o o o o o 106 c~29 1986 Concentrations of Gamma Emitters ******************.******** 107 BLUE CRABS C-30 1986 concentrations of Strontium-89 and Strontium-90: Gamma Emitters and Tritium. o El * * * * * * * * * *a o * *

  • o o * *
  • o * * * * * . 0. e o 108 BENTHIC ORGANISMS
       .i C~3J.                1986 Concentrations of Gamma Emitters **************************                                                                                                              109 I

SEDIMENT C-32 1986 Concentrations of Strontium~90 and Gamma. Emitterso**O****o 110 

     -:...l SPECIAL TAE!LES i

LLDs C-33 1986 PSE&G Research corporation LLDs for Gamma Spectrometry **** 111 

      **.1 l

1.

')\>j 63
.:*1
         . --.-~..,. . --.-.---~-----;-------...... -- ~.~-:-------:- :---------.--.- --,.._,.,---- -------~-.- --:---*-----*-.-:~----------*--  *-*- ,. -,~*- --.-     ....... - ---, ..,_, - ,.,-: **:-'"":"""* ,... -~- - --.-* -- -- ---*---* *---** -* ---

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

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

                                                                                                                                              .:i, *.
                                                                                                                                                                                                                                                      - .... *-:~-J *.

I i TABLE C-1 j 1986 CONCENTRATIONS OF GROSS ALPHA EMITTERS IN AIR PARTICULATES 1 I Results in Unit5 of 10- 3 pCt/m3 :t i sigma I 

        .1 1

STATION ID 

      **1                                     MONTH*                      SA-APT-2S2                           SA-APT-651                             SA-APT-601**    SA-APT-1001     SA-APT-16El       SA~APT-lfl   SA-APT-ZFZ  SA-APT-3HJ   AVERAGE
        .]                                                                      1.7:t0.9                              2.2t0.8                             1. 7+/-1.1      2.6:tl. l        l.8:t0.8         1. 8+/-0. 8    2. l:t0.9   3.l:tl.1   2. l:tl.O j                                    JANUARY i                                                                      1.8tl.O                               1.8t0.9                             2.l:tl.1      1.9:t0.9         2.0:t0.8          ( 1.0       2.4tl.O     1. 7t0.8   1.8+/-0.8
         *1                                                                       <4.0 (1)                             l.4:t0.6                           2.0tl .0      1.3+/-0.8          1.7t0.7          1. 7:t0.8    1.8+/-0. 7    3. 2:tl.O  1. 9+/- 1. 3
     >j"'                                                                       1. 4:t0. 7                            1.9t0.8                               <0.9        l.6t0.9          l.6t0.8          1. 6+/-0. 8    1. 3t0. 7   l.4t0. 7   1.5+/-0.6 I
2. 8tl. 0  ?.4:t0.8 <0.9 1.9:t0.9 1. 7+/-0.9 2.0:t0.9 2.0:t0.8 1.8tl.O l.'9fl. 1
     *.:*1 "i

I FEBRUARY ( 1.0 l.3:t0.9 3.Jtl.6 1.3:t0.8 2.0:t0.9 1. 7+/-0.8 l.9:t0.9 <0.9 1.7+/-1.5 

        *1 l                                                                    2.0:t0.8                              2.9:t0.8                            1. l:t0.8     2.6:t0.9         2.6:t0.8         2.2:t0.9     2.0:t0.7    2. l:tO. 7 2;2:i:1. l "I. *~                                                                     l.3:t0.8                               l.6:t0.9                             ( 1.0       l.6:t0.9         2.6:t0.9         1.6+/-0.8      1. 7+/-0.8    1. O:tO. 6 1.5tLO*

l 2.4:t0.9 l.9:t0.8 1.6:tl.O 1.6+/-0.8 2.3:t0.9 1. 9:t0. 9 l.9:t0.8 2.4t0.8 2.0+/-0.7 

  ' * .. i
      ..1 MARCH                             2.7+/-1.0                               2.3:t0.8.                           2.6:tl. 3     2.6:to:8         3.0:t0.9         2.4:t0.8     2.6:t0.8    2.4+/-0.8    2.6+/-0.4
        ~j 0) 1.2:t0.8                                   <0.9:* .                         <1.0          <1.1             <0.8            <0.9         <0.9       1. l:tO. 7 1.0t0.3
      .j                                                                        2.4:t0.8                              2. 2:t0. 9-:                        . <1.0        2.8:tl.O         3.0:tl.O         2.0:t0.8     2.2:t0.8    2. l:tO. 8 2:211.2
                            &fl.
i. l.'8:t0.8 0.8:t0.6 1.3:tl.O 2.4:t0.9 2.3:t0.8 2.6:t0.9 1.6+/-0.li 2.3:t0.8 1. 9.i). 2 i APRIL 2.2:t0.8 2. l:t0.8 <1.0 l.3:t0.8. l.2:t0.8 1. l:tO. 7 l.6:t0. 7 1. 3:t0. 7 1. 5+/-0. 9 1*

j 0.9:t0.7 l.l:t0.7 <1.0 <0.8 l. l:t0.6 1.4:t0.7 l.6t0. 7 l.O:t0.6 1. l:til. 6 1* i l.8:t0.8 **t.J:tO. 7 1.8:tl.3 1.6:t0.9 1. 7+/-0. 8 2.0:t0.8 ( 1. 3 2. l:tO .8 1. 7:i:0.6 

     '*1                                                                        2.0:t0.8                               l.3:t0. 7 .                        l.7:tl.l      l.O:tO. 7        2.0:t0.8         1.6+/-0.8      2.2:t0.8    1. l:tO. 7 Lfii1L9
l MAY 2.2:t0.8 3. 3:tl.O 1. 8:tl. ~ 3.0:tl.O 3. 2:tl.O 2.3:t0.8 2.8:t0.9 1. 9:t0. 7 2.611.2
           !                                                                    . 22:t2 ll:t2 2l:t2 10:t2
                                                                                                                                                            <0.8
                                                                                                                                                            <3.0 (1) 19:t2 9.9:tl.6 21:t2 8.9:tl.6 19+/-2 12:t2 20:t2 10+/-2 20:t2 9.8:tl.6
                                                                                                                                                                                                                                              . 18114.

10+/-? :. 

        .!                                                                      7 .4tl.3                              6;8:tl.2                         '* 3.0:tl.4. 6.6:tl.3         6.6tl.1          5.3+/-1.1      7. ltl. 3   4.7:tl.O   5. 7+/-2.8
7. 2:tl.6 6.2:tl.6 2.6:tl.8 6.2:tl.~ <9.2 (1) 6.8+/-1.4 7 .4:tl.6 7 .4:tl.6 6.1+/-3.4 JUNE 12:t2 9.3:tl.6 <2.0 10:t2 8.2:tl.4 9,'Z:tl.6 9.6:tl.6 8.7+/-1.4 8;6+/-ui 2.0:t0.8 1.3+/-0. 7 ( 1.0 0.9:t0.7 1. 7:tO. e l.6:t0.B 1.910.8 1.6:t0. 7 1. !110. 8 2.8:tl.O 3.0:tl.O 2. l:tl.2 2.0:tl.O 2.2:t0.8 2.3:tl.O 2.4+/-0.9 2.4+/-0.9 2'.410.1 2.6:t0.9 <0.8 1. 4:tl. 1 l.9:t0.B 1. 2:t0. 7 l.8t0.8 1.h0.8 2.2:1;1>.8 Lhi.l
  • -*. - *-****-* ---~-*~ *--* ,_
                                           .. ____** ~~.
.~ *.. ~ :.:. **---*-*:. :..., ..':* _,_._: ~~.:*; .. .:... ..... :*~.'.' ..... ; ..-;'-... .

IABlE C-R (cont'd) 1986 CONCENTRATIONS Of GROSS ALPHA EMITTERS IN AIR PARTICULATES Results in Units of 10- 3 pC1/m3 t 2 sigma S!AHOM ID MONTH* SA-APT-252 SA-APT-liSl SA-APT-501** SA-APT-1001 SA-APT-16El SA-APT-lfl SA-APi-2f2 SA-APT-3H3 AVERAGE JULY R.2:1:0.1 A.h0.6 <2.0 2.2t0.9 2.4+/-0.8 2.4t0.9 2. l:tll. 8 1. 3t0. 7 1. 8+/-1. l i.8t0.9 2.0t0.8 <2.0 2.2t0.9 A.8:1:0.8 2.2:1:0.9 2.8:1:0.9 2.6t0.9 2.210.1 

                                                                     ~i.z                                         <A.2                                    2.3:1:1.4     1.6:1:0.9       1.7t0.9      1.ltO .8. 1.8:1:1.0         l.6tli.9   l. 6t0. 8
                                                                     <!. i                                    L4t0.8                                       <1.0         2.h0.9          2.8ti.O       <1.1        1.3t0.9            ( 1.1     1.6+/-1. 6 AUGUST                        1.6:1:0.9                                    n.2:1:0.8                                    <1.0         1.0t0.8         1.0t0.8      1.8t0.8      1.9tl.O           1. 7t!J.8  l.4t0.8 Z.6:1:LO                                      1.9+/-0.9                                      <2.0         1.8:1:0,9       2.6:1:0.9     <1.1        i.8:1:0.9         2.0tll.9   2.0t0.9 3.8:1:1.0                                     3.8:1:0.9                                    <1.0         4.0tl.O         4.6:1:1.0    4.4:1:1.0    2.6:1:0.8         1.6:1:0.8  3.2t2.6 2 .6t1.1                                     1. 2+/-0.8                                     <2.0         2.6t0.9         2.2+/-0.9      1.8+/-0.9      1. 7+/-0. 9         3.0:1:1.0  2.ltl.l 1.0:1:0.7                                         <O. 9                                  1. 9tl. l     2.0t0.8         3.6+/-0.9      1.4t0. 7     R.6:1:0.8         1.2:1:0.8  l.7t1.7 SEPTEMBER                     1.4t0.9                                      R.2t0.8                                      <2.0         1.4+/-0.9         1.9+/-1.0      1. 2+/-0 .8    1. 7t0. 9         1.6+/-0.9    1. 6+/-0 .6 all                                              2.4t0.8                                      3.0t0.8                                     1.9+/-1.2       3.1:1:0.9       2.9t0.8      2.7':1:0.8   3.2:1:0.8         2.4:1:0.8  2Jt0.9 IClll                                            2.0t0.8                                      1.6:1:0.8                                   l. 9tl. 6     1.6:1:0.8       1.6:1:0.8    1. 7t0.9     1.7:1:0.8         1.6:1:0.8  1. 710.3 L7t0.8                                       L9t0.8                                      2.2tl.3       2.0t0.8         1.2+/-0.~      2.0t0.8      1. 2+/-0. 7         2.0t0.8    1.8t0.8 OCfOBER                           <1. 2                                         <1.1                                     <1.0         <1.3            <l. 2        <1.1          ( 1.2            ( 1.2 1.lt0.7                                      0.8t0.6                                       <1.0        1. 7:!:0. 7     1.6:1:0.6    1.6:1:0. 7   1.6:1:0. 7        1.8t0.8    1.4t0. 7 2.0:1:0.9                                    2.0t0.8                                       ( 1.0       i.7t0.8         2.0t0.9      1.4t0.8      l. 2t0. 7         1.6:1:0.8  1. 6t0. 8 2.3:1:1.0                                    2.4t0.9                                     3.3+/-1.6       1.8:1:0.8       1.9t0.8      1. 7t0 .8    1. 9:1:1.0        1.9t0.9    2.2tl.O l.2t0. 7                                     1.4t0.8                                     2.8+/-1. 6      1.2+/-0.8         2. ltO. 9    1.5t0.8        <0.8            2. lt0.8   1.6+/-1..3 NOVEMBER                      3.7:1:1.l                                    3.lt0.9                                     l.8+/-1. 2      3.b0.9          4.0tl.O      4.!tl.l      3.6:1:1. l        3.2tl.O    3.3tl.4 I                                                             1.7tll.9                                     1.2+/-0.8                                     2.2:1:1.3     1.1:1:0.8       L4t0.8       1.6+/-0.8      1.6+/-0.8           1.6t0.8    1.5t0 .'7 L9t0.9                                       2.6t0.9                                       <l.0        1.8+/-0.9         1.8t0.8      2.7tl.0      1.2:1:0.8         2.4:1:1.0   l. 9tl. 2
                                                                 <29 (1)                                       i.8t0.9                                    3.7+/-1.7       2.h0.8          2.2:1:0.8    1. 8t0. 9    2.0t0.9           2.6t0.9    2.3+/-1:.3 DECEMBER                       L2t0.9                                       1.-tt0.8                                   2.0tl.2         <1.0          1.6:1:0.8      ( 1.0        <1.0              <3.6 (1)  1. 3:1:0. 7 2.9:1:!..0                                   2.7+/-1.0                                     2.0tl.3       2.2t0.9         2.4t0.9      2.0t0.9      2. l:tO. 8        2.6t0.9     2.410.7 2.1:1:1.0                                    2. lt0.9                                    <20 (l)       2.6:1:1.0       R.9t0.8      1.910.8      1.8:1:0.9         2.6:1:0.9   2.lt0. 7 2.0:1:0.a                                    2.Zt0.9                            '*,
2. ltl.3 2.4:1:0.9 2.610.8 1. 2+/-0. 7 L4t0.8 . 1.010. 7 1.811.}

AVERAGE 2.9:1:7. l Z.6:t6.-t 1. 8:1:1. 4 2.7:t6.9 Z.8:1:6.0 2.6t6.1 Z.7t6.Z 2.h6.l Grand AveragQ l.6t6.9 v Sampl1n~ dates can be found ~n Table C-6. vv Results by Teledyne isotopes. (A) High iLD due to 1ow samp~e vo~ume. Result not included ijn any a111arage5.

II 

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

l 

  . '\

I I i TABLE C-2. 1986 CONCENTRATIONS OF GROSS BETA EMITTERS IN AIR PARTICULATES Re~ults 1n Units of 10- 3 pC1/m3 :t 2 sigma 

 .I                                                                                                                                                                                                    STATION ID i

I MONTH** SA-APT-ZSZ SA-APT-6Sl SA-APT-501** SA-APT-1001 SA-APT-16El SA-APT-lfl SA-APT-ZFZ SA-APT-3H3 AVERAGE 

       .I I
         !                                                                                                                                                                          25t3       3Z:t3                              28:t3       26t3        28t3       32t3         28+/-5
    *I                                                JANUA~Y                              Z6:t3                                       Z7:t3 I                                                                                 29:t3                                       27:t3                                        26t3       28:t3                              27:t2       14tZ        27:t3      Z5:t3        26+/-9
  .*j                                                                                     32:t12 (1)                                   l9:t2                                        20+/-3       2Zt3                                20:t2      20t3        22t2       28t3       . 22t6
   .     '                                                                                 2l:t3                                       20+/-2                                         22t3       24:t3                               22:t3      17t2        19:t2      18:t2        20+/-5 29+/-3                                        28+/-3                                         29t3       29:t3                               30+/-3       32t3        29:t3      24+/-3         29+/-4
    .i.I
   . !!                                                FEBRUARY                            17tZ                                        15+/-3                                         19t3       19+/-3                              '18t2        16t2        14t2       13t2         16+/-4
      *I 30t3                                        32+/-3                                         29t3       36t3                                30:t2      33t3        32:t2      27t2         31+/-6
     *.1 16:t3                                       14+/-3                                         17t3       18t3                                17t3       16+/-3        13t2       15+/-2         16t3 1                                                                                                                                                                                       24:t3                               24:t3      22+/-3        24t3       24:t3        2~+/-3 i                                                                                    28t3                                        24+/-3                                         23:t3

. MARCH Z5t3 Z2:t2 24:t3 26+/-3 22tZ 25t3 26t3 20t2 24+/-4 13:tZ 13t2 17t2 16t3 13tZ 16tZ 15tZ 17tZ 15+/-3 I ()) 24tZ Z4t3 21+/-3 24t3 2Zt3 22t2 2lt2 19tZ 22+/-4 ()) 20t2 21t2 24t2 22+/-3 l 23:t? ~3tZ ZO:t3 24+/-3 23:t2 i 

      *1                 .                             APRIL                                16:t2                                       13t2                                         17t3       lO:tZ                               12:t2     16t2        13t2       12t2          14+/-6
   .~i                                                                                  9.4+/-2.3                                      7.6t2.2                                         10+/-2     9.0:t2.3                         8.6tZ.O       8.0t2.3    8.0t2.2      llt2       8.9t2.3 19+/-3       22+/-3                               ZO:t3      18+/-2        12t3       20t2          18t6
    *1   j 19:t2 24t3 16:t2 2l:t2                                        23t3       2lt3                                2l:t2     19+/-2      . 21t3       16t2          2lt5
 *:.1                                                                                                                                                                                                                                                     20+/-3       22t2          23+/-3 MAY
  • 23+/-3 Z4t3 23+/-3 26:t3 24+/-3 23+/-3
        .i                                                                               350:t8 .                                    340+/-8                                           20t3     330+/-8                             370:t8       350+/-8       340+/-8      330t8        300+/-230
 .;*;"                                                                                   270+/-7                                       260t7                                        170tl0 (1)  260+/-7                             240+/-7        270t7       260t7      260t7        260t22'
  .: I
     *1J                                                                                 170+/-6                                       180t6                                        140+/-10      180t6                             160+/-6        180+/-6       180+/-6      130+/-6        160+/-40
    **:                                                                                  170+/-6                                       160+/-6                                        140t10      170:t7                            200+/-27 (1)   160+/-6       160+/-6      190t7        160+/-34 I

JUNE 200t6 180:t6 160tl0 190t6 160+/-6 190+/-6 180+/-6 170+/-6 180+/-29 3lt3 26t3 . 27t3 30+/-3 29t3 35t3 26t3 31t3 -29t6 . 32t3 34+/-3 28+/-3 34t3 34+/-3 30+/-3 36t3 37+/-3 .33+/-6 27t3 6.7tl.9 26+/-3 24:t3 25t3 24+/-3 23+/-3 . 24t3 :z211~ 

    .I
    .i
      *' ~
     .i

_., .*..... * * .'I

  • t I*
                                                                                                                                     '. {'
. ~ . **:.... ~.* ..-~.* ..~..' ..... -* ... . *1 *.:~~ **L. *- . ..... __ , :: :*...,*' ..... : * *-*- ~-. ~ ::. .t:".. **:

TABLE C-2 (cont'd) 1986 CONCENTRATIONS OF GROSS BETA.EMITTERS IN AIR PARTICULATES Results in Un~t~ of 10-3 pCt/m3 :t Z sigma STATIOff ID MONTH* SA-AP1"-2SZ SA-APT-liSl SA-APT-liDl** SA-APT-1001 SA-APT-16El SA-APJ-lfl SA-APT-ZFZ SA-APT-3H3 AVERAGE JULY Z9:t3 24t3 Z7:t3 3lt3 31+/-3 Z4:t3 24+/-3 Zli:t3 Z7:t6 30+/-3 26+/-3 20+/-3 30+/-3 28+/-3 30:t3 31+/-3 Z7:t3 Z8:t7 26:1:3 24*31 27t3 24+/-3 24+/-3 Z4:t3 27+/-3 24:1:3 25:t3 21::1:3 24t3 26+/-3 26+/-3 26:t3 2Zt3 22+/-3 Z4:t3 Z4t4* AUGUST 22+/-3 2Z:t3 ZZt3 2l:t3l 24+/-3 20tZ 23+/-3 19+/-3 22+/-3 36+/-3 33t3 30:t4 32t3! 33+/-3 3Z:t3 3h3 28:t3 32+/-4 28t3 26:1:2 21+/-3 24:t3 Z6:t3 28+/-3 27+/-3 2Zt3 25:t5 20t3 "!6:t3 24+/-3 20:1:3 ZO:t3 ZO:t3 18+/-3 19:t3 ZO:t5 23tZ 22:t2 23+/-3 22:t2 24:t2 26+/-2 24+/-3 24:t3 Z3t2 SEPJEMBU 26:t3 26:t3 28+/-4 26t3 26:t3 28:t3 26:t3 Z6:t3 Z6:t2 30:t3 3Zt3 30t3 30:t3 32:t3 29:t3 26:t3 28:t3 30:t4 

                      ©ii                                                    22t3                                    20:tZ                          Z6t3            24+/-3              2h2            Z4:t3     23+/-3          19:tZ        22+/-5
                       ~

28ii:3 :ll1:t3 Z4:t3 28t31 28+/-3 27+/-3 28:t3 36:t3 Z9:t1 OCiOBER *21:t3! ll8t2 19:t3 18+/-3 19:t3 19:tZ Hl:t3 ZZ:t3 19+/-3 19:t2 20:tZ lli:tZ 20:1:2 20:tZ 18+/-2 2C:tZ ZO:i:Z 19+/-4 26:t3 Z7:t3 25+/-4 26:t3 26+/-3 26:t3 21i:t3 20+/-3 26:t4 39:t3 40t3 38:t4 36:t3 34+/-3 38:t3 38:t3' 38*3 38+/-4 24+/-31 22:t3 26:t3 21:t3 23:t3 . 24:t3 23:t3 2613 23+/-3 NOVEMBU ll7:t31 lli:tZ 16:1:3 !4:t2 16:t:Z 16:t2 i6:t2 20:t3 1614 22+/-3 24:t3 26:t3 26:1:3 2Z:t2 24+/-3 23+/-3 24:t3 24:t3 28:t3 27:t3 26:t3 28:t3 Z6:t2 28+/-3 26+/-3 32:t3 28+/-4 

                                                                            <90 (Z)                                  29+/-3                           36:t4           23+/-2              26:t3          26:t3     30+/-3          27:t3        28:t:8
  • DECEMBER 20:t3l 2l:t2 23:t3 18:tZ 19:tZ 20:tZ 22+/-3 16:t7 (1) 20:t3 29:1:31 Z9:t3 30:t4 28:t3 29+/-3 Z6t3 Z7:t3 26:t3 28+/-3 31i:t3 36:t3 99:t49 ( 1) 36+/-3 32:t3 33:t3 33+/-3 Z9:t3 33+/-6 i 26+/-2 28+/-3 27:t3 29:1:3 25:t2 27tl 29.t3 Z6:t] Z7:t3 AVERAGE 45:tR30 otZ:t120 3!:1:60 44:!:130 40:U20 43:030 4b!20 4hUO 6rilo4 A11eril!Je 4hlio
                                                   ~ Samp]tng dates can be found In iab1e C-6.
                                                  ~c Result$ by ieledyne isotopes.
                                                 ~1! Due to low sample 1101ume, resuit not tncluded in any 1verage1.

2 High LLD due to 1ow samp1e ~oUu!ll@. Result not tnc~ude~ tn any ~~erages. 

                       ,. * '**---**~*~"~*- ~-'* - "' '~- *** ' ' * ' ' " r ** "** .,..

TABLE C-3 . 1986 CONCENTRATIONS Of STRONTIUM-89* ANO STRONTIUM-90 AND GAMMA EMITTERS** IN QUARTERLY COMPOSITES Of AIR PARTICULATES Results In Units of 10- 3 pCl/m3 +/- 2 sigma STATION IO COLLECTION PERIOD Sr-89*** Sr-90*** Be-7 Ru-103 Ru-106 Cs-134 Cs-137 Ra-226 Th-232 SA-APT-2S2 12-30-85 to 03-31-86 <0.4 <0.3 64+/-5 <0.4 <3.1 <0.6 <0.6 ( 1.0 <Z.2 03-31-86 to 06-30-86 96+/-7 8.8+/-0.8 <7.7 9.8+/-0.9 18+/-1 <1.8 <2.6 06-30-86 to 09-29-86 89+/-6 <0.5 <4.4 <0.6 <0.4 <l.O <l. 7 09-29-86 to 12-29-86 66+/-6 <0.6 <5.9 <0.5 <0.7 <l.2 <2.7 SA-APT-6Sl 12-30-86 to 03-31-86 <0.4 <0.2 66+/-5 ' <0.3 <4 .1 <0.6* <0.4 ( 1.1 ( l. 9 03-31-86 to 06-30-86 *- ..: 77:tli 7.8+/-0.6 4.0:tZ. l 9.3+/-0.8 17+/-1 <l. 3 ( 1.6 06-30-86 to 09-29-86 88:tli <0.3 <4.3 <O .Ii <0.4 <0.3 ( i .2 09-29-86 to J2-29-86 66:tli <0.3 <6.3 <0.6 <0.6 <1.0 <2.1 m O> SA-APT-601 (1) 12-30-85 to 03-31-86 <2.0 <0.3 86+/-8 <0.8 <6.0 <0.6 <0.6 <9.0 (2) 03-31-86 to 06-30-86 110+/-12 9.2+/-1.3 <7.0 8.4+/-1.1 18+/-2 <10 (2) 06-30-86 to 09-29-86 89+/-11 <1.0 <8.0 <l.O ( 1.0 <10 (2) 09-29-86 to 12-29-86 - 80+/-6 <0.6 <3.0 '<0.3 <0.4 <6.0 (2) SA-APT-1001 12-31-86 to 04-01-86 <0.4 <0.3 71+/-5 <0.4 <4.7 <0.6 <0.3 ( 1.0 <2.3 04-01-86 to 07-01-86 88+/-6 8.7+/-0.7 <7.0 9.ilt0.9 17+/-1 ( 1.6 <2;4 07-01-86 to 09-30-86 76:tli <0.6 <4.3 <0.6 <0.4 ( 1.0 ( 1. 2 09-30-86 to 12-30-86 60+/-4 <0.6 <2.7 <0.5 <0.4 <0.7 ( 1.6 

*i

.'1 

   .,'                                   !!                      .. ***         /: .
       . .... . .          .. .... **- - '. .... ~ ... .:, .....

I TABLE C-3 (cont'd)* 1986 CONCENTRATIONS Of STRONTIUM-89* AND STRONTIUM-90 AND GAMMA EMITTERS** IN QUARTERLY COMPOSITES OF AIR PARTICULATES Results In Units of 10- 3 pCl/m3 :1: 2 sigma STATION ID COLLECTION PEMIOD Sr-89*** Sr-90*** Be-7 Ru-103 Ru-106 Cs-134 Cs-137 Ra-226 lh-232 SA-APT-16El 12-31-86 to 041-01-86 <I!. 41 <0.3 64:1:4 <0.4 <3.9 <0.4 <0.4 ( 1.0 (I. 6 l 04-01-86 to 07-01-86 83:1:!5 1.6:1:0.6 4.2:1:2.1 8.411:0.8 16tl ( 1.4 '( i .6 1 01-01-86 to 09-30-86 83tli <0.3 <4.2 <0.6 <0.4 <0.'11 *< 1.1 J J 09-30-86 to 12-30-86 64t4 (0,3 <2.6 <0.4 <0.4 <0.6 <1. l I I l l SA-APT-lfl .! 12-30-86 to 03-31-86 <0.6 <0.3 66:1:6 <<C. n <4.6 <0.6 <0.6 l.Zt0.6 <2.2 03-31-86 to 06-30-86 86:1:6 8.8+/-!1. 7 8.3t3.3 lOtl 17tl ( 1.4 <2.3 06-30-86 to 09-29-86 79:1:6 <<0.4 <4.6 <0.6 <0.5 <0.9 1. 7+/-1.0 09-29-86 to 12-H-186 64tE <0.2 <3.6 <0.6 <0.4 <0.8 <l. 3 Cll co SA-APT.:.2f2 .., AZ-30-85 to 03-31-86 <G.3 <0.2 63:11:~ <<lli.3l <Z.8 <0.6 <0.3 <0.3 <L2 03~31-86 to 06-30-86 80:1:6 9.0tG.8 <7.2 lOti Htl <1.1 <2.3 06-30-86 to 09-29-86 78t6 <0.6 <3.0 <0.6 <0.4 <1. R <2.2 09-29-86 to iZ-29-86 6h6 <<0.6 ( 1.6 <0.4 <0.4 <L 1 <LB SA-AP1f-3H3 

                           'Contiro])

12 6 to 03-31-86 <O.:ll <0.2 64t4 <0.31 <3.9 <0.4 <0.4 <0.9 (l, l 03-31-86 to 06-30-86 83t6 7.6t<<l.li 4.0tl.9 9.2:1:0.7 17tl <0.3 ( 1.1 06-30-86 to '09-29-86

  • 90t7 <0.1 <7.6 (0,6 (0,6 <1. R <2.1 09-29-86 to lZ-29-86 64+/-6 ((),6 <6.8 (0,3 (0,6 ( 1.3 ( 1. 9 AVERAGE 76tU u Sr-89 results are corrected for decay to &ample stop dmts.
                     =* AJl ot~er ganma emitters searched for were <LLD; typlc~I llDs ar~ given In Table C-33.

aaa Management audit anaUyses, ~ot required by Techolca~ specAflcilijons or by specific conmitments to Joe al off ic iii Iii. (1) Results by Veledyne Isotopes. 

                    <<Z) Not analyzed by Te]edyne isoto~es.

r--*~-'- . . '--*'. . -* *--.. * - -* * . . . . ... *.* I 

     ~1 l; .

l*_i. 

     *1
    ,j                                                                                               TABLE C:-4
 *.1
 .!      I 1986 CONCENTRATIONS OF IODINE-131* IN FILTERED AIR Results 1n Units of 10- 3 pCt/m3 t Z sjgma STATION ID
                          *MONTH**        SA-AIO-ZSZ      SA-AI0-651         SA-AI0-6Dl*** SA-AIO-lODl     SA-AI0-16El  SA-AIO-lfl SA-AIO-ZFZ SA-AI0-3H3 AVERAGE JANUARY           <19            <16                <ZO           <33              <ZZ         ( 9.3      <Z4        <16
                                             <14            <Z6                <20           <14              <17         ( 8.0      <14        <13
                                            <140 (1)        <13                <20           <23              <18         <22        <17        <22 I                                   <17            <23                <20           <27              <18         <16        <17        <16
     *1 I                                   <16            <16                <10           <11              <26         <16        <22        <29 i
      .1 I

FEBRUARY <Zl <Z4 <20 <23 <18 <21 <19 <16 I <19 <10 <10 <11 <14 ' <17 <11 <16 

   *J                                        <16            <41                <30           <13              <28         <30        <21        <13 I                                    <16            <Z4                <10           <28              <20         <18        <14        <17
j
       .\

i 0 MARCH <Z6 

                                           . <16
                                             <19
                                                            <Zl
                                                            <17
                                                            <14
                                                                               <30
                                                                               <10
                                                                               <20
                                                                                             <14
                                                                                             <26
                                                                                             <17
                                                                                                              <14
                                                                                                              <20
                                                                                                              <19
                                                                                                                          <19
                                                                                                                          <16
                                                                                                                          <19
                                                                                                                                     <ZZ
                                                                                                                                     <18

( 11 

                                                                                                                                                <U
                                                                                                                                                <18
                                                                                                                                                <18
      .1
    .J                                       ( 13           <16                <10           <13              <12         <16        <20        <16 j

APRIL <18 < 8.7 <40 <19 <22 <18 <26 <20 

     .!                                      <16            <20'               <20           <21              <16         <18        <17        <14 i!                                     <19
                                             <16
                                                            <30

( 9.9 

                                                                               <30
                                                                               <40
                                                                                             <18

( 16 

                                                                                                              <Zl
                                                                                                              <13
                                                                                                                          <17
                                                                                                                          <23
                                                                                                                                     <39
                                                                                                                                     <13
                                                                                                                                                <12
                                                                                                                                                <16 j

1 MAY <20 <16 <40 <16 <26 <20 <26 <22

I
        !                                    310t34         310t32             280t60        310t29           300t32      320t36     270t32     320t32   300t37
   **!                                       230t30         180t28             610t220 (2)   180t28           190t29      220t28     220t28     230t30   210t46 oj                                          8ltl4         66t16              73t16         60tl7             70t18      76t16       73tl8     65t16    69tl7 1

I 48tZO <32 <60 46t20 <390 (1) 42t23 62t22 64t20 48t20 

       !i
       *,                  JUNE                26tll         33t13             <30           <28              <28          32tl6     <30        (3)

J <16 <22 <40 <29 <19 <18 <20 <16 .. .- 

.. j                                         <17            <22                <20           <14              ( 8.9       <28        <21        <19 .

( 17 <14 <30 <14 <18 <14 <22 <20 I

,1

..... j

lABlf C-4 (cont'd) 1986 CONCENTRATIONS Of IODINE-131* IN FILTERED AIR Re5ults in Units of 10- 3 pCi/m3 +/- 2 sigma SJAHOU rn lllONJH** SA-Al0-2S2 SA-AR0-551 SA-AI0-501*** SA-AI0-1001 SA-Al0-16El SA-AIO-lfl SA-AI0-2f2 SA-AI0-3H3 AVERAGE JULY <24 <A4 <20 <26 <20 <19 <26 <l8 

                              <22            <U             <30            <16             <21             <18       <20        <16
                              <20            <!4            <20            <22             <19             <16       <30        <17
                              <19            <!2            <20            <1l             <13             <20       <16        <20 AUGUST         ( 9.4          <H             <30            ( 9.9           <28             <14       <18        <15
                              <26            <n9            <20            <22             <23             <12       <21        <15
                              <14            <Il6           <20            <30             ( 8.0           <21       <lO      . <24
                              <U             <18            <30            <19             <lJ             <23       <!6        <18
                              <16            <12            <20            <14             <13             <20       <iii       <16 SEPTEMBER     <22            <24            <30            <21             <27             <23       <17        <20
                              < 9.1          ( 7.7          <20            <26             <16             <19       <21        <22

..;ii <26 <24 <20 <H If-' 

                                                                                           <25             <33       ( 11       <12
                              <18            <32            <20            <14             <25             <13       <22        <19 OCIOBER       <20            <10           <20             <36             <20             <21       <11        <17
                              <R4            <H            <10             <14             ( 9.0           <16       <22        <18
                              <23            <H            <30             <22             <31             <33       <26        <19
                              <18            <A9           <20             <H              ( 8.6           <20       <30        <20
                              <16            < 9.6         <20             <26             <14             <12       ( 8.5      <18 NOVEMBER       <20            <Ali          <20            ( 19             <15             <20       <24        <15
                              <21            <28           <10            <21              ( 17            <17       <231       <26
                              <!9            <Ui           <30             <21             <H              <16       <14        <18
                              < lOOO (1}     <17           <10            <19              <21             <28       <25        <21 DECEMBER      ( 9.2          <18           <20             < 8.1 *         <12             <13       <19        ( 120 0)
                              <22            <16           <10            <19              <16             <21       <22        <18
                              <20            <H            ( 1000 ( 1)     <20             <R3             <16       ( 1. 9     ( 17
                              <23            <2!           <10             <29             <AB             <29       ( 36       <30
                   ~ I-131 results are corrected for decay to sample stop date.
                  ** Sampling date$ ~an be ffound ~~ Table C-6.
               *** Results by Te]edyne Isotopes.

ll) High LLD due to lo~ sample volume.

2) High uncertainty due to low samp]e volume. Result not included i~ any averages.
                ~3) No results due to faul~y sampiing assembly.

                  .. :~ ...... ~.. _* ... ~:.:.:....:..~~~ ... '_.: ._ *...:..:.. .. _          ' .. * **--" ****- "' ... , ; '. * .,.., * *: o >' '**~
  • M,o/ ... i - . *"*' ... .. .. *.... :.:. *. "***-*** . , ..

I. 

        *I
)

i 

          .,l
         *l i'

i TABLE C-6 1986 SAMPLING DATES FOR AIR SAMPLES j I l. 1* STATION ID MONTH zsz 6Sl 601 1001 16El lfl ZFZ 3H3

1 JANUARY lZ-30-86 lZ-30-86 lZ-30-86 JZ-31:-86 lZ-31-86 lZ-30-86 lZ-30-86 12-30-86 "i to to to to to to to
                !                                                                                           to                                                                                                                                      01-06:...86 J

I Ql-06-86 01-06-86 01-06-86 01-06-86 01-06-86 01-06-86 01-06-86 ii 01-06-86 to 01-06-86 to 01-06-86 to 01-06-86 to 01-06-86 to 01-06-86 to 01-06-86 to 

                                                                                                                                                                                                                                                  . 01-06-86 to I

01-13-86 01-13-86 01-13-86 01-14-86 01-14-86 01-13-86 01-13-86 01-13-86 

       .i
               !                                                                                    01-13-86                                     01-13-86                01-13-86         01-14-86                  01-14-86  01-13-86  01-13-86    01-13-86 to                                             to                to                  to                     to        to        to           to
       *.]                                                                                          01-14-86*                                    01-Z0-86                01-Z0-86         01-Zl-86                  01-21-86  01-20-86  01-20-86    01-20-86 I
          .J                                                                                      1  01-20-86                                     01-20-86               01-20-86         01-Zl-86                  Ol-Zl-86  01-20-86  01-20-86    01-20-86 to                                             to                to                  to                     to        to        to            to II                                                                                   01-27-86                                      01-27-86              01-27-86         01-28-86                   01-28-86 01-27-86  01-27-86    01-27-86
  . *. *1
                '                                                                                                                                                                                                                       01-27-86    01-27-86 .
     . *)                                                                                            01-27-86                                      01-27-86              01-27-86         01-28-86                   01-28-86 01-27-86
                                            ..;z                                                                                                                             to                  to                     to        to        to            to
           .j                                                                                               to                                             to r

(\) 02-03-86 02-03-86 02-03-86 02-03-86 02-03-86 OZ-03-86 02-03-86 02-01-86* 

     .* .i                                                                             FEBRUARY      02-03-86                                      OZ-03-86              OZ-03-86         02-03-86                   02-03-86 02-03-86  02-03-86    02-03-86
         .i                                                                                                 to                                             to                to                  to                     to        to        to            to
          ..I.,                                                                                      OZ-10-86                                      02-10-86              OZ-10-86         OZ-11-86                   02-11-86 OZ-10-86  02-10-86    02-10-86
     *, J
    . *,I l                                                                                        !>2-10-86                                     02-10-86              02-10-86         OZ-11-~6                   02-11-86 02-10-86  02-10-86    02..:10-86 to                                            to                to                  to                     to         to       to            to .*
        .1     ,I                                                                                     02-18-86                                     02-18-86              02-18-86         OZ-19-86                   02-19-86 02-18-86  02-18-86    02-18-86
          .I                                                                                          OZ-18-86                                     OZ-18-86              02-18-86          OZ-19-~6                  02-19-86 02-18-86  02-18-86    02-18-86
        '.I                                                                                                                                                                   to                  to                     to        to        to           th ; .                   ( ..

to to 

     .         :I                                                                                     02-24-86                                     02-24-86              02-24-86          02-26-~6                  02-25-86 02-24-86  02-24-86    02-24-86 j
      .. ~           .                                                                                                                                                                                               02-25-86 02-24-86  02-24-86     02-24-86 I                                                                                    02-24-86                                     02-24-86              02-24-86          02-26-86
        *:i                                                                                                  to                                             to                to
  • to to to to to
       .~J                                                                                            03-03-86                                     03-03-86               03-03-86         03-03-86                 "03-03-86  03-03-86 03-03-86     03-03-86
       .;j                                                                                                                                         03-03-86               03-03-86         03-03-86                  03-03-86  03-03-86  03-03-86    03-03-86 MARCH          03-03-86                                                                                                                                            ta* *
    .. 1                                                                                                     to                                             to                to                  to                     to        to        to
    *;;'J
           *1 03-10-86                                     03-10-86               03-10-86         03-11-86                  03-11-86  03-10-86  03-10-86    03-10-86
-:*" :; 03-10-86 03-10-86 03-10-86 03-11-86 03-11-86 03-10-86 03-10-86 03-10~86
     ., .l to                     to        to        to            to
        .i                                                                                                   to                                           .to                 to
,I 03-17-86 03-17-86 03-17-86 _03-1. 03-18-86 03-17-86 03-17-86 OJ:.. lJ-86
         *1
       .j

                                                                                                                ,*.,.~.:~ ... ~....:..:--...:, . .. .:.::.::..::~ .. *...: .~:.::.., ~ ...
  ~: ~,:.. .* ~ .:i. ....*.-....:.......~.*~- *. *~*;..,,_.. ~        . ~- <.** J ,. .* "" .*.* (  " ... :... ,                                                                                      ;   ..... '

iI I I. TABLE C-6 (cont'd) 1986 SAMPLING DATES FOR AIR SAMPLES STATION ID MON!H 252 651 6Dl 1001 16El lf! 2F2 3H3 MA!ICH 03-17-86 03-U-86 03-17-86 H-nll-86 03-18-86 03-17--86 03-17-86 03-17-86 to to to to to to to to 

                                                                                     @3-24-86                                         03-24-86                                             03-24-86              03-25-86         03-26-86  03-24-86    03-24-86   03-24-86 03-24-86                                         03-24"-86                                            03-24-86              03-26-86         03-26-86  03-24-86    03-2'4-86  03-24.-86 to                                                  to                                           to                    h                to         to         to         to 03-3R-86                                         031-31-86                                            03-31-86              04-01-86*        04-01-86  03-31-86    03-31-86   03-31-86 APIUL                 <<>3-:U-86                                        03-31-86                                             03-31-86              04-01-86         04-01-86  03-31-86    03-31:-86  03-31-:86 to                                                 to                                            to                    to               to         to         to         to 04-07-86                                         04-01'-86                                            04-07-86              04-01-86         04-07-86  04-01'-86   04-07-86   04-07-86 04-07-86                                         04-07-86                                             04-07-86              0~-0?-86         04-07-86  <<>4-0?-86   04-07-86'  04-07-86 Q:.o                                                to                                           to                    to               to         to         to         to o4-a4-86                                         ID4-!C-86                                            04-14-86              04-16-86         04-16-86  04-14-86    04-14-86   04-14-86
                           ~                                                         04-14-86                                         04-14-86                                             04-14-86              04-16-1116       04-16-86  04-14-86    04-14-86   04-14-86
                           ~                                                                  to                                                 to                                            to                    to               to         to         to         to 04-21-86                                         04-21-86                                             04-21-86              04-U-86          04-21-86  04-21-86    04-18-86*  04-21-86 04-U-86                                          04-21-86                                             04-21-86              04-21-86         04-21-86  04-21-86    04-21-86   04-2*i-86 to                                                 to                                            to
  • to to to to to 04-28-86 04-28-86 04-28-86 04-29-86 04-29-86 04-2!1-86 04-28-86 04-28-86 MAY 04-28-86 04-28-86 04-28-86 04-29-86 04-29-86 04-28-86 04-28-86 04-28-86 to ta to to to to to to Oli-06-86 Oli-05-86 06-06-86 06-0li-86 06-06-86 06-06-86 06-06-86 06-06-86 06-06-86 l!lli-06-86 06-06-86 Oli-06-86 06-0!i-86 06-06-86 O!i-O!i-86 O!i-06-86 to to to to to to to to Oli-12-86 06-12-86 06-12-86 06-12-86 06-12-86 Ol:i-12-86 06-12-86 05-12-86
 \

.~ i 06-12-86 Olii-ll2-86 O!i-12-86 06-12-86 O!i-12-86 06-12-86 06-12-86 06-12-86 to to to to to to to to 06-19-86 06-19-86 06-14-86* 06-19-86 O!i-19-86 06-19-86 06-19-86 06-19-86 

 '                                                                                   06-19-86                                         06-19-86                                             O!i-19~86             Oli-H-86         06-19-86  Oli-19-86   06-19-ij6  06-19-Bfi to                                                 to                                            to                    to               to        t.9         t9         tq Oli-27-86                                        06-27-86                                             06-27-86              Oli-27-86        Oli-U-86  Ofi-i1-116  Q§-U,.11~  O!i-27-'~g Oli-Z7-86                                        06-Z?-86                                             06-U-86               Oti~U~96         C16-n-e6  (lij,.iHlfi o~-n~a~    Qij-27:-ij~

to to to ~o to to to to I 06-02-86 06-0Z-86 06-02-86 06-02-86 06-28-86* 06-02-86 06-02-86 06-02-86 1 

             **::_; _,L_.:~~-::..:.;: .. ~ =.! **:.&.:.. . . h .... *........... --*-~--:~-.:_:, ..  ;... ... - **.,. ....:...J.-'..*.- -,.~.r::,,, ,;, .... ***.!; **- **                  ' ..... ,. *****~- **- .. , ..                ****-** . *-- ... *-* .....

l j I 

                                                                                                                                                                                                                                                                                            \.

II 

         .i j                                                                                                                                                                        TABLE C-6 (cont'd)

I

1
         .j                                                                                                                                                                 1986 SAMPLING OAT~S        FOR AIR SAMPLES I

1* j STATION ID MONTH 252 65~ 601 1001 16El lfl 2F2 3H3 JUNE 06-02-86 06-02-86 06-02-86 06-02-86 06-03-86 06-02-86 06-02-86 06-02-86 i" to to to to to to 

                                                                                                                                                                                                                                    . 06-09-86 to         to r.
           *1 06-09-86                                        06-09-86               06-09-86       06-09-86                         06-09-86                               06-09-86    06-09-86
                                                                                                                                                                                                                                                                                          )

06-09-86 06-09-86 06-09-86 06-09-~6 06-09-86 06-09-86 06-09-86. 06-09-86 1 to to to to to to to to - I 06-16-86 06-16-86 06-16-86 06-16-86 06-16-86 06-16-86 06-16-86 06-16-86 I J i 06-16-86 06-16-86 06-16-86 06-16-86 06-16-86 06-16-86 06-16-86 06-16-86 

              '                                                                                                to                                              to             to                to                            to          to                          to         to i                                                                                      06-23-86                                        06-23-86               06-23-86       06-23-86                         06-23-86   06-23-86                    06-23-86    06-23-86 i
       '.j                                                                                          06-23-86                                        06-23-86               06-23-86       0~-23-86                         06-23-86   06-23-86                    06-23-86    06-23-86
              !                                                                                                to                                              to             to                to                            to          to .                        to         to II
          . -~
                             ..,,                           JULY 06-30-86 06-30-86 06-30-86 06-30-86 06-30-86 06-30-86 07-01-86 07-01-86 07-01-86 07-01-86 06-30-86 06-30-86 06-30-86 06-30-86  '

06-30-86 06-30-86 I 

       .t                    ~                                                                                 to                                              to             to                to                            to          to                          to         to .
  . -3                                                                                              07-07-86                                        07-07-86.              07-07-86       07-07-86                         07-07-86   07-07-86                    07-07-86    07-07-86 I

j 07-07-86 07-07-86 07-07-86 07-07-86 07-07-86 07-07-86 07-07-86 07-07-86 j to to to to to to to to 

          **I                                                                                       07-14-86                                        07-16-86               07-16-86       07-16-86                         07-16-86   07-14-86                    07-16-86    07-14-86
           .j                                                                                       07-14-86                                        07-16-86.              07-16-86       07-16-86                         07-16-86   07-14-86                    07-16-86    07-14-86
         '1I                                                                                                   to                                              to             to                to                            to .        to                          to        *to
       .. ,                                                                                         07-21-86                                        07-21-86               07-21-86       07-21-86                         07-21-86   07-21-86                    07-21-86    07-21-86 i

i 07-21-86 07-21-86 07-21-86 07-21-86 07-21-86 07-21-86 07-21-86 07-21-86 1I to to to to to to to to l 07-28-86 07-28-86 07-28-86 07-29-86 07-29-86 07-28-86 07-28-86 07-28-86 

       .*Ij                                                 AUGUST                                  07-28-86                                        07-28-86               07-28-86       07-29-86                         07-29-86   07-28-86                    07-28-86    07-28-86
     .. i'                                                                                                     to
  • to to to to to to to
         .  *~

08-04-86 08-04-86 08-04-86 08-04-86 08-04-86 08-04-86 08-04-86 08-04-86. 

      .I 08-04-86                                        08-04-86               08-04-86       08-04-86                         08-04-86   08--04-86                   08-04-86    08-04-86
        ~j_,                                                                                                   to                                              to             to                to                            to          to                          to         to 1

08-11-86 08-11-:86 08-11-86 08-12-86 08-12-86 08-11-86 08-11-86 08-11-86 

     ~ ..t                                                                                          08-11-86                                        08-11-86               08-11-~6                                        08-12-86   08-12-86*'*                 08-11-86    08-11-86
   .... i
  • ' .. *.**1 to to to to to to to
     ***\
  . ...:1                                                                                           08-19-86                                        08-19-86               08-19-86                                        08-19-86   08-19-86                    08-19-86    08-18-86
     *<1!
      *..,j
       ;,j

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

TABLE C-6 (cont'd) 1986 SAMPLING DATES fOR AIR SAMPLES S'H"ATION ID flCOtHH 252. 6Sl 6Dl lODl l6El lfl 2.fZ 3H3 AUGUST 08-19-86 08:..19-86 08-19-86 08-H-86 08-19-86 08-19-86 08-19-86 08-18-86 to to to to to to to to 08-2.6-86 08-26-86 08-26-86 08-26-86 08-26-86 08-26-86 08-26-86 08-2.6-86 08-2.ii-86 08-26-86 08-2.6-86 08-26-86 08-2.6-86 08-26-86. 08-2.6-86 08-2.6-86 Q:o to to to to to to to 09-02-86 09-02-86 09-02-86 09-03-86 09-03-86 09-02-86 09-02-86 09-02.-86 SEPTEMBER 09-02-86 09-()2-86 09-0Z-86 09-03-86 09-03-86 09-02.-86 09-02.-86 . 09-02.-86 to to to to to to to to 09-08-86 09-08-86 09-08-86 0~-08-86 09-08-86 09-08-86 09-08-86 09-08-86 09-08-86 09-08-86 09-08-86 09-08-86 09-08-86 09-08-86 09-08-86 09-08-86 to to to to to to to to 09-16-86 09-16-86 09-16-86 09-16-86 09-16-86 09-16-86 09-16-86 09-1~-86 

   ~

09-16-86 09-16-86 09-16-86 09-16-86 09-16-86 09-16-86 09-16-86 09-16-86 IO!I to to to to to to to to 09-22-86 09-22-86 09-2.2-86 <<19-22-86 09-2.2.-86 09-22-86 09-22.-86 09-2.2.-86 09-22-86 09-22-86 09-22.1-86 09-22-86 09-2.2.-86 09-2.Z-86 09-22.-86 09-22.-86 to to to to to to to to 09-29-86 09-29-86 09-29-86 09-30-86 09-30-86 09-29-86 09-29-86 . 09-2.9-86 OCTOBER 09-29-86 09-29-86 09-2.9-86 09-30-86 09-30-86 09-29-86 09-2.9-86 09-29-86 to to to to to to to to 10-06-86 l0-06-86 10-06-86 i0-06-86 10-06-86 10-06-86 10-06-86 10-06-86 10-06-86 no-06-86 10-06-86 10-06-86 10-06-86 10-06-86 10-06-86 10-06-86 to to to to to to to to 10-14-86 10-14-86 10-14-86 10-16-86 10-16-86 10-14-86 10-14-86 10-14-86 10-14-86 . 10-14-86 10-14-86 10-16-86 10-16-86 10-14-86 . 10-14-86 10-14-86 to .to to to to to lo t'o 10-20-86 10-20-86 10-20-86 !0-20-Si> 10-20-86 A0-20-116 10-20-96 lO-i0-.1i6 Uh?0~86 tO-tlHl6 HH!!l-8!> U!-Z0-86 10-Z0-86 10-20-86 10-Z0-86 10-20-86 

!I                                             to                                              to         ~Q               to                 to        to          to           to
  • ~

l0~2Mti to=-n=s6 H)-U:-@li ll)-2~-86 10-28-86 10-27-86 10-27-86 10-27-86 RG-27-86 Ull-27-86 i0-27-86 10-28-86 10-28-86 10-27-86 10-27-86 10-27-86 to to to to to to to to 11-03-86 U-031-86 11-03-86 H-03-86 11-03'-86 11-03-86 11-03-86 11-03-86

I 

     .j j
     *I
      *1 I                                                                               TABLE C-6 (cont'd) l                                                                       1986 SAMPLING DATES FOR AIR SAMPLES J
j STATION ID
     ~j I   MONTH                 252                             651            6Dl            ~ODl             16El       lfl      2F2      3H3 l
  --1
  • 11-03-86 11-03-86 11-03-86 11-03-86 11-03-86 11-03-86 11-03-86 11-03-86 NOVEMBER
\ to to to to to to to to 11-10-86 11-10-86 11-10-86 11-10-86 11-10-86 11-10-86 11-10-86 11-10-'86

. :*J1 

     **.                     11-10-86                       11-10-86          11-~0-86       11-10-86 .       11-10-86  11-:10-86 11-10-86 11-10-86
.    *-1                          to                              to             to              to               to        to       to       to
  *.:1                       11-17-86                       11-17-86          11-17-86       11-17-86
  • 11-17-86 11-17-86 11-17-86 11-17-86 11-17-86 11-17-86 11-17-86 11-17-86 11-17-86 11-17-86 11-17-86 11-17-86 J *' to to to to to to to to
  ;'i .                      11-24-86                        11-24-86         11-24-86       11-24-86         11-24-86  11-24-86  11-24-86 11-24-86 11-24-86                        11-24-86         11-24-86       11-24-86          11-24-86 11-24-86  11-24-86 11-24-86 Ii to 11-24:..86*

to 12-01-86 to 12-01-86 to 12-02-86 to 12-02-86 to 12-01-86 to 12-01-86 to 12-01-86 I DECEMBER 12-01-86 12-01-86 12-01-86 12-02-86 12-02-86 12-01-86 12-01-86 12-01-86 I

l. to to to to to to to to 12-08-86. 12-08-86 12-08-86 12-09-86 12-09-86 12-08-86 12-08-86 12-03-86*

1 12-08-86 12-08-86 12-08-86 12-09-86 12-09-86 12-08-86 12-08-86 12-08-86 to to to to to to to to

  • 12-16-86 12-16-86 12-16-86 12-16-86 12-16-86 12-16-86 12-15-86 Il 12-16-86 12-16-86 12-16-86 12-16-86 12-Ui-86 12:..16-86 12-16-86 12-16-86 12-16-86
     . -~

i to to to to to to to to * 

   *. :j                      12-22-86                       12-22-86         12-16-86*       12-22-86         12-22-86 12-22-86  12-22-86 12-22-86
         "{                   12-22-86                       12-22-86         12-22-86        12-22-86         12-22-86 12-22-86  12-22-86 12-22-86 I                        to                             to             to              to               to        to        to       to l                   12-29-86                       12-29-86         12-29-86        12-30-86         lZ-30-86 12-29-86  12-29-86 12-29-86
              *Reduced sampling period due to instrument malfunction.
             ** Start date was delayed by one day due to instrument malfunction at time of startup.

This required replacement of the air sampler. 

  . -~j I
  • 1986 CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMITTERS, AND TRITIUM IN PRECIPITATION TABLE C-6 STATION ID: SA-RWA-2F2 Results in Units of pCi/L +/- 2 sigma COLLECTION PERIOD ALPHA BETA TRI TI OM 12-31-85 to 01-27-86 <l. 6 <l.6 <140 01-27-86 to 02-25-86 <1.5 1.9+/-1.2 <130 02-25-86 to 03-31-86 <l. 6 4.4+/-1.4 <140 03-31-86 to 04-28-86 <0.3 3.7+/-0.8 <140 04-28-86 to 06-03~86 <0.3 lStl <140 06~03-86 to 07-01-86 1.J+/-Oo7 8.4:H.O <140 07-01=86 to 01~29*-86 <l.l 3.8:!::0.8 <140 07~29-86 to 09-03-86 1. 2:t:l.l 12+/-1 <130 09-03-86 to 09-30-86 0.9+/-0.5 3.8+/-0.8 <140 09-30-86 to 10-27-86 <l. 2 2.2+/-0.6 <140 10-27-86 to 12-01-86 0.6+/-0.6 3.5+/-0.7 <140
              ...                                     12-01-86 to                                             12-29~86                                         <l. 7                                             l.9:!::0.6               <130
              .' . ~
      .. *' **t  .i AVERAGE                                                                                                                                                    5.2+/-8.6
          *.**I w   * **     '
     .. . .:..       ~
   ' ._. ;: *.. *' ~

..  : . -~ I 

        ;       * 'i
.'. ;;.::! 77
.. *     -~ '
               . f
                .*    !-----~-~---
                                   .. **- .. -*~ ----;--.. --...-.,--;-*............-, o*-~--- ...... --.----.-------*-****~**-***--..--,*--.**----*** *-*-------- .. *----**- ---*- **-;- ....... - ---.,.- - --*-- --- ..  - *-**.------- - .  .. I

TABLE-C-7.

  • 1986 CONCENTRATIONS OF GAMMA EMITTERS* IN PRECIPITATION
                                                                             ~

STATION ID: SA-RWA-2F2 Results.in Units of pCi/L +/- 2 sigma. COLLECTION PERIOD Be-7 K-40 I-131 cs-137 Ra-226 Th-232 12-31-85 to 01.-27-860 Ol-27-86 to 02-25-86 35+/-12 <39 <2.4 <2.4 7.0+/-3.0 <7.2 02-25-86 to 03-31-86 71+/-21 <57 <4.7 " <2.9 <6.7 <12 03-31-86 to 04-28-86 64+/-15 <32 <2.6 <2.0 <4.6 <8.0 04-28-86 to 06-03-86 41+/-23 <81 7.4+/-3.5 4.8+/-3.0 <13 <21 06-03-86 to 07-01-86 54+/-13 <40 <3.4 <3.2 <6.4" <11 07-01-86 to 07-29-86 52+/-14 <42 <4.8 <3.2 <6.4: <ll 07-29-86 to 09-03-86 42+/-10 <25" <l.6 <0.8 <4.2 7.5+/-4.l 09-03-86 to 09-30-86 35+/-14 59+/-25 <3.8 <3.7 <7.7 ~14 09-30-86 to 10-27-86 36+/-12 <40 <3.4 <2.6 5.1+/-2.4 <ll 10-27-86 to 12-01-86 43+/-12 <41 <l.5 <2.l 4.8+/-2.7 <7.6 12-01-86 to 12-29-86 42+/-13 <29 <4.8 <2.0 <4.8 <7.4 AVERAGE 47+/-24

  • All other gamma emitters searched for were <LLDJ typical LLDs are given in Tal:>le C-33.

I **Not analyzed.due to insufficient pre~ipitation during sampling period. " i 78 

   -~~~        ___.._ . _ .

                                                                                    .  '. ~  .     . ....... .
  • TABLE c~e 1986 DIRECT RADIATION MEASUREMENTS - QUARTERLY TLD :RESUL'.l'.S .
                                                             .Rasul.ts in mrad/standard month*

(.Resul.ts by Teledyne Isotopes) JANUARY APRIL JULY OCTOBER STATION ID to to to to AVERAGE MARCH JUNE SEPTEMBER DECEMBER SA-IOM-2S2 5.3+/-0.3 4.4+/-0.2 5.2.:1:0.3 4.7+/-0.6 4.9+/-0.8 SA-IOM~5Sl S.l:!:0.2 4.0+/-0.3 4.9:t0.3 4.2:t:0.3 4.6:tl..l SA-IOM~6S2 5.3:!:0.3 4.3+/-0.2 5.4:t:0.2 4.6:!:0.3 4.9:t.l.l SA-IDM-7Sl 6.6+/-0.7 5.6+/-0.S 6.2+/-0.4 5.6:t:0.5 6.0+/-1..0 SA-IOM-lOSl s.a+/-o.5 5.0:t0.3 4.8:t0.2 5.1+/-0.3 5.2+/-0.9 SA-IOM llSl00 5.0+/-0.2 S.2:t:0.3 5.2:t0.3 4.7+/-0.3 5.o:to.s SA-IOM 402 00 5.0:1:0.2 4.9+/-0.4 6.7:t:l.8 5.1+/-0.5 5 .6:t;l..6 SA-IDM-501 5.5+/-0.2 4.6:1:0.l 5 .4::!:0.3 4.6+/-0.3 5.0:l:l..O SA-IOM-1001 5.4+/-0.4 5.0+/-0.3 5.7+/-0.5 4.8+/-0.4 5.2:!;0.8 SA-IDM-1401 5.4+/-0.6 4.5:1:0.2 5.5+/-0.3 4.9:1:0. 7 5.1:.1:0.9 SA-IDM-2El 5.6:.1:0~5 4.2:1:0.5 5.5+/-0.4 4.7+/-0.5 S.O:.l:l.3 SA-IOM-3El 5 .2:.1:0 .4 4.4+/-0.2 5.3+/-0.3 4.5+/-0.5 4~8:.1:0 .9 SA-IDM-9El 6.3+/-0.8 5.4+/-0.3 6.2:.1:0.5 5.7+/-0.9 5.9+/-0.8 SA-IDM-11E2 5.9+/-0.6 5.2:1:0.7 6.3+/-0.5 5.5+/-0.7 5.7+/-1.0 SA- IDM-l2El 5.7+/-0.5 4.8+/-0.3 6.0+/-0.4 5.4+/-0.8 5.5:t:J..O SA-IDM-13El 4.9+/-0.l 4.2+/-0.2 5.0:1:0.3 4. 3:t:O .4 4.6+/-0.8 SA-IDM-16El 5.5+/-0.2 4.8+/-0.5 5.6+/-0.3 5.0+/-0.5 5.2:!:0.8 SA-IOM-lFl 5.4:.l:0.5 4.3:1:0.4 5 .5:.1:0 .4 5~0+/-0.5 5. O:.l:l..l SA-IOM 2F2 00 4.5:1:0.7 3.6+/-0.3 4.4:1:0.3 3.7+/-0.3 4.0+/-0.9 SA-IDM-2F5 5.4+/-0.l 4.6:1:0.2 5.4+/-0.4 4.8+/-0.5 s.o+/-o.a SA-IOM-2F6 5.1+/-0.2 4.4+/-0.4 5.4:1::0.4 4.8:t0.2 4.9+/-0.8 SA-IOM-3F2 5.Sil.2 4.2:1:0.3 4.9:!:0.2 4.1:1:0.3 4. 7+/-1..2 SA-IOM-3F3 5.0+/-0.2 4.3:t:0.2 s.o:to.2 4.3:t:0.3 4.6:1:0o7 SA-IOM-5Fl 5.2:t:0.7 4.3:!:0.5 5.l+/-0.3 4.6:!:0.S 4.8:1:008 SA-IDM-6Fl 4.7+/-0.3 3 .6:1:0.,l 4.6:1:0.2 3.8:!:0.3 4.2+/-1.l SA-IOM-7F2 4.6:t0o2 3.4:1:0o2 4.3:1:0.2 3.5:1:0.1 4.0:Uo2 SA-IOM-10F2 5.7:1:0.5 5.1+/-0.4 5.9:1:0.3 5.l.+/-0.5 5.4:1:0.8 SA-IOM-llFl 5.0:1:0.5 5.2:1:0.4 5.8:1:0.5 5.3:!:0.6 5.5+/-0.6 SA-IDM-12Fl 5.7:!:0.3 4.7+/-0.3 5.7+/-0.l 4o9:!:0.4 5.2:!:1.0 SA-IDM-13F2 5.3+/-0.4 4.6+/-0.4 5.4:1:0.3 4.8+/-0.4 5.0:1:0.a SA-IDM-13F3 5.7+/-0.4 4.8+/-0.3 5.7:1:0.4 5.0:!:0.5 5.3:!:0.9 SA-IOM-13F4 5.7:1:0.2 4e6:1:0.S 5.6:1:0.3 4.9:1:0.5 5.2:1::J..l SA-IOM-14F2 5.3:1:0.l 4o5:1:0.4 5.5+/-0.4 5.1:1:0.1 S.l:!:0.9 SA-IOM-l5F3 6.0:1:0.5 .5.2:1:0.2 6.3:1:0.4 5.4:1:0.4 5~7:1:1.0 SA-IDM-16F2 5.2:1:0.1 4.3:1:0.2 5.4:1:0.3 4.S:t:0.4 4.9:!:1.0 SA-IOM-lG3 ~C~ 5.8:!:0.4 5.5:1:0.8 6.4:1:0.4 5.7:1:0.4 5.8:!:0.8 SA-IOM-3GJ. C 5.8:!:0.4 4.9:1:0.3 5.8:1:0.3 5.1:1:0.6 5.4:!:0.9 SA-IDM-lOGl ~ C~ 6.l:!:0.6 s.1:1:0.s 5.9:t:O.S 5.3:t0.5 5.6:1:1.0 SA-IDM-16Gl C 6.l.+/-0.6 S.3:1:0.5 6.3:1:0.6 S.8+/-0.7 5.9+/-0.9 SA-IOM~3Hl ~C~ 6.0+/-0.5 5.0+/-0.3 5.0+/-0.2 5o2:!:0.5 S.5:t:l.O SA-IDM-3H3 C 5.9:!:0.S s.o:t:o.2 5.9:1:0.3 5.2:1:0.s 5.5:1:0.9 AVERAGE 5.s:ta.9 4.6il.O 5.5:!:1.l 4.9:!:1.l

. ~-

Grand Average 5.l:!::l.3 ~ .. 

                 ~ The standard month (C) Control station
                                                            = 30.4        da.ys *
  • 79
                                                             \
         -----***,-- --.---*-.*--o-r,~~-~--*-~-;--*-.::;*-::'--~ *~~7*-~~":-~*-- -.--:.,.-**-*-.*- - . - .* °'**-~,-: *-~**      ..*  -- **- *-* - -- - . *-** ...... -- .. ***.--------~---*-*--**,.--... -

   ' ..I -* ---*-*-**-*~--- ---- .... ~ .

TABLE C-9 1986 DIRECT RADIATION MEASUREMENTS - MONTHLY TLO RESULTS Results in mrad/standard month* (Results by Teledyne Isotopes) STATION ID ' JANUARY FEBRUARY MARCH APRIL MAY JUNE SA-IDM-2S2 5.3+/-0.3 6.6+/-0.l 5.2+/-0.4 6.6+/-1.2 6.7+/-0.8 5.6+/-0.5 SA-IDM-5Sl 5.2+/-0.4 5.9+/-0.l 4.5+/-0.2 6.2+/-0.7 5.9+/-0.6 5.0+/-1.2 SA-IDM-6S2 5.6+/-0.4 6.4+/-0.4 4.9+/-0.5 6.8+/-0.5 6.3+/-0.4 5.9+/-0.5 SA-IDM-7Sl 6.5+/-0.6 7.5+/-0.7 6.0+/-0.7 7.7+/-0.6 7.3+/-0.6 7.0+/-0.9 SA-IDM-lOSl 5.9+/-0.6 6.8+/-0.2 5.4+/-0.5 7.4+/-0.7 6.9+/-0.6 6.4+/-0.7 SA-IDM-llSl 5.2+/-0.4 6.1+/-0.3 4.7+/-0.2 6.9+/-0.4 7. 7+/-1.0 6.0+/-0.9 SA-IDM-501 5.5+/-0.5 6.1+/-0.l 5.0+/-0.5 6.6+/-0.8 6.1+/-0.4 5.8+/-0.6 SA- IDM-1001 5.7+/-0.5 6.6+/-0.3 5.3+/-0.4 7.2+/-0.6 6.9+/-0.6 6.7+/-0.7 SA-IDM-1401 5.6+/-0.4 6.6+/-0.4 5. 5+/-1. 3 6.9+/-0.5 6.9+/-0.7 6.2+/-0.7 SA-IDM-2El 5.5+/-0.3 6.2+/-0.4 4.9+/-0.5 6.6+/-0.6 6 .7+/-1.0 5.6+/-0.6 SA-IDM-3El 5.5+/-0.5 6.1+/-0.3 4.7+/-0.1 6.5+/-0.5 6.4+/-0.6 5.2+/-0.8 

.'                                                           6.2+/-0.2        4.7+/-0.3      6.5+/-0.4    5.8+/-0.7   5.9+/-0.7 SA-IDM-13El        5.3+/-0.8 Q)             SA-IDM-16El       5.6+/-0.6      6.7+/-0.6        5.0+/-0.2      7.0+/-0.4    6.8+/-0.7   6.3+/-0.9 0              SA-IDM-lFl        5.7+/-0.3      6.4+/-0.6        5.1+/-0.3      6.9+/-0.6    6.5+/-0.6   6.3+/-0.8 SA-IDM-2F2        4.8+/-0.4      5.8+/-0.3        4.1+/-0.2      6.0+/-0.5    5.4+/-0.3   5.0+/-0.4 SA-IDM-2F6        5.9+/-0.6      6.6+/-0.5        5.0+/-0.6      6.8+/-0.6    5.9+/-0.5   6.0+/-0.9 SA-IDM-5Fl        5.5+/-0.6      5.9+/-0.3        4.6+/-0.3      6.5+/-0.5    6.1+/-0.4   5.6+/-0.7 SA-IDM-6Fl         5.0+/-0.3     5.7+/-0.1           (1)       5 .* 9+/-0.4  5.4+/-0.3  5.0+/-0.3 SA-IDM-7F2         4.3+/-0.3     5.4+/-0.3        3.8+/-0.3      5.5+/-0.7     5.1+/-0.4  4.5+/-0.7 SA- IDM- llFl     5.8+/-0.4      7 .0+/-1.0       5.5+/-0.5      7.4+/-0.6    7.1+/-0.9   6.5+/-0.6 SA-IDM-13F4        5.8+/-0.6     6.9+/-0.7        4.9+/-0.3      7.0+/-0.5    6.6+/-0.6   6.2+/-0.4 SA-IDM-3Gl (C)     5.5+/-0.2     6.3+/-1.0        5.3+/-0.4      7.4+/-1.5    6.8+/-0.8   6.1+/-0.4 SA-IDM-381 (C)     5.9+/-0.2     6.8+/-0.3        5.3+/-0.4      7.2+/-0.4     6.7+/-0.7  6.3+/-0.8 SA-IDM-383 (C)    6.3+/-0.6      7.4+/-0.4        5.6+/-0.3      7.6+/-0.6     7.3+/-0.6  6.6+/-1.0 AVERAGE            5.5+/-0.9     6.4+/-1.0        5. 0+/-1.0     6.8+/-1.1     6.5+/-1. 3 5.9+/-1. 2 I:

__-:_ **~--~L-."~ . :*,_ . . -. . ~e:.:. -* - ~:':*. I . . - . 

                                                                                   "p , **
                                                                                                                                                         ~ '*. '

i 1 l TABLE C-9 (COBlt 9 d)

  • .*1 1986 DIRECT RADIATION MEASUREMENTS - MONTHLY TLD RESULTS l Results in mrad/standard month*

(Results by Teledyne Isotopes) STATION ID JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER AVERAGE SA-IDH-282 -. 5.9+/-0.3 5.7+/-0.5 5.3+/-0.5 5.4+/-0.3 4.9+/-0.4 '7.1+/-0. 7 5.8+/-1.4 

*1                               SA-IDH-5Sl                                 5.5+/-0.4        5.9+/-0.7       4.9+/-0.7         5.3+/-0.3  4.6+/-0.3      6.2+/-0.5           5.4+/-1.2
   *I                            SA-IDH-6S2                                 6~1+/-0.5        6.1+/-0.4       5.5+/-0~4         5.7+/-0.4  4.9+/-0.5      6.6+/-0.6           5.9+/-L2 SA-IDM-7Sl                                 7.0+/-0.8        6.9+/-0.4       6.6+/-0.8         6.5+/-0.9  5.9+/-0.7      7.7+/-1.0           6.9+/-1.2, 1l                             SA- IDH-lOSl                               6.5+/-0.6        6.5+/-0.4       5.7+/-0.5         6.4+/-0.6  5.5+/-0.3      7.6+/-0.9           6 .4+/-1.4  I I

SA- IDM-llSl 6.4+/-0.6 6.1+/-0.5 5.0+/-0.2 5.4+/-0.3 5.0+/-0.l 6.9+/-0.9 5.9+/-1.8 i' SA-IDM-5Dl 6.2+/-0.5 6.0+/-0.7 5.5+/-0.5 5.5+/-0.5 4.8+/-0.4 6.5+/-0.6 5.8+/-1.l SA- IDH-lODl 5. 7+/-1.l 6.3+/-0.5 5.8+/-0.4 6.1+/-0.5 5.3+/-0.4 6.9+/-0.6 6.2+/-1.3 SA- IDH-1401 6.8+/-0.l 6.2+/-0.3 5.7+/-0.5 6.0+/-0.8 5.2+/-0.4 6.9+/-0.6 6.2+/-1.2 SA-IDM-2El 6.0+/-0.7 6.0+/-0.3 5.5+/-0.3 5.6+/-0.5 4.9+/-0.6 6.5+/-0.9 5.8+/-1.2 SA-IDH-3El 6.0+/-0.4 5.9+/-0.5 5.1+/-0.3 5.5+/-0.3 4:8+/-0.4 6.3+/-0.5 5.?+/-1.2 SA-IDM-13El 5.9+/-0.4 5.9+/-0.4 5.2+/-0.6 5.7+/-0.4 4.8+/-0.5 6.6+/-0.6 5. 7+/-1.2 

                  ~              SA-IDM-16El                                6.4+/-0.5        6.1+/-0.4       5.8+/-0.6         5.9+/-0.5  5.1+/-0.4      7.1+/-0.7           6.1+/-1.4 l}-<l

_SA- IDM-lFl 6.3+/-0.5 6.2+/-0.3 5.5+/-0.3 5.9+/-0.5 5.1+/-0.5 6.7+/-0.4 6.0+/-1.2 SA-IDM-2F2 ~-4+/-0.4 5.3+/-0.2 4.7+/-0.2 4.8+/-0.2 4.2+/-0.2 5.9+/-0.3 5.1+/-1.2 SA-IDH-2F6 6.0+/-0.6 6.1+/-0.3 5.6+/-0.3 5.6+/-0.3 5.0+/-0.5 1.-uo.6 6.o'+/-L3 

   '!                            SA-IDM-5Fl                                 6.1+/-0.3        5.9+/-0.2       5.5+/-0.3         5.6+/-0.4  5.0+/-0.3      6.4+/-0.6           5. 7+/-1.l SA-IDM-6Fl                                 5.6+/-0.3        5.3+/-0.2       4.8+/-0.3         5.0+/-0.3  4.3+/-0.2      6.1+/-0.5           5. 3+/-1.0 SA-IDM-7F2                                 5.0+/-0.3        4.9+/-0.l       4.2+/-0.2         4.6+/-0.3  3.8+/-0.2      5.5+/-0.6           4.7+/-1.2 SA-IDM-llFl                                6. 8+/-1. 0      6.7+/-0.4       6.2+/-0.8         6.2+/-0.5  5.6+/-0.5       7.2+/-0.8          6-5+/-1. 3 SA- IDM-13F4                               6.5+/-0.4        6.1+/-0.2       5.7+/-0.4         6.0+/-0.5  5.3+/-0.4      6.9+/-0.5           6.2+/-1. 3 SA-IDM-3Gl (C)                             6.7+/-0.5        6.6+/-0.7       6.1+/-0.4         6.3+/-1. 3 5.1+/-0.3       7.2+/-0.3          6. 3+/-1.4 SA-IDM-3Hl (C}                             6.7+/-0.9        6.7+/-0.4       5.6+/-0.6         6.0+/-0.5  5.4+/-0.2       7_.2+/-0.5         6.3+/-1.3 '

SA-IPM-383 (C) 6.9+/-0.5 6.9+/-0.4 6.3+/-0.8 6.5+/-0.3 5.9+/-0.4 7.4+/-0.6 6. 7+/-L 3 AVERAGE 6.2+/-1.0 f).1+/-1.0 5.5:1:1.l 5.7+/-1.0 5.0+/-1.0 6.8+/-1.l Grand Av~rng~ ~rQ!l.6 Ill The standard month * .3o.4 daye. 

                                  <<c> Control station U) TLD missing from field Jocat!on.

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

   *'\     .    -  -- . J      .

TABLE C-11 1986 CONCENTRATI0NS OF STRONTIUM-89* ANrr STRONTIUM-90 IN' MILK** Results in Units of pCi/L +/- 2 sigma STATION ID COLLECTION PERIOD Sr-89 sr-90 SA=MLK;,.,13E3 07/06-07/86 <0.9 1.9+/-0.3 SA~MLK~2F4 07/06~07/86 <0.8 l.St0.3 SA~MLK-2F7 08/03-04/86 <l.5 2.4+/-0.6 SA-MLK-5F2 07/05-07/86 <l.l 3.0+/-0.4 SA-MLK-llF3 07/07-08/86 <0.8 1.7+/-0.3 SA-MLK-l4Fl 07/06-07/86 <0.8 1.2+/-0.3 SA~MLR~3Gl 07/07=08/86 <0.9 2.7+/-0.3 {Control) AVERAGE :ic1:1::1.2

  • sr-89 results are corrected for decay to midpoint of collection period.
                                                  ** Management audit analyses, not required by Technical Specifications or by specific commitments to local officials.
  • .-~- '*
          -~ i
             *1
~ *.. .:. ~ *1                                                                                                                                                                                                                   i

.. ':.::*::':'.l 83 

          ...i
          . '~

___ .,.. __ . __, ___ ., _____ ~- ---- ... ~ ------*-* --.-...-;--v----*---------*** -*-- -.-,.......... -... -.**-*.---*-~:---:--*-**--**7--*<-*:-*--*-..---*-* ,- ----- --*-*-*--*.......

TABLE C-lZ 1986 CONCENTRATIONS OF GAMMA EMITTERS* IN. MILK' Results in Units of pCi/L :1: Z sigma .* STATION ID** NUCLIDE JANUARY FEBRUARY MARCH MONTHLY MONTHLY MONTHLY SA-MLK-13E3 Na-ZZ <3.4 <3.9 <4.0 K-40 1400:1:75 1400:1:79 1400:1:98 Mn-54 <Z.5 <3.4 <4.0 Zn-65 <1.Z <1.7 <10 I-131 <3.0 <Z.5 <4.7 Cs-137 <Z.7 <Z.8 <4.9 Ra-ZZ6 <5.9 <1.Z <9.4 SA-MLK-ZF4 (1) Na-ZZ <3.7 <5.6 <3.4 K-40 1400+/-74 . 1400+/-98 1400:1:76 Mn-54 <Z.5 <4.1 <Z.3 Zn-65 <5.9 <6.3 <6.9 I-131 <3.0 <3.8 <3.0 Cs-137 <Z.9 <4.6 <Z.7 Ra-ZZ6 <5.5 <7.4 <5.9 SA-MLK-ZF7 (2) Na-ZZ K-40 Mn-54 Zn-65 I-131 Cs-137 Ra-ZZ6 SA-MLK-5FZ Na-2Z <3.5 <2.Z K-40 1300+/-72 1300+/-81 1300:1:82 

                                                                                'Mn-64                                   <2.5                                          <3.3                                            <Z.7 Zn-66                                   <5.9                                          <9.1                                            <1.8 I-131                                   <3.Z                                          <3.8                                            <0.6 Cs-137                                  <2.9                                          <2.9                                            <3.6 Ra-Z26                                  <6.2                                          <1.7                                            <5.9 SA-MLK-11F3                                   Na-22                                   <4.6                                          <4.5                                            <3.6 K-40                                1300:1:90                                    1300:!:82                                         1300+/-74 Mn-54                                   <3.2                                          <Z.O                                            <Z.3 Zn-65                                   <8.7                                          <7.3                                            <5.9 I-131-                                  <3.3                                          <0.6                                            <3.3 Cs-137                                  <3.3                                          <3.7                                            <Z.9 Ra-226                                  <6.6                                          <6.8                                            <6.Z SA-MLK-14Fl                                   Na-22                                   <Z.4                                          <3.6                                            <3.5 K-40                                1300+/-81                                     1400+/-77                                            1400:t77 Mn-54                                   <3.8                                         <2.6                                             <3.Z Zn-66                                   <9.1                                         <6.9                                             <1.8 I-131                                   <4.7                                         <3.l                                             <4.7 Cs-137                                  <3.9                                         <Z.6                                             <3.7 Ra-Z26                                  <6.1                                         <S.6                                             <7.9 SA-MLK-361                                    Na-Z2                                   <4.Z                                         <6.Z*                                            <4.9 (Control)                                     K-40                                1300+/-92                                      1300:t9Z                                          1400:1:92 Mn-64                                   <3.Z                                         <3.S                                             <3.Z Zn-65                                   <8.7                                         <8.7                                             <8.Z
   .;.*                                                                          I-131                                   <3.1                                         <3.4                                             <3.6

- ,:*:j Cs-137 <3.3 <3.5 <3.3 0 Ra-226 <7.0 <7.0 <6.6 

    .-(                            AVERAGE                                       K-40                                1300+/-100                                    1400+/-110                                           1400:1:100 84
         - ---- -----------.--,- -- *-....,--..,*-~.7*-:-*-,-~----------~.--:--**-*-****-*-**-*-*r'.*~---~-~~----~-.,,.--..v.-,-~-*- ......-*-*-*-------- *----;--*.--,~---*: * -*---- * ** *- *--~-***-* * * '* *.

TABLE C-12 (cont'd.) 1986 CONCENTRATIONS OF GAMMA EMITTERS* IN MILK

  • Results in Units of pCIJL ~ 2 sigm~

STATION ID"'"' NUCLIDE APRIL MAY JUNE SEMI-MONTHLY SEMI-MONTHLY SEJfI-MONTHL Y SA-MLK-l3E3 Na-ZZ <4.9 <4.5 <4.6 <4.Z <4.9 <4. 5 . K-40 1400:100 1400+/-83 1300+/-76 1300+/-77 1300.:1:92 1400+/-79 Mn-54 <4.9 z. 9+/-1. 7 <2.8 <1.8 <3.IJ <1.4 Zn-65 <8.6 <7.4 <9.7 <7.3 <9.5 <8.3 I-131 <0.8 '<1. 9 <3. 9 13+/-Z 3.S:tZ.3 <4.4 Cs-137 <4.S <3.6 <3.6 <3.4 <l.6 <4.Z Ra-ZZ6 <8.6 <7.0 <7.4 <S.O <7.0 <6.Z. SA-MLK-Zf4 Na-ZZ <6.Z <4.4 <4.8 <4.6 <3.1 <4.6 K-40 1400:1:99 1400+/-77 1400:1:99 1400+/-92 1400+/-77 1400:1:93 Mn-54 <3.8 <LB <4.4 <3.5 <Z.5 <3.l 

                                                                   . Zn-65                            <11                        <6.9                          <8.8                            <8.7                      <6..6               <8;z I-131.                           <Z.3                     <3.4                          <3.5                            3Z.t3                      <l.5               <4.0 Cs-137                           <4.Z                    <4.2                           <3.0                            <3.8                       ~.z. g             <3.6 Ra-2Z6                           <9.Z                    <8.3                           <7.9                            <7.0                       <5.9               <6.Z SA-MLK-ZF7                       Na-2Z K-40 Mn-54 Zn-65 I-131 Cs-137 Ra-Z26 SA-MLK-6FZ                      Na-ZZ                             <2.8                    <4.5                           <4.0                         4.6:1:2.3                    d .* 6             <3.6 K-40                         1ZOO:t74                 1300:1:96                     1300+/-74                        13Cl0:1:76                   1200:s:94        1300:t7Z Mn-54                             <2.9                    <3.8                           <Z.9                            <3.S                      <4!.Q              <2.3 Zn-65                             <7.D                  <U                               <6.4                            <6.2                      <l*.a              <6.7 I-131 *                          <3.D                     <3.7                           <3.Z                           49:!:4                   7.M.T                <3.4 C:s-137                          <3.0                     <4.7                          <3.7                            <3.6                     5.W.4*            3.9:1.6 Ra-2Z6                           <7.6                     <6.6                          <7.7                            <7.7                       <3* .0i            <6.Z SA-MLK- l1F3                    Na-2Z                            <1.D                     <4.9                          <4.8                            <4.1                       <t.3-              <3. l K-40                         1400+/-77                  1400:t9Z                      1400:t97                      1300+/-83                       1ZOO:t:75*      1300:1:82 Mn-54                            <Z.3                     <3.1                          <4.6                            <1. 9                      <l.3               <3.l Zn-65                            <9.1                     <8.7                          <9.2                            11:1:6                     <3,7               <8.l I-131                            <3.9                     <3.7                          <3.5                            24+/-3                       <4.Z               <3.0 Cs-137                           <2.3                     <3.Z                          <4.3                            <3.8                       <l.8,              <3.3 Ra-ZZ6                           <6.3                    <7.4                           <7.8                            <6.7                       <1.L               <7.l SA-MLK-14F1                     Na-2Z                            <3.8                    <5.1                           <1.2                            <1.6                       <l.7               <4.9 K-40                         1300+/-94                 1300:t96                      1300+/-83                        1300:1:95                    140G.t76-        1:400:t97 Mn-54                            <1.1                    <3.6                           <2.8                            <3.8                       <Z.l'.t            <3.9 Zn-611                           <6.7                    <5.0                           <4,7                            <5.4                       <1.Z            (, lCI I-131.                           <4.4                    <3.2                           <2,8                            26:!:4                   4. 7~:1:.!Jl         <4.9
        ..                                                           Cs-137                            <Z.G                    <3.1                           <3.8                         . <4.1                      3.hl.T               <4.l
     - .....                                                          Ra-226                           <8.1                    <8.8                        7.3:!:4.3                          <7,9                     4.4:t.Z. 8<          <.8.2
     ,',">     ::!                    SA-MLK-3Gl                     Na-ZZ                             <4.8                    <3.5                           <4.8                            <5.5                       <4.7:              <4.8 (Control)                      K-40                         140Cl:!:93               1400:1:74                     140Cl:1:82                     14C!O:t97                    1300:!:&1.       ll.4ll0:1:93
Mn-54 <3.5 <2.6 <2.9 <3.l <C.Z* <3.7
         -. *:;                                                      Zn-65                             <8.i                    <6.7                           <4.8                         <11                          <8~&.               <.i,4
    . . ' :~                                                          X-131.                           <4,1                    <3.4                           <4.0                           65:t5                     7.4t-.L&             ,3,3
    ~

Cs-137 <-3.8 <Z.9 <Z.7 <4.2 <4.l ,3,9 

                  ,;                                                 Ra-ZZ.6                           <7.7                  !i.!i:tZ.9                       <7,Q                           <!LB                       di.i                t6.6
             ..                      AVERAGE                         IC-40                        1400:1:170              1400:d00                       1400:1:110                    1.300:1:100                   1:.100:18@       Jl4".CtO:i:100
           ",    .-~
.: .~:  .;'   ;' ..

i { '-.;.J.";1 

 ..     .*' .~";
  • -... :* rt .
                              -~*--,*--~..-.,-...-.~-~:---,---*-*--* **-*-**** ---:*r--~- * --**--:"'~*--*-.---_--;***-:-.- ----..*--*- -;-**-- ..-:-* -.- -.-** ----.:******* ,": ***~  -. -**- *.** ,. ** .. --* *

~ TABLE C-lZ (Cont'd;) 1986 CONCENTRATIONS* OF GAMMA .EMITTERS* IN. MILK Results in Units of*pCi/L :1: Z sigma STATION ID** NUCLIDE JULY AUGUST SEPTEMBER SEMI-MONTHLY SEMI-MONTHLY SEMI-MONTHLY SA-MLK-13E3 Na-ZZ <3.5 <5.0 <4.9 <3.0 <Z.1 <3.3 K-40 1400:1:75 1500+/-97 1400+/-96 1400:1:85 1400:1:78 1400:1:96 Mn-54 <Z.6 <3.8 <Z.8 <0.8 <0.7 <4.4 Zn-65 <5.4 <11 <8.0 <Z.1 <3.6 <9.7 I-131 <3.6 <3.3 <4.0 <Z.9 <3.1 <Z.8 Cs-137 <Z.7 <4.5 <3.9 <4.0 . 3. 7+/-Z.O <4.0 Ra-226 <5.9 <8.4 <6.6 <6.0 <8.8 <8.4 SA-MLK-ZF4 Na-ZZ <4.8 <3.7 <Z.9 <5.4 K-40 1300:1:92 1400+/-75. 1400+/-96 1500:1:96 Mn-54 <3.0 <Z.5 <4.1 <3.0 Zn-65 <9.5 <5.9 <9.0 <9.7 I-131 <4.0 <3.4 <0.7 <3.8 Cs-137 <3.8 <3.0 <4.5 <3.3 Ra-2Z6 <7.0 <5.5 <8.0 <7.0 SA-MLK-ZF7 Na-ZZ <3.7 <3.5 <4.5 <Z.6 K-40 1400:1:74 1300+/-73 1400+/-78 1400:!:78 Mn-54 <Z.6 <Z.5 <Z.6 <4.3 Zn-65 <6.7 <6.9 <8.1 <3.5 I-131 Cs-137 Ra-2Z6 - -- 

                                                                       <3.Z
                                                                        <3.Z 5.l:t:Z.8
                                                                                          <3.Z
                                                                                          <Z.7
                                                                                          <5.5
                                                                                                                          <3.Z
                                                                                                                          <3.2
                                                                                                                          <8.1
                                                                                                                                                <Z.3
                                                                                                                                                <3.7
                                                                                                                                               *<8.7.

SA-MLK-5F2 Na-22 <3.9 <4.9 <6.4 <3.Z <1.6 <3.9 K-40 1300:1:77 1300:t:92 .1300:1:95 .1300:1:72. 1ZOO:t91 1ZOO:t7 Mn-54 <0.7 <3.1 <3.9 <Z.Z <2.0 <LG Zn-65 <5.5 <8.2 <7.3 <6.4 <lZ <Z.l I-131 <4.1 <3.4 <4.3 <3.Z <Z.3 <4.6 Cs-137 <4.7 <3.9 <3.8 <Z.9 <5.1 <3.8 Ra-226 <7.1 <7.0 <7.Z <5.9 <7.3 <7.7 SA-MLK- llF 3 Na-22 <6.3 <3.Z <6.0 <5.0 <5.9 <4.4 K-40 1500:1:98 1300:1:78 .1400+/-98 1500+/-100 1300:1:96 1300:1:93 Mn-54 <3.6 <3.1 <Z.9 <3.Z <3.3 <3.1 Zn-65 <14 <9.5 <4.7 <9.0 <8.Z <8.5 I-131 <4.6 <0.6 <4.5 <4.7 <0.8 <3.8 cs..:137 <4.8 <4.0 <3.0 <3.7 <4.4 <3.6 Ra-226 <6.8 <7.3 <8.3 <8.Z <8.Z <6.6 SA-MLK-14Fl Na-22 <5.5 <4.8 <4.1 <3.9 <3.5 <3.3 IC-40 1400:1:80 1400:1:97 1400:1:77 1400+/-78 1400+/-75 1300:1:82 Mn-54 <3.3* <1.8 <3.1 <1.7 <Z.3 <3.1 Zn-65 <9.4 <11 <1.8 <9.3 <6.4 <8.8 I-131 <Z.l <3.7 <3.7 <4.4 <3.Z <3.6 Cs-137 <3.6 <4.0 <3.7 <Z.9 <2.7 <3.7 Ra.:226 <8.0 <7.5 <6.3 <8. 7 ' <6.Z <6.9. SA-MLK-3Gl Na-22 <3.9* <Z.9 <4.6 <4.5 <3.9 (3) (Control) IC-40 1300:1:73 1400:1:84 1300+/-83 1100:1:86 1300:1:92 

      **'                 Mn-54         <Z.5            <2.4           <Z.Z               <3.2                           <3.5
       ~

Zn-65 <6.9 <8.6 <6.3 <7.7 <9.0 I-131 <3.0 <3.7 <3.3 <3.3 <3.7 Cs-137 <Z.9 <3.Z <3.7 <3.8 <3.5 

 *   *,!                  Ra-226         <5.5           <7.5           <5.8               <6.6                           <7.0 AVERAGE         K-40        1400:1:160     1400:1:150      1400:1:100     1400:t:Z80                      1300:1:160              1300:!:170
       .~                                                       86
                                                                                .----  ----*-- - . -;---:- .. *~---,--***  -----*- *- *- *--,      -, __ --*-- -*- -**

  ... 'J TABLE C-lZ (cont'd.)

1986 CONCENTRATIONS OF GAMMA EMITTERS.* .IN MlLK'

  • Results in Units of pCi/L % Z sigma
               *.r*'                         ;_ ,**
 . . .  --**----~>-'; ...*. ~ *. :. **..           ** -.1 ** ~- ;. ** ** , * .' * * . *. *  **  * **.*****
                                                                                                                                     . TABLE C-13
  • 1986 SAMPLING DATES FOR MILK SAMPLES STATION ID MONTH 13E3 ZF4 6FZ llf3 14Fl 361 JANUARY 01-06-86 01-06-86 01-04-86 01-06-86 01-06-86 01-06-86 to
  • to to to to to 01-07-~6 01-06-86 01-06-86 01-07-86 01-06-86 01-07*-86 FEBRUARY OZ-03-86 OZ-OZ-86 OZ-01-86 OZ-03-86 OZ-OZ-86 OZ-03-86 to to to to to to .

OZ-04-8~

  • OZ-03-86 OZ-03-86 OZ-04-86 OZ-03-86 OZ-04-86 MARCH 03-03-86 03-03-86 03-01-86 03-03-86 03-0Z-86 03-03-86 to to to to to . to .

03-04-86 03-04-86 03-03-86 03-04-86 03-03-86 03-04-86 APRIL 04..,07-86 04-07-86 04-06-86 04-06-86 04-07-86 04-06-8"6 to to to to to to 04-08-86 04-08-86 04-07-86 04-07-86 0*4-08-86 04-07-86 O> 

       <<>>                                                                           04-ZZ-86                04-Zl-86                               04-Z0-86   04-Z0-86 04-Zl-86  04..:zo~a6 to                to                                     to         to        to        to 04-ZZ-86                04-ZZ-86                               04-Zl-86   04-Zl-86 04-ZZ-86  04-Zl-86 MAY                                             06-06-86                06-06-86                               06-04-86   06-04-86 06-06-86  06-04-86 to                to                                     to         to        to        to 06-06-86                05-06-86                               06-05-86   0~-05-86 06-06-86  05-06-86 06-19-86                06-19.:.86                             06-18-86   05-19-86 05-19-86  05-18-86 to                 to                                    to         to        to        to 06-Z0-86                06-Z0-86                               06-19-86   05-19-86 05-Z0-86  05-19-'86 JUNE                                            06-08-86                06-08-86                               06-07-86   06-09-86 06-08-86  06-09-86 to                to                                     to         to        to        to     ~ .

06-09-86 06-09-86 06-09-86 06-10-86 06-09-86 06-10-86 06-ZZ-86 06-ZZ-86 06-Zl-86 06-Z3-86 06-ZZ-86 06-Z3-'86 to to to to to to 06-Z3-86 06-Z3-86 06-Z3-86 06-Z4-86 06-Z3-86 06-24-86 

                                   *JULY                                            07-06-86                07-06-86                               07-05-86   07-07-86 07-06-86  07-07-86 to                 to                                    to         to        to        to 07-07-86                07-07-86                               07-07-86   07-08-86 07-07-86  07-08-86 01-'Zl-86               07-20-86                         *7-19-86         07-Zl-86 07-20-86  07-21-86 to                to                                    to          to       to        to 07-ZZ-86                07-21-86                                7-21-86   07-22-36 07-21-86  07-ZZ-86

  *j**'**-"*-<<'.!.~cc.:.:_.:o:_ --              -      --             . -*--*** .. '......~.*--****-*~.:*:.* ,::~ ..
 *1 1

I 1 TABlE°C-13 (co~t'd) 198~ SAMPLING DATE$ IF.OM MILK SAMPLES STATION IO MONTH R3U 2f4* fifZ 11f3 14f l 361 

  *i "1                                  AUGUST                                       H-0~-86                          08-03-86          08-03-86          08-02-86    08-04-86  08-04-86    08-03-86
 )                                                                                            to                        to                 to                to         to         to          to 08-IH!-86                        08-04-86        . 08-04-86          08-04-86    08-06-86  08-0fi-8,6  08-04-86
1

'J I 'i 08-R9-86 08-19-86 08-19-86 08-18-86 OB-18-86 08-18-86 08-'-19-86 

  .I to                        to                 to                to         to         to          to 08-20-86                         08-Z0-86          08-20-86          08-19-86    08-19-86  08-19-86    08-20-86 SEPTEMBER                                    09-08-86                                           09-08-86          09-07-86    09-0)-86  09-07-86    09-08-86.

to to to to to to 

      *,I                                                                           09-09-86                                           09-09-86          09-08-86    09-08-86  09-08-86    09-09-86 09-U-86                                           09-22-86          09-Zl-86    09-21-86  09-21-86     09-22-86
   *I.!                                                                                       h1                                           (to               to         to         to           to 09-23-86                                          O!ll-U-8(i        09-22-86    <<19-22-86 09-22-86     09-23-86 i1~

OCTOBER Ul-06-86 !0-06-86 10-06-86 !O-Oli-86 10-05-86 10-06-86 j to (to to to to to . RO-<<H'-86 A0-0}'-86 10-06-86 10-06-86 10-'-06-86 10-07-86 Uli-20-86 10-20-86 10-19-86 10-19-86 10-19-86 . 10-20-86 to to to to to to 10-21-86 10-2fi-86 10-20-86 10-20-86 10-20-86 10-21-86 NOVEMBU RHJJZ-86 H-09-86 11-01-86 U-02-86 11-02-86 11-0i-86 to fto to to to to

  • lll-O:lH!6 H-10-86 11-0Z-86 11-03-86 11-03-86 11-03-86 U-H-86 U-H-86 11-16-86 11-16-86 11-16-86 ll-l7-'86 tl:o to to to to to U-iS-86 U-ll.8-86 U-17-86 11-17-86 11-17-86 11-18-86 i DIECEMBU RZ-O'Jl-86 iZ-07-86 12-06-86 12-08-86 12-08-86 12-07'-86 i fto to to to to to l AZ-08-86 lZ-08-86 lZ-08-86 12-09-86 12-09-86 12-08.:.86 j
                                         "' Stat 1011 SA-MLK-21F4! termh!al:111tdl mHk production on September~ A, R986.
                                        "'"'Station SA-MlK-2f7 replaced stal:ton SA-MLK-2f4 on September i, R986.

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

TABLE C-14 1986 CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMITTERS, POTASSIUM-40 AND TRITIUM IN WELL WATER Results in Units of pCi/L +/- 2 sigma STATION ID RADIOACTIVITY 01-13-86 02-10-86 03-10-86 04-14-86 05-12-86 06-16-86 SA-WWA-2S3 Alpha <2.2 <l. 2 <l.6 <1.1 <l.O(l) <0.5 Beta 3.3+/-0.8 5.8+/-0.9 3.6+/-0.8 3.2+/-0.7 5.4+/-0.9 2.5+/-0.7 K-40 3.0+/-0.3 6.9+/-0.7 4.2+/-0.4 3.6+/-0.4 5.9+/-0.6 2.9+/-0.3 H-3 <130 <130 <140 <140 <130 <140 SA-WWA-5Dl 

     <O   Alpha                                         <3.7               <l. 4        <1.9       <0.8      <0.7 0                                                                                                                0.9+/-0.5 Beta                                          13+/-1               13+/-1         13+/-1       12+/-1      13+/-1     2.0+/-0.6 K-40                                    8.8+/-0.9                  13+/-1         15+/-2       15+/-2      14+/-1      12+/-1 H-3                                           <130               <140         <150       <140      <130      <130 SA-WWA-3El (control)

Alpha <2.9 <l. 4 <1.9 <0.9 <0.8 <0.8 Beta 8.5+/-1.0 9.5+/-1.1 8.1+/-1.0 8.8+/-1.1 8.4+/-1.0 2.5+/-0.6 K-40 17+/-2 9.3+/-0.9 9.6+/-1.0 9.9+/-1.0 9.1+/-0.9 7.6+/-0.8 H-3 <130 <140 <140 <140 <L~O <140 AVERAGE Alpha 

   '      Beta                                   8.3+/-9.7              9.4+/-7.2          8.2+/-9.4    8.0+/-8.9   8.9+/-7.6   2.3+/-0.6
**:'      K-40                                    9.6+/-14              9.7+/-6.1          9.6+/-11     9.5+/-11    9.7+/-8.2   7.5+/-9.l H-3

                              .  ~ I .

TABLE C-14 <<cont~d) 198~ CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMITTERS, POTASSIUM-40 AND TRITIUM IN WELL WATER Results in Units of pCi/L +/- 2 sigma STATION ID RADIOACTIVITY 07-14-86 08-11-86 09-15-66 10-14-86 11-10-86 12-15-86 AVERAGE SA...:wwA-2S3 Alpha 1.7+/-1.3 1. 6+/-1. 2 0.9+/-0.6 0.7+/-0.5 <1.3 . <l. 9 Beta 8.6+/-Ll 6.5+/-1.0 2.5+/-0.6 7.3+/-1.0 3.6+/-0.8 3.8+/-0.8 4.7+/-4.0 K-40 7.J+/-0.7 8.0+/-0.8 4.7+/-0.5 3.2+/-0.3 -2.9+/-0.3 2.7+/-0.3 4.6+/-3.8 H-3 <130 <140 <140 <140 <140 <130 SA-WWA-5Dl U!J l}..,j) Alpha <l.5 2.0+/-1.2 0.6+/-0.5 <0.5 <l.4 <l. 9 . -- Beta 13+/-1 12+/-1 3.8+/-0.7 4.9+/-0.8 12+/-1 15+/-1 10+/-9 K-40 13+/-1 16+/-2 12+/-1 12+/-1 !2+/-1 11+/-1 13+/-4 H-3 <130 <130 <140 <140 <140 <130 SA-WWA-3El 

             <<control)

Alpha <1.5 <l.2 <0.5 <0.5 <1.5 <2.0 Beta 8.5+/-1.l 8.8+/-1.l 5.3+/-0.S J.5+/-0.7 8.6+/-1.0 8.6+/-1.l 7.4+/-4.6 K-40 8.5+/-0.8 11+/-1 8.1+/-0.8 8.2+/-0.8 7.7+/-0.8 7.4+/-0.7 9.4+/-5.2 H-3 <130 <130 <140 <140 <140 I <130 AVERAGE Alpha 1.6+/-0.8 0.7+/-0.4 Beta HUS 9.1+/-5.5 3.9+/-2.8 s. 2+/-3. 0* 8.1+/-8.4 9.1+/-11 7.6+/-7.7 K-40 9.6+/-6.0 12+/-8 8.3+/-7.3 7.8+/-8.8 7.5+/-9.l 7.0+/-B.3 9.0+/-8.0 iH-3 (].) Station SA-WWA-2SJ was collected on 05-13-86. 

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

I TABLE C-15 1986 CON~ENTRATIONS OF GAMMA EMITTERS* IN WELL WATER I Results in Units of pCi/L +/- 2 sigma STATION .ID NUCLIDE 01-13-86 02-10-86 03-10-86 *04-14-86 05-12-86 06-16-86 SA-WWA-283 K-:40 <27 <28 <26 <27 <23 (1) <32 Ra-226 3.3+/-1.9 15+/-3 6.0+/-3.l <5.2 <3.3 7.4+/-2.9 Th-232 <6.6 <1.1 <4.6 <7.1 <5.3 <6.8 SA-WWA-5Dl K,.-40 <38 <.34 35+/-15 <33 <26 <40 

 <<O    Ra-226                                            <4.0        15+/-3        59+/-5       42+/-4      <4.0        44+/-4 t.)

Th-232 <7.1 <6.1 <8.0 <7.9 <7.1 8.4+/-4.8 SA-WWA-3El (control) K-40 * <23 <38 <45 <42 <41 ~ <31 Ra-226 2.9+/-1.5 21+/-3 110+/-7 71+/-5 <4.6 63+/-5 Th-232 <5.8 <7.1 <9.9 <10 <8.7 <8.2 AVERAGE K-40 Ra-226 3.4+/-1.l 17+/-7 58+/-100 39+/-66 38+/-56 Th-232 

        '  .: . ' - ~

. :.. *~-. ;: ..:~ :....,'.:...:...._. *-*" '.: .... ---- TABLE C-15 (cont'd) 1986 CONCENTRATIONS OF GAMMA EMITTERS* IN WELL WATER Results in Units of pCi/L +/- 2 sigma STATION J[ Dl NUCLIDE 07-14-86 08-11-86 09-15-86 10-14-86 11-10-86 12-15-86 AVERAGE SA-WWA-2S3 K-40 <23 <27 <30 <21 <27 <30 .. ~* Ra-226 15+/-2 <4.8 <4.4 <3.7 9.6+/-2.6 8.4+/-2.9 7.2+/-8.3 Th-232 <5. 3l <7.0 <6.3 <5.3 <5.2 <6.7 SA-WWA-5Dl K-40 <29 <29 <26 41+/-15 47+/-16 44+/-17 

                               <IJi                      Ra-226          50+/-4       29+/-4        lO+/-J        66+/-5      21+/-3       96+/-6       37+/-56
                               ~

Th-232 <7.l <7.l 10+/-4 <7.5 <7.1 <8.4 SA-WWA-3El (Control) . *'* K-40 <30 <39 <39 <32 <23 <33 Ra-226 97+/-6 11+/-3 11+/-4 170+/-7 28+/-3 68+/-5 55+/-100 Th-232 <8.0 <7.7 <B. e~ <6.1 <5.3 <8.0 AVERAGE lK-40 Ra-226 54+/-82 15+/-25 8.5+/-7.l 80+/-168 20+/-18 57+/-89 33+/-77 Th-232

  • All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-33.

U) Station SA-WWA-2S3 was* collected on 05-13-86~ 

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

TABLE C-16 1986 CONCENTRATIONS OF STRONTIUM-89* AND STRONTIUM-90 IN QUARTERLY COMPOSITES OF WELL WATER Results in Units of pCi/L +/- 2 sigma 01-13-86 14-86 07,..14-86 

                                                                                                                     .. 10-14-86 STATION ID                                to                 to                 *to          to NUCLIDE                                03-10-86           06-16-86            09-15-86   12"-15-86
/

SA-WWA-283 Sr-89 <0.4 <11 (1) <0.6 .<0. 9 Sr-90 <0.3 <0.5 <0.4 <0.6 

                    ~

SA-WWA-5Dl Sr-89 <0.5 <8~oU> <0.5 <0.7 Sr-90 <0.4 <0.4 <0.4 <0.5 

 \                               SA-WWA-3El i

i (Control) Sr-89 <0.6 <9.o(U <0.5 .<0.8 Sr-90 <0.5 <0.4 <0.4 <0.5 

                                   ~ Sr-89 results are corrected for decay to sample stop date.

(1) High LLD due to extended period between collection and analysis . 

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

TABLE C-17 1986 CONCENTRATIONS OF GROSS ALPHA AND GROSS BETA EMITTERS 0 POTASSIUM-40 AND TRITIUM IN RAW AND TREATED POTABLE WATER STATION !Dg SA-PWR/T-2F3 Results in Units of pCi/L +/- 2 sigma RADIOACT!VXTY JANUARY FEBRUARY HARC!l! APRIL MAY JUNE Alpha {Raw) <2.4 0.7+/-0.5 0.1:1:0.5 <0.5 0.5:t0.4 <1.0 (Treated) <l.9 0.6+/-0.5 <0.6 0.8+/-0.5 0.6:t0.5 <1.4 Beta (Raw) 2.2+/-0.6 3.7+/-0.8 2.4+/-0.6 2.2+/-0.6 2.l:t0.6 2.4+/-0.7 (Treated) 2.4+/-0.7 2.6+/-0.7' 2.3+/-0.6 3.0+/-0.7 2.2+/-0.6 2.1+/-0.7 "JK-40 (Raw) 1.4+/-0. l 1. 7+/-0.2 1.4+/-0.l 2.0+/-0.2 1.3+/-0.l 1.4+/-0.l {Treated) 2.uo.~ l. 7+/-0. 2 l.4+/-0.l 2.0+/-0.2 l.~:i:O. 2 1.5+/-0.2 ilCI m H-3 (Raw) <140 <140 <140 <130 150+/-80 <140 (Treated!) <140 <140 <140 <140 <130 <130

  • 1 I RADIOACTIVIT'lf JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER AVERAGE Alpha (Raw) 0.7+/-0.5 1.0+/-0.8 <0.6 <l.3 <2.0 1. 5+/-1.0 (Treated) 1.1+/-0.1 0.9:t0.6 <0.5 <l.3 <l.1 <0.9 Beta (Raw) 2.* 0+/-0.6 3.1+/-0.7 13+/-1 2.8+/-0.p 3.2+/-0.7 4.5+/-0.8 3.6+/-6.l (Treated) l . 7+/-0.6 8.2+/-1.0 5.1+/-0.8 6.5+/-0.9 2.8+/-0.? 3.8+/-0.? 3.6+/-4.0 JK-40 (Raw) l.3+/-0.l l. 3+/-0. l 1.3+/-0.l 1. 5+/-0 .1 l. ?+/-0.2 2.6+/-0.3 l.6+/-0.8 (Treated) l.3+/-0.l 1.3+/-0.l 1.3+/-0.l 4.9+/-0.5 1.6+/-0.2 2.3+/-0.2 2.0+/-2.0 H-3 (Raw} <130 <140' <140 <140 <130 <130 (Treated) <130 <140 <140 <140 <140 <130
   ')

T~BLE ~8 I 1986 CONCENTRATIONS OF GAMMA EMITTERS* IN RAW AND TREATED POTABLE WATER Results in Units of pCi/L +/- 2 sigma 01-01-86. 02-01-86 03-01-86 04-01-86 05-01-86 06-01-86 STATION ID to to to to to to NUCLIDE 01-31-86 02-28~86 03-31-86 04-30-86 05-31-86 06-30-86 SA-PWR-2F3 K-40 <22 <40 <23 <22 <27 ~44 Ru-103 <l. 7. <l. 5 <1.4 <4.6 <3. 3 <2 *. 1 Ra-226 2.6:tl.4 <5.0 <3.7 <3.7 <4.0 <5.1 

           'l'h-232         <5.8          <8.1          <4.9        <5.8         <7.1          <9.1 SA-PWT-2F3                                                                                             '

K-40 <36 <29 <28 <26 <37 <26 Ru-103 <2.2 <l. 9 <0.9 <5.6 <1. 9 2.6:tl.3 Ra-226 <4.4 '<4.2 <4.0 <4.4 <5.3 <4.6. co Th-232 <6.6 5.7:t3.4 <7.3 <7.1 <7.2 <1.1 CJ) 07-01-66 06-01-66 09-01-86 10-01-86 11-01-66 12-01-86 STATION ID to to. to to to to NUCLIDE 07-31-86 06-31-86 09-30-86 10-31-86 11-30-86 12-31-86 SA-PWR;_2F3 K-40 <29 <23 <27 25+/-13 <37 25+/-14' Ru-103 <2.2 <l. 4 <1. 7 <2.1 <l. 8 <1. 9 Ra-226 <4.4 <3.7 . <4. 2 6.4+/-2.4 <4.3 <4. 4 . 

           'l'h-232         <7.5          <5.8          <6.0        <7.1         <6.1        5.8+/-3.3 SA-PWT-2F3 K-40            <22          <29           <41          <22          <40          <22 Ru-103           <2.0          <l. l         <l. 2       <l. 7        <0.5          <1. 6 '. .*

Ra-226 <3. 7 <4.5 <4. 8 6.6+/-1.6 <5.8 <3. 7 . 

           'l'h-232         <4.~        6.8:t3.6        <9.6.       <5.3         <9.5        . < 5. 3
         *-other       gamma emitters searched for were <LLD1 typical LLDs are given in  Ta~le  C-33.
  • *'1 i.:
                                 ..:~ .. , ~.......... :. .~~::);:~*.<<.:.,:.;::...:::.~~ - ~ *"- . .- .- ...... ,:, ',', ... :;, ~~**~* ...

j 

   *1 I
    *J l

j TABLE C-19 1986 CONCENTRATIONS OF STRONTIUM-89* AND STRONTIUM-90 IN QUARTERLY COMPOSITES OF POTABLE WATER Results in Units of pCi/L +/- 2 sigma 1 

     .,                                                                             01-01-86                                        04-0ll-86     07-01-86 10-01-86
        .       STATION ID                                                                    to                                             to      to        to NUCLIDE                                                             03-31-86                                        dll6-30-86    09-30-66 12-31...:.86 SA-PWR-2F3 (Raw)

Sr-89 <l. 6 <0.8 0.8+/-~L3 <l 00 Sr-90 <l.0 <0.5 <0.6 <0.8 

          <<O
 '   ~    ->\!!

. 'i SA-PWT-2FJ 

                <<Treated) sr-89                                                                    <0.8                                             <0 7.

0 <0.5 <O .*a Sr-90 <0.5 <0.5 <0.4 <0.6 i

  • . l
  • Sr-89 results are corrected for decay to sample stop date.

1* 

                                      ,.... . *1 *                                                          .r... : ..
                 . *~**** :~                                                                                                            . *. .. ~- "*~ -.

TABLE C-20 1986 CONCENTRATIONS OF GAMMA EMITTERS* IN VEGETABLES Results in.Units of pCt/kg (wet) +/- 2 sigma COLLECTION STATION ID OATE(S) SAMPLE TYPE Be-7 K-40 I-131 Cs-137 Ra-226 Th-232 SA-FPV-2El 06/14-16/86 Asparagus <110 2300+/-310 33+/-13 <21 <47 < 94 SA-FPV-3El 07-30-86 Tomatoes < 12 2300+/-64 < 2.3 < 1.6 < 1.8 < 5.7 SA-FPV-3El 07-30-86 Corn <130 2400+/-310 < 4.0 <12 <36 < 55 SA..:FPL-lf3 "07-29-86 Cabbage ( 27 2200+/-93 < 3.1 ( 3.8 ( 7.9 < 13 SA-FPV-1F3 07-29-86 Peppers ( 82 .1800+/-300 <25 <14 <61 < 83 SA-FPV-lf3 07-29-86 Tomatoes ( !6 2200+/-63 < 3.3 ( 2.2 ( 3.6 (

7. ~

SA-FPL-4Fl 07-29..:86 Cabbage 24+/-16 2300+/-99 < 3.9 < 3.7 8.3+/-3.6 ( 15 SA-FPV-4Fl 07-30-86 Tomatoes < 17 2600+/-74 < 4.0 < 2.2 < 3.9 ( 6.7 SA-FPV-6Fl 07-29-86 Peppers <130 1800+/-270 <24 <11 <37 ( 61 co SA-FPV-14F3 07-28-86 Tomatoes < 17 1700+/-53 < 3.7 < 2.0 < 3.7 8.8+/-4.7 Q) SA-FPV-14F3 07-28-86 Corn <160 2300+/-260 ( 3.8 < 3.2 <33 ( 63 SA-FPV-14F3 07-30-86 Peppers <130 910+/-230 <22 <18 <36 <67 

        *SA-FPV-lGl (C)          07-28-86            Tomatoes           < 11         1600+/-62         < 3.3  1.6+/-0.8    < 2.9    (   6.1 SA-FPV*lGl (C)          07-28-86            Corn               <140         2200+/-290 -      <20    <18        <40      < 78 SA-FPV-161 (C)          07-28-86            Peppers            <190         1700+/-280        < 3.8  <24         68+/-34   ( 110
  • SA-f PV-2Gl (C) 06-13-86 Asparagus ( 28 3400+/-340 62+/-20 <23 <61 < 95 SA-FPV-3H6 (C) 07-28-86 Tomatoes ( 14 1600+/-62 < 3.2 2.1+/-0. 9 < 2.9 ( 5.5 SA-FPV-3H6 (C) 07-28-86 Corn <170 2700+/-350 <22 <22 58+/-26 < 95 SA-FPL-3H5 ( c) 07-28-86 Cabbage < 40 1900+/-120 < 5.2 < 4.7 <10 < 21 SA-FPV-:3H6 ( c) 07-29-86 *Peppers <130 1600+/-260 <20 <21 <44 < 70 AVERAGE 2100+/-1100 11 other gamma emitters ~earched for were <LLD; typical in Table C-33.

ntrol Stat ion 

                           . - t TABLE C-21 1986 CONCENTRATIONS OF GAMMA EMITTERS* IN GAME AND MEAT Results in Units of pCi/kg (wet) +/- 2 sigma COLLECTION STATION ID                                                           DATE(S)                             SAMPLE TYPE                       K-40                     Cs-137 SA=GAM~llDl                                                  01/11=13/86                                         Muskrat                 2200+/-:170                      <9o9 (Control)

SA~GAM-4Cl 01~12-86 Muskrat 2400+/-220 <15 SA-FPB-3El 02-24-86 Beef 2500+/-180 7.3+/-4.6 AVERAGE Muskrat 2300+/-280 Beef 2500+/-180

  • All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-33.
                      **i
               *J
              -. i
* :. _*...*'*; ...~ *; *1!
  • ..:>-1
                           ~.--- . . -- __ ,_ - --:-*-**-c;:----~- ----*-:;*--.. - -:-***:*- ..- ---~-----~------ -*-. *-*** -- *----.----* ---. .--* ****--***-* .. * .. -:- -* ---* -----          ** *,"r- ---:--***-,: * ,_ __ -~*

TA~LE C-22 1986 CONCENTRATIONS OF GAMMA ~HITTERS* IN FODDER CROPS Results in Units of pCi/kg (wet) +/- 2 sigma COLLECTION STATION ID DATE(S) ~AMPLE lrYPE Be-'7 K-40 Cs-137 Ra-226 Th-232 SA-VGT-3E~ 10-13-86 soybeans <160 15000+/-590 <25 <39 <88 SA-VGT-13E3 09/01-05/86 Silage 1000+/-190 3600+/-510 <28 <67 <120 SA-VGT-2F'7 09/03-08/86 Silage 370+/-90 2600+/-280 <17 35+/-17 <63 SA-VGT-5F2 09-14-86 Silage <250 2300+/-470 <28 <76 <130 0 0 SA-VGT-5F2 11-01-86 soybeans <150 15000+/-610 <21 <38 <11 SA-VGT-llF3 09-01-86 Silage '740+/-180 4000+/-430 <19 <51 <76 SA-VGT-14Fl 09-15-86 Silage 1400+/-260 3400+/-520 <54 <100 170+/-100 SA-VGT-3Gl (C) 09-08-86 Silage 11Q0+/-240 3000+/-550 <41 <83 <130 SA-VGT-3Gl (C) 11-01-86 Soybeans <140* 14000+/-480 13+/-7 <36 <59 AVERAGE 590+/-960 7000+/-12000

  • All other gamma emitters searched for were *<LLD; typical LLDs are given in Table C-33.

(C) control station 

                                                                            *                                                 .~. . I
                                                                                                                                 .j

                                                          ~
       ..,*.*-= *-*- --* ...                      ***~-*--"* .. ,., ..........  ..:.:.:.                                                ,..........: .. ..... ,
 **! I i

I 1. I J ... TABLE C-23 "i 

    .I 1

1986 CONCENTRATIONS OF STRONT!UH-90 AND GAMMA EMITTERS* IN SOIL 

  *J
   .)

Results in Units of pCi/lltg {dry.) +/- 2 sigma j 1I COLLECTION STATION ID DATE Sr-90 IK-40 Nb-95 Cs-131' Ra-226 Th-232 

                             *SA-SOL-6Sl        01-30-86                                   27+/-10        9200+/-450        34+/-19        100+/-19                      490+/-40   620+/-72 SA-SOL-5Dl        07-30-86                                  120+/-14        5200+/-340        <22          350+/-23                      510+/-37   550+/-64 SA-SOL-lODl       07-30-86                                  110+/-14        8300:1:420      <29          370+/-24                      800+/-41   840+/-70 SA-SOL-2El        07-29-86                                  110+/-13        7300+/-400        <12          380+/-27                      700+/-45   720+/-14 SA-SOL-16El       07-30-86                                  110+/-14      12000+/-410         <27          260+/-18                     1000+/-40  1200+/-68 SA-SOL-lFl        07-30-86                                  120+/-13        3600+/-240        <15         1500+/-35                      260+/-24   270+/-35 SA-SOL-2Fl        07-29-86                                  140+/-15        9100+/-430        <24          330+/-25                      870+/-47   840+/-77 SA-SOL-2F2        07-29-86                                    <22         5500+/-380        <22          110+/-16                      380+/-36   340+/-60 SA-SOL-2F4        07-29-86                                   55+/-10        7400+/-400        <28          370+/-24                      770+/-40   730+/-67 SA-SOL-2F?        07-30-86                                   87+/-13        8300+/-420        63+/-22        330+/-26                      890+/-50   890:t~l SA-SOL-5Fl        07-29-86                                   97+/-14        5100+/-270        <18          800+/-26                      340+/-26   410+/-41 SA-SOL-5F2        07-29-86                                   77+/-12        3200+/-330        <22          290+/-24                      480+/-38   410+/-59 SA-SOL-llF3       07-30:-86                                  43+/-12      13000+/-560         < 4.5          78+/-19                    1000+/-51  1100+/-98
  .. I '

SA-SOL-14Fl 07-30-86 87+/-14 12000+/-500 <19 230+/-25 960+/-48 1000+/-82 SA-SOL-3Gl ~C) 01-29-86 56+/-11 7900+/-450 <15 210+/-22 770+/-46 780+/-82 SA-SOL-3H3 (C) 07-28-86 130+/-15 9200+/-440 <26 690+/-31 850+/-46 810+/-76 AVERAGE 87+/-74 7900+/-5800 400+/-700 690+/-490 720+/-540

  • All other gamma emitters searched for were <LLDa typical LLDs are given in Table C-33.

(c) Control station 

                     ** l',, **>***~*-'***

1* TABLE C-;-24 1985 CONCENTRATIONS OF GROSS ALPHA ~HITTERS IN SURFACE WATER Results in Units of pCi/L +/- 2 sigma STATION ID 01-20-86 02-03-86 03-03-86 04-08-86 05-05-86 06-09-86 SA-SWA-llAl <2.0 8.3+/-4.2 2.6+/-1.6 5.2+/-4.0 <4.0 . 2.0+/-1.4 SA-SWA-12Cl <l. '1 <4. '1 <l.2 8.3+/-2.5 1.8+/-1.3 <l.4 (Control) SA-SWA-'1El <2.0 3.6+/-2.6 1.2+/-0.9 <3.8 <l.4 <l.2 SA-SWA-1F2 <l.8 5.0+/-3.l <l.l 12+/-3 <1.6 <l.3 SA-SWA-16Fl <3.'1 4.4+/-2.9 <Ll <4.1 <1.5 <l.2 0 l\) AVERAGE 5.2+/-3.6 6.7+/-6.9 STATION ID 0'1-11-86 08-04-86 09-08-86 10-07-86 11-03-86 12-08-86* AVERAGE SA-SWA-llAl 1.6+/-1.2 1.8+/-1.0 <0.8 <0.8 <1.8 1.2+/-0.9 2.7+/-4.4 SA-SWA-12Cl 2.2+/-1.6 1.8+/-1.0 <l.6 <0.6 <1.9 <1.l (Control) SA-SWA-7El 1.6+/-1.2 1.3+/-1.0 1.1+/-0. '1 1.2+/-0.8 <l. '1 <1.1 SA-SWA-1F2 <l.5 2 .6+/-1. l <0.8 <0.8. <1.8 <l. 2 SA-SWA-16Fl <1.6 1. 5+/-1.0 0~'1+/-0.5 <0.9 <2.0 <1.1 AVERAGE l. 7+/-0.6 1.8+/-1.0 

                                                                                                                                                ~

                   *=*.*      - ..
         *.~ >>. **, .. ;**                                                                      '_.
  • ..~.*.. .:.~.. :. . ' * * . *-* -* *****" .......... ., ... ~ ....... -*~ ** ~<-** .... *"
  • j 1

I 

'j

_i 

 )

TABLE C-25* ii 1986 CONCENTRATIONS OF GROSS BETA EMITTERS IN SURFACE WATER I 

-1 Results in Units of. pCi/L +/- 2 sigma STATION   :m                                        01-20-86                          02-03-86     03-03-86       04-08-86   05-05-86     06-09-86 SA-SWA-llAl                                                  181+/-8                       21+/-4        12+/-1           32+/-4       24+/-4          24+/-4 SA-SWA-12Cl                                                  BU::8                      17+/-3        1 .5+/-1.l        17+/-3       36+/-5          33+/-5 (Control)

SA-SWA-7El 92+/-9 51+/-6 16+/-2 50+/-6 63+/-7 42+/-6 I SA-SWA-1F2 39+/-5 fi.0+/-2.4 2.4+/-0.'7 10+/-2 9.2+/-2.? 22+/-4 SA-SWA-16Fl 50+/-6 8.1+/-2.6 3.8+/-0.8 13+/-3 11+/-3 25+/-4 II-"' 0 

                          ~            AVERAGE                                                      69+/-46                       22+/-37      a.Jui           24+/-33      29+/-44         29+/-16
~

i STATION ID 07-11-86 08-04-86 09-08-86 10-07-86 11-03-86 12-08-86 AVERAGE SA-SWA-llAl 89:t9 96+/-9 130+/-12 77+/-8 120+/-11 14+/-3 60+/-86 SA-SWA-12Cl 68+/-8 69+/-7 76:t8 59+/-7 72+/-8 9.8+/-2.7 '45+/-56 (control) SA-SWA-7El 110+/-12 120+/-11 130+/-12 110+/-11 100+/-11 3_0+/-4 76+/-77 SA-SWA-1F2 42+/-6 38+/-5 85+/-9 45+/-6 51+/-6 6.4+/-2.4 30+/-50 SA-SWA-16Fl 48+/-6 66+/-7 75+/-8 56+/-6 87+/-8 11+/-3 38+/-58 AVERAGE 1U5? '18+/-62 99+/-57 69+/-51 86+/-53 14+/-18. Girand Average 50+/-73 0

TABLE C-Z6 1986 CONCENTRATIONS OF GAMMA EMITTERS* IN SURFACE WATER Results tn Untts of pCi/L t Z sigma STATION ID NUCLIDE Ol-Z0-86 OZ-03-86 03-03-86 04-08-86 05-05-86 06-09-86 SA-SWA- llAl K-40 80tZ6 <41 80+/-19 33t18 43t19 64:tZO Ra-2Z6 <4.6 <4.4 <4.4 <4.9 <4.4 <3.7 Th-232 <7.6 <6.6 6.Z:t3.7 8.8+/-4.0 <8.4 5.3t2.8 SA-SWA-12Cl . K-40 86tZO

  • Z9:t17 41t18 <29 46tZ3 <43 (Control) Ra-Z26 <6.2 <3.7 <3.7 <4.8 <4.6 <4.7 Th-232 <6.8 <6.8 <6.3 <6.4 9.2:1:4.3 <7.6 SA-SWA-7El K-40 90+/-27 84tl8 67tZ1 73+/-26 87tZO 83t22 Ra-226 <4.4 <6.6 <4.6 <6.0 <4.6 <4.4 Th-232 <8.1 <8.6 <8.3 <6.5 <6.2 <7.1 SA-SWA-lFZ K-40 67t19 <39 <24 <3Z <35 <Z7 Ra-226 <4.4 <4.4 <3.3 <3.9 5.4:tZ.9 <3.3 Th-232 <6.6 <9.0 <4.9 <7.6 <1.4 <6 ..3 SA-SWA-16Fl K-40 61+/-2Z <Z7 <Z6 <41 <26 <30 Ra-Z26 <4.2 <4.0 ll:t3 <6.1 <4.3 <4.9 T~-232 <6.9 <7.1 <6.2 <8.2 <5.7 <7.7
   ..... AVERAGE             K-40            76:t32                           48+/-50                          47:1:47 0
   ~

STATION ID NUCLIDE 07-11-86 08-04-86 09-08-86 10-07-86 11-03-86 lZ-08-86 AVERAGE SA-SWA-llAl K-40 1ZO:t24 110tZ6 140+/-26 140:tZ3 lZOt23 <3Z 84:t83 Ra-226 <4.6 <4.8 <4.l <4.4 <4.9 <4.6 Th-232 <7.8 <7.5 7.6:1:4.4 <8.0 <7.4 <7.5 SA-SWA-12Cl K-40 73+/-26 92+/-21 79:1:26 95+/-20 9l:t23 <43 62:t52 (Control) Ra-226 <6.3 <4.5 <4.3 25+/-3 <4.6 <6.1 Th-232 <8.6 <6.4 <8.9 <6.8 <6.8 <1.8 SA-SWA-7El K-40 l40:t21 lOO:tZ6 160+/-24 130+/-27 140+/-31 66+/-17 102+/-64 Ra-2Z6 . 2.9:tl. 7 <4.4 <4.6 <5.5 . <6 .1 <4.4 lh-232 <6.3 <6.2 <7.6 <8.5 <9.0 <7.1 SA-SWA-1F2 K-40 44t2Z 49+/-17 86:1:Z6 95:t20 61tZO <24 Ra-226 <4.0 8.4+/-2.0 <4.8 <5.7 <4.6 Z.6:tl.6 Th-232 <7.6 <6.8 <7.2 <7.5 <6.9 <6.3 ,. SA-SWA-16Fl K-40 68:1:19 63:tZ3 lOOtZl 60+/-18 94+/-27 <27 Ra-226 <4.9 <4.0 <4.4 3.3:tl. 7 5.2:t2.8 <4.5 Th-232 <6.3 <7.5 <6.4 <5;8 9.3:t4.8 <6.5 AVERAGE K-40 89+/-79 81+/-56 110+/-71 100:t64 100+/-60 e Grand Average K-40 69:t72

  • other ganlna emitters searched for were <LLD; typical LlDs a . n in Table C-33.
             .~:.:..:, * .:.**** ~:.. 1 **** * .~.  * -**
                                                                        ~~.. '
                                                              ...........:.:*,:* ..... _.\/                                  ******
                                                                                                                                                                              .1
  • I I

I TABLE C-27 *I 1986 CONCENTRATIONS OF TRITIUM IN QUARTERLY COMPOSITES OF SURFACE WATER Results in Units of pCi/L +/- 2 sigma 01-20-86 04-08-86 07-11-86 10-07-86 STATION ID to to to to AVERAGE 1!)3J-03-86 06-09-86 09-08-86 12-08-86 SA-SWA-llAl 150+/-80 <140 270+/-90 <140 ll-" SA-SWA-l2Cl 150+/-80 <130 <140 <130 a <<control>> 

                       <<im SA-SWA-7El                                l3CU80               <140                        140+/-90    <140 SA-SWA-lF2                                  <130               <130                        170+/-80    <140 SA-SWA-l6Fl                               140+/-80               <130                        160+/-80   140+/-80  140+/-25 AVERAGE                                   140+/-20                                           180+/-110

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

I! I i i 

     .i TABLE C-28 1986 CONCENTRATIONS OF STRONTIUM-89* AND STRONTIUM-90 AND TRITIUM IN EDIBLE FISH r: \:.                                                                                                                        'l'RITIUM (FLESH)**

I STRONTIUM (BONES) AQUEOUS FRACTION pCi/kg (dry) +/- 2 sigma pCi/kg (wet) +/- 2 sigma i STATION ID COLLECTION PERIOD sr-89 Sr-90 H-3 I I iI I I SA-ESF-llAl 05-05-86 to 05-13-86 <70 240+/-17 <50 

 ,' l
 . I .                                                                10-08-86 to 10-08-86       <48          <29                    <50 I

I

1 SA-ESF-12Cl 05-12-86 to 05-19-86 330+/-100 1500+/-64 i
                                                                                                                                     <50
                                ~

a (Control) 10-08-86 to 10-08-86 <75 <44 <50 m SA-ESF-7El 05-06-86 to 05-07-86 <65 34+/-13 <50 10-09-86 to 10-09-86 <40 <24 <50 

   .I I
   *J t Sr-89 results are coriected for decay to sample stop date.
                                                      ** Tritium results by Controls for Environmental Poilution, Inc *

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

I I I TABLE C-29 

 . j
    '                                                                 1966 CONCENTRATIONS OF GAMMA EMITTERS* IN EDIBLE FISH
. i 1
  *1                                                                             Results in Units of pCi/kg (wet) +/- 2 sigma STATION ID                       COLLECTION PERIOD          K-40       Cs-137   Ra-226 Th-232 SA-ESF-llAl                05-05-86 to 05-13-86           2nHll+/-l80     8.3+/-4.5  <20    <31.

10-08-86 to 10-08-86 3300+/-290 <19 41+/-19 <*61 SA-ESF-12Cl 05-12-86 to 05-19-86 2700+/-230 <12 <24 29+/-18 (Control~ 10-08-86 to 10-08-86 33CHU240 <16 <34 <59 II-" 0 19 

                              ~

SA-ESF-7El 05-06-86 to 05-07-86 2800+/-230 <12 <24 <47 10-09-86 to 10-09-86 3000+/-240 <14 33+/-17 <53 AVERAGE 3000+/-560

  • All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-33.

.i -r ... : ._ , 1 

   ./
  .11
    *,                                                                                                      TABLE C-30 I

Ii 1986 CONCENTRATIONS OF STRONTIUH-89* AND .STRONTIUM-90, GAMMA EMITTERS** AND TRITIUM IN BLUE CRABS Results in Units of. pCi/kg (wet) +/- 2 sigma COLLECTION AQUEOUS FRACTION STATION Ill PERIOD SAMPLE Sr-89 Sr-90 . K-40 Ra-226 H-3*** e

  • SA-ECH-llAl 06/05-06/86 Flesh <28 <18 1700+/-210 <30 <50 Shell (1) 300+/-32 150+/-24 (2) (2) . (2) 10/08-09/86 Flesh <46 <24 2000+/-210 <28 <50 Shell (1) <67 380+/-19 (2) (2) (2)

Q--1 0 SA-ECH-12Cl 06/05".""06/86 Flesh <29 <19 2000+/-160 19+/-9 <50 (Control) Shell (1) <11 490+/-26 (2) (2) (2) 

                                                                     .10/08-09/86         Flesh           <44         <24      .1700+/-150    20+/-9            <50 Shell (1)       <89       ~20+/-24         (2)        (2)           (2)

AVERAGE Flesh 1800+/-350 Shell. 340+/-280

  • sr-89 results are corrected for decay to sample stop date.
                    ** All other gamma emitters searched for were <LLD; typical LLDs are given in Table C-33.
               *** Tritium results by Controls for Environmental Pollution, Inc.                                                                                           .I Strontium results in units of pCi/kg (dry).

ma and tritium analyses not required *. 

        . I TABLE   C~31 1986 CONCENTRATIONS OF GAMMA EMITTERS* IN BENTHIC ORGANISMS   . . *.

Results in Units of pCi/kg (dry) COLLECTION GAMMA STATION ID DATE* ACTIVITY SA=ESB=llAl 06~05=86 <LLD 10=14=86 <LLD SA-ESB~l2Cl 06-05-86 <LLD (Control) 10-14-86 <LLD SA-ESB-7El 06-05-86 <LLD 10-14~86 <LLD SA=ESB~l6Fl 06=05=86 <LLD io*.;.,14=86 <LLD

  • All gamma emitters searched fo-r were <LLD: typical LLDs are given in Table c-33.
~  *. i e  . j
  ***)
.. **i
  • . . . J

I'.** '*:!.* *.*..,.. I. I~. I _....... :,:.~ .~.:.. ;~~.:'.l..:.c*' .. .. ... ..*--** ..... -**-** .... 1c~ i I II 

      ...,\1
   . I i

i l TABLE C-3Z 

      *1 1986 CONCENTRATIONS OF STRONTIUM-90 AND   ~AMMA EMITTERS* IN SEDIMENT**

I j Results in Units of pC1/kg (dry) t 2 sigma 

     .-1.
       \i l

iI. STATION ID l DATE Sr-90 K-40** Mn-64 Co-68 Co-60 Cs-134 Cs-137 Ra-2Z6 Th-232 I 

    *1 i                                            SA-ESS-JJAJ

'** 1 j 06-06-86 <19 3600t410 Z9+/-16 <3Z 9Zt17 <34 <ZS 330+/-44 360:t8Z* 

   .I                                                   10-14-86                  <Z1    8600+/-430         26+/-14       38*17        110t23         <22        82t19  . 760+/-46   980+/-.83
   *i I

56-ESS-1561 06-06-86 . <20 7800t610 <34' <33 97tZ2 <44 <36 390+/-1i0 440+/-92 I 10-14-86 <Z~ 6800t360 <18 80t16 37tll <16 <22 400t33 300+/-57 I 

    . I' S6-ESS-J661
   .f                                                                             <Z4                      <35         <38 06-06-86                         4300t460                                   80tZ6        82+/-27        <16     810+/-62   iJOO:tliO
                                    ........            10-14-86                  <38    6000t400         Z4tl3      '79t18         49t21         <21         <29     760+/-46   780:t76 q

S6-ESS-IZC1 

      *1                                                (Control) 06-06-86                  <21   16000t830          <34 .        <37         <48          60+/-24        <35     670+/-63   880+/-110 10-14-86                  <26   14000t640          <23          <23         <36           <20        20t1Z    840+/-42   870+/-74 56-ESS-ZEl i
          '                                             06-06-86                  <20   16000t660          <26          <27        37t19         46+/-18       49t16    690t44   770+/-80
     .I
10-14-86 <30 l3000t660 <29 31tl6 78t26 <21 6lt15 690+/-42 720+/-78
1 "i S6-ESS-16Fl 06-0b-86 <28 16000t830 <38 <37 <48 66+/-26 <39 680+/-66 940+/- 110 10-14-86 <29 16000t670 <33 <36 <44 <24 <26 680t47 1000+/-91 AVERAGE 10000t9900 63t63 620+/-330 740+/-490
  • All other ganma emitters searched for were <LLD; typical LLDs are given in Table C-33.

Sediment samples which iriclude*benthic organisms constitute t thos sample.

_c'! 

                                                    ......... -* - ;...... ~**4**-~*-*** --*

I TABLE C-33 1986 fSE&G RESEARCH CORPORAT!OM LLDs FOR GAMMA SPECTROMETRY AIR WATER FOOD PRODUCTS MEAT AND PARTICULATES ALL TYPES HILK AND FODDER CROPS GAME JMUCLIDES <<!0- 3pCi/m3 ) _ (pCi/L) h>Ci/L) (pCi/k.g-wet) (pCi/kg-wet) I GEOMETRls 13 Filters 3.5 Liter 3.5 Liter lOOml 400ml lOOml 400ml 

  *l.i l
1
. -*~                                 Jae-7                                         3. 0            14               14              e.o     120    37         92 1

I Ma-22 0.54" i.a l.B 1.2 15 5.3 11 . *i JK-40 e.o 32 "' II< 

                                                                                                                                              *
  • If!

Cr-51 2.18 12 12 9.5 140 45 107 

   *1                                 Hn-54                                         0.38             1.4               1.4           1.0      14      4.4      10
 -i Co-58                                        0.39              1.6               1.6           0.99     15      4.5      11 Fe-59                                         0.83             3.2               3.2           2.4      32    10      *- 24 Co-60                                        0.46              2.0               2.0           1.1      16      5.0      11 Zn-65                                         0.86             3.3               3.3           2.0      31      9.0      22 Hb-95                                         0.43             1.7               1.7           l.l      16      5.0      12 0--0 ll-'         zr-95                                         o.n              3.0               3.0           2.0      2a      a.a      21 ll-'         ZrMb-95                                       0.71             3.0               3.0           2.0      28      8.a      21
     ~

_,; Ho-99 12 20 20 51 1300 370 2400 Ru-103 0.39 1.4 1.4 1.0 16 4.9 12 Ru-106 4.0 14 14 10 130 42 98 Ag-llOm 0.67 1.5 1.5 1.6 14 7.2 11 Sb-125 0.90 4.1 4.1 2.6 39 12 27 Te-129m 14 63 63 40 620 183 480 J[-131 0.46 1.8 1.8 1.7 30 9.0 30 Te-132 0.89 2.1 2.1 3.9 99 26 170 Cs-134 l0.51 1.7 l.7 1.3 13 5.7 9.3 Cs-136 0.49 1.9 1.9 1.3 22 6.4 20 Cs-137 0.35 l.7 1.7 1.0 17 4.4 12 

- '                                   !Ba-140                                       l.6              6.2               6.2            5.0     82     25        71 La-140                                        0.73             2.3               2.3            2.2     32     11        28 JBaLa-140                                     1.6              6.2               6.2            5.0     82     25        71
   .~                                 Ce-141                                        0.42             2.4               2.4            1.2     19      5.6      15 Ce-144                                        l.4             10               10               4.1     79     18        57 Ra-226                                        0.86             4.0               4.0            2.2     32     10        23 Th-232                                        1.1              6.8               6.8            3.8     54     17        40

TABLE C~33 (cont'd) 1986 PSE&G RESEARCH CORPORATION LLDs FOR GAMMA SPECTROMETRY SEDIMENT AIR FISH SHELLFISH AND SOIL IODINE NU CL IDES (pCl/kg-wet) (pCi/kg-wet) (pCi/kg-dry) NUCL IDES (lo- 3 pci/m3 ) GEOMETRY: lOOml 400ml lOOml 400ml lOOml lOOml Be-'1 3'1 92 142 85 120 I-131 15 Na-22 5.3 11 21 10 14 I-132 26 K-40 * * * *

  • I-133 39 Cr-51 45 10'1 1'10 91 150 I-135 1.2 Hn-5~ 4.4 10 1'7 10 13 Co-58 4.5 11 18 10 14 Fe-59 10 24 41 22 36 Co-60 5.0 11 19 11 15 zn-155 9.0 22 35 22 25 Hb-95 5.0 12 19 10 15
        &-' zr-95
        ~

8.B 21 35 20 26 l\) ZrNb-95 8.8 21 35 20 26 Ho-99 3'70 2400 1200 530 13000 RU-103 4.9 12 19 11 14 RU-106 42 98 160 9'7 120 Ag-llOm 1.2 11 28 10 '19 Sb-125 12 2'1 46 2'1 28 Te-129m 183 480 '720 430 600 I-131 9.0 30 33 18 52 Te-132 26 1'10 85 49 650 Cs-134 5. '1 9.3 22 9 12 Cs-136 6.4 20 24 14 31 Cs-13'7 4.4 12 1'7 12 12 Ba-140 25 ' '71 94 51 105 La-140 11 28' 41 20 52 BaLa-140 25 '71 94 51 105 Ce-141 5.6 15 22 13 1'7 Ce-144 18 5'7 '73 56 55 Ra-226 10 23 40 23 230 1'7 40 69 40 48 cates a positive.concentration was measured in a . . p l e s analyzed.

APPENDIX D SYNOPSIS OF ANALYTICAL PROCEDURES

  • I ll~

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

1-SYNOPSIS OF .. ANALYTICAL PROCEDURES . Appendix D presents a synopsis of the .analyti.c.al procedures utilized by various laboratories for analyzing. the 1986

  • Artificial Island Radiological Environmental Monitoring Program samples.

TABLE OF CONTENTS LAB* PROCEDURE DESCRIPTION PAGE GROSS ALPHA PSE&G Analysis of Air Particulates ******************** 117 TI Analysis of Air Particulates ******************** 119 PSE&G Analysis of Water ** 0 0 0 Cl Cl 0. 0. Cl 0 e e Cl GI Cl 0 0 e Q c I) e I) e 0 fl Cl> Cl 120 GROSS BETA PSE&G Analysis of Air Particulates .***.*************.* 122 TI Analysis of Air Particulates ******** : *********** 124 PSE&G Analysis of W a t e r o * * *

  • c o e c e o o o C l e o c i o o o e o o G C l
  • C C O O C I 125 POTASSIUM~40 PSE&G Analysis of Water o Clo. o o Clo o e o * ., o o o o e o Cl Q o o o c e o" Iii o ~Cl 126 TRITIUM PSE&G Analysis of Water ******************************* 127 CEP Analysis of Aqueous Fraction of Fish and crab *** 128 IODINE-131 PSE&G Analysis of Filtered Air ************************ 129 TI Analysis of Filtered Air ************************ 130 PSE&G Analysis of Raw Milk ********************.******** 131 STRONTIUM-89 AND STRONTIUM~90 PSE&G Analysis of Air Particulates *********** e******** 132 TI Analysis of Air Particulates **********.********** - .l.35 PSE&G Analysis of Raw Milk **************************** 137 PSE&G Analysis of Water 0 Q Q Q G 0 0 e 0 0 0 e 0 Q 0 t> 0 Cl E> 0 Cl Cl c 0 g 0" Cl ID Q 0 140 PSE&G Analysis of Vegetation, Meat and Aquatic Samples 143 PSE&:G Analysis of Bone and Shell ********************** 146 PSE&G Analysis of Soil and Sediment ******************* 149
        . '                                     PSE&G                          Analysis                 of Samples for Stable Strontium ********                                                                                                      152 115
  .- ; :*.~-::~
 ' .~    ".\!
    .   ..    ~
                -:-----------..,,.. ,.... --~ . . . :--:t**,-.*-;*--:-*-*--- . -~~"' -*-:*--..-- -~-.------~- **-:* .- . -;-*----: . .---*,**.---.-. -----* *- ... *- -- ... - -- ....   --***-~;-- -*- .. - --- -- . -- - . ***-*:-* ...... **-- *--

SYNOPSIS OF ANALYTICAL PROCEDURES (cdnt'd) TABLE OF CONTENTS L.AB* PROCEDURE DESCRIPTION PAGE GAMMA SPE::::TROMETRY PSE&G Analysis of Air Particulates ***************.***. 154 TI Analysis of Air Particulates ******************** 155 PSE&G Analysis of Raw Milk * *

  • e *
  • o * * * * * * * * * * *
  • e * * *
  • u * *
  • 156 PSE&G Analysis of Water *************** " ******.******* c
  • 157 PSE&G Analysis of Solids (combined procedures) ******** 158 ENVIRONMENTAL DOSIMETRY TI Analysis of Thermoluminescent Dosimeters .*****.. 160
  • PSE&G - PSE&G_Research Corporation TI - Teledyne Isotopes CEP - Controls for Environmental Pollution, Inc *
  '  .* ~

. --. *. ~ 

     .. -~
"-] 116
         **-,--- - -;-* - ***--*-*-----,.-- *:-;-** ..-~-* -......--7.~---**--**.*:-~ *-:*-- * .,.---,;:---""';"*~**-~--*7.~*---.---;---r- *--:-.,.... - - - . - .- * ---* - - * *- <---- ..,*.~* *--:*-~* -~ ~--,;- --,----* *---- ***--: --** *-.- . -** ** - *- . -*.* *
  • SYNOPSIS OF.. PSE&G. RESEARCH CORl?ORA'l'ION PROCEDURE GROSS ALPHA.ANALYSIS OF AIR PARTICULATE SAMl?LES After a1low:i.ng at least a three~day (extendi.ng from the sample stop date to the sample count time) period for the short-lived radionuclides to decay out, air particulate samples are counted for gross alpha activity on a low back~

ground gas proportiona1 counter. Along with a set of air particulate samples, a clean air. filter is in:luded as a blank with an Am-241 air filter geometry a1pha counting standard. The specific a1pha activity is computed on the basis of total corrected air flow sampled during the collection period. This corrected air flow takes into*account the air ~ressure correction due to the vacuum being drawn, the correct.ion factor of the temperature-corrected gas meter as well as the gas meter efficiency itself. caiculation of Gross Alpha Activity: Air flow is corrected first by using the following equations: P = (B-V)/29.92 P = Pressure correction factor B = Time-averaged barometric pressure during sampling period, ivHq . V = Time-averaged vacuum during sampling period, "Hg 29.92 = Standard atmospheric pressure at 32°Fu "Hg V = F~P~0.946*0.0283 E F = Uncorrected air flow, ft 3 o.946 = Temperature correction factor from 60°F to 32°F 0.0283 = CUlJic meters per cUlJic foot E = Gas meter efficiency (= % efficiency/100) v "" corrected air flow, m3 p = Pressure correction factor Usinq these corrected a.:!.r flows. the gross alpha activity is computed as follows~ Result (pCi/m3 ) ~ (G--B)/T 

    *1

( 2 a22) *(E)$1 (V~ G = Sample gross counts B = Background counts (from blank filter) 

                                                                                                     'l' = Count time of sample and blank, minso E = Fractiona1 Am-241 counting efficiency V   = corrected air   flow of sample, m3 2.22   = No. of dpm per pCi 117

. .. ...~ 

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

l 

 .. I 2-sigma error (pCi/m 3 ) =  (l.96*(G+B)l/ 2 )~A (G-B)

A = Gross alpha activity, pCi/m 3 G = Sample gross counts 

                                                       =

B Background counts (from blank filter) caiculation of lower limit of detection: A sample activity is assumed to be LLD if the sample net count is less than 4.66 times the standard deviation of the count on the blank. LLD(pCi/m3 ) = 4.66

  • ca) 1 / 2

{2~22)*(E)*(V)*(T) B = Background counts (from blank filter) E = Fractional Am-241 counting efficiency v = corrected air flow of sample, m3 T. = Count time of blank, mins. 118

  • SYNOPSIS OF TELEDYNE ISOTOPES **PROCEDURE ANALYSIS OF AIR !?ARTICULATE FILTEHS.FOR GROSS ALPHA AND-BETA The air filter is first stored for 2 to 5 days from date of receipt to allow for decay' of the radon-thoron daughters. It is then placed in a stainless steel planchet which has been coated in the center with ruJ:lber cement. The filter is then counted for.beta activity and suosequently repeat counted for alpha activity (at a different voltage setting) in a Beckman-Sharp Wide Beta II automatic alpha-beta counter.

Gross alpha and beta activity (pCi/m3 ) are computed as follows: A = {G/T ~B)  % qm~((G/T +B)/T)l/2 (2.22*V>11Y*D*E) (2o22*V'*Y*D*E) Where G = Total. sample counts B = Background counts per minute T = Sample count time, mins. 2.22 = dpm/pCi v = Sample volume, m3 Y = Chemical yield (Y = 1 in this case) D = Decay factor from collection to count date (D =1 in this case) E = Counter efficiency crm ::a* MUl.tiples of ccmntinq error. If the net activity (G/T -B) is equal to or less than the counting error, then the activity is considered to be the minimum detectable level, or MDL. where MDL = 3*(2*B/T)l/2 (2o22*V*Y*D*E) Varia.l:lles are as previously defined

SYNOPSIS OF:PSE&G-RESEARCH CORPORATION l?ROCEI;JURE GROSS ALPHA ANALYSIS OF WATE~ SAMPLES - The sample is thoroughly miXed. Then, a 250ml portion.of sample and an equal volume of deionized water blank are acidified with dilute sulfuric acid. Barium carrier is added and the sample heated to 50°C in order to help pre-cipitate barium sulfate. Maintaining the same temperature for the remainder of the procedure, iron carrier is then introduced. After a 30 minute equili-bration period, the sample is neutralized with dilute ammonium hydroxide to precipitate ferric hydroxide. The mixed precipitates are then-filtered onto a membrane filter, dried under -an infrared heat lamp, weighed and mounted on a stainless steel planchete The sample is then alpha-counted for lOO minutes on a low background gas proportional counter, along With a U-238 source of the same geometry. The blank is treated in the same manner as the sample. Water samples found to be excessively turbid due to the presence of suspended organic material require pretreatment of this material for the purpose of keeping the final sample thickness to a minimum. This is accomplished by filtering a measured aliquot of the sample (while the filtrate is set aside) and ashing the collected residue in a crucible. A blank of the same volume is handled in the same manner. Whatever leftover sample residue remains,after the ashing,is dissolved in concentrated nitric acid and passed through a hardened fast filter paper and combined with the sample- filtrate. The combined sampl is then neutralized with dilute ammonium hydr'oXide. From this point, both sample and-blank are acidified with dilute sulfuric acid. Barium carrier is added and the sample is heated to so 0 c in order to help.precipitate barium sulfate. Maintaining the same temperature for the remainder of the procedure, iron carrier is then introduced. After a 30 minute equilibration period, the sample is neutralized with dilute ammonium hydroXide to precipitate ferric hydroXide. The miXed precipitates are then filtered onto a membrane filter, dried under an infrared heat lamp, weighed and mounted.on a stainless steel planchet. The sample is then alpha-counted for the appropriate time on a low - background gas proportional counter,- along with a U-238 source of the same geometry. The blank is treated in the same manner as the sample. calculation of Gross Alpha Activity: Result (pCi/L) = (G-B)/T (2.22)*(E)*(V)*(S) G = Sample gross counts B = Background counts (from blank sample) T = count time of sample and blank E. = Fractional counting efficiency from U-238 source

.. ** v = Sample volume, liters s = Normalized efficiency regression equation as a function of thick-ness 2.22 = No. of dpm per pCi 120

2~sigma. error. (pCi/L)- = (l.96*(G+B)l/?)1iA ** * * (G-B) A= Gross alpha activity, pCi/L G = Sample gross counts .. B = Background counts (from blank sample) 

                                                                                                                                                                       .-.'}    :
                                                                                                                                                                       ...  ' ~
..* .. -:--,- ~,- .* - -*- *-.:***--,.. -.*****-**'7"-*-**," , ___ _ -** *_--.. ~--:---.,.---- ......... ,__ .... - ..--- ****--* - .

SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE GROSS BETA ANALYSIS OF AIR PARTICULATE SAMPLES . After allowing at least a three-day (extending from the sample stop date to the sample count time) period for the short-lived radionuclides to decay out, air particulate samples are counted for gross beta activity on a low back-ground gas proportiona1 counter. Along with a set of air particulate samples, a clean air filter is included as a blank with an sr-90 air filter geometry 

     .beta counting standard.

The gross beta activity is computed on the basis of tota1 corrected air flow sampled during the collection period. This corrected air flow takes into account the air pressure correction due to the vacuum being drawn, the correction factor of the temperature-corrected gas meter as well as the gas meter efficiency itself. calculation of Gross Beta Activity: Air flow is corrected first by using the* following equations: p = (B-V)/29.92 p = Pressure. correction factor B = Time-averaged barometric 

..                                                             pressure durinq samplinq period * *
                                                               "Hg v = Time-averaged vacuum during sampling period, "Hg 29 *.92 = Standard atmospheric pressure at 32°F, "Hg V = F*P*0.946*0.0283 E                                         F = Uncorrected air flow, ft 3 0.946 = Temperature correction factor from 60°F to 32°F 0.0283 = CUbic meters per cubic foot E = Gas meter efficiency (= %

efficiency/100) v = corrected air flow, m3 p = Pressure correction factor Using these corrected air flows, the gross beta.activity is computed as follows: Result (pCi/m3 ) = (G-B)/T ( 2

  • 22 ) * ( E) * ( V )" G = Sample gross counts B = Background counts (from blank
filter)

T =Count time.of sample and blank, mins. E = Fractiona1 Sr-90 counting efficiency

  • v =corrected air flow of sample, m 2.22 = No. of dpm per pCi
  • j

.i 

 '                                                    122
  • 2-sigma. error (pCi/m3 ) = (l.96,..(G+B)l/2)*A (G-8)

A = Gross beta activity, pCi/m 3 G = Sample gross counts B = Background counts (from blank filter)

  • ca.J..culation of lower limit of detectiong A sample activity is assumed to be LLD if the sample net count is less than
  . i 4.66 times the standard deviation of the count on the blank.

LLD(pCi/m3) = 4.66 "' (B)l/2 (2.22)*(E)*(V)*(T} B = Background counts (from blank filter) E = Fractional Sr-90 counting efficiency v = Corrected air flow of sample, m3 T = count time Of blank, mins. i_

  • 1

. ,j

SYNOPSIS OF TELEDYNE I.SOTOPES PROCEDURE* . .._,_ **--* ~ _,__ -* .. ANALYSIS OF AIR PARTICULATE*. FILTERS* FOR *GROSS ALPHA .AN:El BETA* --- The ai.r filter is .first stored for 2 to 5 days from date of receipt to allow. for decay of the radon-thoron daughters. It is then placed in a stainless steel planchet which has been coated in the center with rUbber cement. The filter is then counted for beta activity and subsequently repeat counted for

  • alpha activity (at a different voltage setting) in a Beckman-Sharp Wide Beta II autQmatic alpha-beta counter.

Gross alpha and beta activity (pCi/m3 ) are computed as follows: A= (G/T -B) +/- ~m*((G/T +B)/T)l/2 (2.22*V*Y*D*E) (2.22*V*Y*D*E) Where G = Total sample counts B =Background counts per.minute T = Sample count time, mins. 2.22 = dpm/pCi V = Sample volume, m3 Y = Chemical yield (Y = l in this case) D = Decay factor from collection to count date (D =l in this case) E = Counter efficiency 

                                                              ~m = Multiples of counting error If the net activity (G/T -B) is equal to or less t.han the counting error, then the activity is considered to be the minimum detectable level, or MDL.

where MDL = 3*(2*B/T)l/2 (2.22*V*Y*D*E) Variables are as previ~usly defined 124 .. , ' I .* * . F * 

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

1*.* SYNOPSIS OF PSE&G RESEARCH CORl?OaATION PROCEDURE GROSS BETA ANALYSIS OF WATER SAMPLES The sample is m.iXed thoroughly. Then, a l.O liter portion is removed from the potal:!le, rain or well water container and 250ml taken from each surface water. A deionized water blank is prepared for each di.fferent volume of sample (e.g. l.O liter blank for l.O liter samples and 2SOml for 250ml samples). All samples and blanks are then evaporated on a hotplate until the volume approaches 20 to 25ml. At that point, the samples and blanks are transferred to tared stainless steel ribbed planchets and evaporated to dryness under an infrared heat lamp. They are sUJ:lsequentlY cooled in a desiccator, weighed and counted on a low background gas proportiona.1 counter along with an sr~90 source of the same geometry. calculation of Gross Beta Activity~ Result {pCi/L) = (G-B)/T (2.22)*{E)*V)*(S) G = Sample gross counts B = Background counts (from blank sample) T = Count time of sample and. blank E. :.:;, Fractional counting efficiency 

                                                                                                      . * . <'*from sr~9o source v ~ Sample volume, liters S ~ NormaL.ized efficiency regression equation as a function of thick=

ness 2.22 = Noe of dpm per pCi 2-sigma error {pCi/L) = (l.96*(G+B)l/2)*A (G--B) A = Gross beta activity, pCi/L G = Sample qross counts B ~ Background counts (from blank 

        .... -:-;                                                                                              sample)
           . . ~
-~

-~{*'.jt'.-~-~ _>[ 

  . **.r* -: .:

125 _._.-' l 

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SYNOPSIS OF l?SE&G RESEARCH CORPORATIO

N. PROCEDURE

ANALYSIS OF WATER FOR .POTASSIUM 40 A 60 ml aliquot of water sample (with the exception of rain water) received by the Research and Testing Lal:loratory is first acidified to pH <2 With con-centrated nitric acid and then analyzed. for potassiwn by the following Atomic Absorption Spectrophotometry method: potassiwn standards of known concentra-tion (similar to that of the unknowns) are first prepared. An aliquot of each sample and standard is pipetted into stoppered flasks. In addition, a duplicate sample, ERA standard and blank water sample are likewise pipetted into their respective flasks. A solution consisting of 4% sodiwn is diluted 1:1 with water and then added to all the flasks. Depending on the AA instrument used, a calibration curve is prepared from the standards after which the samples are ~hen run. If the al:lsorbance of any sample is higher than the upper standard used, the sample is then either diluted and re-run, the burner head turned 90°, a more concentrated standard added to the calibration curve or a less sensitive wavelength used. Tne results, reported in parts per million (ppm), are converted to pCi/L by means of a computer program. Calculation of K-40 Activity: K-40 Activity (pCi/L) = 0.85*C 0.85 = Proportionality constant for converting ppm to pCi/L c = Potassium concentration, ppm 

  . ~
    '                                                                                                                                  126
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----~--.-*--::;---.~: --,---..~*~7*:*-- *-*--***-~ --.-~---~ ...

SYNOPSIS . OF' PSE&G RESEARCH CORPORATION . PROCEDURE .* ANALYSIS OF WATER FOR TRITIUM ApproXj.mately SOml of raw sample is mixed with sodium hydroxide and potassium permanganate and is distilled under vacuum" Eight mi of distilled sample is mixed with lOml of Instagel liquid scintillation solution, and placed in the liquid scintillation spectrometer for counting. An internal standard is prepared by miXinq Sml of sample, lOml of Instagel, and o.lml of a standard with known activity. The efficiency is determined from this. Also prepared is a blank consisting of Sml of distilled low~tritiated water and lOml of Instagel, to be used for a background determination. This is done for each pair of samples to be countedc Activity is computed as follows: A (pCi/L) = (G-B)*(lOOO) 2.22*(E)*(V)*(T) A = Activity B = Background count of sample G = Gross count of sample E = Counting Efficiency v = Aliquot vol.ume (ml,) I T = count. time (min) 

                                                *'"     2o22 - DPM/pCi .

1000 = Number of m.l per L Efficiency (E) is computed as followsg E = (N)*(D) 

                  .A' N = Net CPM of spiked sample D = Decay factor of spike A' = DPM of spike N is determined as follows:

N = C~(G/T) 

 - .......                                                 C = CPM of spiked sample G = Gross counts of sample
        .~

T = Count time (m.in) The associated error is expressed at 95%-confidence l.imit,.as followsg l.96*(G/T2 +B/T 2 ) 1 /2 ~(l000) 2.222 (V) * (E)

  • . J
       *i Samples are designated LLD if the activity is less than the following value:

LLD (pCi/L) == (4o66)*(B) 112.,ciooo) 2.22*(V)*(E)fl(T)

SYNOPSIS OF CONTROLS FOR ENVIRONMENTAL .POLLUT.ION, INC., PROCEDURE TRITIUM ANALYSIS OF AQUEOUS FRACTION OF BIOLOGICAL MATERIALS An aliqtlot of fish or cral:J flesh is placed in a round bottom flask, along with 200ml of benzene, and the water removed via azeotropic distillation. Three milliliters of the extracted water is then mixed with aquasol cocktail (NEF-934 Aquasol cocktail, manufactured by New England Nuclear corporation). The resultant miXture is comprised of 19 percent sample in a clear gel-type aquasol and provides a tritium counting efficiency of approXimately 30 percent, when counted on a Beckman r..s~100 Liquid Scintillation Spectrometer. The efficiency of the counting system is determined by placing 6 tritium standards (certified by NBS) before each set of water samples to be counted. The counting efficiency is determined from these standards which are equal in activity but vary in the amount of quenching. All samples are counted for 500 minutes each. 

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SYNOPSIS OF PSE&G RESEARCH CORPOAA'l'ION'

  • PROCEDURE *.

GAMMA ANALYSIS OF AIR IOD!NE ApproXiJnately 30om3 of air is drawn through a SOml

  • b_ed of triethylenediamine (TEDA)=impreqnated charcoal granules at a rate which closely corresponds to the :breathing rate of an adult male. The contents of the exposed air iodine cartridge are emptied into an aluminum sample can containing SOml of fresh TEDA-impregnated charcoal. The can is hermetically sealed and then counted on a gamma detector.

ca1culation of Gamma Activity~ The followinq are the ca.l.culations performed for the gamma activitYr 2 sigma 00 error and LLD: Result (pCi/m 3 ) = N*D =R (2.22}*(E)*(A)*(T)*(V) N = Net counts under photopeak D = Decay correction factor Atl.*EXP(At2) l.-EXP( 00 ~tl) 

                           '   .                          Acquisition live time
                        ._*i                        tl. ~
                        ~: : ..~:.-.                t2 = Elapsed time from sample collection to start of acquisition
                                                     ~ = 0.693/nuclide half life E = Detector efficiency A = Gamma al:>undance factor (no. of photons per disintegration)

T = Acquisition live time, mins. v = Sample volume, m3 2o22 ~ No. of dpm per pCi 2~sigma error (pCi/m3 ) = 1.9S*(GC+Bc) 112 *R N Ge = Gross counts BC ~ Background COW'ltS All other varia.Dles are as defined earlier. The LLD (pe1/m~) = 4.ss~cac) 1 12 ~o (2.22)~(E)~(A)*(T)*(V) i l 

            *I SYNOPSIS OF TELEDYNE ISOTOPES PROCEDURE ANALYSIS OF CHARCOAL. FILTERS FOR. I(JDINE-131 Charcoal car~ridges are analyzed for I-131 using a lithiwn-drifted germanium detector interfaced With a 2048 channel pulse height analyzer calibrated at l.O Kev per channel. Teledyne Isotopes employs one of three possible data acquisition and computation systems. The first, a Data General NOVA mini-computer, in series with the pulse height analyzer, calculates* the number of
                                              .counts (and the standard deviation) in the peak region by performing a linearly-interpolated background subtraction. If no peak is observed, then only tne background is used (along with sample volume, collection date and length of count) to.determine the detection lilni.t. The activity or MDL of each nuclide is computed on an IBM 360. This semi-automatic system is in contrast with the other two data acquisition* and computation systems, namely, a Tracor Northern TN-11 and a Nuclear Data 6620, which perform all the above computations automatically. All resultant spectra are stored on magnetic tape.
          .*,*\
       *1
  -    ~
          .i 130
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SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE ... ANALYSIS OF RAW MILK FOR IODINE-l3l Stable iodine carrier is equil.:U:lra.ted in a 4~J.iter volume of raw milk before two separate SOml batches of anion exchange resin are*introduced to extract iodine. After each batch has been stirred in the milk for an appropriate timef both are then transferred to an aluminum sample can where the resins are rinsed with demineralized water several times and any leftover rinsewater removed with an aspirator stick. The can is hermetically sea:led and then counted on a qamma. detector. C!a.lcUl.ation of I~l3l Activity: I~l3l Results (pCi/L) = (G->B)/T*(l.OS)x(H) (2.22)*(E)*(V)*(Y) G = Sample gross counts B = Background counts (from blank sample) 

                                                             'I' = count time of sample and blank E = Eo*EXP{-A.*M) = efficiency equation where Ea ~ countinq efficiency at zero sample thickness A.  =  Self~cwsorption coefficient M = sample thickness, mg/cm2 v :.:: Sample volume, liters y = Chemical recovery =

R 

                                                                                    ~--

Rl+R2 where R = mq of I- recovered Rl = mq of I- carrier. added R2 = mq of intrinsic staole I- measured in sample 

       . ~~,_.;

l.05 = Correction factor for protein~

-~ bound iodine H ~ J/(l-K)*EXP(L) = correction factor for I-131 decay during count.i.nq period J = (Oc693/8.0S)~(R/l440)
                                                                 =

R count time, minutes l440 = Noc of minutes per day 8c05 = Hal,f~life Of I=l3lf days K "" EXP(~J) L = (0~693/8.0S)*N N = Elapsed ti.me (days) from mid= point of collection period to beginning of count time * . ~- *. : '

SYNOPSIS OF PSE&G .RESEARCH CORPOBATION~-PROCEDURE . BADIOSTRONTIUM* .ANALYSIS OF AIR FILTERS The air filters are placed in a sma1l beaker and just enough fuming nitric acid is added to cover t~e filters. A blank, composed of the same number of clean air filters, is prepared in the same way. Stable strontium carrier is then introduced into each sample and several fuming nitric acid leachings are carried out to remove the radiostrontium from the filter media. once this is done, the resultant nitrates are dissolved in distilled water and the filter residue is filtered out. Radioactive interferences are stripped out by coprecipitation on ferric hydroXide (yttrium strip) followed by a barium chromate strip. The strontium* is precipitated as a carbonate, which is dried and weighed. The samples and b~ank are then counted on a low background gas proportional counter and, again, at least 14 days later. The basis for this two count method is-that sr-90 and sr-89 are both unknown quantities requiring two simultaneous equations to solve for them. . calculation of sr-90 Activity:

  • sr-90 Results (pCi/m3 ) = N4/R (2.22)*(E)*(E(l5)/E')*(S6)*(V)*(U)
                                                                                              = W2 where SS           = A + B*M     + C:11M~ (This is the general form of the norma1ized Sr-90 efficiency regression equation for one particular gas proportional counter, where A, B ~d Care regression coefficients.)

M = Thickness density of strontium carbonate precipitate, mg/cm2

  • E(l5)/E' = Ratio of sr-90 efficiency at thickness value of l5mg/cm2 to sr-90 counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples)

E = sr-90 counting standard efficiency v = sample quantity (m3) u = Chemical yield 

              .,                                         N4 = (N2           Fl*Nl)/W1                        = net              counts due to sr-90 only i

1 

          - *\
              *1 Il = l - EXP ((-0.693/2.667)*tl)

I2 = l - EXP ((-0.693/2.667)*t2) tl = Elapsed time from Y-90 strip to first count 

 . *: . ,.. j 132
         .. j
                 - - - - * ---*-* - ~--- --*--- ----_~.. *-....--*-----**-~-~-; -:-- *. .-.---'"-~*--::"':' . ,:--~~-"--::--*-;---- - -- --~... -~*--:-:--=*~---~-:* -* :--~--.,---- .,.- ---- *------, ... -* - - - -- - - - *:- ....... - ..... - *. --

t2 = Elapsed tJ.me from. Y-90 strip* to second count*** - 2.667 = Half-life of Y-90, days R1 =D + E*M + F*M2 (This is the general. form of the regression equation for Y-90 effwy/sr-90 eff'Y ratio for one particular gas proportionaJ. counter, where D, E and F are regression coefficients.) N2 =X - Y, where X and Y are recount gross counts and background counts, respectively Nl = Xl ~ Ylu where Xl and Yl are initi.a.l gross counts and background counts, respectively 2.22 = No. of dpm per pCi Fl= EXP ((-0.693/2.667)*t2) i R = Count time of sample and blank Using the same variable definitions as above, the 2-sigma error for sr-90 (pCi/m3 ) = Again, keeping the same variable definitions, the LLD for sr-90 (pCi/m3) = 

                                                                                                 + (Xl+Yl1*Flj l/:2 Wl         .

ca.J.culation of sr-89 Activity: sr-89 Results (pCi/m3 ) = N6/R 

                                                                                                    . (2.22)*(E)*(E(l5)/E')*(S7)*(V)*(U)*(F9)

S7 ~ G + H*M + I*M2 ('rh.is is the general. form of the normalized sr~89 efficiency regression equation for one particular gas proportional 

*1 counter where G, Hand I are regression coefficients.)

N6 = Nl - N7*(l + Rl*Il) H'1 = (N2 ~ Fl*Nl)/Wl (This represents ec:runts due to Sr=90) E(l5)/Ew = Ratio of sr-89 efficiency at thickness value of l5mq/cm2 to sr countinq standard efficiency run at the time of instrument cal.;U:)ration (This standard is run with each group of environmental stront.iwn samples). 

   ---..---.-~*- .--------,--:-*-*....---..------*- :-'..,.........,:--.-0*~**.-.*-:;- -*.....,-.-**-**--~-----------~~ .. -------..-,......-~~-*-- *.-;--o- **-~:-""..,_ **. ,-. -::---:-*:--.--**-****--. *--**** *-----: ~':'"*---*-~* ..* , "n ---* - * - ... - - * - ** ** - - - - ....

F9 =EXP _((-0.693/S0.5)~t) t =Elapsed time from midpoint of collection.period.to time of recount for milk samples only. For all other samples, this represents the elapsed time from sample stop date to time of recount. 50.5 = Half-life of Sr-89, days All other quantities are as previously defined. The 2-sigma error for sr-89 (pCi/m3 ) = 2* (sa2+s92)2 ~W3 (Nl - N7*(l+Rl*Il)) S9 = (Xl+Yl).1 / 2 All other variables are as previously defined. Keeping the same variable definitions, the LLD for sr-89 (pCi/m3 ) = 4.66*(sa2 +s9 2 ) 1 12 

      *.    ~:
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         . i
  • .: *. j 134
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     *-.; i
                  -----.----~ ... - - - - - - - _ _ _ _ ..,.....:. _ _* -
                                                                        ** ----.---~.-- - - * --~---------*-:";"".,- ---*- ___ _,, _ _ _ _,_"""7 - ----- - - -----_:." ~ ** - **..-- - --- -- - - -*----- - -* -* -- - - -~. - -

SYNOPSIS OF *TELEDYNE *ISOTOPES PROCEDURE.* ANALYSIS OF COMPOSITED AIR PARTICULATE FILTERS FOR RADIOSTRONTIUM The composited air filters are leached with concentrated nitric acid, with 

           *heating, in the presence of strontiwn carriero After adding deionized water, the sample is gravity filtered through a paper filter and the filtrate diluted further with additional deionized water, cefore ceing split into two equal parts. One part is put aside for gross alpha analysis. and the other part evaporated on a hotplate to a small volume. The sample is transferred to a centrifuge tu.be and fuming nitric acid added to form the strontium nitrate precipitate. After centrifuging and pouring off the supernate, the precipi=

tate is dissolved in deionized water and an iron scavenge performed. This marks the ~eginning of the Y~9o ingrowth period. centrifuging and discarding the precipitate, standardized yttr1Wl1 carrier is added to the supernate and the sample is set aside for 5 to 7 days. After this period, the sample is alkalinized with ammonium hydroXide and heated in a hot water oath to form 

          *yttrium hydroxide. After cooling, the sample is centrifuged and the supernate saved for Sr-89 determination. The precipitate is dissolved with dilute nitric and hydrochloric acids, and the yttrium precipitated as oxalate using saturated ammonium oxalate solution. The yttrium oxalate is mounted on a .

tared paper filter, oven dried, weighed and counted on a gas proportional counter. 'l'he sample is then recounted the fol1owing day to confirm the decay of Y-900 The superna.te, saved for sr-89 determination. is treated with saturated sodium car~onate solution to precipitate strontiwn carbonate which is filtered on a tared qlass fil:ler filter, oven-dried and likewise counted 200 minutes on a gas proportional. counter. These samples, however, are covered with an aomq/cm2 aluminum al:>sorber to stop the sr~90 beta emissions, thus allowing the Sr-89 betas to be counted aloneo The sr-89 activity (pCi/m3 ) is computed as follows: A = (G/T-Bc-Ba) +/- ~m*((G/T+Bc+Ba)/T)l/2 (2.22*V*Y*D*E) (2.22*V*Y*D*E) If the net activity (G/T -a) is less than or equal to the 2a: counting error, the activity is considered MDL 

     .!                  where MDL   =  2*(2:eB/T)l/2 (2.22*V*Y:eD:sE) where    G  = Total. sample counts
                    'r = sample count time, mins
  • Be =Background rate of counter,-cpm

..* Ba = Backqround addition from Sr-90 and ingrowth of Y~90 2o22 = dpm/pCi 

      *.            v = sample volume, m3 y = Chemical yield of strontium D = sr~89 decay factor from midpoint of collection period to counting date.

E = sr-89 counting efficiency with 80 mq/cm2 alW!Unum absorber a:m = MUl.tiples of counting error 

   . I
.    'i

The sr-90 activity (pCi/m3 ) .is computed as.* fol.lows; A = (G/T-B) +/-. ~m*((G/T+B)/T) 1 / 2 (2.22*V*Y*D*E) (2.22*V*Y*D*E) Y = Chemica1 yieJ.d of the mount or sample counted D = Decay factor from the colJ.ection to the counting date E = counter efficiency AJ.1 other variabJ.es are as previousJ.y defined. If the net activity (G/T-B) is less* than or equa1 to the 2~ counting error, the activity is considered MDL 

          . j where MDL                   =              2*(2*B/T) 1 /2 (2.22*V*Yi*Y 2*I*D*&)
      ~ :     _;

.. ____ :_~--- - 136 

                 -----~ -- ---------~---- -----=- -~*- -....---..--,,_-.-,....,--~-- - - -----:,.--------"<'"' --_--:--:,.........- ------~-- -**- ----- .,......,,__, -c------**-.----*.~-

SYNOPSIS OF PSE&G. RESEARCH CORPORATION PROCEDURE *. RADIOSTRONTIUM ANALYSIS.OF*RAW MILK StalJle strontiwn carrier is first introduced into.a nti.lk sample and into a distilled water sample of equal volume to be used as a blank. The sample(s) and blank are passed through cation resin columns which adsorb strontium, calcium, magnesium and other cations. These cations are then e1uted off with a TRIS-buffered 4N sodi~ chloride solution into a beaker and precipitated as carbonates. The carbonates are converted to nitrates with 6N nitric acid and, by aqidifying further to an* overall concentration of 70% nitric acid, strontium is forced out of solution somewhat ahead of calcium. Barium chromate precipitation is then performed to remove any traces of radium and rad.iobarium.e Strontium recrystallization is carried out to remove residual calcium which may have been coprecipitated with the initial strontium precip~ itation. Another recrystallization removes ingrown Y=90, marking the time of the yttrium strip * . The strontiwn is precipitated as its carbonate, filtered, dried and weighe~ to determine strontium recovery. The samples and blank are then counted on a low background gas proportional. counter and, again, at least 14 days later. The basis for this two-count method is that sr-90 and sr-89 are both unknown quantities requiring two simultaneous equations to solve for them. caiculation of 0 Sr~9o Activity: Sr-90 Results (pCi/L) = N4/R (2o22)*(E)*(E(l5)/E 9 )~(S6)*(V)li(U) where SS =A + B*M + C*M2 (This is the qenera1 form of the norma1ized Sr-90 efficiency regression equation for one particular gas proportional counter, where A, Band care regression coefficients.) M = Thickness density of strontium carbonate precipitate, mg/cm2 E(lS)/E' = Ratio of sr-90 efficiency at thickness va.l.ue of l5mg/cm2 to Sr-90 countinq standard efficienc:y run at the time of instrument cal.illration (This standard is run with each group of environmental strontium samples)

  • E = sr~90 countinq standard efficiency

.l v .,, Sample quantity (liters) u "" Chemical yiel.d N4 "':! (N2 ~ FlsaNl)/Wl = net counts due t.o Sr=90 onl.y Wl, 

                                                  "" ((l + R11iI2)                ~      (1 + R1*Il}liFl)

Il, 

                                                  ""   l~      EXP ((=Oo693/2o667)*'t:l}

I I. 

   - - * ... **-* - * -----~.---: --:--*-:--,------.~~--,* ~*-----~-------. .. -~..,._-o";"..--;-T--*--,*:- **-* ,. ---~***.**-*-:- -;-*--:-* -----;

_.. ~ 

       "j I2 = 1              -   EXP     {(-0.693/2.667)*t2) tl = Elapsed time.from Y-90 strip to first count*

t2 = Elapsed time from Y-90 strip to second count 2.667 = Half-life of Y-90, days Rl = D + E*M + F*M2 (This is the general form of the regression equation for Y-90 eff'y/sr-90 eff'Y ratio for one particular gas proportional counter, where D, E and F are regression coefficients.) H2 = X - Y, *where X and Y are recount gross counts and back~ound counts, respect~vely Hl = Xl - Yl, where Xl and Yl are initial gross counts and background counts, respe~tively 2.22 = Ho. of dpm per pCi Fl= EXP ((-0.693/2.667)*t2) R .:. count time of sample and blank Using the same variable definitions as above, the 2-sigma error for Sr-90 (.pCi/L) = 2* lix:u.l + (XJ+Y1}*F12]l/2* (Wl*W2). Lwi2 Wl J (H2-Fl*Nl) Again, keeping the same variable definitions, the LLD for sr-90 (pCi/L) = 4.66* ~ + (Xl+Yla*n 2J l/2 Lwi wi J calculation of sr-89 Activity: sr-89 Results (pCi/L) = N6/R (2.22)*(E)*(E(l5)/E')*(S7)*(V)*(U)*(F9) 

                                                                                                                       = W3 S7        =G+           H*M + I*M2 (This is. the general form of the normalized sr-89 efficiency regression equation for one particular gas proportional counter where G, Hand I are regression coefficients.)

NS = Nl - N7*(l + Rl*Il) N7 = (N2 - Fl*Nl)/Wl (This represents counts due to Sr-90) 138 

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

E(lS)/Ew = Rat:ro of.Sr;..99 effic.iencyat thickness va.J.ue of lSmq/cm2 to sr-90 counting standard ef.ficiency run *at the time ~.of instrument calibration (This standard is.run with.each grqup of environmental strontiwn samples) .*. t = Elapsed t.ilne from midpoint of collection period to time of recount for milk samples only. For all other samples, this represents the elapsed t.ilne from sample stop date to time of recount. All other quantities are as previously defined. The 2-sigma error for sr~eg (pCi/L) = 2* (sa2+s92)1/2 *W3 (Nl - N7*(l+Rl*Il)) sa =f<x+Yl + <xi+n~*Fl ~ l/2 Lw1 2 w1 J S9 = {Xl+Yl)l/2 

           . All.other varial:Jles are as previously definedQ i

' ..~

SYNOPSIS OF P.SE&G RESEARCH' CORPORATION* *PROCEDURE_*:.:*;.... - RADIOSTBONTIUMANALYSIS OF WATER Stal:>le strontium carrier is introduced into a water sample and into a distilled water sample of the same volume which is used as a blank. The sample(s) and blank arethen made alkaline and heated to near boiling"before precipitating the carbonates. The carbonates are converted to nitrates by fuming nit~ic acid recrystallization which acts to purify the sample of most of the calcium. Radioactive interferences are stripped out by coprecipita-tion on ferric.hydroxide (yttrium strip) followed by a barilim chromate strip. The strontium is precipitated as a carbonate before being dried and weighed. The samples and blank are then counted on a low background gas proportional counter and, again, at least 14 days later. The basis for this two count. method is that sr-90 and sr-89 are both unknown quantities requiring two simultaneous equations to solve for them. Since surface waters , _as well as some drinking water samples , have bee*n found to contain significant amounts of siaJ:>le strontium, a separate aliquot from each sample is a.!alyzed for stal:>le strontium. These results are used in correcting the chemical recovery of strontium to its true value. Calculation of sr-90 Activity: Sr-90 Results (pCi/L) = N4/R (2.22)*(E)*(E(lS)/E')*(S6)*(V)*(U)

  • = W2 where SS =A + B*M + C*M2 (.This is the general form of the normalized sr-90 efficiency regression equation for one particular gas proportional counter, where A, Band care regression coefficients.)

M = Thickness density of strontium carbonate precipitate, mg/cm2 E(lS)/E' = Ratio of sr-90 efficiency at thickness value of 1Smg/cm2 to Sr-90 counting standard efficiency run at the time of instrume.nt calibration (This standard is run with each group of* environmental 

  . j'                                                        strontium samples)
     ..                                               E   = sr-90 counting standard efficiency
.. j
   ~-:.

v = Sample quantity (liters) 

  .. j u   = Chemical yield N4    = (N2 - Fl*Nl)/Wl = net counts due to                                  Sr-90 only Wl    = ((l + Rl*I2) - (l + Rl*Il)*Fl)

. ::~::J .*.*

  • 1 Il = l - EXP ((-0.693/2.667)*tl) 140*
   .. ,.')

i 

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

I2 =l - EXP ((-0~693/2.667)*t2) tl =Elapsed time*from Y-90 strip to first count t2 = Elapsed time from Y-90 strip to second count 2.667 = Half-life of Y-90, days R1 = D + E*M + F*M2 (This is the general form of the regression equation for Y-90 eff'y/Sr-90 eff 'Y ratio for one particular gas

  • proportional counter, where D, E and F are regression c:oeffic.ients.)

N2 =X - Y, where X and Y are recount gross counts and background counts, respectively Nl = Xl - Yl, where Xl and Yl are initial gross counts and background counts, respectively 2.22 = No. of dpm per pCi Fl= EXP ((-0.693/2.667)*t2) R = count time of sample and :blank Using the same variable definitions as anovef the 2=sigma. error for sr-90 (pCi/L) = 2~ r~ + CX1+Yl~*F11l/2 1i (Wl*W2) LWl Wl (N2-Fl*Nl) Again, keeping the same variable definitions, the LLD for Sr-90 (pCi/L) = 4.66*[<x+Yl t (Xl+Yl~*Fl] l/2 Wl 2 Wl caJ.culation of sr-89 Activityg sr~eg ResuJ.ts (pCi/L) = N6/R

  • , (2.22)*(E)*(E(l5)/E')*(S7)~(v)~(U)*(F9)
                                                                              = W3 S7 =    G   + R1iM + I*M2 (This is the general form of the normalized sr~89 efficiency regression equation for one particular gas proportional counter wn.ere Gf H and I are regression coefficients * .)

N6 = Nl - N7*(l + Rl*Il) N7 = (N2 = Fl*Nl)/Wl (This represents counts due to Sr=90) 141 

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

E(lS)/E' =Ratio of sr-89 efficien~y at* thickness valu~ of l5mq/cm2 to sr-90 count.inq standard efficiency run at the time*of i.ns-trument calibration (This standard is. run.with each qroup of environmental strontiuin samp~es)

  • F9 = EXl? ((-0.693/50.S)*t) t = Elapsed time from midpoint of collection period to time of recount for milk samples only. For all other samples, this represents the elapsed. time from sample stop date to time of recount.

so~s = Half-life of. sr-89, days All other quantities are as previously defined. The 2-sigma error for sr-89 (pCi/L) = 2* (sa2+592yl/2 *W3 (Nl - N7*(l+Rl*Il)) sa =Rx+;) + cx1+na*r1j l/2 Lw1 wi S9 = (Xl+Yl) 1 / 2 All other variables are* as previously defined. Keeping the same variable defini.tions, the LLD for sr-89 (pCi/L) = 4.ss*(sa 2+s9 2 ) 112 

           . I
           .t
'_ .* 142
               ----------- ~-~-~----,-~--- ... ----~-----~---- - - - - - ---,..~------ .. - -~- --~--- ----~ - .-- - * ----- -- **. ..,.. - ~ -* **.---**~ ---.- -._::--.." .** *.*=-. r-****-:---**-.

SYNOPSIS OF PSE&G RESEARCH CORPORATION*: l?ROCEDURE - RADIOSTRONTIUM ANALYSIS OF VEGETATION, MEAT AND AQUATIC SAMPLES The samples are weighed (recorded as "wet" weight) as received, .before .being placed in an oven to dry at l00°Cc At the completion of the drying period, samples are again. weighed (recorded as "dry" weight) and then pulverized. A measured amount {quantity dependent on desired sensitivity) of the pulverized sample is first charred over a Bunsen .burner and then ashed in a muffle - furnacec The ash is fused with 40g sodium carbonate, along with 20mg strontium carrier, at 90o 0 c for 1/2 hour. After removal from the f~rnace, the melt is cooled, pulverized and added to 500ml distilled water and heated to near boiling for 30 minutes, with stirtingc The sample is filtered (filtrate discarded) and the carbonates on the filter dissolved with lgl nitric acid (HNa 3 ). The resultant nitrates are heated to dryness and are dissolved in 20ml di,stilled water before adding 60m.J. fuming HN0 3 o After calcium removal with anhydrous acetone, radioactive interferences are stripped out by coprecipitation on ferric hydroXide followed by. coprecipitation on barium chromate. *The strontium is precipitated as its carbonate, which is dried and weighed. The samples are then counted on a low background gas proportional counter and, again, at least 14 days later. The basis for this two-count method is that ~r-90 and sr-89 are .both unknown quantities requiring two simultaneous equations to solve for them *

  • caicuiation of sr-90 Activity:

Sr=90 ResUl.ts (pCi/kq wet) = 

                                                                                                          = W2

( 2 e 22 ) "' ( E) "' ( E ( 15 ) /E: i N4/R 

                                                                                                                                                                          ) .... (SS ) "' ( V ) * ( u.)

where SS =A + B*M + C*M2 (This is the general form of the normalized sr-90 efficiency regression equation for one particular gas proportional counter, where A, Band care regression coefficients.) M = Thickness density of strontiwn carbonate precipitate, mg/cm2 E(l~)/Ev = Ratio of sr~9o efficiency at tlti.ckness va.J.ue of l5mg/cm2 to. sr~9a counting standard efficiency run at the time of instrument Cal.illration ('rhiS Standard is run With each g'I'OUp Of environmental strontiwn samples) E = sr-90 countinq standard efficiency V = Sample quantity (kq wet) u = Chemical yield N4 = (H2 Fl"'Hl)/Wl. = net counts due to sr~9o only 

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

Il = l -*EXE' ((-0.693/2.667)*'!:1) I2 = l - EXE' ((-0.693/2.667)*t2) tl = Elapsed time from Y-90 strip to first count t2 = Elapsed time from Y-90 strip to second count 2.667 = Ha1f-life of Y-90, days Rl = D + E*M + F*M2 (This is the genera1 form of the regression equation for Y-90 eff'y/Sr-90 eff'Y ratio for one particular gas proportiona1 counter, where D, E and F are regression coefficients.) N2 =X - Y, where X and Y are recount gross counts and background counts, respectively' Nl = Xl - Yl, where Xl and Yl are initia.J. gross counts and background counts, respectively 2.22 = No. of dpm per pCi Fl = EXP ((-0.693/2.667)*t2) R = count time of sample and blank 

         -~                         Using the same varial:lle definitions as above,
         *'                         the 2-siqma error for Sr-90 (pCi/kg wet) =

2*r~ + (X1+Y1~*F111/2* (W1*W2l Lw1 w1 (N2-Fl*Nl) Again, keeping the same variable definitions, the LLD for Sr-90 (pCi/kq wet) = 4.66* ~~;> + (Xl+Y1l*F121 l/2 calculation of sr~99 Activity: Sr-99 Resul.ts (pCi/kq wet) = N6/R 

        ;:*!                                                                                    (2.22)*(E)*(E(l5)/E')*(S7)*(V)*(U}*(F9}
          .~
                                                                                            = W3 S7    = G + H*M +               I*M2 (This is. the genera1 form of the normaJ.ized Sr-89 efficiency regression equation for one particular qas proportional counter where G, Hand I are regression coeff:Lcients.}

N6 = Nl - N7*(1 + Rl*Il) 

          . ~
= ***:

144 

         ~--' - - _______ + _ _ _r -,.--------~-.-~-r.*..,__,....__~,.-,-,---. -------~--*-*---;**.-* -******---..-.,....*--*-:----,....---,--~---."""": -*"":-.-:~--" -,...-.~*,...._,***** ** ****.-- -~*-.**-~~; *- --..~-* -**-:; . e-:** ;-  -*t~-

    -N7   = (N2     -   Fl:s.Nl)/Wl (This represents counts.due to Sr=90)

E(lS)/E' = Ratio of sr-89 efficiency at thickness *value of l5rng/crn2 to sr-90 counting standard efficiency run. at the.time* of instrument caJ..il'.>ration (This standard is run with each group of environmental strontium samples) F9 =EXP ((-0.693/50.S)*t) t = Elapsed time from midpoint of collection period to time of recount for milk samples only. For all other samples,_ this represents the elapsed time from sample stop date to time of recount. so.s = Half-life of sr-89, days A1l other quantities ~e as previously defined. The 2-sigma error for sr-89 (pCi/kg wet) = 2~ (sa 2 +s9 2 ll/2 1lW3 (Nl - N7*(l+Rl*Il)) SS =li.x.+/-..tl_ + (XJ+/-yJ~*FJJ l/2 

            ~                   Wl S9   = (Xl+Yl)l/2 Keeping the same variaJJle definitions, the LLD for sr-89 (pCi/kg wet)                          =

4.ss~csa 2 +s9 2 > 1 1 2 

                                                                              /
                                                                                * * * - " *r*-* **--;-**--.--* *-* .... - - - --~--.,***. -

SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE.* RADIOSTRONTIUM. ANALYSIS OF. BONE AND SHELL The bone or shell is first physically separated from the rest of the sample* before being broken up and boiled in 6N sodiwn hydroXide (NaOH) solution for a brief time to digest remaining flesh/collagen material adhering to the sample. After multiple rinses with distilled water, the bone/shell is then oven dried and pulverized. An aliquot of the sample is removed, weighed and ashed in a muffle furnace. Then, in the presence of strontiwn carrier and cesiwn holdl:lack carrier, the radiostrontium is leached out of the ash by boiling in diluted nitric acid, after which the sample is filtered. The sample is then treated with concentrated (70%) nitric acid and boiled 

     *. ~

until strontiwn nitrate crystallizes out. The strontiwn nitrate is freed of calcium by repeated fwning nitric acid recrystallizations*. From this point on, any radiological impurities are removed by coprecipitation with ferric hydroXide followed by coprecipitation with bariwn chromate. The strontium is precipitated as strontiwn carbonate, which is dried, weighed, then beta.- counted on a low background gas proportional counter. A second count is performed at least 14 days later. The basis for this two-count method is that Sr-90 and Sr-89 are both unknown quantities requiring two simultaneous equations to solve for them. caJ.cuJ.ation of sr-90 Activity: - . sr-90 Results (pCi/kg dry) = N4/R 

   ~.

(2.22)*(E)*(E(l5)/E')*(S6)*(V)*(U) 

                                          = W2 where S6   =A +  B*M + C*M2 (This is the general form of the normalized sr-90 efficiency regression equation for one particular gas proportional counter, where A, Band care regression coefficients.)

M = Thickness density of strontium carbonate precipitate, mg/cm2 

     - .i E(lS)/E'   = Ratio  of sr-90 efficienC:y at thickness val.ue of l5mg/cm2 to sr-90 counting standard efficiency run at the time of instrwnent Calibration (This' standard is run with each group of environmental
 -. t strontiwn samples)

E = sr-90 counting standard efficiency V = Sample quantity (kg dry) 

*~:     !

u = Chemical yield N4 = (N2 - Fl*Nl)/W1 = net counts due to sr-90 only 

                                                                                               -*- -* ." ~-~'--
    • Wl IJ.
                                                           = ((l + Rl*I2) ~ (l + Rl*Il)*Fl)
                                                           = l - EXP ((-0.693/2.667)*tl)

I2 = l - EXP ((-0.693/2.667)*t2) tJ. = Elapsed time from Y-90 strip to first count t2 = Elapsed time from Y-90 strip to second count 2.667 = Half-life of Y-90, days lU =D + E*M + F*M2 (This is' the general form of the regression equation for Y~90 eff'y/sr~90 eff 'Y ratio for one particular gas proportional counter, where D, E and F are regression 

                                                                .coefficients. )

N2 =X - Y, wnere X and Y are recount gross counts and background counts, respectively Nl = X1 - Yl, wnere Xl and Yl are initial gross counts and background counts, respectively 2.22 = No. of dpm per pCi Fl= EXP ((-0.693/2.667)at2) R = Count t.ime of sample and :t:llarut Using the same variable definitions as above, the 2-sigma error for sr-90 (pCi/kg dry) = Again, keepinq the same variable definitions, the LLD for sr-90 (pCi/kg dry) = 4.66111 ~~p + (Xl+;;:~*Flj 1/2 caJ.cul.ation of sr~89 Activityg sr~89 Results (pCi/kg ctry) = N6/R (2.22)*(E)~(E(l5)/E')*(S7)~(V)*(U)~(F9) S7 =G + H~N + I*M2 (This is the general. form of the normalized sr~89 efficiency regression equation for one particular gas proportional counter where G, Hand I are regression coefficients.) i 

. l
      **- -----.---- ---:--- * * - - - ----.--*--- .-----..,--- *0*--..~~---* ---;- *--. -~- .,..*. -**- ----- -- --- ---- ---~-;-~----r--- ..... ,. .. -**------ - :_ --~--- -**-- -- -- ****--* ------, ....... *- ---- .. ---*-*- *c-:-.--- --*

N7 = (N2 - Fl1tNl)/Wl (This represents .counts. due to sr~9a) E(lS)/E' = Ratio of Sr-89 efficiency at thickness value of l5mg/cm2 to sr-90 counting standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontium samples) F9 =EXP ((-0.693/50.S);tt) t = Elapsed time from midpoint of collection period to time of recount for milk samples only. For all other samples, this represents the elapsed time from sample stop date to time of recount. so.s = Half-life of sr-89, days All other quantities are as previously defined. The 2-sigma error for sr-89 (pCi/kg dry) = 21' (sa2+s92)l/2 *W3 (Nl - N71t(l+Rl*Il)) SS = r~~) + (X1+~~*Flj l/2 S9 =* (Xl+!l)l/2 All other varialJles are as previously defined. Keeping the same varialJle definitions,. the LLD for Sr-89 {pCi/kg dry) = 4.66*{S82 +s9 2 ) 1 / 2 

 ...     ~
         )
        'l
  • _.,. :**i

. ' ~ 

       *t
                                                                               --.--.--~-""- --.-~-::-**-.--:- *-;---,-*-*-'---   - --      - -~ . - - .....
  • SYNOPSIS OF PSE&G RESEARCH CORPORATION PROCEDURE' RADIOSTRONTIUM ANALYSIS OF SOIL AND SEDIMENT After the soil or sediment sample has been dried and pulverized, a SOgm aliquot is added to approx:ima.tely 1/3 - liter concentrated hydrochloric acid (HCl), containinq Sml of strontium carrier (lOmq sr++/ml). A blank con-taininq only 1/3 - liter concentrated HC~ and Sml strontiwn carrier is run in parallel with the sample. The samples are stirred viqorously for at least 30 minutes and then filtered. The filtrate is then diluted to a known volume and aliquots removed for stable str:ontiwn. The remaining sample is alka.linizeci with ammonium hydroXide to precipitate all the transitional elements. After filtering out these interferences, the filtrate is heated and sodium carbonate added to precipitate strontiwn and calciwn carbonate.

These carbonates are first filtered and then di.qested with 6N HN0 3

  • Two

_fwn:i.nq (90%) mro 3 recrystallizations are then performed to remove calcium. Subsequently, radi.oactive impurities are removed by two precipitation steps, using ferric hydroxide and bariwn chromate as carriers. The strontium is precipitated as strontium carbonate before beinq dried and weighed. The samples are counted for beta activity in a low background gas proportional counter (Count time will vary, depending on the desired sensitivity.). There is a second count at least 14 days later. The basis for this two-count method is that sr-90 and Sr-89 are both unknown quantities requiring two simultaneous equations to solve for them. caJ.cUlation of sr-90 Activity~ sr-90 Results (pCi/kg dey) *= N4/R (2.22)*(E)*(E(lS)/E')*(S6)*(V)*(U) 

                                                                             = W2 where S6       =A +        B*M + c~M2 (This is the genera.I. form of the normalized sr-90 efficiency reqression equation for one particular gas proportional counter, where A, Band care reqression coefficients.)

M = Thickness density of strontium. carbonate precipitate, mq/cm2 E(l5)/E' = Ratio of Sr-90 efficiency at thickness vaiue of 15mg/cm2 to Sr=90 countinq standard efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontiwa samples) E = sr-90 counting standard efficiency v = Sample quantity (kq dry) u = CheliCLcal. yield N4 = (N2 - Fl*Nl)/WJ. = net counts due to Sr-90 only

  • Wl. = ((l + Rl*I2) - (l + Rl~Il)~Fl)
*-.--~---~--*-:--:---*--::___,,....-.-~ -.--7*..---.-*-*--..*--*----------- -  --~*~,...--..,~--~~---***--*----~---~-- --* ----- *--- *- - -*----.----- -* ----~...,..--- .. ~---~ *---*

Il = l - EXP ( (-0 .693/2 .667) *tl) . I2 =l - EXP ({-0.693/2.667)*t2) tl = Elapsed time from Y-90 strip to first count t2 = Elapsed time from Y-90 strip to second count 2.667 = Half-life Of Y-90, days Rl =D + E*M + F*M2 (This is the general form of the regression equation for Y-90 eff'y/sr-90 eff 'Y ratio for one particular gas proportional counter, where o, E and F are regression* coefficients.) N2 =X - Y, where X and Y are recount _gross counts and background counts, respe(:tively Nl = Xl - Yl, where Xl and Yl are initial gross counts and background counts, respectively 2.22 = No. of dpm per pCi Fl = EXP ((-0.693/2.667)*t2) R = Count t;Lme* of sample and blank* 

 .*J
  • Using the same varial:lle definitions as aJ:>ove, the 2-sigma error for sr-90 (pCi/kq dry) =

2*[CX+Y) + on+n~*F11 1 12 .. (Wl*W2) [ Wl2 Wl (N2-Fl*Nl) Again, keeping the same varial:lle definitions, the LLD for sr-90 (pCi/kq dry) = 4.66* Rx+;p + cxi+n~*F1J 1 12 [wi

  • Wl
  • calcul.ation of sr-89 Activity:
-j sr-89 Results (pCi/kq      dry)  =                       NS/R (2.22)*(E)*(E(l5)/E')*(S7)*(V)*(U)*(F9)
                                        = W3

. i S7 =G + H*M + I*M2 (This is the general form of the normalized sr-89 efficiency regression equation for one -particular gas.proportional 

                  .counter where G, Hand I are regression coefficients.)

150 

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

N7 = (N2 = Fl~Nl)/Wl (This represents counts due to sr~90) E(lS)/E' =.Ratio of sr-89 efficiency at thickness value of 15mg/cm2 to sr-90 counting standard.efficiency run at the time of instrument calibration (This standard is run with each group of environmental strontiwn samples) F9 =EXP ((-0.693/50.S)*t) t = Elapsed t.ime from midpoint of collection period to time of recount for milk samples only. For all other samples, this represents the elapsed time from sample stop date to time of recount. 50.5 = Half=life of Sr=89, days All other quantities are as previously defined. Th~ 2-sigma error for Sr=89 (pCi/kg dry) = 2* (se2+sg2)l/2 *W3 (Nl - N7*(l+Rl*Il)) SB =rc.x+/-Y.l + (Xl+Yla*Fl~ 1/2 [Wi2 Wl sg = cxi~u> 1 1 2 All other varial:lles are as previously defined * 

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

SYNOPSIS OF PSE&G RESEARCH CORPORATION.PROCEDURE ANALYSIS OF ENVIRONMENTAL SAMPLES FOR STA~LE STRO~TIUM It has been the practice of the Environmental Division to perform a stable strontium determination on any samples to be analyzed for strontium 90 and 89, i f they are likely* to contain significant amounts of the stable isotopes.. In the case of mineral (soil or sediment) or biological (bone and shell) media, an ashing and/or acid leaching is performed to extract the element{s) of interest. The removal of the aliquot is done early in the course of the radiostrontium analysis and involves the withdrawl of 25 ml of diluted leachate (soil and sediment only) from the regular sample, transferring it to a flask. Bone and shell are prepared by ash~ng 2 g of sample, digesting in 6N HCl, filtering out insoluble residues and then transferring to a flask. All, the above samples are analyzed by the method of Standard Additions, whereby each sample leachate is spiked with known concentrations of stable strontium. Absorbances for sample, spiked samples and blank are determined by Atomic Absorption Spectroscopy (AAS) and are then plotted graphically and the true concentration is then extrapolated. Chemical and ionization interferences are controlled by adding 1% or more of lanthanum as chloride to all samples to be analyzed. Stable strontium is then determined by AAS in the air-acetylene flame at the 460.7 run line. For analysis of water, a 60-ml aliquot of sample is removed, acidified to pH<2 with hydrochloric acid and analyzed by AAS as follows: A group of strontium standards (of similar concentration to: the unknowns) is prepared. Then, to 9 ml of each prepared sample'* blank and standard, is added 1 ml. of lanthanum oxide solution. These are ana,lyzed at 460.1* run by air"".'acetylene AAS, following the manufacturer's recommended instrument parameters. All. results (calculated as milligrams of strontium per liter) are then used to find the true chemical recovery of strontium based on both the amount of carrier added (only in the case of soil and sediment) and the quantity of strontium intrinsic to the sample. 

                                    . Sample calculation of corrected Chemical Recovery of Strontium in Soil and
 ~ -c *.

Sediment: Reported concentration of stal:>le strontium (mg/L):ll9 Volume of specimen (mll:2S (removed from lOOOml of diluted leachate) Proportion of sample used for aliquot: 0.025 Milligrams strontium in 25ml flask= (119mg/L) x (.025L/25ml) x (25ml) 

                                                                                                = 2.98mg sr i
            .  ~                      Since 2.98mg Sr represents the quantity of stable.strontium in 2 1/2 percent of the sample, total strontium (stable + carrier) in the full sample =

2.98mq Sr = 119 mg o.02s 152 

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

                 ~ ..
  • Net weight of srco 3 precipitate.(mg): 125 Percent of Sr in precipitate: 59.35 Quantity of strontium recovered= (l25mg) x (.5935) = 74.2.

corrected chemical recovery of strontiwn = 74.2 = 0.623 ll.9.0 The calculations f_ollow the same sequence for :bone and shell samples. Sample ca.1.culation of Corrected Chemical Recovery of Strontium in Water~ Reported concentrations of stable strontium (mq/L)~ l.65 

                                *volume of radiochemical water sample (liters): 2.0 Stable strontium in 2 liter sample                                               = (l.65mg/t)                          x (2.0L)
                                                                                                                  = 3.30mg Quantity of strontium carrier added to sample (mg)~ 20.0 Total amount of strontium in sample (mg): 20.0 + 3.30 = 23.3mg Net weight of srco 3 precipitate (mg): 28.9 Percent of Sr in precipitate: 59.35 Quantity of strontium recovered= (28.9mg) x (.5935)                                                                                     = l7.2mg
  • corrected chem.ical. recovery of strontium~ 17.2mq 23.3mq
                                                                                                                                                                ~       .738 I
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      --------::----.---'<-* -:----------*-- -- - ----- -* . -:--""7---~--- ----------* - *- --~- ----.. -- ------ .. ----- - * ------ ~ ----- -;---------- .... - ----* -- - - .. - . - *-*-- --- ------ --

SYNOPSIS OF PSE&G RES~RCH CORPORATION PROCEDURE GAMMA ANALYSIS OF A.IR PARTICULATE COMPOSITES At the end of each calendar quarter, 13 weekly air filters from a giv~n location are stacked in a two inch diameter Petri dish in chronological order, with the oldest filter at the bottom, nearest the detector, and the newest one on top. The Petri dish is closed and the sample counted on a gamma detector. The following are the calculations performed for the gamma activity, 2-sigma error and LLD: Result (pCi/m 3 ) = N*D =R (2.22)*(E)*(A)*(T)*(V) N = Net counts under photopeak D = Decay correction factor 

                                                                                     .\.tl.*EXP(:\t2) 1-EXP(-.\.tl) tl = Acquisition live time t2 = Elapsed time from sample collection to start of acquisition A. = 0.693/nuclide half life
  • E = Detector efficiency A = Gamma abundance factor (no. of photons per di~integration)

T = Acquisition live time, mins. 

                                                                                   =

V Sample volume, m3 2.22 = No. of dpm per pCi 2-sigma error (pCi/m3 ) = l.96*(GC+Bc)l/2,.a N GC = Gross- counts BC = Background counts All other variables are as defined earlier. The LLD (pCi/m3) = 4.66*(Bc)l/2,.D (2.22)*(E}*(A)*(T)*(V} 154 -*** _] 

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

SYNOPSIS OF TELEDYNE ISOTOPES PROCEDURE: *. ANALYSIS OF AIR PARTICULATE FILTERS FOR GAMMA . Ai.r particulate filters are analyzed for gamma using a lithium~drifted germanium detector interfaced with a 2048 channel pulse height analyzer calibr~ted at 1.0 Kev per channel. Teledyne Isotopes employs one of three possible data acquisition and computation systems. The first, a Data General NOVA minicomputer, in series with the pulse height anaJ.yzer, calculates the _number of counts (and a one standard deviation). in the peak region by performing a linearly-interpolated background subtraction. If no peak is observed, then only the background is used (along with sample volumep collec~ tion date and length of count) to determine the detection limit. The activity or MDL of each nuclide is computed on an IBM 360. This semi-automatic system is in contrast with the other two data acquisition and computation systems, namely, a Tracor Northern TN-ll and Nuclear Data 6620 which perform all the above computations automatically. All resultant spectra are stored on magnetic tape. 

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SYNOPSIS OF PSE&G .RESEARCH .COREORl\TION PROCEDURE GAMMA ANALYSIS OF.RAW.MILK A well miXed 3.5-liter sample of raw milk is poured into a cal~rated Marinelli beaker along with 20ml of 37% formaldehyde solution (used as a preservative). After stirring, the sample is allowed to reach ambient temperature and then counted on a gamma detector.* calculation Of Gamma Activity: The following are the calculations performed for the gamma activity, 2-sigma error and LLD: Result (pCi/L) = N*D = R (2.22)*(E)*(A)*(T)*(V) N = Net counts under photopeak D = Decay correcti.on factor X. tl*EX1?(X.t2) 1-EXP(-x.tl) tl = Acquisition live time t2 = Elapsed time from sample collec-tion to start of acquisition

x. = 0.693/nuclide half- life
        **                                             E =  Detector efficiency A=   Gamma aJJundance factor (no. of photons per disintegration)

T = Acquisition live time, mins. V= Sample volume, liters 2.22.= No. of dpm per pCi 2-sigma error (pCi/L) = l.96*(GC+Bc)l/2*R N GC = Gross counts 

       ..                                             BC = Background counts

. . .*' l 

         *1 All.other variaJJles are as defined earlier.

The LLD (pCi/L) = - 4~66*CBc)l/2wo (2.22)*(E)*(A)*(T)*(V) _.. *~ 

      . T'

~*. ..~. SYNOPSIS OF PSE&G RESEARCH* CORPORATION.. PROCEDURE GAMMA ANALYSIS OF WATER After thoroughly agitating the sample container, 3.5 liters of water sample is poured into a calibrated.Marinelli beaker and then counted on a gamma detector. ca1cu1ation of Gamma Activity: The following are the calculations performed for the gamma activity, 2-sigma error and IJ:.JJg Result (pCi/L) = Nao =R (2.22)*(E)~(A)*(T)*(V) N ~ Net counts under photopeak D = Decay correction factor 

                                                                                                                                       .\.tl*EXP(.\.t2) 1-EXP(-.\.tl) tl = Acquisition live time t2 = Elapsed time from sample collec-tion to start of acquisition
                                                                                                                           ~ = 0.693/nuclide half life E ~ Detector efficiency A = Gamma. aJJundance factor (no. of
                                                                                                                                      *pnotons per disintegration)

T = Acquisition live time, mins. V = Sample volume, liters 2.22 = No. of dpm per pCi 2-sigma error (pCi/L) = l.96*(GC+BC)l/2*R N GC = Gross counts BC = Background counts 

    ;.!                    All other variatiles are as defined earlier.
   '.*i                    The LLD (pCi/L)                  =               4.66~{BC)l/2.o (2.22)~(E)~(A)*(T)~(V)
   .* 1*
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I 157 

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

SYNOPSIS.OF PSE&G RESEARCH CORPORATION *PROCEDURE. GAMMA ANALYSIS OF SOLIDS several methods are employed in preparing solids for gamma anal.ysis, depending on the type of sample or sensitivity required. For high sensitivity anal.ysis of vegetation, meat and seafood, the sample is first weighed, then oven-dried to a constant weight. A ratio of wet-to-dry weight is computed before the sample is ground and compressed to unit density (lg/cm 3 ), whenever possible, in a tared al.uminum can. The can is weighed and then hermetical.l.y sea.l.ed and counted on a gamma detector. In most cases, a wet sample is prepared (assuming sensitivity can be met) by using a food processor to puree it. The sample is then poured into a cal.i-brated and tared clear plastic container until. a standard volume is reached. The sample is weighed and then seal.ad with a screw cap before gamma counting. Soil. and sediment samples are first oven dried until. a constant weight is achieved and then pul.verized. The sampl.e is added to a tared al.uminum can, compacted to a standard vol.lime and weighed. It is hermetical.l.y seal.ed and gamma counted. Benthic organisms are oven dried; followed by the physical. removal of any * 

           *obvious impurities-(such as shells or twigs). The dried organisms are weigh and then wet-ashed with.concentrated nitric acid~ After al.l solids have been digested, the sample is evaporated to near drYt1ess and the residual. sal.ts taken up with distilled water. The sample is filtered and the filtrate added to an al.uminum can. The* sample volume is brought up to the standard geometry with distilled water and the can hermetical.ly sealed before gamma counting.

calculation of Gamma Activity: The following are the calculations performed for the gamma activity, 2-siqma error and LLD: Result (pCi/kg) = N*D = R (2.22)*(E)*(A)*(T)*(V) N = Net counts under photopeak D = Decay correction factor. 

                                                                  >..tl.*EXP(>..t2) 1-EXP(->..tl) tl = Acquisition live time t2 = Elapsed time from sample collec-tion to start of acquisition
                                                            >.. = o.693/nuclide half life E = Detector efficiency A - Gamma abundance factor (no. of photons per disinteqration)

T = Acquisition live time, mins.

  • v = Sample volume, kiloqrams 2.22 = No. of dpm per pCi

2~sigma error (pCi/kg) "" l.$l6"'(GC+Bc)l/4,.,e *. N GC = Gross counts BC = Background counts All other variables are as defined earlier. The LLD (pCi/kg) = 4.661'(Bc)l/2,.,o (2.22)*(E)"'(A)*(T)*(V) 

                            /
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---~ - -: SYNOPSIS OF TELEDYNE ISOTOPES PROCEDURE, ANALYSIS OF TELEDYNE ISOTOPES THERMOLUMINESCENT. DOSIMETERS These devices are rectangular Teflon wafers impregnated with 25% caso 4 :Dy phosphor. They are first annealed in a 2S0°C oven prior to exposure in the field. Following field exposure (for a 1-month or 3-month period) four separate areas of the dosimeter are read in a Teledyne Isotopes model 8300 TLD reader. The dosimeter is then re-irradiated by a standardized cs-137 source and the four areas are read again. Calculation of the environmental exposure is performed by computer, using the re-irradiation readings to determine the sensitivity of each area of the dosimeter. The readings of control dosimeters are sUbtracted to aJ.1ow for transit dose and system back-ground. The results are computed as follows: For. any given area of the dosimeter, the dose in mR is calculated by the following formula: DOSE = R * (REDOS~/RR)-AVC R = Initial reading of the area RR = Second reading of. the area (after re-irradiation) REDOSE = Re-irradiation dose, mR AVC =Average of control values, mR 4N where AVC = ~CDOSE/4H i=l H = Total number of control dosi-meters 

        *,*,                                                                     CDOSE = CR*(CREDOSE/CRR)

CDOSE *= control area dose, mR CR = Initial reading of control area CRR = Second reading of the control area (after re-irradiation) CREDOSE = Re-irradiation dose of the control dosimeter, mR ' * . *i 

     **.l '
     ... '~

160 

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APPENDIX E

SUMMARY

OF USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARISON STUDIES PROGRAM RESULTS 

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SUMMARY

O~ USEPA INTERCOMPARISON ~TUDIES PROGRAM_ Appendix E presents a

  • summa.ry of the analytical* results for the 1986 USEPA Environraental Radioactivity Laboratory Intercomparison Studies Progr*am.

TABLE OF CONTENTS TABLE NO. TABLE DESCRIPTION E-1 Gross Alpha and Gross Beta Emitters in Water and Air Particulates ******************************* 164 E-2 Gamma Emitters in Milk, Water, Air Particulates and Food Products ***..*..**********.*******.*** 165 E-3 Tri ti um in Water ............* o ******************* 167 E-4 Iodine in Water and Milk ************************* 168 E-5 Strontium-89 and Strontium-90 in Air Particulates, Milk, Water and Food Products ****************** 169

  • ~

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TABLE E-l USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM Gross Alpha and Gross .Beta Analysis of Water (pCi/L) and Air Particulate (pCi/filter) DATE ENV SAMPLE CODE PSE&:G EPA GRAND AVG MM-YY ENV ID MEDI-UM ANALYSIS Mean :!: s.d. Known Mean :!: s.d. Ol-86 EPA-WAT-ABl69 Water Alpha 3.6:1:0.3 3.0:!:8.7 3 .6:!:l.4 86-90 Beta 6.7:1:0.S 7.0:1:8.7 7 .2:1:l.8 03-86 EPA-WAT-ABl75 Water Alpha 18:1:3 15:1:8.7 13:!:3 86-374 Beta 8:1:1 8:1:8.7 10:!:3 03-86 EPA-APT-GABSl76 APT Alpha . l7:!:l 15+/-8.7 16+/-3 86-660 Beta 50+/-1 4"1+/-8. 7 51+/-6 04-86 EPA-WAT-Pl78 Water Alpha 18:!:1 17+/-8.7 15+/-4 86-512 Beta 29:il '35:!:8.7 32:!:5 05-86 

      .07-86 EPA-WAT-ABl80
                '86-871 EPA-WAT-ABl89 86-1204 Water
                                  *Water Alpha Beta*

Alpha Beta 8:1:1 14:1:1 6:1:1 lS:!:l 8:1:8.7 15:1:8.7 6+/-8.7 18+/-8.7 7:1:2' 15:!:3 6:1:2 18:1:3 08-86 EPA-APT-GABSl92 APT Alpha 24:1:1 22:1:8.7 22+/-4 86-1567 Beta 90:1:2 66:!:8.7 71+/-8 09-86 EPA-WAT-ABl94 Water Alpha 15:1:1 15:!:8.7 15:!:4 86-1766 Beta 8:1:2 8+/-8.7 10:!:3 10-86 EPA-WAT-Pl97 Water Alpha 44:!:1 40:!:8.7 36+/-10 '. '-i 86-2079 . Beta 19:!:1 51:1:8.7 47+/-6 ll-86 EPA-WAT-ABl99 Water Alpha 19:!:2 20:!:8.7 17+/-5 86-2666 Beta 16:!:1 20:1:8.7 21:!:3

  • s.d. - one standard deviation of three individual analytical results
        *** known value with control limits, indicating whether results are in agreement or disagreement
       *** s.d~ - one standard deviation of acceptable results of all participating laboratories 164

.. \. .' J' TABLE E-2 USEPA ENVIRONMENTAL. RADIOACTIVITY LABORATORY INTE.RCOMPARSION STUDY PROGRAM Gamma Analysis of Milk, Water (pCi/L), Air Particulate (pCi/filte!-> and Food Product_s (pCi/kq) DATE ENV SAMPLE CODE PSE&G EPA GRAND AVG MM-YY ENV ID MEDIUM ANALYSIS Mean +/- s.d. Known Mean +/- s.d. 01~86 EPA-ORG-GS170 Food I~l:U <30 20:1:10.4 21+/-2 86~100 c:s~l37 14:1:1 15+/-8.7 17+/-2 K(l) 922:1:11 950+/-248 957+/-90 02-86 EPA~WAT-Gl71 Water cr-51 42+/-4 38+/-8.7 39+/-6 86-173 Co-60 18+/-1 18:1:8.7 18+/-3 Zn-65 41+/-2 40:1:8.7 41+/-4 

                                                                                                                             .Ru-106                            <ll                                            0 Cs-134                               28:1:1                                 30:1:8.7                        28+/-4 Cs-137                               22:tl                                  22+/-8.7                          22+/-3
  • 04=86 04-86 EPA=APT=GABSl76 86-660 EPA=WAT-Pl78 86=512 APT Water cs-137 co-60 cs-134 cs-137 lOi:l
  • 9:!:1 Sil 6+/-1 10:1:8.7 10:.tS.7 5:t8.7 5:!:8.7 ll:t2 10+/-2 S:U 6:U 06-86 EPA-MLK-GS184 Milk I-131 43:1:1 41:1:10 .6 44+/-4 86-1071 Cs-137 37+/-1 31+/-8.7 37+/-3 K(l) 1660:1:10 1600:1:140 1600:1:110 06-86 EPA-WAT~Gl81 water cr-51 <18 0 o 86-921 Co-60 66il 66:1:8.7 64+/-4 zn-ss 87+/-3 86:1:8.7 86+/-6
                                                                                                                            .Ru-106                               43+/-5                                 50:1:8.7                         SO:t:ll cs-134                                46:1:1                               49+/-8.7                          46:i:4 CS-137                                lOil                                 10+/-8.7                          11+/-2 07=86              EPA~ORG-=GSl90                                       Food                  I=l3l                                 26:ll                                30:1:10.4                       28+/-3 86=1205                                                                    CS-137                               2lil                                  20:1:s.1-                       21:!:3 K(l)                            l.150:1:30                           usoiloo                         llSO:l::l.04 oe-es              EPA-APT=GABSl92                                     APT                    CS-137                               2lil                                  22:1:8.7                        24:M 86-1567
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                                                                                          .....--.-,--..,..-.-~.--- -**--:-*--.~~i- ... *-:*~-,..~---------*~*-******-*** -- -- -* ---.---**--~~-*- .._,. ____ - - - - . -- - **--- --*-*-**-*-:- *--* ....* ,._ **-.*

TABLE E-2. (cont'd) USEl?A ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMl?ARSION STUDY PROGRAM Gamma Anal.ysis of Milk, Water (pCi/L), Air Particulate (pCi/filter) and Food Products (pCi/kg) DATE ENV SAMl?LE CODE PSE&G El?A GRAND AVG MM-YY ENV ID MEDIUM ANALYSIS Mean :!: s.ci. Known Mean :!: s .ci. 10-86 .EPA-WAT-Gl95 Water cr-51 57:!:8 57:!:8.7 56::1:17 86-1964 Co-60 28::1:2 3l::l:8a 7 31+/-3 Zn-65 79:!:6 85:!:8.7 85+/-7 RU-106 69+/-9 74+/-8.7 68:!:8 cs-134 26+/-2 28:!:8.7 26+/-3 Cs-137 "42:!:2 44:!:8.7 45:!:4 10-86 EPA-MLK-GSl98 Milk I-131 48:!:1 49:!:10.4 . 49+/-5 86-2147 cs-137 44+/-1 39+/-8.7 44+/-3 K(l) 1540:1:20 1565:1:135 1565::1:106 ll-86 El?A-WAT-.E'l97 Water co-60 23il 24:1:8.7 24::1:2 86-2079" CS-134 ll:l:l 12:1:8.7 11:1:2 CS-137 8::1:1 8::1:8.7 9:!:2 

                               "' s.d. - one standarci deviation of three inciiviciual analytical results
                             "'"' known value with control limits, indicating whether results are in agreement or disagreement
                           "'"'"' s.ci. - one standard cieviation of acceptable results of all participating laboratories (l) Reported as mg/L of Potassium.

. *-~- 166 

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USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM Tritiwn Anal.ysis of Water (pCi/L) DATE ENV SAMPLE CODE PSE&G EPA GRAND AVG MM-YY ENV ID MEDIUM ANALYSIS Mean +/- Sod. Known Mean +/- s.do 02~86 EPA=WAT-Hl72 Water H=3 5170+/-70 5227:!:906 5105+/-340 86~244 06=86 EPA~WAT~Hl82 Water H-3 3000:1:80 3125+/-624 3052+/-347 86-981 10-86 EPA-WAT-H196 Water H-3 5890+/-l.OO 5973+/-1.034 5694+/-406 86-1965 

             ,,. Sodo - one standard deviat.ion of three individual analytical results
           ** known value with control limits, indicating whether results are in agreement or disagreement
        **a Sodo - one standard deviation of acceptable results of all participating laboratories
  • 167
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TABLE E-4 USEPA ENVI*RONMENTAL :RADIOACTIVITY LABORATORY IN'I'ER.:OMPARSION STUDY PROGRAM Iodine Analysis of Water and Milk (pCi/L) DATE ENV SAMPLE CODE* PSE&G EPA GRAND AVG MM-YY ENV ID MEDIUM ANALYSIS Mean +/- s.d. Known Mean +/- s.d. 03-86 EPA-MLK-Il 72 Milk(l) I-l3l 2.4+/-1 9::1:10.4 9+/-2 86-245 04-86 El?A-WA'I'-Il 77 Water I~131 8::1:l 9::1:10.4 9+/-2 

                         *86-424
                *08-86    El?A-WA'I'-Il9l      Water   I-131           39::1:1    45+/-10.4       42+/-6 86-1305
                   " s.d. -.one standarc1 deviation of three individual analytical results
                  "" known value with control limits, indicating whether results are in agreement or disagreement
                 """ s.d. - one standarc1 deviation of acceptable results of all participating laboratories (1) Special El?A/NRC low level study *
   . /~ **';
           *-~

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...: _(\ TABLE E-5

  • USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARSION STUDY PROGRAM*

Strontium-89 and Strontium-90 Analysis of Air Particulates (pCi/filter), Milk, Water (pCi/L) and Food Products (pCi/kq) DATE ENV SAMPLE CODE PSE&G EPA GRAND AVG MM-YY ENV ID MEDIUM ANALYSIS Mean :t: s.d. Known Mean +/- s.d. 01=86 EPA-WAT-5168 Water sr-89 24+/-2 31+/-10.4 31+/-5 86-26 Sr-90 12+/-1 15+/-2.6 14+/-2.2 01-86 EPA-ORG-GS170 Food sr-89 (l) 86-108 sr-90 (1) 03-86 EPA-APT-GABSl76 APT sr.:..90 16+/-1 18+/-2.6 17+/-2 86-660 04-86 EPA-WAT-Pl78 Water Sr-89 6:1::1 7+/-8.7 6+/-2 7+/-1 86-512 sr-90 6:t::l 7+/-2.6 05=86 EPA-WAT-SJ.79 water Sr=89 - 4:tl S:t8.7 5+/-2 86-675 Sr=90 4::1::1 5:1::2.6 5+/-1 os~ss EPA-MLK-GS184 Mi.lk. Sr=89 <4 o 0 86-1071 sr-9o l2il 16+/-2.6 15+/-3 07-86 EPA-ORG-GSl90 Food sr-89 24+/-2 30+/-8.7 25+/-3 86-1205 sr-90 16+/-2 19+/-2.6 19+/-7 08-86 EPA-WAT-GABSl92 APT sr-90 22+/-1* 22+/-2.6 22+/-3 86-1567 10-86 EPA-MLK-GSl98 Milk sr-89 8:t:l. 9+/-8.7 9+/-3 86 2147 00 sr-90 <l.6 0 1+/-0.S l.l-86 EPA-WAT-Pl97 Water sr-89 10+/-1 10+/-8.7 9+/-3 

       ;                         86-2079                                             sr-90                      3:t:l                              4+/-2.6                          4:.t:l i
  • s.d ... one standard deviation of three incli.vidual analytical results_
                        ** known value with control l.i.mits, inclicat~ng whether results are in agreement or disagreement a*a   s.d. - one standard deviation of acceptal::lle results of all.                                                                  part~cipating laboratories (l) Not analyzed by PSE&G.
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APPENDIX F SYNOPSIS OF LAND USE CENSUS

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  • APPENDIX F SYNOPSIS OF l986°LAND USE CENSUS A land use census was conducted to identify, within a distance of 8 km (5 miles), the location of the nearest milk animal, the nearest residence and the nearest garden of greater than 5om2 (500ft2) producing broad leaf vegetation in each of the 16 meteorological sectors.
  • Tabulated below are the results of these surveys:

Milk Nearest Vegetable Animal Residence Garden Meteorological Aug., 1986 Aug., 1986 Aug., 198 6 Sector km (miles) km (miles) km (miles) N None None None NNE None 6.9 (4.3) None NE None 6.4 (4.0) None ENE None 6.1 (3.8) None E None 5.4 (3.4) None ESE None None None SE None None None SSE None None None s None 6.1 (4.1) None SSW None 5.5 (3.4) None SW None 6.9 (4.3) None WSW None 7.1 (4.4) None w 7.8 (4.9) 6.5 (4.0) None WNW None 5.5 (3.4) None NW None 5.9 (3.7) None NNW None 6.8 (4.2) None 

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