ML20206E050
| ML20206E050 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 12/31/1998 |
| From: | Langenbach J GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 1920-99-20201, NUDOCS 9905040323 | |
| Download: ML20206E050 (160) | |
Text
.h 5
< 1 l
l , GPU Nuclear,Inc.
(- Route 441 South NUCLEAR Post Office Eax 480 Middletown, PA 17057-0480 Tel 717 944-7621 i
April 27, 1999 l
1920-99-20201 h
U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Gentlemen:
Subject:
. Three Mile Island Nuclear Station j Units I and 2 ( TMI-l & TMI-2 )
Operating License No. DPR-50 and Possession Only License No. DPR-73 Docket Nos. 50-289 and 50 320 1998 Radiological Environmental Monitoring Report In accordance with TMI-1 Technical Specification 6.9.3.1 and TMI-2 Technical Specification 6.5.1.1, enclosed is the 1998 Radiological Environmental Monitoring Report for the Three Mile Island Nuclear Station.
Please contact Adam Miller of TMI Licensing at (717) 948-8128 if you have any questions regarding this submittal.
Sincerely, I ps-
}f .
James W. Langenbach Vice President and Director, TMl AWM Enclosure Region I Adrainistrator cc:
TMI-1 Senior Project Manager TMI-2 Project Manager
[b' ,
1
~
TMI Senior Resident Inspector . l File 99011 ~
9905040323 981231 PDR ADOCK 05000289 R PDR g -u j
.:. ' . . _. *. ' .*l.. ;y ': -- . _ . "_' : . ;; ,Q l l ~
~ '
F^ ' 1 ' ,y %
'r
'p.l _, ..L .. ~.l
,g
.: :[. '. ^,, ',._
. . : ..;.,.', Gg.;S: . - l Q;f.,,z . @lV.;. (:.:t)*f':% 0*, ' _ L' l
.. . ';.s..;3.,;. ;y 7..= .
{;[. .l.f.kf. }.j-Qf.$ ,&:;&jhfl
- . - l
- .c_?.l 1, ', , : L
' % . ( , ., '
j{,gptygggy$Qgh.;g;l: l4
. -:.'.. , l . ' s.. ,
^
. ,q. -. l..-:. . .. 7, :. . . :' :.. ' .W.M :r. . ,f;>m'::;h;.;. Q,
.s'M. p Le % ATtsa M iyio.m ;..j& ' ' -
r.
. :q.
'*. i .Q..b' .:7l '# ,, 3, ,.,g""'. , , N,'I. .*
.....q...,y'A""# ,',.'*
. . c -
- ' ' ?.;.;,.~..Q,,'l*
- g ;q, .;.f.&.s;.$f.f;jg;jj, .t.': :.. i . ,. %. .* -]
~
s.' 9 , .'
g, ,;) . ' .
lt ' ;k l '
r
~
-l' .
, [,q. ,_l,
(
.<a....? e ,?. . : .n;; s .h . . . -r - -
) 'll- YQ' .\.y p h f h,.r;;D :sg% .a ' -
.. e -
_. ,, ~ ~ . lA *I ^
,.Q
~
.W ,.(, '
%.d.,Q, fQ@d Q.9; :;g , V. 7
. . ./ . \ ^.,~'
~ .
3, u . .
' L '. y .~. . ?q,: q ;;v:.y.%.}ff!hQ$
n_ , , . . . .
.?.. ..;.]. .; a 6 &a>- . , . . 1 .
2 . ..
.: ..dw '.?'?$.%.9g
. ,.n.t., . w 97 .
iU
. q . f. :( .;. . Q. k'{y
- h. 'f.> .
.'-'.. l, 4 . b' I' Ij. .. i',.
4
/.',2."'l. .'. ' [: f2,k. %
l[ ; .-
. ? \*4 7
i . ' ' ,' '
~ ' '
' - ; U.* . .;t - [ '
.,., N/h. Y.',Y'[.5h h., , g' gL3b $ i '";?,ifh .
.?
.n, Q.Iy..g g r - t. ;.. .. *r .
7
.'i:. .; . .; .- r % -
' ; ;,.y.
'.q:_'q;y:gQ:
- - !...:'S:.Syhd.M:(%,.]O-Qgl .
'ii.
Ql. . [g[,[
- a. .. i , . ,: - .
i
. l'lh '; , f h: , h?
~
.b.'I. .h
' ~
. iI'0 . - ,
- o. .. ( , ,I , _;' .? .
', - .. ft. ht '* N .
- i., j:.Q f*7:!G';: < : ?.".b,5"* l,l: ${ )&} ' {
% ;f % . .' '
l f..,g.L .. . i c:.f-
, Q -
1 ' q 9. .', *.; ' d.>f' "; . . , .
s f a 4 * .e- [; [_?_
y,v *= .$<
.h
- ev.
- 3. ; ..v:.
. ; U.!: .;c c .v..
. - - - 4 i s; e.. ,.
. np ; *-
r ' ' y. i g:' ;31. :.4. ;r;;. e: ;yWy . k .W._ y*Q, ..
(' ' '
"' *ii. 3~.: t'y& u ' y,, f y,;hxxi, t'.
,.4 w ;;, %, r . ;
o < s y. . . , . .
.. . . .: ~,. , %1 1;p.% , t
\ . .
- .. - e; ' .Q*ff Y;A.h 3,.l. ,
" ,r. '
. * . + ' .' : * *a ._ J
. F, .*
r,. k: ,b, f.,k , ..- -
c ; .. [.
- "h , s .'
, ' .j ] .cf,j,.;',J .y.! ~.' jt, . :[%.NQ ,j ltgi p . 1
. ,. l.. 1; ( U-4.; .. ' p . . . . } #;. -; /..':t.>. . ? ,. . . 3 -. - . ~ at - y - + g * ,
2
.c.d... ' . s.% A.g - . .: g :?.
- .z.
.? '
..'; ' . s t' * ,
.':,b'.v{j...f.?:g[
1'
.)
9' * '
@%.L a p,' . ', .'w.z a[. -
- +
't..
s .
.,.?'. _
4
'. s
.r .
f ' J'.% f ), 4 ,. . t i, Y, . . . h
- l':ij'/,. ' .& ./. , #
- c. - q ).s - ' .
' l -
b ', ,. , . . , . ..n .'- ' : ' .
9,, .
N
.. ...i.+ b ,3 '. I ' 'l '.-
(' .
lh $N
.; S. ?;l:l
.'.'O*.'
.' .y ),' ; - ? l } &. .\. ?.! %. , % . ,
c.' ::p . . . . . : .e.,
..g s n.' ' ' ' ' " ' . . ,(% % ~ , s# $.' .t.'
- ~ . ." u s
- - // ' ..' l.O.9., %[. :,' - 4.:
) I! . ,. .q [ y ) [. . - . .-~ ' , .
~
I ,. ,p.%.59$ Dig;y:. l4 .c r .
.. . a.., ,
- l. .!; ie.A 3 .A p.J f $lE. i 4 .
.,..)c.
. j, 4 '. **?, ,( -
,,}'
't-k .' M g y.
.P . .
.d ..
%@ . ., . 4 WMD ,
,c . s - - .j 4 ,e r -
s w .e 3 b.
/* [ jed. , a
' ' ;6' ,.
. . . ~. _; . .' . '. j }' >r.
f.)
. . :. { lG. .bl
.. % yp .r . hg . .'.'-',.'.;
s... .Q
- 4-
[..: .-
. ;.T.
v.
.;. ~-,.'..;, . .
. . .' .- : )*, *E -
. : 9. g .t', . . .
~ .. . ,. ,
~
,;r .
- - b
.., . _' g .
. . _ . ' fy y l ,'
^
- '. c .,9 : . . . , - *
.. . . ~ es _ '
.: y.> 5-
. [k j . '.,e c 6 g .' .
.: % ; ;p _4._-
- f. . y, .
- ,.' ,'a.y .::d g q . p q f
- s'. de. . .
, , . a ), 4, e ..:s .
- e .
, [ .. M ..l.: ', .S .k- 4r.I ;'/ - '
., , bei .3-k. . : ir.P .p:,C .I. %,?: .
$ . '. 'N.' ... -
- ', ,. j - .
T ,. ,
h . '[, 7.; [.;' .
[. / d ,.{ ' " ,,le 4 . ;;l* . ,. . . . ;
Y.$'. ,
.. ..l..:.
&;,l : L :.% :p*-' * 'P t": .'yi p.
- i.h.'{: y; . h[b , f ' * -
. y ';.
,9 . ' ,a. e C'W.
f' ( *
- Q.; 9 ;
t .
., - .,.~.,,: .- " ; - . * %::s r" - i} *..g. t 1 .
. ? J . c .. , v.. . (r;. .r,, -
.+
\. .#. ~a
,.i o . . l e
a.-
. .<';. .'. ..L; . 94 ': ... l ; u.:
%..s'.
i :
3 7,,. . / ;'. : .. <. :_.;. ,. .;p' ' :
. *i*..,' L......A- > ,..j .,p ; 3
- :.; v. ..g - , . ,7 '.,e.
- - s
_g, .;;,. .Q. _ r. : t(y . ., J,. -
, . . -a e...9*
.. ". 1g::, .; . -' j.
z
,, .s.,. .
- f. ' t ,., . Y .f~ .l,[_ ,
-[.. . , y- .? ' { }r.x _ ;)[ . . . .j,f:.l. .
.,e - ..
g-1
. .-' . n. u. .;< . . :;l
. -l ;. . :." *L h ;: . . .:: .1 .
..
- t.l]_ .. ..%.t.. ; .: , .' Qj,..:g:.O.L.N
..:...>. : x .. ,. . . :21::h,3.Q.
sq '{s
- L . ;[e ?j.
.: ' q.
- e, o ,,t ,
- c. . [ .
. n.:: .. ..:,... -.:.../. ._i. ..-:
. . .s. .,, ,y , ,
,e; a.p . ,
- e. ;....,. .. .-.:,~... . .. n. .
.i7.., ..
....x;. ..<...y : . .
?. .:. :..+.e
- f. . ..
c s
. . . ' . L :. . ': . s R. . . .4; J, . .
l . . ~ . ; ;. ': , .;_ y ...; + < ; ; g: P .6 J,:.:'. g ;K,.y.:k ' &.. q..,s.,Q R ,,. .}.1;.;f.._ . . .p n ^
G. .: . 7 ; _ .+; _:. . n;:p .y.Q(* _ _g, ~ ( q' . t :
g .
...- .j; i.1j -: 4~'
! =; ' . "
.J .
C." PppareQy.dJ ; fyg.s..slile,
,, .:;. . -p; _ ( m : . . ~ + 9 ;.: . ;r . M 9. s . . . .
.; Island EnvironmentafAffairs. :
_.. .g u k E. * *Y [. . _ . ., .
a
- "3 :.-
l . , :W . . ,
y .?. .
% H,.'. ; % {GPU. Energy Prun Shop 1, .- o :: - < .~'?
O i. '.U W. ~
. , , '4 G; T,W.bg .'
~
1 :. e:. ?'. pp w.. me isi nswongo, g y' : M" : JO Q..,$ i .y . 1 g-
,+ . . , .
- t. .Nyt ; .' 4. ',, J., :[.'.V:
Rl3. ^:$". .*J. ..
A +. Q:, ' D ,.pFm# ' - c. /,.
.w*h(Li.,. '.i. : . ' .
- {-
^.
.s...
. ..b. .y.q ;.9..e/h .y .
.i.gg;y%.C; g .esources;, gManagemergCetstr
. . m, .
!py.e. .i . 7 7.
- . .c ^4. <...H 3.
.. . i; .
^ dl. %,. .n.% $ D: N '
.. ,;?
. .x . ~. ..' ;' ; M.h:
5;f.A %q;.g;g .
y,m. ,.h., g!?.$m; L .Q ' : ' .- ;, . *, 'q\ ?
- 'l -
' . ,; c V .
- y. ; ,. '.
_Y l . I. _ ..j. -l : l J.f;l., .ll f:.'gM . .
[' .,l.... ** '
' T. g .. s - ;
Y
- 3. 4! d,j %GT .. / I * .r.
_.c.y ()g
- , 1
, ,g ,. .
, , , . t flfs Y (M$
i -
- r 'h, f h.1
- -p h" ) $ e
"n'; . ' . ,
o[, :! J.yQ. ., ' ,, j ;.Q, . s: ) l, .,,', ;, ',
2 3 -
'; p'w . . . Ri, ** ' : f,.
g .O !!<r n s' $, . ; 1
,W.g . I;i 1( 7 ' r,
- I@4 >; .,M+ d , g7 p , '%h
!% D < <* ,Vi r 1% 44h i:
I' ' l'/ .i
,t f
., ,$ ,.f p'-T' > q) _ ' #
e y
> "34M/ <g, , 3 ,. (>.
i
".o *
~~ 2 4.' -
i, ,,iz W c . 9, '
fNN ,, ,h. [: .
h '._i ti J v(
h G ,F j
- h[.((h ?
9
.,i4 h ), _ t #
pg . -k. , ,
lil 7l -
I.
..'( , .
r.
(' /h f
..Ws 9[- b%' ,
$w..< u,@h,.. :G
, ! Wy' _Mf pl[y.A
'#r~ '
- M, s ('<
-. , .T J 9
,.4 4
'h *gs' b' p t ' ~ .3i f ( l[e Us <- ' #' M '*
4 '
' .h
. T . I, ' m,ss
..d
' Y /.T
.x C ( !"' #' 5' #..je $y L.[
- p %y; 26 '
ji t t
- '. /
( 1.
-;3 ' Y i 1
7 Jr.:) 9 9 YA 3 % f s
a ? ,. , * . p e ' . ' ,; .d < .
l j 'y G)?
y~
N L <$
'*}(jN( l k ,
i ' ' -
, Y !. u hI . s 'dd Y': }N Y f%
4 Wp h h p ;,[Y y \&)G djAkWh. y m b,
W; @6~
..h.1,h,
(
,lb
$y h, ; Wh.,, p r*b'%p;[. [ [ h M( mh W,g,M, h A DQh. '
i g ,g,y* M"$[4
~
ur - s :su -
ep ;A~ a
? w.,AV a %). , mf77. ,3.,- 4 f 3...,
35 2 % y G' hs R ;a/ysfM,ye- %(;,c. ~>
w^ p, @Vr a,9 s {' L. ' ' W' , ,\, L,p.<y.q, yY} A, ' s g W:m 4 4l., v%<
g Q , % - % .b*e : -
J <~, >i'* hy$
r y y!r , + M1 f, ,7 yv gJj ms
_g
-- ., > .~- v 7 - a OT M - m;j
- 4 y 4
f l;y 92.fr w ; ; ,h " ?' '?-
,pi d]i.y ' (: &
.y c;Q i
f,.a Ql yhjt ; .} ,s s1 , b! p Vli
- s
.,.M .y t.
.' f,
>\ -
t ji Mf (l >
et;,
<}ft- [ l y'.!" '
1to ; t.
,x : rQ ' , ,;. p'W .
At 4' * . its %~ o"f . , . . , - ' -
- i
,.y s
+ g /g i v s, '.;
F , S '(
"g q ,7g^; 4 ijs /Q [,f; {'u ':p , ,p t j
^1 ' .- .4 %-0 3 gr f
A 4 .if-
'hht f k4i $ fg [
$3
> 4_.e
.jp 9 m cy o,,
g j.
- .,i
=-
e g
,..y
$ [ s p, .k, s i;;. , a . , , < . ,u g A
glWl' y{ 9, y y,,g ,tl17 n, d. .o s vx'.J~q, ;e f'2, >) rf.ye [9.y M, 4 %,,, e; 4 ' ,
- , N
- :. .. O y :-
'y' 4;3 a
, ,i ,. i x
- , ,6
. .. . s
<y,n
. .h tV,L 1s
,, tis .,a y;'
n h3 y y1 . . ?, p @ % wm r:
.q ,.3 .3 ,. ,
k
( . i k ,,
? . c l'
, 7.
. fh'~
m (? WsaQ w&' h[Q f ,
MQ(mg }L ; @ '
) '
k % ,
Q tv %,, f l& p l (p 4] Mp p] cll k g?
rf M, K{ki ,
- t. ,
' Gc,RV -n & +. r
%4
- h si.
.e ,.',f f f i;- ?p te pj 9 i.s< u_f
- ww= . hg 3
p'l
'.b Q. , j
.w, v a
h'
- . c 3 Y
,j
+
/-
' 4_ .
.f*g a
F! 8 f,
- m% . ps -y f ji , ' .. (5 f ,* jn t', vs .,
Q$ f */ (, _} u
' [
- Q g ' ' V' t A. . e ,, .,. k '&) ^f' c ss u r)J. @. WQ h ,; 4 4 /; 'y 4/'
y Qj l,, rS 5 T ' 'j W ..-j l /jf'
.i yj. ..Y. '
j', f .) ;* ~ ~ .
W, , : ' .,, ,
Q f
y;'
, .F , m Ar rv ,
. s ~n e 6' '
'm. j t i.*' $l" py s .?y,p o,g4, ' '
1 4 '
~ . . , x_ ,
U. 3 ,
. , j.,% ) Q Q. ed ,,
g 1[ [ > ,7
) ;k
, g , ' ' .f..:.,
' j / t Ma @-2 :<
i p i,c , 4 2 4 -
'. _ ; ' ,4ldT =[:'!\.f5f :.i, c+
a f ,' < s v l
}
' ,: f),( ' .. .
yg 7
1 .
t >
1,
,5-p ,.
N.p Oi'?
j ,
w ps ,.
- n
> ! Ah" g h. D Q V h t s
fg j W
., . tq-K
- N% 1
@W,b -
M s,d '% ,
w ,e- ( .M w gl*
e *m asQ p y <p
- ,.5 g
- m-c '
n ;E f *c*<%:*
' Qyy A$W
$Qg y .m ont ... .
& s , D Y ?kl w
- p s
jas% G .b a 4. - et,
}Y I 's g . ,
l' % , ,
' f,AV}7 .F4 Q* , *! ,n h- ? ,.,;, ' ,U Ty j y*4 y '. h } ,
,' y . n. '
4 e
- l,
, $" * # # f, 4 s w 5S, ,G.,s- .,nm ', w? ' , ~< ?, {.cw,$
n . . , '$, , ' <,$5+, , +-
b&q%. e., SF is . ,> .
s y
,%Alek I *2 > A' .
- ' +b W488d P W 8dP'ed n Wr*A Me g w .y Y. _ ?k$&'W*** * TW # '*'
"W L?N D N % %*m. .-,rmtg eg* ?
i,
~ :W 4 , {hf h
,r. -
tP
., M. i -
% MM.MW
- -~ < - - ~
f <
mj
%w M.j&,;;f$W& ou dq eye
,q#M. h w% - * - - . - + * ,A r ~4 a
, Lg ,
y9' QP- t ' ' .~)(($ f asg' Jf Q )j fg.g
- 1e9 ..w
. g dP\gMS M'm8%gp e.. ; 13,' c 4 gt.v m; .
3 y Q u.u ,* WA 4,'g e
. 1+1,\. , ' i qi , , s
- 4. &..'0:.L,g1 . . t .,y. s ).
- ~
. 3g
'lQ g_ s f,,gm i.4 kg. '.: % n;QRMqfQ ff, s < lT} "@. J.- y, k j s ._
h,dQ "i'",> syy' % ,
W -
aA(
mp-
'd, L: v 'l s a
&t s' *
, t,y> ~p.y 1
>;' y .; - 't fr y
,f ! '
lkY'?$
?w h fw ?. ':7'lh 5W p' i; y a ! . +
- t $1 NA ,sI f L ' '.. , ,+
g,f .( y 9 \V - '.Jt) " ',.',t'. A:
?
. 1 ^., , .f;qa-f, :.tV 1 .Lr,, e t
- g- 4
. ,3.. A; -. y, 4 . ?
<- ' i C Mdhb,Id 1'il
I
\ 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE OF CONTENTS Page Title i TABLE OF CONTENTS iii LIST OF TABLES iv LIST OF FIGURES v LIST OF ABBREVIATIONS, SYMBOLS AND ACRONYMS I
SUMMARY
AND CONCLUSIONS 5 INTRODUCTION 5 Characteristics of Radiation 6 Sources of Radiation 9 Nuclear Reactor Operations 10 Sources of Liquid and Airbome Effluents 13 DESCRIPTION OF THE TMINS SITE 13 General Information 14 Climatological Summary 1998 O 16 16 17 EFFLUENTS Historical Background Effluent Release Limits 18 Effluent Control Program 18 EfYluent Data 25 RADIOLOGICAL ENVIRONMENTAL MONITORING 26 Environmental Exposure Pathways to Humans from Airborne and Liquid Effluents 26 Sampling 27 Analysis 28 Data Review 28 Quality Asstirance Program 40 DIRECT RADIATION MONITORING 41 Sample Collection and Analysis 42 Results 46 ATMOSPHERIC MONITORING 46 Sample Collection and Analysis 47 Air Particulate Results 49 Air lodine Results 55 AQUATIC MONITORING 56 Sample Collection and Analysis 57 Water Results 62 Fish Results 63 Sediment Results O Page i
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT Page Title 72 TERRESTRIAL MONITORING 73 Sample Collection and Analysis 74 Milk Results 75 Terrestrial Vegetation Results 75 Rodent Results 78 GROUNDWATER MONITORING 79 Sample Collection and Analysis 80 Groundwater Results 84 Storm Water and EDCB Sediment Results 85 RADIOLOGICAL IMPACT OF TMINS OPERATIONS 86 Determination of Radiation Doses to the Public 87 Results of Dose Calculations 92 REFERENCES APPEND!X A: 1998 REMP Sampling Locations and Descriptions, Synopsis of REMP, and Sampling and Analysis Exceptions APPENDIX B: 1998 Lower Limit of Detection (LLD)
Exceptions APPENDIX C: 1998 REMP Changes APPENDIX D: 1998 Action Levels APPENDIX E: 1998 Quality Control Results APPENDIX F: 1998 Cross Check Program Resuhs APPENDIX G: 1998 Annual Land Use Census APPENDIX H: 1998 Data Reporting and Analysis APPENDIX 1: 1998 Dose Calculation Methodology and Results APPENDIX J: 1998 Groundwater Monitoring Results APPENDIX K: 1998 Meteorological Data Summary APPENDIX L: 1998 REMP Sample Collection and Analysis Methods APPENDIX M: 1998 TLD Quarterly Data Page ii O
m 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT LIST OF TABLES Page Title 7 Table I Sour.;es and Doses of Radiation 22 Table 2 Radionuclide Composition of TMINS Efiluents for 1998 33 Table 3 Summary of Radionuclide Concentrations in 1998 Environmental Samples from Three Mile Island Nuclear Station 44 Table 4 1998 Monthly Average Exposure Rates for OfTsite Real-Time Gamma Radiation Monitoring Stations 50 Table 5 1998 Average Gross Beta Concentrations in Air Particulates 50 Table 6 1998 Average Gross Alpha Concentrations in Air Particulates 65 Table 7 1998 Average Tritium Concentrations in Surface g and Drinking Water )
66 Table 8 1998 Average Gross Beta Concentrations in Surface and Drinking Water 89 Table 9 Calculated Maximum Hypothetical Doses to an l Individual from 1998 TM1-1 and TMI-2 Liquid and Airborne Releases 90 Table 10 Calculated Whole Body Doses to the Maximum Individual and the Population from 1998 TMI-I and TMI-2 Liquid and Airborne Releases Page iii
i i
l 1998 RADIOLOGICAL ENVIRONMENTAL MONITORANG REPORT i
LIST OF FIGURES l
Page Title 12 Figure 1 Three Mile Island Nuclear Station 23 Figure 2 Historical Releases of Radioiodines and Radioactive Particulates in TMI l Liquid Efiluents 24 Figure 3 Historical Releases of Tritium in TMI-l Liquid Effluents 30 Figure 4 Locations of REMP Stations Within 1 Mile of TMINS 31 Figure 5 Locations of REMP Stations I to 5 Miles from TMINS 32 Figure 6 Locations of REMP Stations Greater Than 5 Miles from TMINS 45 Figure 7 Historical Gamma Exposure Rates 51 Figure 8 1998 Gross Beta Concentrations in Air Particulates 52 Figure 9 Historical Gross Beta Concentrations in Air Particulates 53 Figure 10 1998 Gross Alpha Concentrations in Air Particulates 54 Figure 1I Historical Gross Alpha Concentrations in Air Particulates 67 Figure 12 1998 Tritium Concentrations in Surface Water 68 Figure 13 Historical Tritium Concentrations in Surface Water 69 Figure 14 1998 Tritium Concentrations in Drinking Water 70 Figure 15 1998 Gross Beta Concentrations in Drinking Water 71 Figure 16 Historical Cs-137 Concentrations in Aquatic Sediments 77 Figure 17 Historical Strontium-90 Concentrations in Cow Milk 91 Figure 18 Exposure Pathways for Radionuclides Routinely Released from TMINS Page iv O
b 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT LIST OF ABBREVIATIONS, SYMBOLS AND ACRONYMS ABBREVIATIONS south-southwest.. . ..SSW cubic feet per second. .. efs standard deviation.. ..std dev cubic meter (s).. . m' standard month.. ..std month curie (s) .. .. Ci west.. .. W curie (s) per year . . ..Ci/yr west-northwest.. . .WNW cast .. . . .E west-southwest.. ..WSW east-northeast . .. ENE year (s).. . . .g east-southeast.. . ..ESE gram (s).. ..g ELEMENT SYMBOLS hour (s).. . . . .h actinium.. . .Ac liter (s).. . . . . . .L americium.. . . Am meter (s) .. ..m antimony.. . ..Sb microroentgen(s) per hour. .. R/h argon. .. Ar mile per hour . .. mph barium .. .Ba millircra(s)... .. mrem beryllium.. . Be millirem (s) per hour.. .. mrem /h carbon . .C mil ll rem (s) per standard cesium . ..Cs month.. . mrem /std month chromium .. . .. Cr millirem (s) per year.. . mrem /yr cobalt . .Co milliroentgen (s). .. mR curium. .Cm milliroentgen (s) per hour.. .. mR/h hydrogen (tritium) . . . H -3 mi.iliroentgen(s) per standard iodine . . ..I month.. ..mR/std month iron.. .. Fe north .. .. N krypton.. .. Kr northeast.. .NE lanthanum.. ..La northwest.. .. NW manganese.. .Mn north-northcast . .NNE niobium. .. Nb north-northwest . .. NNW nitrogen .. .. N percent.. .% oxygen.. .. O picoeurie(s).. .. pCi plutonium . . . Pu picoeurie(s) per cubic meter. ..pCi/m' potassium . .. K picoeurie(s) per gram.. .. pCi/g radium .. , . Ra picoeurie(s) per liter.. ..pCi/L radon.. .Rn reference (s) . . Ref. (Refs.) silver . .. Ag rem (s) per ycar.. . rem /yr strontium . . .Sr Roentgen (s).. .. R thorium.. ..Th Roentgen (s) equivalent man. .. rem tritiated water vapor.. ..HTO south.. .S uranium . .. U southeast.. .. SE xenon.. .. Xe southwest.. ..SW zinc.. . .Zn south-southeast.. ..SSE zirconium . .. Zr Pagev
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT ACRONYMS Aboveground Tank Monitoring high efficiency particulate air.. .IlEPA Program . .. ATMP Intemational Committee on Accident Generated Water.. .. AGW Radiation Protection.. .ICRP American National Standards lower limit of detection . ..LLD institute. .. ANSI nuximum permissible Annual Land Use Census. .ALUC concentration.. .MPC as low as reasonably mean sea level . ..msl achievable.. ..ALARA Milton Hershey School . ..MllS biological effects of atomic radiation . . BEAR ininimum detectable concentration . ..MDC biological effects ofionizing National Academy of Sciences.. .NAS radiatiori. .BEIR National Council on Radiation borated water storage tank . .BWST Protection and Measurements . .NCRP Building 48.. . .48S National Institute of Standards and Technology. . NIST Department of Energy.. . . .. DOE National Voluntary Laboratory East Dike Catch Basin.. ..EDCB Accreditation Program.. .NVLAP Environmental Measurement Offsite Dose Calculation Manual. ..ODCM Laboratory.. .EML Operations Support Facility. ..OSF Environmental Radioactivity Laboratory.. .ERL Pennsylvania State Bureau of Radiation Protection.. . ..PaBRP Federal Radiation Council.. . .FRC Post Defueling Monitored Storage . ..PDMS Final Safety Analysis Report.. .. FSAR pressurized water reactor.. ..P W R GPU Nuclear, Inc . ..GPU Nuclear quality assurance.. ..QA Groundwater Monitoring Program.. .GMP quality control . ..QC Page vi O
W O
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT ACRONYMS radiological environmental United States Nuclear Regulatory monitoring program . . .REMP Commission . .USNRC Red Hill Dam . .RHD York Haven Generating Station... ..YHGS Safe Harbor Dam.. .SHD York Haven Dam . ..YHD simplified environmental York Haven Pond.. .YHP effluent dosimetry system.. .. SEEDS Teledyne Brown Engineering... . ..TBE thermoluminescent dosimeter.. ..TLD Three Mile Island.. . .TMI Three Mile Island Environmental Affairs.. . . TMIEA Three Mile Island Nuclear Station.. ..TMINS Three Mile Island - Unit 1. . TMI-l Three Mile Island - Unit 2. . TMI-2 Title 10 of the Code of Federal Regulations, Part 20. .10 CFR 20 Title 10 of the Code of Federal Regulations, I Part 50, Appendix I . .10 CFR 50 App. I l
{
Title 40 of the Code of !
Federal Regulations, )
Part 190. . 40 CFR 190 l s
1 United Nations Scientific i Committee on the Effects of Atomic Radiation.. .UNSCEAR United States Environmental i Protection Agency.. ..USEPA l r
( f Page vii !
nn RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT
SUMMARY
AND CONCLUSIONS The radiological environmental monitoring performed in 1998 by GPU Nuclear for Three Mile Island Nuclear Station (TMINS) is discussed in this report. The environmental sample results and the doses calculated from measured effluents indicated that TMINS operations in 1998 had no adverse effect on the health of the public or the environment.
The operation of a nuclear power station results in the release of small amounts of radioactive materials to the environment. A radiological environmental monitoring program (REMP) has been established to monitor radiation and radioactive materials in the environment around TMINS. The results of environmental measurements are used to assess the impact of TMINS operations, to demonstrate compliance with the TMI-l and TMI-2 Technical Specifications (Refs. I and 2) and applicable Federal and State regulations, and to verify the adequacy of containment and radioactive effluent control systems. The program also evaluates the relationship between amounts of radioactive material released in effluents to the environment and resultant radiation doses to individuals.
f PageI
i 1
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT i
Summaries and interpretations of the data are Impact of TMINS Operations and I published annually in the Radiological Appendix I).
Environmental Monitoring Report. Previous reports in this series are referenced at the end The results provided in this report are of the report (Refs. 3 through 28). Additional summarized in the following highlights:
information concerning releases of radioactive j materials to the environment is contained in E in 1998,1327 samples were collected the Radiological Emuent Release Reports. from the aquatic, atmospheric and l These reports are submitted annually to the terrestrial environments around TMINS.
United States Nuclear Regulatory There were 2049 analyses performed on Commission (USNRC). these samples. Also,2100 radiation )
exposure measurements were taken using j Many of the radioactive materials discussed in thermoluminescent dosimeters (TLDs). j this report are normally present in the Finally,261 groundwater samples were l environment, either from natural processes or collected and 302 analyses were performed j as a result of non-TMINS activities such as on these samples. The monitoring !
prior atmospheric nuclear weapon tests and performed in 1998 met or exceeded the j medicalindustry activities. To determine the sample collection and analysis l impact of TMINS operations, if any, on the requirements of the TMI-l and TMI-2 l' environment and the public, results from Technical Specifications.
samples collected close to TMINS (indicator stations) are compared to results from samples e in addition to natural radioactivity, low i I
obtained at distant sites (control or concentrations of radionuclides such as background stations). Comparisons with H-3, Sr-90, cesium-137 (Cs-137) and ,
historical data also are performed, as 1-131 were detected in various media and l appropriate. were attributed to either fallout from prior nuclear weapon tests, the medical industry During 1998, samples of air, surface, emuent, or TMINS operations. i drinking and storm water, sediments, fruits, vegetables, grains, fish, groundwater, milk, a As a result of routine TMINS operations, ;
and rodent carcasses were collected. Direct the raw surface water collected 1 radiation exposures also were measured in the downstream of the TMINS liquid j vicinity of TMINS. Samples were analyzed discharge outfall typically had H-3 ;
for gross beta and gross alpha radioactivity, concentrations greater than those detected tritium (H-3), strontium-89 (Sr-89) and in control samples. This was expected strontium-90 (Fr-90), iodine-131 (1-131) because H-3 was released in liquid j and/or gamma-emitting radionuclides. The emuents and the samples were collected results are discussed in the various sections of from a site where mixing ofliquid emuents i this report. Additionally, radiological impacts with Susquehanna River water was in terms of radiation dose as a result of incomplete. Although raw water is not TMINS radioactive releases were calculated consumed by humans, all of the measured and are discussed in this report (Radiological concentrations were well below the United l
l Page 2
(3 I 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT States Environmental Protection Agency's u Groundwater samples collected from the (USEPA) Primary Drinking Water onsite monitoring wells, the industrial Standard of 20,000 picocuries per liter wells and the clearwell contained H-3 (pCi/L). above ambient concentrations as a result of routine operations at TM1-1 and past a Several indicator drinking water samples operations at TMI-2. Additionally,it is contained H-3 at concentrations above possible that a pipe leak may be those detected in control samples. A contributing to elevated levels of H-3 in portion of the H-3 measured in the certain onsite wells. A project was started indicator samples was attributed to routine in March of 1999 to repair or replace the operations at TMINS. Like surface water, pipe ifit is found to be leaking. All H-3 the H-3 concentrations measured in concentrations detected in onsite drinking water were we'l below the groundwater were below the emuent standard established by the USEPA. concentration specified in USNRC 10 CFR 20 (Appendix B, Table 2).
m Tritium was detected in indicator fish samples as a result of routine TMINS E Tritium was detected in onsite operations. Its presence was not groundwater used for drinking. The unexpected because H-3 was released in presence of H-3 in these samples was liquid emuents and the indicator fish attributed to routine TMI-l operations
(/ samples were collected in a zone where and possibly past TMI-2 operations. All mix ng of emuents and river water was of the H-3 concentrations measured in incomplete. The hypothetical whole body onsite drinking water were well below the dose from consuming fish flesh at the USEPA Primary Drinking Water measured concentrations was insignificant Standard.
and a small fraction of the dose received from natural background radiation. E Gamma radiation exposure rates recorded at the offsite indicator TLD and real-time E Low concentrations of TMINS-related monitoring stations averaged 54 and 67 Cs-137 were detected in aquatic sediments milliroentgens per year (mR/yr),
collected proximal to orjust down:.tream respectively. Offsite controls were similar, of the TMINS liquid discharge ou' fall. averaging 59 mR/yr. The exposure rates During 1998, as well as in previous ye.rs, were consistent with those presented by this material was routinely released in the National Council on Radiation TMINS liquid emuents. Additionally, Protection and Measurements (Ref 29).
Cs-137 is readily adsorbed by suspended No significant increase in ambient gamma particles in the water column and bottom radiation levels was detected.
sediments. Since Cs-137 also was detected in the control samples, a portion a During 1998, small amounts of radioactive of the Cs-137 measured in the indicator materials were released in TMI-l and samples was attributed to fallout from TMI-2 liquid and gaseous emuents.
l n prior nuclear weapon tests. Excluding H-3, the amount of radioactive (d'
Page 3
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT material released from TMI-l was one of only a small fraction of the doses received the lowest in its operating history. This from natural background radiation.
achievement was attributed to good fuel Additionally, the results indicated that there integrity, minimal leakage in the steam was no permanent buildup of radioactive generators and improved efficiency of the materials in the environment and no significant waste processing systems. Tritium, increase in background radiation levels.
because ofits chemical and physical properties, can not be removed from water Therefore, based on the results of the or air. radiological environmental monitoring program (REMP) and the doses calculated a The calculated doses to the public from from measured effluents, TMINS operations TMINS operations in 1998 were well in 1998 did not have any adverse effects on below all applicable regulatory limits and the health of the public or on the environment.
significantly less than doses received from other common sources of radiation. The hypothetical maximum whole body dose potentially received by an individual from 1998 TMI-l and TMI-2 liquid and airborne effluents combined was conservatively calculated to be 0.0429 mrem. This dose is equivalent to 0.0143 percent of the dose that an individual living in the TMI area receives each year from natural background radiation.
5 The hypothetical maximum whole body dose to the surrounding population from all 1998 liquid and airborne effluents was calculated to be 7.77 person-rem. This dose is equivalent to 0.00118 percent of the dose that the total population living within 50 miles of TMI receives each year from natural background radiation.
In conclusion, radioactive materials related to TM. INS operations were detected in environmental samples, but the measured concentrations were low and consistent with measured effluents. The environmental sample results verified that the doses received by the public from TMINS efiluents in 1998 were well below applicable dose limits and Page 4
O 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT V
INTRODUCTION Characteristics of Radiation Instability within the nucleus of radioactive atoms results in the release of energy in the form of radiation. Radiation is classified according to its nature -- particulate and electromagnetic.
Particulate radiation consists of energetic subatomic particles such as electrons (beta particles), protons, neutrons, and alpha particles.
Because ofits limited ability to penetrate the human body, particulate radiation in the environment contributes primarily to internal k radiation exposure via inhalation and ingestion.
Electromagnetic radiation in the form of x-rays and gamma rays has characteristics similar to visible light but is more energetic and, hence, more penetrating. Although x-rays and gamma rays are penetrating and can pass through varying thicknesses of materials, once they are absorbed they produce energetic electrons which release their energy in a manner that is identical to beta particles. The principal concem for gamma radiation in the environment is their contribution to external radiation exposure.
O Page5
\
l 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT Atoms of radioactive elements disintegrate The biological effects of radiation to the continually. The rate that atoms undergo entire human body (whole body equivalent
! disintegration (radioactive decay) varies dose) are the same whether the radiation among radioactive elements, but is uniquely source is external or internal to the body.
constant for each specific radionuclide (or The important factor is how much radiation radioactive isotope). The term " half-life" energy or dose is deposited. The unit of defines the time it takes for the activity of a radiation dose is the Roentgen equivalent radionuclide to decay to one half ofits man (rem), which also incorporates the original activity. Half-lives can vary from a variable effectiveness of different forms of fraction of a second for some radionuclides radiation to produce biological change. For to millions of years for others. In fact, the environmental radiation exposures, it is natural background radiation that all convenient to use millirem (mrem) to express mankind has been exposed to is largely due dose (1000 mrem equals I rem). When to the radionuclides of uranium (U), thorium radiation exposure occurs over periods of (Th), and potassium (K). These radioactive time, it is appropriate to refer to the dose elements were formed with the creation of rate. Dose rates, therefore, define the total l the universe and, owing to their very long dose for a fixed interval of time. I half-lives, will continue to be present for Environmental radiation exposures are i mi!! ions of years to come. For example, usually expressed with reference to one year potassium-40 (K-40) has a half life of 1.3 (mrem /yr). l billion years and exists naturally withm our bodies. As a result, approximately 4000 Sources of Radiation atoms of potassium emit radiathn internally within each of us every secoM of our lives. Lifb on earth has evolved amid the constant exposure to natural radiation. In fact, the In assessing the impact of radioactivity on single major source of radiation to which the the environment, it is important to know the general population is exposed comes from quantity of radioactivity released and the natural sources. Although everyone on the resultant radiation doses. The common unit planet is exposed to natural radiation, some of radioactivity is the curie (Ci). It people receive more than others. Radiation represents the radioactivity in one gram (g) exposure from natural background has three of natural radium (Ra), which is also equal to components (i e., cosmic, terrestrial, and a decay rate of 37 billion radiation emissions internal) and varies with altitude, geographic every second. Because extremely small location and living habits.
amounts of radioactive material exist in the environment, it is more convenient to use For example, cosmic radiation originating fractions of a curie. Subunits like picoeurie, from deep interstellar space and the sun pCi, (one trillionth of a curie) are frequently increases with altitude, since there is less air used to express the radioactivity present in which acts as a shield. Similarly, terrestrial environmental and biological samples. radiation resulting from the presence of naturally-occurring radionuclides in the soil and rocks varies and may be significantly Page 6
1
/
l 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT higher in some areas of the country than in background radiation sources (Ref 29). This others. Even the use ofparticular building estimate was revised from about 100 to 300 materials for houses, cooking with natural mrem because of the inclusion of radon gas j gas, and home insulation affect exposure to which was always present but was not natural radiation. previously included in the caku%tions. l The presence of radioactivity in the human in some regions of the country, the amount body results from the inhalation and of natural radiation is significantly higher.
ingestion of air, food, and water containing Residents of Colorado, for example, receive naturally-occurring radionuclides. For an additional 60 mrem /yr due to the increase !
example, drinking water contains trace in cosmic and terrestrial radiation levels. In f amounts of uranium and radium and milk fact, for every 100 feet above sea level, a j contains radioactive potassium. Table I person will receive an additional 1 mrem /yr j summarizes the common sources of radiation from cosmic radiation. In several regions of and their average annual doses. the world, naturally high concentrations of uranium and radium deposits result in doses The average person in the United States of several thousand mrem /yr to their receives about 300 mrem /yr from natural residents (Ref. 30).
(
TABLE 1 i Sources and Doses of Radiation
- Natural (82%) Manrnade (18%)
Radiation Dose Radiation Dose Source (mrem /vr) Sourcy 6ntem/vri Radon 200 (55 %) Medica) X-rays 39 (11 %) l Cosmic rays 27 (8%) Nuclear Medicine 14 (4%) j Terrestrial 28 (8%) Consumer products 20 (3%) l internal 40 (11 %) Other < l (< 1%) l (Releases from nat. gas, phosphate i mining, burning of coal, weapons fallout, & nuclear fuel cycle) l APPROXIMATE APPROXIMATE TOTAL 300 TOTAL 60
- Percentage contribution of the total dose is shown in parentheses.
Source: Ref. 29 Page 7
I998 MD10 LOGICAL ENVIRONMENTAL MONITORING REPORT Recently, public attention has focused on some radionuclides stay in the body for very radon (Rn), a naturally-occurring radioactive short times while others remain for years.
gas produced from uranium and radium decay. These elements are widely distributed In addition to natural radiation, we are in trace amounts in the earth's crust. exposed to radiation fmm a number of Unusually high concentrations have been manmade . sources. The single largest source found in certain pans of eastern Pennsylvania comes from diagnostic medical x-rays, and and northern New Jersey. Radon levels in nuclear medicine procedures. Some 180 l some homes in these areas are hundreds of million Americans receive medical x-rays times greater than levels found elsewhere in each year. The annual dose to an individual the United States. However, additional from such radiation averages abaut 53 mrem.
surveys are needed to determine the full Much smaller doses come from nuclear extent of the problem nationwide. weapon fallout and consumer products such as televisions, smoke detectors, and Radon is the largest component of natural fertilizers. Production of commercial nuclear I background radiation and may be responsible power and its associated fuel cycle for a subrtantial number oflung cancer deaths contributes less than 1 mrem to the annual annually. The National Council on Radiation dose of about 360 mrem for the average Protection and Measurements (NCRP) individual living in the United States.
estimates that the average individual in the United States receives an annual dose of Fallout commonly refers to the radioactive about 2,400 mrem to the lung from natural debris that settles to the surface of the earth radon gas (Ref. 29). This lung dose is following the detonation of a nuclear considered to be equivalent to a whole body weapon. It is dispersed throughout the dose of 200 mrem. The NCRP has environment either by dry deposition or recommended actions to control indoor radon washed down to the earth's surface by sources and reduce exposures. precipitation. There are approximately 200 radionuclides produced in the nuclear weapon When radioactive substances are inhaled or detonation process. A number of these are ,
swallowed, they are not uniformly distributed detected in fallout. The fallout radionuclides !
within the body. For example, radioactive that produce most of the radiation exposures l iodine selectively concentrates in the thyroid to humans are I-131, Sr-89, Cs-137, and I
gland, radioactive cesium is distributed Sr-90. There has been no atmospheric throughout the body water and muscles, and nuclear weapon testing since 1980 and many radioactive strontium concentrates in the of the radionuclides, still present in our bones. The total dose to organs by a given environment, have decayed significantly.
radionuclide also is influenced by the quantity Consequently, doses to the public from inhaled or ingested, the duration of time that fallout have been decreasing.
it remains in the body and its physical, biological and chemical characteristics. As a result of the nuclear accident at Depending on their rate of radioactive decay Chernobyl, Ukraine, on April 26,1986, 1 and biological elimination from the body, radioactive materials were dispersed :
Page 8 l
l 1
- 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT V
throughout the environment and detected in structures of the reactor. In such cases, various environmental media such as air, stable atoms often become radioactive. This milk, and soil. Cesium-134, Cs-137,1-131 process is called activation and the and other radionuclides were detected in the radioactive atoms which result are called weeks following the Chernobyl accident. activation products.
Nuclear Reactor Operations The TMINS reactors (TMl-1 and TMI-2) are pressurized water reactors (PWR). Only Common to the commercial production of TMI-l is an operating reactor. At the end of .
electricity is the consumption of fuel to 1993, TMI-2 was placed in a condition called j produce heat and steam. The steam drives Post-Defueling Monitored Storage (PDMS). l the turbine which generates electricity. As the name implies, TMI-2 will continue to {
Unlike the burning of coal, oil, or gas in be monitored until operations at TMI-l l
fossil-fuel powered plants to generate heat, cease. At that time, both TMI-l and TMI-2 I the fuel of most nuclear reactors is comprised will be decommissioned.
of the element uranium in the form of uranium oxide. The fuel produces heat by the The nuclear fuel used in an operating reactor process called fission. such as TM1-1 is contained within sealed fuel
] In fission, the uranium atom absorbs a rods arranged in arrays called bundles. The bundles are located within a massive steel neutron (an atomic particle found in nature reactor vessel. Pressurized water reactors and also produced by the fissioning of utilize steam generators to transfer the heat of uranium in the reactor) and splits to produce the coolant water to the secondary steam ,
smaller atoms termed fission products, along loop. Thus, the steam generators serve as a !
with heat, radiation and free neutrons. The boundary between the radioactive primary free neutrons travel through the reactor and loop and the secondary steam loop.
are similarly absorbed by the uranium, permitting the fission process to continue. As depicted in Figure 1, heat is added to the l water as it is pumped around and through the As this process continues, more fission fuel bundles in the reactor vessel. The hot products, radiation, heat and neutrons are primary coolant then passes inside thousands l produced and a sustained reaction occurs. of sealed tubes within the steam generator. l The heat produced is transferred - via the Heat is transferred through the tube walls reactor coolant water - from the fuel to into the secondary water which flows around produce steam. The steam drives a turbine the tubes, thereby creating steam for use in generator to produce electricity. Most of the the turbine. After the energy is extracted fission products are radioactive. That is, they from the steam in the turbine, it is cooled and are unstable atoms that emit radiation as they condensed back into water by a third loop decay to stable atoms. Neutrons which are which circulates water between the condenser not absorbed by the uranium fuel may be and the cooling towers.
p absorbed by sta' ole atoms in the materials which make up the components and (v) Page 9
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT Several hundred radionuclides of some 40 The fourth barrier consists of the reactor different elements are created during the pressure vessel and the steel piping of the process of generating electricity. And, primary coolant system. The reactor pressure because of reactor engineering designs, the vessel is a 36-foot high tank with steel walls short half-lives of many radionuclides, and about 9 inches thick. It encases the reactor their chemical and physical properties, nearly core. The remainder of the primary coolant all radioactivity is contained. system includes the pressurizer, steam generators and associated piping. This Pressurized water reactors have five system provides containment for radioactivity independent barriers that confine radioactive in the primary coolant. l materials given off by the reactor fuel as it l heats the water. Under normal operating The reactor building (or containment conditions, essentially all radioactivity is building) provides the fifth barrier. It has contained within the first two barriers. steel-lined concrete walls about 4 feet thick that enclose the reactor pressure vessel and l The ceramic uranium fuel pellets provide the the primary coolant system.
first barrier. Most of the fission products are either trapped or chemically bound in the fuel Sources of Liauid and Airborne Ef11uents where they remain. However, a few fission products that are volatile or gaseous at Although the previously described barriers normal operating temperatures may not be contain radioactivity with high efliciency, contained in the fuel. small amounts of radioactive fission products diffuse or migrate through minor flaws in the The second barrier consists of zirconium (Zr) fuel cladding and into the primary coolant.
alloy tubes (cladding) that resist corrosion Trace quantities of reactor system component and high temperatures. The fuel pellets are and structure surfaces that have been contained within these tubes. There is a small activated also get into the primary coolant gap between the fuel and the cladding, in water. Many of the soluble fission and which the noble gases and other volatile activation products such as iodines, radionuclides collect and are contained. strontiums, cobalts, and cesiums are removed by demineralizers in the purification system of The primary coolant water is the third barrier. the primary coolant. The physical and Many of the fission products, including chemical properties of noble gas fission radioactive iodine, strontium and cesium are products in the primary coolant prevent their soluble and are retained in water in an ionic removal by the demineralizers.
(electrically charged) form. These materials can be removed in the primary coolant Because the reactor system has many valves purification system. However, krypton (Kr) and fittings, an absolute seal cannot be and xenon (Xe) do not readily dissolve in the achieved. Small amounts of noble gases and coolant, particularly at high temperatures. trace quantities of residual fission and Krypton and xenon collect as a gas above the activation products have the potential for coolant when the water is depressurized. escape into the reactor building and Page 10
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT associated buildings. A portion of the demineralizers, and evaporators to remove airborne effluents comes from the atmosphere radioactivity from the water prior to release.
around the primary coolant system, which Purified water is reused or released to the receives steam and liquid leakage from valves river and the processed wastes are and pumps on systems carrying primary concentrated for offsite burial at approved, coolant. Environmental release of airborne licensed facilities. Tritium, because ofits radioactivity is reduced by simply holding the chemical behavior, is not removed from liquid l radioactivity inside the reactor building for a wastes. l period of time which allows for the natural i radioactive decay of some radionuclides. As a result of minor leakage in the steam Radioactive gases from purification systems generators, small amounts of radioactive also contribute to airborne effluents and are materials are present in the secondary (steam collected and stored in tanks for radioactive loop) water. Although not all of the water is l decay before being released. treated, all of the water is monitored and '
diluted with nonradioactive water prior to l Airborne effluents pass through a two-stage being released.
filtration system prior to environmental release. High efficiency particulate air GPU Nuclear conducts operations such that (HEPA) filters effectively remove releases ofliquid and gaseous wastes are c small radionuclides such as strontium and cesium percentage of the Federal limits. Consequently, with a 99 percent (%) efficiency. Activated the doses associated with these releases are a charcoal filters remove radiciodines with a 90 small fraction of the dose limits established by to 95 % efliciency. Noble gases and tritium, the Federal Government.
however, cannot be removed by either of these filtration processes because of their chemical and physical properties.
Ventilation systems throughout the plant are designed to maintain a negative pressure (suction) with respect to the outside atmosphere. This pressure differential assures that all building air and air exhausted j from potentially radioactive areas of the buildings is filtered by HEPA and charcoal filters prior to release to the environment.
Liquid wastes are generated from the primary coolant purification system and from small amounts ofliquids which escape from valves, piping, and equipment associated with the primary coolant system during normal operations. Liquids are treated using filters, Page 11 l
2 0 n'...
o b
t e
S 1
P e
g a
i t
t a '.,
'g V i t s S #
r a - a ,
e e
r .' t -
a -
t sp om l a nm -
e c r e
n dunP u e G
C o
N / r r
e e
d \ s n
t a
n w
e d e
l a /
c d
n o
F
/
t e
e -
s x. a s
0 I e /
/
d C
n e
n o
l =
i p M l; g d. m eu rP eG
. ~
l N
eI r D L r o
h I U
B a _
T f
T o N G E -
n
" p M
N r .
mI e u _
A i z P , _
r T
uc u
N >
s s d O e o -
u C P r R l
R o r
O t rt 1 onm T o C t ae e 0 %a A E
R C
cl t aos eoy RCS i F
r u
g l ll\
s 1998 RAI)l0 LOGICAL ENVIRONMENTAL MONITORING REPORT DESCRIPTION OF THE TMINS SITE General Information Three Mile Island (TMI) is located in Londonderry Township of Dauphin County, Pennsylvania. It lies approximately 2.5 miles north of the southern tip of the county, where the county borders of Dauphin, Lancaster, and York converge.
The Island is part of an 814 acre tract of Company-owned land which encompasses TMI and several adjacent islands in the Susquehanna River (Refs. 31 and 32). Aligned north to south, TMI is approximately 11,000 feet long and 1700 feet wide. The eastern and western riverbanks are 900 and 6500 feet, respectively, from TMI. Covering about 200 acres of I land, Three Mile Island Nuclear Station (TMINS) is situated on the northern one-half of TMI.
The Island is relatively Hat with elevations ranging from I about 280 feet above mean sea level (msl) at the water's edge to slightly more than 300 feet above msl in the north-central portion. The topography of the area immediately surrounding TMI is characterized by rolling terrain which I slopes to the river valley Door. The hills within a two mile radius have a maximum relief of about 200 feet with the highest elevation seldom exceeding 500 feet above msl. The Susquehanna River at the site drains a watershed area of approximately 25,000 square miles.
O Page 13
l 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT With the exception of the southern border of ten-mile radius of TMINS. The nearest TMI, the Island is bounded by the part of the population center is Goldsboro with a Susquehanna River known as York Haven Pond population of 458 people. It lies approximately or Lake Frederick. The pond, which is 1.5 one mile to the west of the site. About 2.5 miles wide at the site, is formed by the York miles to the north,9,254 people reside in the Haven and Red Hill Dams. Three Mile Island town of Middletown. Harrisburg, situated 12 and Shelley Island divide the river into three miles to the northwest, is the nearest major city main channels. Several lesser channels also are with a population of 52,376. Land within a 10 formed by smaller islands. mile radius of the site is used primarily for farming. Farm products include poultry, meat, The historical average annual flow of the fruit, dairy products, vegetables, corn, wheat, Susqueharna River in the TMl region is 34,000 alfalfa, tobacco, and other crops oflesser cubic feet per second (cfs). During 1998, importance.
however, the annual average flow was slightly higher than the historical average. The flow in Climatological Summarv - 1998*
1998 averaged about 37,844 for the TMI region i with monthly averages ranging from 4,505 cfs The Appalachian Mountains, located about 20 l in September to 89,462 cfs in March. The miles to the north ofTMI, protect the area maximum flow was recorded in March at somewhat from the cold winter outbreaks of 158,000 cfs (Ref. 33). The historical average Arctic air that invade central and western annual maximum flow is about 300,000 cfs Pennsylvania. However, the site is too far while the minimum daily flow recorded for the inland to derive the full benefits of a coastal region is 1,700 cfs (Ref. 31). A flood climate like that in the more southeastern region protection dike completely surrounds TMINS of Pennsylvania. Summers tend to be warm and and was designed based upon a flow of humid and winters are cool, with frequent 1,100,000 cfs. For comparison, the maximum periods of precipitation. Summer rainfall flow / flood of record occurred in June 1972 as a typically comes from thunderstorm activity, result of tropical storm "Agnes" This event while most of the precipitation in the winter is a produced a flow of 1,020,000 cfs. result of coastal winter storms. Normal yearly i
precipitation (water equivalent) for the TM1 Present uses of the Susquehanna River include region is 40.5 inches. Winds primarily are from public and industrial water supply, power the northwesterly direction.
generation, and recreation such as boating, ;
swirmning and fishing. While there are no During 1998, the winds blew from the west-commercial fisheries on the Susquehanna River northwest (WNW), the northwest (NW) and the ,
in the TMI region, recreational fisherman catch north-northwest (NNW) approximately 36 several different sporting species that inhabit the percent of the time. 1 River. Three of the more prevalent sporting fishes in the vicinity of TMI include Smallmouth i bass, Channel catfish and Walleye.
- Sources: i
- 1) Onsite Meteorological Data.
Based on 1990 census data (Ref. 34), 2) National Climatic Data Center, Asheville, NC approximately 175,000 people reside within a 3) National Weather Service, State College, PA Page 14
O 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REEY)RT The annual average wind speed during 1998 in tower. When real-time data are not available or the TMI region was about 8.6 miles per hour invalid, default values are entered into the (mph). Monthly averages ranged from 6.7 mph database. The default values are consistent in September to 11.7 mph in March (Ref. 35). with actual meteorology for the TM1 vicinity.
During 1998, a total of 42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br /> of real-time During 1998, the average monthly temperatures data (.5%) were not available or invalid. This ranged from 38.2
- F (January) to 75.3
- F (July). was mainly due to seueral electric storms The maximum monthly deviation occurred in during the year which rendered some of the January when the temperatures averaged 9.6 F equipment inoperable or inaccurate.
above the normal monthly temperature. The lowest temperature of the year occurred on December 31 (1
- F). The highest temperature was recorded on September 6 (93
- F). The overall annual average temperature was about 56.6 F which is about 3.7*F above the normal annual average temperature (normal dry bulb).
For the TMI area,1998 was the warmest year on record.
A total of 48.6 (water equivalent) inches of V precipitation was recorded at TMI during 1998.
This amount was about 8.1 inches above the normal total. Monthly precipitation totals ranged from a low of about 0.4 inch in December to a high of 6.4 inches in May. The amount of precipitation that fell in May exceeded the normal total for the month by approximately 2.1 inches.
The greatest daily precipitation event in the region occurred on July 8 when about 2.8 inches of rain fell. The year's greatest snowfall event (2.8 inches) in the region was recorded on January 25. The highest snowfall month also was January. A total snowfall of 5.3 inches was recorded for the month. The annual snowfall totaled 7.1 inches. i l
A summary of wind and dispersion information l (a wind rose and joint frequency tables) for the '
TMINS site is provided in Appendix K. This p information is normally generated from data obtained from the TMINS meteorological
(
Page 15
A
) 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT EFFLUENTS Historical Background Almost from the outset of the discovery of x-rays in 1895 by Wilhelm Roentgen, the potential hazard ofionizing radiation was recognized and efforts were made to establish radiation protection standards. The International Commission on Radiological Protection (ICRP) and the NCRP were established in 1928 and 1929, respectively.
These organizations have the longest continuous experience in the review of radiation health effects and with making recommendations on s guidelines for radiological protection and I radiation exposure limits.
In 1955, the United Nations created a Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) to summarize reports received on radiation levels and the effects on man and his environment. The National Academy of Sciences (NAS) formed a committee in 1956 to review the biological effects of atomic radiation (BEAR). A series of reports have been issued by this and succeeding NAS committees on the biological effects ofionizing radiation (BEIR), the most recent being 1990 (known as BEIR V).
1 O Page 16
(
I l
I 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT These committees and commissions of specified in the Technical Specifications for )
nationally and internationally recognized TMI-l and TMI-2 and the Offsite Dose j scientific experts have been dedicated to the Calculation Manual, ODCM, (Ref. 40). GPU understanding of the health effects of radiation Nuclear conducts operations such that by investigating all sources of relevant releases of radioactive emuents are a small knowledge and scientific data and by percentage of the Federal limits. l providing guidance for radiological ]
protection. Their members are selected from A recommendation of the ICRP, NCRP, and !
universities, scientific research centers and FRC is that radiation exposures should be l other national and international research maintained at levels which are "as low as i organizations. The committee reports contain reasonably achievable"(ALARA) and l scientific data obtained from physical, commensurate with the societal benefit biological, and epidemiological studies on derived from the activities resulting in such radiation health effects and serve as scientific exposures. For this reason, dose limit references for information presented in this guidelines were established by the USNRC for report. releases of radioactive effluents from nuclear '
power plants. These guidelines are presented Since its inception, the USNRC has depended in Title 10 of the Code of Federal upon the recommendations of the ICRP, the Regulations, Part 50, Appendix I(10 CFR 50, NCRP, and the Federal Radiation Council App.1). Maintaining doses within these (FRC), incorporated in the USEPA in 1970, operational guidelines demonstrates that for basic radiation protection standards and releases of radioactive effluents are being guidance in establishing regulations for the maintained "as low as reasonably achievable" nuclear industry (Refs. 36 through 39). These USNRC ALARA guidelines are a fraction of the dose limits established by the Efiluent Release I,imits USEPA.
As part of routine operations at a nuclear The USNRC 10 CFR 50, App. I guidelines power station, limited quantities of radioactive are as follows:
materials are released to the environment in liquid and airborne effluents. At TMINS, an a The dose to a member of the public from effluent control program is implemented by radioactive materials released in liquid GPU Nuclear to ensure that the amounts of effluents is limited to 5 3 mrem /yr to the radioactive materials released to the total body or 5_10 mrem /yr to any organ.
environment are minimal and do not exceed
. release limits. 5 The air dose due to noble gases at a location which would be occupied by a The Federal government establishes limits on member of the public is limited to 510 radioactive materials released to the mrad /yr for gamma radiation or 5 20 environment. Regulated by the USNRC, mradlyr for beta radiation.
these limits are set at levels to protect the health and safety of the public. They are Page 17
l l
l 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT ]
a The dose to a member of the public from Emuent Instrumentation: Liquid and noble gases released in gaseous emuents is airborne emuent measuring instrumentation is limited to 5 5 mrem /yr to the total body or designed to monitor the presence and the 515 mrem /yr to the skin. amount ofradioactivity in efiluents. The instruments provide continuous surveillance of a The dose to a member of the public from radioactivity releases. Calibrations of emuent airborne iodines, tritium and particulates is instruments are performed using reference limited to 515 mrem /yr to any organ. standards certified by the National Institute of Standards and Technology (NIST) The The USEPA dose limits as defined in Title 40 instruments are calibrated to respe 1 to of the Code of Federal Regulations, Part 190 specific radionuclides and are sensitive enough I (40 CFR 190), are as follows: to measure 100 to 1,000 times below the applicable release limits.
5 The dose to a member of the public shall not exceed in a year 25 mrem /yr to the Each instrument is equipped with alarms total body,75 mrem /yr to the thyroid, and which are connected to the Control Room.
25 mrem /yr to any other organ as a result The alarm setpoints are set to ensure that of uranium fuel cycle operations. effluent release limits will not be exceeded. If radiation monitor alarm setpoints are reached, f Emuent Control Program liquid and airborne releases are automatically i terminated.
Efiluent control includes plant components such as the ventilation system and filters, Emuent Sampling and Analysis: In waste gas holdup tanks, demineralizers and addition to continuous radiation monitoring evaporator systems. In addition to minimizing instruments, samples of effluents are taken the release of radioactivity, the eflluent and subjected to laboratory analysis to identify control program includes all aspects of the specific radionuclide quantities being efIluent monitoring. This includes the released. Sampling and analysis provide a operation and data analysis associated with a sensitive and precise method of determining complex radiation monitoring system, effluent composition. Samples are analyzed collection and analysis of efiluent samples, using state-of-the-art laboratory counting and a comprehensive quality assurance (QA) equipment. Radiation instrument readings and program. Over the years, the program has sample results are compared to ensure correct evolved in response to changing regulatory correlation.
requirements and plant conditions. For example, additional instmments and samplers Emuent Data have been installed to ensure that measurements of efiluents remain onscale in The amount of radioactivity released from the event of any accidental release of TMINS varies and is depende.nt upon radioactivity. operating conditions, power levels, fuel conditions, efficiency ofliquid and gas p processing systems, and proper functioning of Page 18
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REli)RT plant equipment. The largest variations occur Noble Gases: Noble gases such as argon, in the airborne emuents of fist. ion and xenon and krypton are produced and released activation gases that are particularly sensitive from operating nuclear power stations. These to the holdup time capability in the gas gases are readily dispersed in the atmosphere processing system and to the integrity of the when released and do not react chemically or fuel cladding. biologically with other materials. Typically, xenon and krypton are the predominant During 1998, small amounts of radioactive radioactive materials released in TMI-l materials were released in TMI-l and TMI-2 airborne emuents. This was not true for liquid and airborne emuents. Excluding 1998. The predominant radionuclide released tritium (H-3), the total amount of radioactivity in TMI-l airborne emuents was H-3. Lesser released from TM1-1 in 1998 was one of the amounts of xenon and krypton were released lowest in its operating history. This notable due to good fuelintegrity.
achievement was due primarily to good fuel integrity, minimal leakage in the steam During 1998, TMI-l released only 1.57 Ci of generators and improved emciency of the noble gases to the atmosphere. Specifically, waste processing systems. Tritium, because 1.0? Ci of xenon (primarily Xe-133),0.405 Ci ofits chemical and physical properties, can of Kr-85 and 0.143 Ci of Ar-41 were released.
not be removed from air or water. However, For comparison,14.4 Ci of xenon, 0.00930 Ci the doses from inhaling and ingesting H-3 of krypton and 0.143 Ci of argon were released 'n TMINS liquid and airborne released in 1997 TMI-l airborne emuents. A emuents are relatively small because this very small amount of xenon (0.00000281 Ci) radionuclide is a low energy beta emitter. also was released in TMI-l liquid emuents.
Radioactive noble gases svere not detected in As expected, the doses potentially received by 1998 TMI-2 liquid or airborne emuents.
individuals from 1998 TMI-l and TMI-2 liquid and airborne emuents were ve,ry low lodines and Particulates: The discharge of and a small fraction of the Federal limits. radiciodines and radioactive particulates to Doses to the public are discussed in more the environment is minimized by factors such detail in Radiological Impact of TMINS as their high chemical reactivity, solubility in Operations and Appendix 1. water, and the high emeiency of removal in airbome and liquid processing systems.
The amounts of radioactive materials released from TMINS as well as the associated doses During 1998, radiciodines were not detected to the public are summarized and reported in TMI-214 quid or gaseous emuents. For annually to the USNRC. The following TMl 1, ra6iniedines 1-131 and I-133 were sections discuss the radioactive constituents of detected in gaswus emuents, but not in liquid the 1998 TM1-1 and TMI-2 liquid and emuents. The other isotopes ofiodine were i airborne emuents. They also are summarized not released at detectable amounts either in Table 2. All amounts are reported in curies because of a very short half-life or a low (Ci) to three significant figures. production rate. For example,1-129 has a 17 million year half-life but its production in the I
, Page 19 1
I l l
l l
[\ 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT nuclear fission process is so low that it cannot is a radioactive isotope of hydrogen. It is be detected routinely in efiluents. produced in the reactor coolant as a result of l neutron interaction with 1) naturally-occurring Radioactive particulates were released as a deuterium (alse a hydrogen isotope) present in result of 1998 TMI-l operations. Released water, 2) boron used for reactivity control of were radiocesiums Cs-134 and Cs-137, the reactor and 3) lithium hydroxide used for I radiostrontium Sr-90 and activation products pH control.
cobalt-58 (Co-58), Co-60 and antimony-125 (Sb-125). All of these radionuclides were During 1998, the amcunts of H-3 released in released in TMI-l liquid emuents. Only TMI-l liquid and gaseous emuents were 319 Cs-137 were measured in TMI-l airborne Ci and 120 Ci respectively. For comparison, emuents. For TMI-2, small amounts of Sr-90 747 Ci and 125 Ci of H-3 were released in I and Cs-137 were released in !.iquid emuents; a 1997 TMI-l liquid and gaseous emuents.
small amount of Cs-137 was released in Figure 6 shows the amounts of H-3 released airborne emuents. in TMI-l liquid emuents for the period 1986-1998. For TMI-2, H-3 releases were The total amounts of radiciodines and 0.000412 Ci and 4.64 Ci for liquids and gases, radioactive particulates released from TMI-l respectively. Similar amounts of H-3 were and TMI-2 in 1998 liquid emuents were released in 1997 TMI-2 liquid and gaseous ;
0.000970 Ci and 0.0000358 Ci, respectively. emuents.
, For airborne emuents,0.0000285 Ci and l' O.00000134 Ci of radioiodine and radioactive To put these amounts of H-3 into perspective, particulates were released from TMI-l and the world inventory of natural cosmic ray TMI-2, respectively. produced H-3 is 70 million Ci, which corresponds to a production rate of 4 million The combined amounts of radiciodines and Ci/yr (Ref. 41). Tritium contributions to the radioactive particulates released in liquid environment from nuclear power production emuents from TMI-l for the period of 1986 are too small to have any significant effect on through 1998 are depicted in Figure 5. As the existing global environmental shown in Figure 5, the amounts released in concentrations.
1996 through 1998 were much lower than those released in previous years. The Transuranics: Transuranics are produced by reduction was due primarily to good fuel neutron capture in the fuel, and typically emit integrity, minimal component leakage and alpha and beta panicles as they decay.
improved efficiency of the liquid waste Important transuranic isotopes produced in processing systems. reactors are U-239, plutonium-238 (Pu-238),
Pu-239, Pu-240, Pu-241, americium-241 Tritium: Tritium was the predominant (Am-241), Pu-243, plus other isotopes of radionuclide released in 1998 TMI-l liquid americium and curium (Cm). They have and gaseous emuents. This radionuclide also half-lives ranging from hundreds of days to was released in TMI-2 liquid and gaseous millions ofyears. Transuranics are mostly emuents, but at much lower amounts. Tritium retained within the nuclear fuel. Because they
$gv)
Page 20
l l
l l
l 199L R.Wl0 LOGICAL ENVIRONMENTAL MONIMRING REPORT are so insoluble and non-volatile, they are not readily transported from inplant pathways to !
the environment. Gas and liquid processing systems remove greater than 90% of any transuranics outside the reactor coolant. ;
Since greater than 99% of all transuranics are l retained within the fuel and transuranic removal processes ere extremely efficient, releases in airborne and liquid effluents are not routinely detected.
During 1998, transuranics were not detected in TMI-l or TMI-2 effluents.
l l
l O
Page 21 O
I. . .
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE 2 Radionuclide Composition of TMINS Emuents for 1998
- l Liquid Effluents (Cl) Airborne Effluents (Cl)
Radionuclide
Co.60 5.27E+0 yr 8.78E-7 Kr-85 1.07E+1 y 4.05E-1 Kr-85m 4.48E+0 h Kr-87 7.63E+1 min Kr-88 2.84E+0 day Sr-89 5.05E+1 day Sr-90 2.86E+1 yr 3.35E-6 8.19E-7
- Nb-95 3.51E+1 day Ag-110m 2.50E+2 day Sb-125 2.77E+0 day 5.38E-6 1-131 8.04E+0 day 5.35E-6 Xc-131m 1.18E+1 day 8.83E-3 1-132 2.30E+0 h I-133 2.08E+1 h 2.30E-5 Xe-133 5.25E+0 day 9.98E-1 Xc-133m 2.19E+0 day 2.45E-3 Cs-134 2.06E+0 yr 3.57E-5 Xe-135 9.11E+0 h 1.91E-2 Xe-135m 1.54E+1 min 9.24E-4 Cs-137 3.02E+1 yr 9.1 IE-4 3.50E-5 9.40E-8 1.34E 6 Xe-138 1.41E+1 min 2.81E-6
- The results are expressed in exponential form (i.e.,1.22E-2 = 0.0122).
- Refer to List of Abbreviations, Symbols and Acronytns (p. v) for nomenclature of the radionuclides / elements.
- Kocher. " Radioactive Decay Tables." 1981.
- yr = year, h = hour, min = minute Page 22
a e
~)/
g a
P 8
. - . - 9
_ 9 1
e -
i v -
{
q.L. .
. y.
7 9
9 1
t - - - . - - - . -
c - - - . - - - . -
a
- - 6 i
o s -
9 yx, 9
9 1
d tn )
a e i C - -
- 5 9
Ru m - - -
a.emmn ,,02;,:g. '?wj?[4%a.np3fnC $s
- a 3@m%'e- w 9
( - - - . - - -
1 l s - - - . -
df t e - - - . -
f a -
n
- - . 4 v=$
aE .%; $$3%, ' y}wz.hp
.v.
9
.mM rG l
u - - .
s 9 i
c -
1 t
r sd a - - - . - - - - -
ei u P
.- 3
-l $ '- ,%&.l;wc~ g-n %gsiu 1_MM#ywygw')%$s e -
g$%,~i. t 9 n q y
9 i
v -
l 1
t - - - . - - - - -
i c - - .
a -
di r o - - - . - - - . -
oLa e a i
d Tby0, ygqs~.$n s
2 r 9 a 9 e 1 Y n)(/. io1Yy
(
i R
d n
i t
s e
dI b a i
v - - - . - -
v%ga. ;?
wp;
- vps 1
9 aMiC i
t - - - . - - 9f 9 s c - .
a - - - . - - 1 e a - - . -
n h R
f Tm i p d l a - - - . - - -
0 o - - - - - ;
9 on s
?ge .,yE yz:px i
s - - . - 9 i
o o r -
- - 1 i d g - - - - - - . -
a s s R d
n - - - . - - - . -
e e 3 a
s e
, $j ,m@c-3 9
8 st E s - - - . - - - . 9 a
a a - - - . - - 1 g - . -
e .
el l b
e u l o - - - . -
s 8
n, - - - . - -
a wp% ' @ma R 8 c 3- - - - . -
- i g-i ' 9 Rit H s
1 l r d e -
7 aa u . ~
8 l
c rQaj ._3- c3. f f._> yga&. 9 iPc E x -
1 r
E - - - . - - - .
o T - - - . - - - . 6 O
- . yp 8 t N -
. @- 9 1
i s -
H 0 0
1 0
9 0
8 0
7 0
6 0
5 0
4 0
3 Q
Q 0
1 0
g% 9.tE i
- g ogb@ pa $E)Qog
. !t $ GE n)v (N Ii 2
e r
u g
i F
,1 u
e g
a
" P
%)v(
- . 8 s
h ngF, ,
, o.wN
- 9 9
t - . . 1 n -
e -
7 u
,4
- , ; ,t'.:p'.'+,,
c '.f ';.;jll3%% * - - .
ge" sl 9
- {si
{ l- }3 n * ' , -
9 l - . -
1 f -
f -
E -
- u ,:yypg:s "' -
6 9
9 1
d i
u
- . a j; ,
1 5 b 9 3
[p gcQ,'Q~;sw gp'c< $lnw% ' _n-9 , 0,e;ng'.e q
. 9
- . 1 i - . . -
L -
~ jkgu2 nn?nm.M.ae42,j
- y 4
9 9
1 - . .
1 I -
3 M
)
i
- VMj
},,<-
3wwG e?g4z.;
. ;i: 9 9
C - . . -
1 Tr a (
m
) iYne it i
u r
W;7sy* .r .y c
~
fb.e;y i ..
Jy# . '.wmp=g j;;,
2 r 9 a 9
1 e
Y T - . . -
y s
/(v m b -
1 us - > .-
9 a jldlt,3gsd:n e
s : c%'t0"
- c 9 ie i - .
1 t r i
r u -
m . x. q, 0
- . ,.s; e%';; -
9 9
k: ,
- . 1 f - . -
o -
. . g (a yg36'$:p, 0 f
,2:e3p p%
9 8
9 s - . .
1 e
s a _
- : 8 8
. m W=. %, r4ew& x: 9 l
e -
1 e -
7 R
.y
, yy~ , 8
- . . 9 1
l a .
i c -
sg$-
.j i
g'p_
6 8
9 r -
1 t
o 0 0
0 0
Q 0
0 0
0 0
i s 0 1
8 6 4 2 I
P,/V H go5p 3 4@c2o f 3 _
e r
u g
i F
l 0 im wrotoazcat exviaosusurat uosironisa moar RADIOLOGICAL i 1
ENVIRONMENTAL MONITORING l
GPU Nuclear conducts a comprehensive i radiological environmental monitoring program l (REMP) at TMINS to measure levels of radiation and radioactive materials in the environment.
The information obtained from the REMP is then used to determine the effect of TMINS operations, l if any, on the environment and the public.
The USNRC has established regulatory guides O which contain acceptable monitoring practices.
The TMINS REMP was designed on the basis of I
these regulatory guides along with the guidance provided by the USNRC Radiological Assessment Branch Technical Position for an acceptable radiological environmental monitoring program (Ref. 42). The TMINS REMP meets or exceeds the monitoring requirements set forth by the USNRC.
O Page 25
1 l
1 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT The important objectives of the REMP are: may deposit on grass and when eaten by cows may be transferred into milk. The milk may E To assess dose impacts to the public from then be consumed by humans. This route of TMINS operations. exposure is referred to as the air-grass-cow-milk-human pathway.
m To verifyinplant controls for the containment of radioactive materials. Although radionuclides can reach humans by a l number of pathways, some are more important l E To determine buildup oflong-lived than others. The critical pathway for a given radionuclides in the environment and radionuclide is the one that produces the I changes in background radiation levels. greatest dose to a population, or to a specific l segment of the population. This segment of a To provide reassurance to the public that the population is called the critical group, and the program is capable of adequately may be defmed by age, diet, or other cultural assessing impacts and identifying factors. The dose may be delivered to the noteworthy changes in the radiological whole body or confmed to a specific organ. i status of the environment. The organ receiving the greatest fraction of the dose is called the critical organ. This E To fulfill the requirements of the TMI-l information was used to develop the TMINS and TMl-2 Technical Specifications. REMP.
Environmental Exposure Pathways to Sampline Humans from Airborne and Liould Emuents The TMINS REMP consists of two phases --
the preoperational and the operational. Data As previously discussed (Emuents), small gathered in the preoperational phase is used as amounts of radioactive materials are released a basis for evaluating radiation levels and to the environment as a result of operating a radioactivity in the vicinity of the plant after commercial nuclear power station. Once the plant becomes operational. The released, these materials move through the operational phase began in 1974 at the time environment in a variety of ways and may TM1-1 became operational.
eventually reach humans via breathing, drinking, eating and direct exposure. These The program consists of taking radiation routes of exposure are referred to as measurements and collecting samples from the environmental exposure pathways. Figure 18 environment, analyzing them for radioactivity illustrates the important exposure pathways. content, * : then interpreting the results.
With e.:S .. is on the critical exposure As can be seen from this figure, these Pathways to humans, samples from the exposure pathways are both numerous and aquatic, atmospheric, and terrestrial varied. While some pathways are relatively environments are collected. These samples simple, such as inhalation of airborne include, but are not limited to, air, water, radioactive materials, others may be complex. sediment, fish, milk, fruits, vegetables and For example, radioactive airborne particulates groundwater. Thermoluminescent dosimeters Page 26
3
(& 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REli]RT (TLDs) are placed in the environment to Analysis measure gamma radiation levels. l In addition to specifying the media to be The OfTsite Dose Calculation Manual, ODCM, collected and the number of sampling (Ref. 40) implements the TMI-l and TMI-2 locations, the ODCM also specifies the Technical Specifications and defines the frequency of sample collection and the types sample types to be collected and the analyses and frequency of analyses to be performed.
to be performed. As appropriate, changes to Also specified are analytical sensitivities the REMP are initiated by recommendations (detection limits) and reporting levels. Table from the scientific staff of the GPU Nuclear A-2 in Appendix A provides a synopsis of the TMINS Environmental Affairs Department. sample types, number of sampling locations, However, the minimum sampling and analysis collection frequencies, number of samples requirements specified in the ODCM are collected, types and frequencies of analyses, maintained. and number of samples analyzed. Table A-3 in Appendix A lists samples which were not Sampling locations were established by collected or analyzed per the requirements of considering topography, meteorology, the ODCM. Sample analyses which did not population distribution, hydrology, areas of meet the required analytical sensitivities are public interest and land use characteristics of presented in Appendix B. Changes in sample
[}
V the local area. The sampling locations are divided into two classes, indicator and control.
collection and analysis are described in Appendix C.
Indicator locations are those which are expected to show effects from TMINS Measurement oflow radionuclide operations, if any exist. These locations were concentrations in environmental media selected primarily on the basis of where the requires special analysis techniques. Analytical highest predicted environmental laboratories use state-of-the-art laboratory concentrations would occur. The indicator equipment designed to detect all three types of locations are typically downstream or within a radiation emitted (alpha, beta, and gamma).
few miles of TMINS. This equipment must meet the analytical sensitivities required by the ODCM. Examples Control stations are located generally of the specialized laboratory equipment used upstream or at distances greater than 10 miles are germanium detectors with multichannel from TMINS. The samples collected at these analyzers for determining specific gamma-sites are expected to be unaffected by TMINS emitting radionuclides, liquid scintillation
- a. Ss. Data from controllocations counters for detecting H-3 and low level prov:os - basis for evaluating indicator data proportional counters for detecting gross alpha relative to natural background radioactivity and beta radioactivity.
and fallout from prior nuclear weapon tests.
Figures 2,3 and 4 show the current sampling Calibrations of the counting equipment are locations around TMI. Table A-1 in Appendix performed by using standards traceable to the A describes the sampling locations by distance National Institute of Standards and and azimuth along with the type (s) of samples Technology (NIST). Computer hardware and j collected at each sampling location. software used in conjunction with the Page 27
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING RELY)RT counting equipment perform calculations and aspects of the REMP including sample l provide data management. Analysis methods collection, equipment calibration, laboratory are described in Appendix L analysis and data review. t l
Data Review The QA program is designed to identify possible deficiencies so that immediate ;
The analytical results are routinely reviewed corrective action can be taken. It also l by GPU Nuclear scientists to assure that provides a measure of confidence in the results !
sensitivities have been achieved and that the of the monitoring program in order to assure l
proper analyses have been performed. the regulatory agencies and the public that the l
Investigations are conducted when action results are valid. The QA program for the ,
levels or USNRC reporting levels are reached measurement of radioactivity in environmental l or when anomalous values are discovered. samples is implemented by:
The action levels were established by GPU Nuclear and are typically 10 percent of the a Auditing all REMP-related activities USNRC reporting levels specified in the including analytical laboratories.
ODCM. These levels are purposely set low so that corrective action can be initiated before a u Requiring analytical laboratories to '
reporting levelis reached. This review process participate in a cross check program (s).
is discussed in more detailin Appendix D. ;
E Requiring analytical laboratories to split l Table 3 provides a summary of radionuclide samples for separate analysis (recounts !
concentrations detected in the primaly are performed when samples cannot be environmental samples. Statistical methods split) used to derive this table along with other statistical conclusions are detailed in Appendix 5 Splitting samples, having the samples H. Quality control (QC) sample results were analyzed by independent laboratories, and used mainly to verify the primary sample result then comparing the results for agreement.
or the first result in the case of a duplicate -
analysis. Therefore, the QC results were a Reviewing QC results of the analytical l excluded from Table 3 and the main text of laboratories including spike and blank this report to avoid biasing the results. sample results and duplicate analysis results.
Ouality Assurance Program The QA program and the results of the A quality assurance (QA) program is cross-check programs are outlined in conducted in accordance with guidelines Appendix E and F, respectively.
provided in Regulatory Guide 4.15, " Quality Assurance for Radiological Monitoring The TLD readers are calibrated monthly Programs" (Ref. 43) and as required by the against standard TLDs to within five percent Technical Specifications. It is J >cumented by of the standard TLD values. Also, each group GPU Nuclear written policies, procedures, and ofTLDs processed by a reader contains records. These documents encompass all control TLDs that are used to correct for Page 28
O O 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REECRT minor variations in the reader. The accuracy were published in the Health Physics Journal and variability of the results for the control (Ref. 46).
TLDs are examined for each group of TLDs to assure the reader is functioning properly. In In addition to the GPU Nuclear TMINS addition, each element (TLD) has an individual REMP, the Pennsylvania State Bureau of correction factor based on its response to a Radiation Protection (PaBRP) also maintains a known exposure. surveillance program in the TMI area. This program provides an independent assessment Other cross checks, calibrations, and of radioactive releases and the radiological certifications are in-place to assure the impact on the surrounding environment. The accuracy of the TLD program: results from this program has compared favorably with those from the GPU Nuclear a Semiannually, randomly selected TLDs program.
are sent to an independent laboratory where they are irradiated to set doses not The GPU Nuclear TMINS Environmental known to GPU Nuclear. TLDs which Affairs Department also collects and analyzes meet the criteria specified by the National samples of the TMINS liquid discharge as a Voluntary Laboratory Accreditation QC check for the inplant efiluent monitoring Program (NVLAP) are used for this test. program. Results obtained by the REMP were The GPU Nuclear dosimetry laboratory consistent with those reported for the inplant processes the TLDs and the results are effluent monitoring program.
compared against established limits.
E Every two years, each TLD is checked to ensure an appropriate correction factor is assigned to each element of the TLD.
E Every two years, GPU Nuclear's dosimetry program is examined and NVLAP recertified by the NIST.
E Ten environmental TLD stations have vendor-supplied quality control badges which are processed by the vendor. The results are compared against GPU Nuclear TLD results.
The environmental dosimeters were tested and t
qualified to the American National Standard Institutes (ANSI) publication N545-1975 and .
the USNRC Regulatory Guide 4.13 (Refs. 44 I and 45). The results for some of these tests
! Page 29
I Figure 4 h
~~~ ~~y ~~. ttzs'
't - ,
- .32625*' .
asw: \
ISL D' R
.p
&' (, C 1/ '.
'[d .
N ,,
p ti 7 75' 28125'- ,a g ,,, T EE ,
E
- 3 ISLAND,I,,,
g N M- ~
N '" SHELLEY
-lSLAND ' ,y g
2 a, N
... g {t
. ..s .
p12s-2sewl ' -
%~ <e . % F.
.. es < n:
- M -
1 MIL E :-
o, t .
K .
? . h3, e m2s-(a, q 7 q
m-f -
[
Locations of REMP Stations Within 1 Mile of TMINS Page 30
Figure 5 O o
{
34875* g 1125'
- 326.25*
-#75 '
'W .g B
-: g4-
~.\ 33 75' SU OE g, C
. num - / _.e.
C. w$0UEHet1A #
a L 303.75 7 .
. isa'- __ .
56.25*
Ne . 5 MIDD ETOWN:..
\ in , ** S H :
s - - -'N.
p "k k s.,
}; e , ..
ONDONDER sTW D
~
a, e ~ s 3,5 3 st2s i e" t i. ..X 78 75' L
h ,, e,- ,,
O .
e- ee<eeeeee s.
" f' . ...
e e
g :q . e nn e"
258.75' \
6 - y" . . .. 012 5*
MILES \3 g ,',
EF OUTH~ !
M K - ; ,e.
. ,.s F
., h, \
,? !
23e 25-NEWB'ERRY x ' "
~
i2375-l j
'.TWP'~ \ . '
l)\
~
L -
G' N:: . \
,,, ,s. N," $ - e2s.
- g. .gu- -
g.
- x. -
19125' ' 168.76*
O v
Locations of REMP Stations !
1 to 5 Miles from TMINS Page 31 l
l p Figure 6
)
U j O
348.75* A R
1125*
]
B ,
326.25 - -
33.75*
[ h hC b LEBANON 303.75
[ 3. 5625' ERSH PALMYRA s
/- **
,,e tPp . , , , RT 322 j
it p - N U" NN -
HILL' I MECH CSBURG- , , .
'a gs-, /3 .,
L 1
5[ , , .
E
-@_ , , , G S. ; TMl .
EUZABETFTOWN ~
tuO ILLS 8U '8 '#( .MTJOY 258 75 jva / _ .
g ; Nemmg., 1 M
\ .
- .. p ,ETT .
RT 30 .
p
--/
.,,,_ ,, e s .- e GETTY RG, "yk UMBIA
/
- [ **
IG SVILLE .
- 12. . . ,,- -S 236.25*
- To- N i2375*
v
.(YORK ,'.
L .. m av.
)J 213 75*
h 14625' ,
K ~
- y m25* J 5875*
hl J
Locations of REMP Stations Greater Than 5 Miles From TMINS Page 32
J f le 3 obm ra et 3
b r^ e sa po^ _
0 0 0 0 0 0 0 0 0 0 0 0 g
a a e -
P NRR s ) ) ) )
n 3 2 2 2 o 0- 0 i
t ) 1) E I) E
- 4 0 -
a4 c( 5S 58 )E2 ) 7 E
o) 4' 4 r t 1 4 8 4 LF(
)
4 -
(
5 -
(
4' - 3' 8-l e e 30 4
2 3
2 (2 (2 rn n 0 - 0 - 0 0 -0 2 -0 0
r-o ea a n E E 2 E- E E- 0E E E CMR D l. 8 6. 43 D D 94 D D D 4. 2 D D
( N 2( 1 ( N N 5( N N N 7( 6 N N
) ) )
3 0-2 0-2 1) s ) ) 0- 0-e ) 1 E 5S 1 E 58 E E T l p 4
)
( /
44
/
1 2
)4 4
9
)
4
)
2 0 )
2 -
R m F
(
4(
- 5 - 4 -
/
t(
/2 2 - l' O a )
e 3 4 2 (3 (2 (2 (
0 -0 2
0 -0 2
P S n n 04 0-1 0 -0 3
0-E l a e n a E E 2 E- 3E E- 4E E E E E R a 9
)
- l. 8 64 E. 5 5 5
4 t
n (
n MR ( - 2( l ( - - 6( - -
I.
2 1 (
9
- 2 -
G e a e
N I m M R n o'
r "n t
e s
O i o h n)
I I si ig o6 W W Et a e
nt H t N N W N Et a ic e '-
imw imwe Nr o t NG Nh r r r e
g e g
O 8 S ht e iria- e toe dh a r
o r r e a iwa ip t m D, de t dh M 9 r 9 a nNec we
- 5. v 3
'i r
i 5. vi 3
k mir
- 7. A ime 8 N 'a e
e c F i s a c
i e c e s i L 1 el in t
o o n -,F a 1, Fa 3, n t
S ~ D dFnn D A
T iu nc aiaD t 5 1
ts 1
5 -
ts 1
- g i 0.
4I N f. o w m
o I, r o wo 3 ot a isd ct ie e IM bt d o let b t l LSDa n l
4b i d toe N sN n - QW QW - - Ql - - BT InBB - InB3 E Eod Lin 1
M t Baarl s N s O At n I n o )3
)
)2
) )
2
)
1
)
3 R
I Tee ci l i
t a
8 04 2E 6 -0 1
4E
)
2E 0- 0-E 0- -
E V n oM c) o4(
/
1 5 6/9 3/ 4 2
)
)O ) 4 N Ce e L) 74 1 -
1 2 4 -
29 3 -
3/ 4 2 4'
4/2 E e r rF o() 3
(
4 2(3 (
2 1
( (
2
- 2
(
3 0 -0 2 0 -0 e 2 L d l t
a 8
)
04 0 1
0 -0 3 0 -0 A il r an E E E- CE E- 4E E E E E
(
l I de en ae D 8 E C c' 96 5 D D 34 D D 4 D l.
nMR N l. 29 22 I
G O i ut n
on d f or t I ( 1 ( 1 (4 N N 6( N N 2 1 ( N 2(
L a i
m O R i L
n o
I i) 5 D f o r e
t 3 c( 7 1 1 5
A y r eD 0 1 0 1 5 5 6 1 2 1 Imf eL t 0 0 0 0 0 0 0 0 0 2 0 0 R r oDL 0 0 0 0 0 0 0 0 0 0 0 0 8 a 9
9 m
m
)
1 u
S f o
r s 2
(
d n
e -
be yo se n l
a mif mr 7
6 5 9 7 6 0 0 6 t
oame 4 2 4 1 1 3 8 8 8 e TNAP l b
a _
t f
c e
o _
p d _
s a S n e h a e n p t e
a m
4 7 6 t -
2 a 1 9 0 3 3 i
n 3 lA- B- 8- 9- m 7- 1 1 2- 9 8-0 9-n r r a e - - 3- s 1
- r r s s a r r e A 1 G G S S G B C C R 1 1 S S t -
o -
y t n
a o m ) - f o
t t
t n -
a e e P m )t e r m e )
W e S
^)
)
odf er m3 ale ou do/i m *r 3 a w. : .
ipt s de mia t P 'm i g
- e ne rC rC h i t o .
MS(M aU i i isC A (p A (p F (p N -
f el ob7 r a(
uee
)
bet ro ts mpsu l
0 0 0 0 0 0 0 0 0 0 0 0 4
3 P
e g
a NRR
) ) )
s 0 0 1 n 0
+ 0 0 1) o + + 0-i t ) E E E E a4 c( )3 )7 )8 )9
) 4 3 2,2 2
/ I 2 1 l aF (
4' (0
- 2 -
(0 2 - l' -
t )
0 !(0 1(2 n ae e 0+ 0
+
0 0+ 0 0+ +0 0 -0 E+E e
ms m E E E 7E E O E o ea O 29 D D D D D D D 2 D
CMR ( 3( N N N h N N N 9.
1 (
1 4 1 (
9 N 3
I (8
)
0 0 1)
+
s E 4 e ) )3 ) ) E T l p )
4
( 2
/3 2
/ 2, )2 2
/ 2 R m F
(
2
( - 2
(
2
( 2 -
O a ) 0 0 0 ! (1 P S am e 04
+
0
+
0
+
1 -0 0
sm E E E l a ) e a O E E E 'E R t n
9(
n MR (
1 3(
3 4
2 8
1 I 2 2(
G e a e
N I m M n5 R o2(
t s
e O r n h n)
T isi o ig o6 I n i I nt H t ic '- e M e v Wf Sh N Et a ht sie re g
r T a O 8 S i s _
f o
a a
hc 5 fo Sl l
iSr o M 9 r 9 a nNe c tn o
s imero ik mro me r
- 3. ho i
rD L
A 1 el nc i
weD6 onn t o aia1 C.pa tv e o
5 0.
h S
- 5. Y 1 e v 0. S T i u ct t sd gd o 2 s t
om 3 t s 1 -
3 e N sN otaie LSDm L eb BPA r
- JW 1
2 JAD b a i
- KW e
n - - - - - -
E Eod Lin M t N Brlaas s )
) )
O At n I n o
0 0 0 0
1 0
)
1 R
I Te cie l i
t a E
+
)E 4
E
+ 0-E V n oM c) o4
)2 4
/3 6 4
)
6 8 ) 2 N LrF)( 4 - / 2 6
7 6
1
- 6/2 E Ce e o() (0 ( - (
0 6
(
e r e 0 0 0+
0I 1 0 1 10 L
t a + 04 0+ 4-A d h i ic ma m E E 8 E+E
+
E E E E c T D D D D D D D l 4 C d e a 02 8. 85 59 I. D 8. 1 u nMR 3( N N N N N N N N I
G n on or I ( 1 ( 1 ( 1 (
O i d f t L a i
n O R in n I L i)o D f o r e
t 3 c( 0 6 A y m teD 5 3
1 3
1 2 3 6 2
3 1
5 1 2 2 5
1 8
1 R eL I.
8 r
a l r oDL Af 0 0 0 0 0 0 0 0 0 0 0 0 9
9 m
1 m )
u f 2
f S o de r s n be yo s re e
l aalaf t s .
oa n er 8 8 le TNAP b t
a f
c c
. o e e d p p s S n e a S. e s
y 4 4 7 4 7 t m 5-8 9 0 5 3 3 - 3 3 a l
a m 0 5
- 5 6 6- 1 1
- 7- 0 1 1 n a 4- n o e o n s
s --
e 4- -
s s
- s A G K M C F C Z C C C B K C C t e
o y n t
a o ht w ) tn e f o
t n n P
a e ) d) e ee s e y s te S r
ede f re w S r icd.
ial yt sou g. t g e
de mmiane a h'i ui q C' t
o Ms(M aU isC F (p A (p N
f e l ) 5 ob7 3 reta (s b rtl e o g mpsu 0 0 0 0 0 0 0 0 0 0 0 0 0 a ue e P NRR _
) ) ) )
s 0 0 0 2 n 0 0 0+ 0 o + + +
i t ) E E )E )E a4 c 2
) 0 )S 2/ 1 28 1
23 1
/2 I
4 F)( 2( - 2( -
/ 3 7 -
/ 1 2
( -
l
( ) 0 0 (0 2 e 0 0 0 0 0 0 0+ 0 o 2 r n n 4 0+ 0 4+
E+E
+ +
t n an e e a E E E+E7 E E CMR( 8.
1 1 7 3.
1 1 6. 1 I.
0 D D D D D D D D D
( 1 ( 2( I 1( N N N N N N N N N
) ) )
0 0 2 0
0 0 s + ) + +
E 2E )E e ) ) ) 6 1 8 29 T l p 4
( 2 2 /
1 5 R m
)
F
(
/
2
(
/ 1 2 -
(
0 l 5 l
(
/
3 -
(1 0 _
a ) 0 0 0 0 0 +0
)Y 2 e 0+ 0 + 0+ + 0 E S n ane +
E R
l t
a n
)
9
(
n e a MR (
E 2
2 E E 51 1 (
5 E+E9
- 9. l 2(
E E 42 2(
9 G e a e
N I m M R n) o *( t s
e D i r n h n) 1 1
vio le io6i I M
n e
r e E nt l t c no v S E ta S N Eat I T a r O 8 S he ei t r t is Sn 'o. SI I
imW imtea M 9 r iwam D, ri r
- er ik mro 6.lel 3i
- 8. W 4
9 a nNe cc s 5. o 1 r- y 0 h o 5. Y 1 v L 1 el in n e e ,t s y , e t
A nc aiaD t o ,S 1 1, v 2hl gp 3- =
Im T 3 iu t t 2- ts om 5i p 5
= Au N sN n I mtas?
SDa i n i e JW 2- b a JAD 1 r GWSu 1
Gt t
E Eod Lin M t aa N Brl s ) )
O At sn I u o
)
0 0
)
0 0
0 0
2 0
R 7
Tee ci l l
e m )E
+
)E
+ ) +
4E )E
+
n ) 28 4 9 F
N oM m4 (
6 0
&3 6/ 1 6 / 5 1 2
' 5 E Ce e i) rF o()
( -
01 6( -
01 2
(
0 0 6(i -
e r t a e 00 00 0 0 +
2 0 0 +
aL4 d h c na e 4 E E E+E3 E+E6 E+E i:T l
i d e n a 0 9 D D D D D D D D D C ut nMR 09 2( 39 1 (
- 7. I 2( 28 2( N N N N N N N N N I
G nn o or I (
O i d f t L a i
m O
I R i L
n o
i)
D f o r e
t 3 cf 0 A y w teD 2 2 0 R r of eL LoDL 0 0 4 0
2 i 5
1 5
1 0
3 5
1 0
3 5
1 0
3 5
1 8 a -
9 m 9 s 1 n e
)
2 t
f (
S o de r s e n u l be ysr e ta ml f ae 6 6 4 6 .
oune TNAP 3 3 8 3 l e
b t
a f
c o
e d p
s S n e
s 6 2 a a e y
t e 4 4 t 2 3 m 8 9 0 5 5 5 3 a l
a 2- 2- B- 3-I 3 m 5
- 5
- 5 4 6 9 1 n a h r a n o e o n- % 9- s
- s A R T G I I
1 1
G M C F C I h Z r
C t e
o = _
y t n _
a t o _
o w )
n e r ht t e f a ne i m t a e P m d) e y W e r s e S r S
% ode f r d, *
) :
ialyt so u -
s 6 L e de nia 6G t
[ s ne aU
- , G' r o _
MS(M A (p D (p N =
[
f el ob7 raf et s h r:
n od
) 6 3
e g
O mps i 0 0 0 0 0 0 0 0 0 0 0 0 a a e e P NRR m
u l
e tn4 e(
)
l)
)
l m)
I. (F
/
1
(
/
1
(
)
lo e 0 0
0 r an +
0
+
n t
sn e e a D D D E E 8 D D D 5 D D D D CMR ( N N N 1 N N N 2 N N N N s
e ) )
T l p 4
(
)
I)
/
1
/
R m F
(
1
(
t
(
O a )
e 0 0
0 P S a e + 0+
E l a )
sn ea E E R t n
9
(
n MR ( - - -
9 I - - -
7 2 - - - -
G e a e
N I m M R n) t s
D o r "n h
e n.
1 I
i vio ig oO i(
nt H tc n N Eat h eo kmip rt e
O i
E E 8 S s is M 9 r w sa D,ir imor mor 9 a nNe c cs 4. s t
i 4. s t
i L 1 el on e i 0, V r 0, i
Vs A nc iat ea nD t
e T iu e t wombn d 2I t l Me n 2I t l Men 3sN N
E M
N O
Ee t
od Lieas Bri s At n I LsDa s
n o
- - - ETC - - - ETC - - - -
O R
I Tee ci l i
t a
V n oM c) o4 l) I)
N LrF)(
/ /
Ce e l( t(
E er t e() e 0 0
0 0
L d h a as + +
ees as r
A i E E C
l cT mMR(
D D D N N N 9 D D D 7 D D D D s7u no N N N 2 N N N N 1
I I G r O i d f t L a d a
O I R J I
n o) i D f o r e
t 3 c(
A y w teD 6 6 8 6 6 8 5
2 R ImfoDL eL r 0 4 0 0 0 4 0 0 0 0 8 5 8 a l 6 I 0 0 0 0 0 0 0 0 0 9 m 9
1 m )
u 2
(
f S o d e
r s n e e srn l b ye anl fa r .
t m oa ne TNAP 2 2 2 l e
b t
a f
c e
p c
e p
d o -
s S S n e
e 0 a =
s 7 0 4 7 a 4 7 t y 3 4 4 m 1 3 3 - 3 3 9 a l
a 1 1 1
m 0 3 1 1 a 0 1 3 1 1 8
- - 4 - 4 - s n s a 4 a - 1 s s a - 1 s s r e _
A C B 1 G K 1 C C G K 1 C C S t o
n y
a t
o _
ht w ) r f o
ds e t
a e a ) e P s ) ) e r u Wg te te f
a st S ele, we edf aie ou s m pt MS(M o d a e xu e aU er lnR n) u nC D (p t
F s 8 m'
rW w
s .g mP aC r
G (p w Lb dt ga a eP o
r egC B V (p N t
e o O-
f e olb 7 3
raw et b r e g
mo p 0 0 0 0 ue 0 0 0 0 0 0 0 P
a NRR s ) )
3 n 0 0
o 0
+ ) +
ia4) t
)E 6E c() I) I) 4 6 16 l oF (
/
1
(
/
1
( 3
(
/ 1 6I 2( -
l ) 3 o e 3 0 01 3 trn e n an 4 0
+
00 -
+E 04
+E E E e ea 7 0 D D D D D E 0 E 53 D D CMR( 4 2 N N N N N l. 8 1 ( 1 I( N N 0
) )
3 4
0 s + )
e ) ) E 5E T l p 4
(
)
1 l
/ 4)7. G6 51 R m F)
(
/
1(
1
( 4
(
/ 1
- 2 -
]Y a )
e 3 0 01 (3 3
0 0 l S n e 0- + 00 - 0+
E l an ea E E E+E2 E+E4 R a )
9 4 4 t
n (
n MR ( 7 2 - - - - - 27 I (
- 5. I I ( - -
G e s e
N m M -
I R n o' t s
0 r "no hg e
n)
T i si o6: W E nt i i H t N
N Et a he n er c
E E E
W O 8 S t i is is S
M 9 r wa .
mor mor immr i
m rm inNeno D,6 t
9 a t L 1 cI ino c 4. si i
- 4. si i
4 a 7 a A nc t aia1 n 0, V r 0, V r e 1,F y 6F
,y T t 2t te 2t t 1 iu l Men n r 1i r 3 cta ot isdn l Me i
- N sN n lSDa ETC ETC - - - -
2 a
- GD 7 a PD - -
E Eod Lin M t N Brlaas s )
O At n I n o
)
0 )3 30 R
I Tee ci l i
t a
)
6 4 0 +
1 E V nM o
c) o4 I) l) / E7 1
2 3' 6 N Ce e L )( /
1(
/
1
(
1
( -
1 01 1(3 E er t rF o() e 3 0 01 3 0 0 00 0 +
L d h a nm 0- + + -
E+E c am A i E E E E c T i ea l 7 C d n
4 4 D D D D D 53 D D I um n
IMR ( 7 2 N N N N N I.
1 (
6 1 1( N N G o or O i d f t _
L a i
m O
I R i L
s n
o i)
D f o r e
t 3 c(
A y w teD 1 0 4 6
0 6
0 2
0 R r efoDL eL 0 0 0 0 0 1 5 2 0
8 5
1 8
1 8 a l 9 m 9
1 m )
u f 2
(
S o s e
r s s m ee s r b yo _
lasl tounes a fr 9
2 0 0 9
2 -
2 2 1 2 2 1 e _
TNAP l b -
t a _
'l _
c c
o e e p p d s S S n e
s 4 7 a e y 4 7 t l 0 0 1 3 3 1 9 0 m 3 3 a a 9 4 3 1 1
3 8- 9- m 0 1 1 n r
- 1 s s a 4- s s
- s 1
r r e A S G K 1 C C 1 S S G K C C t o
y t n
a o fo w
ht ne a e e F n f )
) e r n a . te S
ede f re w w
o al o u i pt s de mia s ne l
degi a
o eC
'g, ki iC l
c)
(L /
t e
o MS(M eU r B V (p M (p N
f e oi) rsfh7 et s b r tl no mps u 0 0 0 0 0 0 0 0 0 0 0 0 0 0 8
3 e
g a
O_.
ae e P _
) )
s 2 0 n 0 0 i
o + ) +
)E 4 t
a4 r(
)
)
67 3 I 1E2 5
I mF( )
/
9
( - 1 1
( -
4 l
o e 2 0 1 0+ 0-t ram ns m * @E e ea E E E CMR (
D h
Dh 2.
1 9 (
2 2. 39 1 (
D D D D D D D D o D N N N N N N N N N N
)
3 )
0 0
+ 0 s ) +
e ) 2E )E 1 8 8 4
T l p (
)
/
6 7 7 42 R
) m F
(
( -
8
( -
Y a )
e 3 0+ 0 01 00 I S ne + + -
E l an e a E E E E R a )
9 49 1
66 l.
t n (
n MR ( - - 2( 1 ( - - - - - - - - _ -
G e a e
N m M I
R n t
s D
1 o
r "'n i o hg e
n) si e6 I
N nt Et a n
I I
l c'
t e
I M ,
O 8 S h e r-t mi S
iT inkee mr n i _
M 9 r mere 9 a sNec . 5. 5.C wo en n 0 h L
A T
1 el i
nc u i
waDb t o aia ctasd t 2- s
,S t 2, ralaet 2t-d ad _
3 sN ot i n I e 3 wi N n l SDa - - JW ASM - - - - - - - - - -
E Eod Lin M
O_
t N Brl aa s )
O Atn s I n o
3 0
R I
Tee ci l i
t a )E
+
V n c)4 28 oM N o( 1
/7 6 -
E Ce l rF) (
e e r t o()
a e 3 0+
11 L d h ica s n
+
A i n E E )
C l
c T d ea D D 4 l. 1 D D D D D D D D D D I un I nMR ( N N 2( 9 1
( N N N N N N N N N N n
G O ow i e L df e d
a u O
I R J n I
io)
D f o r e
t 3 c( 0 A y w te D.
0 5 0 0
0 R r of e1 lod 1 6 1 2 I 5
1 5
1 3 5
1 0
3 5
1 0
3 5
1 8
1 0
6 8 a 9 m 9
1 m )
u f 2
(
S o d e
r s n l
e se rs b yo tanl n fe r oume 8 4 8 .
4 8 4 e TNAP l b
t a
f c
o _
e d p _
s S n _
r e 0 0 a e .
v 4 4 m 4 8 4 2 0 t _
l 1 5 9 0 5 5 5 3 3 4 a _
m= 5- 9 1
a -
1 3- 3 - 5- 6 6- 9 1 1 1 .
n a a 1 a i 0 e o n %h r-s a s _
A B L 1 1 1 GM 0 F C Z Z C C B t e .
o y ) t n
a 0 o ht w )
t 1( f o
a n e
r e e P s )
t a e r s e w o W S ede f r O
c) e) ialyt e s u ( t cl a
e dmia ne ki fi t e m MS(M aU ic l
M (p uC r
o S (p N
j ,Ili 1l1lllt
- f e rh ot 9 olb7 ) o 3 reta (s b r t
- b
- e sspso u l 0
g 0 a u e e NRR 74A. P gm L.. s
)
i.c-. hseu s 0 Mrs .
n o
)0 1
6+ i M .
i 2E tns C e t ) / e d ly D l b
a4 c 1 4 a a o')( 67 on Ra e O
e t
s -
LI ( 2 - i _
(0 e r ht ht l ) h ;
o e 0 0 tr nn n an o ea D 0+
E+E 4
- t. ts ol u
- s b
d y
e i
de n
CMR( N 93 4( wl r e i r
u d
l u
.a q c
)
ym e r i n
g e t Ci r s o 0
)
Qo o n ht e 0 r
+ o n e s
e )
)
4E 73 l(A r
t n . ht a w _
T 4 ,
ww l
p ( 48 o r e r
R
)
F 2 - C e o m ( (
0 y f e
O a )
e 0 0 t ia a. l o r e
P 0 + l S n r e h E a e n E+E u r Q - a l t, a ) a 3. 9 d R t 9
( MR - 7( 6 e w t
a n G n n ( ht r ht a e a m s m N m M e mo ofr D a r
I n fr L g R t s L o o*n r
b s
e n) st h lu us s r
p M iovi l8 o6 s e e -. g I nt l i(
t n E rR a- . m -
N Et a c dC ip .
I e o S e PaD ht e ri S da d ). m O 8 S i mis t lu2 a M 9 r w a D, t r imo c 1 MM s
t 9 a nNew 4. R in0 E> n e
L 1 el i o n cn e 7,wa we ec = Rs u A nc aiaD t o 1 ivni n2 - S ltus l f
f T 3 iu ctasd t 8 at ga r s eE Ne s g
e N sN otSDa in o2 I r t E Eod n l - HSS d 1 Mn md an rks M N
Lin t
Ba rla s
)
9)
I t
) i.
C(
. e, . To ed h es t, a l
i b
u r
o lp i
h e
n O At b n n o
3 0 R0 + Dmr sb e
s e t . t s r R Tee i Mo s. a r c
a ) . e o I ci l t a 9'I E (f
nl a e c a e r Crf u V n c) 3 3 s e D gi N oM o4 L )(
88 oi t.e
- i. t n lymyM a o 2
I Mie f E Ce e rF e() e 1( 0 0 ;oon ns a n i T e t ht caa n l c L er t a 0 +
0 p e i,d r n d nfiasa A id h lenam m E+E _xe r o ht a a n a ard c T D h t sn l
d ea l. t iges C aMR N 4
3 e in d a I
s s u I
G um n
l ( 4(
l e
b d e e oMisM
. I s
e o e O
oo ir *
=
t n .y sT lr twr o ne _
d f edl e o a )w hse L
O R a
Mn b ez ah d n t.
t l h1 -
%.h lyamn a t -
o e I luaa ; .
u eI I
i) -, qoK r D f o r e
t 3 c
eW r
a :
ont a -
ad ;- e A y w t I d . s
. t s e r e o R r of eL 5 e .I lpf yoL r gi e -
winta 1 t a LoDL i s te a e.mde a st 8
. sn uS(
l 9 > s cl m i b a s w 9
1 m ) ts hc l p ca fs)u d M i eodtn u f 2
( lue s r s
dl ui o e sy s imCtrar J.nip
. DsDe o S o de ) e e r d a : .LiOe t
. ge r s 5 u n oTa e c e m (
mn . (h h n ;b b yo r e s l .
0 a c e .
t n
l 0 r inhwe.tsnnn e t t
"s aml t
oun er af 1 2
gt orar r
t o nh ei i e a wA e
TNAP pr g ne t mpeodlp l s v oel b
)
e s o r ei t
gC re mci iaf a emnd ai u a aP sdo isDoopt e s miq t
b e l f
( gh yinueCs)Msf r sl s nsS t o
r r o eyD>
s s
- d. der sal gI t eN s
d a t n s
e s 0 a min no r lnMs a
ar u mulvieT h s e ch a
- a. i M 1 t
e y 4 m e sr e le(h n o a l
- pM fo(
a n
1 a
m a
. r erDf eom4Mt r
i e t th frf r
o r
v s e
A L G ..
- s. rbLoo m L o k. . ra G.
ci e t ws e h p t
,e n uta o n
i
~
J. al d/uMt y
a
)
0 l e
nn Ce!
a r
. Dos t ie n t
t o
w ) 1( ) b a
l at aDh a - t t Co a r s Nc oleiy s f o
%- _hn ht sci.ntoOs oe *.Al t
a n r e t t
t R= l pl e
P e ta o i ge e i h) F l NSDe rra n a e
HhteinT(nAUNnSA i
m A r r W m o S od f re e e Pd
- ias pt o de saiane s u fi c ).
al t c/
ts :
s e t e
rC eR r
))
o to) ))))))))0I _
MS(M aU Su (p i
N D (m N1( 2345
((((((((( 67891 I(
m8 RADIOLOGICAL ENVIRONMENTAL MONIMRING REPORT DIRECT RADIATION MONITORING Radiation is a normal component of the environment resulting primarily from natural sources, such as cosmic radiation and naturally-occurring radionuclides, and to a lesser extent from manmade sources, such as fallout from prior nuclear weapon tests. The cessation of atmospheric nuclear weapon tests and the decay of fallout products have resulted in a gradual decrease in environmental radiation levels. Direct radiation monitoring measures ionizing radiation primarily from cosmic and terrestrial sources.
Gamma radiation exposure rates near TMINS were measured using thermoluminescent dosimeters (TLDs) and a real-time gamma radiation ,
monitoring system. TLD stations were arranged m roughly concentric rings around TMINS, generally with one station in each of the 16 compass sectors, at the site boundary and I,2,5,8 and 10 miles from the site. Those TLD stations more than 10 miles from the site were control (or background) stations while those less than 10 miles from the site were indicator stations. Indicator stations were located to detect any potential effect of TMINS operations on environmental radiation levels. The TLD network was supplemented by 16 real-time gamma radiation monitors located on and around Page 40 l l
l
1
{
l
)
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REEDRT the site. The TLDs were processed each TLD badge which has 4 independent detectors, calendar quarter, while the real-time gamma for a total of 12 detectors at each station. The radiation monitors provided continuous 15 quality control badges are used as an minute averages throughout the year. independent check on the accuracy of the GPU q Nuclear TLD results. i All gamma radiation exposure rates recorded )
during 1998 were within normal ranges and Of the 4 elements in GPU Nuclear's TLDs,3 l were consistent with previous results. are composed of calcium sulfate and 1 is l composed oflithium borate. The calcium l No relationship between TMINS operations sulfate elements are shielded with a thin layer and offsite exposure rates was detected at any oflead making the response to different station. The 1998 quarterly exposure rates for energies of gamma radiation more linear. The the individual TLD stations and a map showing lead also shields the elements from beta onsite TLD station locations are contained in radiation, making them sensitive to gamma Appendix M. Offsite TLD stations are radiation only. The lithium borate element is depicted on Figures 4, 5 and 6. shielded differently to permit the detection of beta radiation as well as gamma. The SamDle Collection and Analysis combination of different phosphor materials, shielding, and multiple phosphors per badge A thermoluminescent dosimeter (TLD) is permit quantification of both gamma and beta composed of a crystal (phosphor) which radiation. Only the calcium sulfate phosphors absorbs and stores energy in traps when are used for environmental monitoring, exposed to ionizing radiation. These traps are however, the lithium borate elements can be so stable that they do not decay appreciably used to evaluate beta exposures or as a backup over time. When heated, the crystal emits light to the calcium sulfate elements should more proportional to the amount of radiation data be required. '
received, and the light is measured to determine l
the integrated exposure. This process is Data from the TLDs were evaluated by j referred to as thermoluminescence. The reading obtaining the average of the usable element i process 'rezeros' (anneals) the TLD and results at each station, and comparing the result I prepares it for reuse. The TLDs in use for to historical averages and ranges for the period j environmental monitoring at TMINS are of TMINS shutdown between the first quarter capable of accurately measuring exposures of 1980 and the third quarter of 1985. The between 1 mR (well below normal averages and overall trends of the indicator and l environmental exposures for the quarterly control stations were also compared with each !
monitoring periods) and 200 R. other and with averages and trends obtained for ;
Each TLD station consists of 2 TLD badges, each of which has 4 phosphors or elements. . All TLD exposure rate data presented in this Since each TLD responds to radiation report were normalized to a standard month independently, this provides 8 independent (std month) to adjust for variable field exposure detectors at each station. In addition,10 periods. A std month is 30.4 days. Several stations have a vendor-supplied quality control badges were used to quantify transit exposure Page 41
b)
Q 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT during storage and handling of TLDs. Transit Quarterly exposure rates at control stations ;
exposures were subtracted from gross field ranged from 3.4 to 7.4 mR/std month.
exposures to produce net field exposures.
The 1998 exposure data were consistent with The real-time gamma radiation monitors previous results, as average exposures at (Reuter-Stokes) are positioned around TMINS, control stations typically have been slightly one in each of the 16 compass sectors. They higher than average exposures at offsite are located 0.1 to 3.5 miles from TMINS. The indicator stations. This is a result of variation detectors are sensitive to gamma radiation only, in the natural radioactive characteristics of rock and can detect exposure rates from I and soil near the stations. The historical microroentgen per hour (pR/h) to 100 mR/h. average exposure rate (for the period from 1980 to 1985, when TMINS did not operate)
At each station, exposure rate information is was 5.2 mR/std month for indicator stations displayed continuously and recorded in a data and 5.7 mR/std month for control stations.
logger. A microprocessor at each monitoring Generally, exposure rates at both indicator and location collects and stores 15 minute averages control stations have been decreasing gradually from the detector. These 15 minute averages due to the cessation of atmospheric nuclear are then automatically collected every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> weapon testing and the decay of fallout (or more frequently if required) by a computer products. This trend is depicted in Figure 7.
p located in Harrisburg.
Some indicator stations located on the site Since this is a real-time system, short-term boundary fence can show elevated exposure variations in exposure rates can be measured. rates, especially in Sectors E, F, and G.
The system involves the use of sensitive and Stations in these sectors are located close complex electronics, and data are occasionally enough to radioactive material transit and lost or inaccurate due to electronic, electrical, storage areas to be affected to some degree. In or mechanical failures in system components. 1998, the average annual exposure rate for all The real-time gamma monitoring system is indicator stations, including those stations used to supplement and backup the TLD located on the TMINS site boundary fence, monitoring program. was 4.4 i 1.6 mR/std month. Quarterly average exposure rates ranged from 3.1 to 8.3 Results mR/std month. Similar exposure rates were ,
measured in 1997 when all indicator stations in 1998, the average annual exposure rate for averaged 4.3 i 1.5 mR/std month and ranged offsite indicator stations, which excludes from 2.9 to 7.5 mR/std month.
stations located on the TMINS site boundary fence, was 4.5
- 1.5 mR/std month. Quarterly Some onsite stations in Sections E, F, and G exposure rates at offsite indicator stations did show slightly elevated exposure rates for ranged from 3.2 to 8.3 mR/std month. The some of 1998, but average onsite exposure average annual exposure rate for all control rates still were lower than is typical for offsite stations, those stations farther than 10 miles stations. This is consistent with previous .
from TMINS, was 4.9 1.6 mR/std month. results and is a function of the differing l characteristics of the land surface and geology Page 42
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT in the immediate vicinity of the TLD stations. mR/std month. Average exposure rates at Many onsite stations are located on or above control stations followed a similar trend.
manmade surfaces or structures, which may The fact that both indicators and controls shield the TLDs from terrestrial sources of increased by similar percentages suggested that ,
radiation. TMINS operation was not responsible for the l noted increase. The increase may have been I Exposure rates at stations on the site boundary due to a TLD handling or processing problem. I fence vary with the movement of onsite The latter statement was supported by static radioactive materials, and with the number and exposure rates for fourth quarter QC TLDs.
placement of stations on the fence. Additionally, the exposure rates reported by Occasionally, stations on the fence may be other REMPs in the fourth quarter also moved or added to ensure comprehensive remained relatively constant. A check by TM1 coverage of some areas. For these reasons, Dosimetry personnel was unable to prove or j year-to-year comparisons between stations on disprove the occurrence of a TLD handling or the site boundary fence and other indicator or processing problem.
control stations usually are not appropriate. i Figure 7 is a plot of gamma exposure rates (as i In 1998, the highest annual average exposure measured by TLDs) in the vicinity of TMINS rate of 7.3 i 1.3 mR/std month was measured from 1974 through 1998. Data from onsite at indicator Station H8-1. This annual average indicator stations are excluded from the graph.
exposure rate is typical for Station H8-1, and is Based on Figure 7, the trends in exposure rates lower than the historical (1980-1985) exposure at indicator stations were similar to those of j rate of 7.9 1.4 mR/std month for Station control stations with the exception of 1979. As H8- 1. a result of the TMI-2 accident, a transitory !
increase in exposure rates from the release of 4 Comparisons of exposure rates by distance ring noble gases was observed. Increases also were !
and radial sector also were performed to test observed in both indicator and control stations !
for potential effects of TMINS operations. in 1976,1977, and 1978 as a result of nuclear j Any effect of TMINS operations on offsite weapon tests. !
exposure rates should be evidenced by an i increase in the ring averages closer to TMINS, in 1998, the real-time gamma radiation i or in the sector averages in predominant wind monitoring system recorded an average directions. For the 1998 data, ring or sector exposure rate at offsite locations of 5.6 mR/std differences were not evident as compared to month, which is consistent with the 1997 historical data. offsite average of 5.6 mR/std month, but higher than the corresponding offsite TLD averages Exposure rates in the first three quarters of for 1998. Some difference between these two 1998 were relatively constant. In the fourth sets of results is expected primarily because quarter, a increase of nearly 20% was observed TLDs and the real-time monitors measure for both indicators and controls. The average gamma radiation at different locations. Table 4 exposure rate observed at offsite indicator shows the monthly average exposure rates stations for the first, second, third and fourth recorded by offsite real-time gamma radiation quarters of 1998 were 4.4,4.3,4.3 and 5.1 monitors.
Page 43
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE 4 1998 Monthly Average Exposure Rates for Offsite Real-Time Gamma Radiation Monitoring Stations Month mR/std Month
{
January 5.6 February 5.6 March 5.6 April 5.6 May 5.6 June 5.6 July 5.6 August 5.6 September 5.8 l October 5.7 November 5.8 p December 5.8 For both TLDs and the real-time monitoring average radiation dose a person receives from system, no elevated exposure rates as a result cosmic and terrestrial sources (Table 1, of TMINS operations were observed at any " Sources and Doses of Radiation").
offsite station. Both TLDs and the real-time monitoring system are sensitive and accurate mechanisms for measuring the low exposure rates characteristic of environmental levels.
Effects of normal TMINS operations, however, are too small to be discernible outside the normal range of background radiation levels.
The annual average gamma radiation exposure rates recorded at all offsite indicator TLD and real-time monitoring stations were 4.5 mR/std month and 5.6 mR/std month, respectively.
These equate to armual exposure rates of 54 mR/yr and 67 mR/yr. Exposures of these magnitudes are consistent with the annual Page 44
l I !\ l:lI 1' l 5
4 e
3 e g
a 46 -
s t 77
- 8 w-
'm s 99 0 . - - .
e 1 1 88 - . -
T r r79 n 3 ee91 - - - . - -
o 7 o 9 bb1 r mmhc e
- - - . - - . 5 v-o -
1 a
e et ee v r b
W JunpSNMO e oatc r
- . - - - . 8 s-a e
- . - - =
l c m .
u 67 8 77 7 N - -
p :. 38u-u-l o 2 99 1 1 9 1 - - -
r n 7 r r - .
tr t A
r 9 7bb 1
4 ee ber -
p s o r o c h1 mm me9 ee t - - - . -
e C i a
r et anppc u ee e
. 9 u-t MMJSSD -
a 89
. 9 u-Rr t e
r 4 77 7 11 9
1 hh1 99 08 96 9
8 1
- E u-e rua t
s e rccr ei l - - - . - -
n na a np r - - - . -
e u u - .
v JMMJ A - - - . - -
. 8 u-E - - - . - -
uQ t '
n e - - . -
a e g
s y i
f i
c l l aaL c
ii+ c n
- r u
P
. 8 s-ob p i S
n o t t ii r r cBly CCARb e
- . 8 uYaer l- -222 on xt h I I I I r MMMMh e -
- r .
. @u &r OEn
" TTTC I - . -
o -
e aM
- - - . - - : 8u ar t u
md V:: 8 w-r - - - - - . - -
a md
- : 3 w-ana -
. 2 w-GtS t r
o -
s '
. 9 w-l a - . - -
ar cp e i
d c
n
. E w-i - - - - - - -
i - - - -
rR - - - - - .
. 8 u-t om s
^
. R u-i - - - - - . - -
H -
.. R u-
. R u-
. R s-
~* -
- R u-
- - - - - - - - . E u-0 5 0 5 0 5 0 5 0 5 O 5 4 4 3 3 2 2 1 1 5
v O
- c. c -* k 1e 7
e r
u g
i F
l'l
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT ATMOSPHERIC MONITORING A potential exposure pathway to humans is inhalation of airborne radioactive materials. To monitor this exposure pathway, ambient air was sampled by a network of continuously operating samplers and then analyzed for radioactivity content. Based on the analytical results, no contribution to the general levels of airborne i radioactivity was attributed to TMINS operations during 1998.
Sample Collection and Analysis The indicator air sampling stations were located primarily in the prevailing downwind directions to the east (TMINS Visitors Center, Station El-2), the east-southeast (500 kV Substation, Station F1-3), the southeast (dairy farm near Falmouth, Station G2-1), and the south-southeast (Falmouth, Station H3-1) of TMINS and in the nearby communities of Goldsboro (Station M2-1) and Middletown (Station A3-1). There also were indicator air sampling sites to the north-northeast (TMINS North Gate, Station B1-4) and the northwest (Harrisburg International Airport, Page 46
1998 RADIOLOGICAL ENVIRONMENTAL MUNITORING REPORT Station Q4-1). The control air sampling quarterly and semiannual composite samples station was located in WeG Fairview (Station that were analyzed for gamma-emitting Ql5-1), a community situated more than 13 radionuclides and strontium, respectively.
miles from TMINS. This station provided background data for comparison. Cartridges containing activated charcoal were used for monitoring gaseous radioiodines.
Mechanical air samplers were used to These cartridges were placed downstream of continuously draw air through glass fiber the particulate filter at each of the air sampling filters and charcoal cartridges. To maintam a stations. Charcoal cartridges were collected constant flow rate throughout the collection weekly and analyzed separately from the period, each sampler was equipped with an particulate filters for 1-131.
electronic mass flow controller. This device automatically adjusted the flow rate to One charcoal cartridge collected during 1998 compensate for dust loading and changes in had a sampling period ofless than two days.
atmospheric pressure and temperature. This sample was not analyzed for gaseous radioiodines because it did not adequately Total air volumes were measured and represent the weekly collection period.
reccrded with dry gas meters. Air volumes were then adjusted based on vacuum readings Air Particulate Results over the collection period. All air samplers were calibrated semiannually and maintained During 1998, more than 450 air particulate by instrumentation technicians. samples (filters) were collected weekly from nine locations and analyzed for gross beta The glass fiber filters were used to collect radioactivity. The particulate matter (dust airborne particulate matter. The filters were particles) collected on all indicator and control collected weekly and analyzed for gross beta filters contained gross beta radioactivity above radioactivity. Five of these filters also were the minimum detectable concentration analyzed weekly for gross alpha radioactivity. (MDC).
The filters were then combined quarterly by individual station locations and analyzed for The gross beta concentrations measured on gamma-emitting radionuclides. Additionally, the filters collected from indicator sites ranged the weekly filters analyzed for gross alpha from 0.0040
- 0.0019 pCi/m' to 0.029
- radioactivity were prepared as semiannual 0.003 Ci/m' and averaged 0.015 0.010 composites by location and smalyzed for Sr-89 pCi/m The air particulate samples collected and Sr-90. from the controllocation had gross beta concentrations that ranged from 0.0043
~
During the year, one glass fiber filter had a 0.0019 pCi/m' to 0.028 0.003 pCi/m3and
, sampling period ofless than two days. This averaged 0.016
- 0.010 pCi/m'. The 1998 filter was not analyzed for gross alpha and annual average gross beta concentrations were ;
gross beta radioactivity because the consistent with the 1997 averages of 0.016 particulate matter collected was not 3 3 )
0.010 pCi/m and 0.017 i 0.011 pCi/m for ;
representative of the weekly sampling period. indicators and controls, respectively. ;
The filter was, however, included in the Page 47
O 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT The air sampling location with the highest atmospheric nuclear weapon tests and the annual average gross beta concentration radioactive decay of fallout products from ,
(based on more than two significant figures) previous detonations. Elevated '
was control Station Q15-1 (West Fairview). concentrations at both indicator and control The average gross beta concentration for air monitoring stations were noted after each airborne particulates collected at this station major nuclear weapon test, the TMI-2 was 0.016
- 0.010 pCi/m'. This average accident, and the Chernobyl accident. The concentration was well below the trends for indicator and control stations were preoperational average concentration of 0.15 similar for the entire TMINS operational 2
- 0.16 pCi/m and, as shown on Table 5, was periud, similar to the annual average gross beta concentrations calculated for particulate The particulate filters collected weekly from samples collected at the other air sampling five air sampling sites (Stations B1-4, H3-1, sites. M2-1, Q4-1 and Q15-1) also were analyzed for gross alpha radioactivity. During 1998, l As depicted in Figure 8, average weekly gross the particulate matter on approximately 83%
beta concentrations at indicator and control of the filters (215 of 259) contained gross air monitoring locations were somewhat alpha radioactivity above the MDC. Air variable, but trended similarly throughout the particulate gross alpha concentrations Q monitoring period. The weekly gross beta concentrations and trends at individual air (detected above the MDC) at indicator stations ranged from 0.00068
- 0.00044 l sampling sites also were similar. pCi/m' to 0.0045 0.0009 pCi/m' and l averaged 0.0019 0.0016 pCi/m'. Control l The 1998 data indicated that gross beta samples ranged from 0.00082
- 0.00055 ,
radioactivity levels did not change as a result pCi/m' to 0.0048 0.0010 pCi/m' and of TMINS operations. Additionally, the gross averaged 0.0021
- 0.0019 pCi/m'. For beta radioactivity associated with airborne comparison, indicators and controls both particulates was due primarily to naturally- averaged 0.0015
- 0.0010 pCi/m' in 1997.
occurring radionuclides.
The air sampling location with the highest Historical trends of average quarterly gross annual average gross alpha concentration beta concentrations associated with airborne (based on more than two significant figures) l particulates from 1972 to 1998 are depicted in was control Station Ql5-1 (West Fairview). ;
Figure 9. Generally, the gross beta The 1998 average gross alpha concentration l concentrations have decreased with time. The for particulate samples collected at this site 1998 average gross beta concentration of was 0.0021
- O 0019 pCi/m'. As shown on l 0.016 pCi/m', for indicators and controls Table 6, similar annual average gross alpha combined, is approximately 10% of the 1974 concentrations were calculated for the other preoperational average concentration (0.15 four air particulate sampling sites.
pCi/m').
Average weekly gross alpha concentrations ,
The overall diminution in gross beta are depicted in Figure 10. Actual l O concentrations is a direct result of the ban on concentrations (whether positive, negative or Page 48 l l
i998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT zero) were used to calculate weekly averages on indicator samples were similar to those because approximately 17% of the weekly detected on control filters.
results were below the MDC. Using actual concentrations eliminates biases in the data Naturally-occurring radium-226 (Ra-226) and and missing data points on graphs. potassium-40 (K-40) also were detected.
Radium-226 was measured on one primary As depicted in Figure 10, average weekly sample while K-40 was measured on three gross alpha concentrations varied throughout quality control samples.
the monitor:ng period. However, the trends for indicator and control concentrations Strontium analyses were performed on a total generally were similar. of 10 air particulate semiannual composite samples during 1998. Neither Sr-89 nor The data obtained in 1998 indicated that gross Sr-90 was detected above the MDC.
alpha radioactivity levels did not change as a result of TMINS operations. Also, the gross Air lodine Results alpha radioactisity measured on the particulate filters was due primarily to During 1998, more than 450 charcoal naturally-occurring radionuclides. cartridges were collected weekly and analyzed for 1-131. None of the weekly samples Historical trends of average quarterly gross contained 1-131 (or any other isotope of alpha concentrations from 1972 through 1998 iodine) above the MDC.
are displayed in Figure 11. Gross alpha concentrations during the preoperational period (1972-1974) averaged 0.001 pCi/m' with maxirrum concentrations up to 0.006 pCi/m'. Although some of the operational concentrations were slightly higher than the preoperational average concentration, control sample concentrations were comparable to indicator sample concentrations. The overall trends for gross alpha concentrations in air particulates at indicator and control stations were similar throughout the TMINS operational period.
Gamma-emitting radionuclides related to l TMINS operations were not detected on any l
of the 40 quarterly composites (including QC filters) that were analyzed in 1998. As ,
expected, all of the quarterly composite i samples contained naturally-occurring beryllium-7 (Be-7). Concentrations detected Page 49 O
l
l O l I
1998 RADIOLOGICAL ENVIRONMENTAL MONITOR 1NG REPORT TABLE 5 1
1998 Average Gross Beta Concentrations I in Airborne Particulates (pCi/m')
Station Description Average +/- 2 std dev*
l A3-10) Middletown 0.016 i 0.011 l B1-40) TMINS North Gate 0.016 i 0.011 El-20) TMINS Visitors Center 0.015 i 0.010 l F1-3 0) 500 kV Substation 0.015 i 0.010 l G2-10) Dairy Farm (Near Falmouth) 0.015 i 0.009 H3-10) Falmouth 0.015 i 0.009 M2-1(I) Goldsboro 0.016 i 0.010 Q4-10) Hbg. International Airport 0.016 i 0.010 ,
Ql5-1(C) West Fairview 0.016 i 0.010 l
- Averages and standard deviations are based on concentrations > MDC.
O 0) = Indicator Station (C) = Control Station TABLE 6 1998 Average Gross Alpha Concentrations in Airborne Particulates (pCi/m')
Station Descriotion Averare +/- 2 std dev*
B1-40) TMINS North Gate 0.0017 i 0.0011 H3-1(I) Falmouth 0.0017 i 0.0013 M2-1(I) Goldsboro 0.0020 i O.0019 Q4-l(l) Hbg. International Airport 0.0020 i 0.0017 Q15-1(C) West Fairview 0.0021 i O.0019
- Averages and standard deviations are based on concentrations > MDC.
- 6) = Indicator Station (C) = Control Station Page 50
i s
e g
pa O
s - -
t e -
3 l
a -
3 u
i c -
t - - - - - - - - .
r l v - - - - - - - - -
a i - - - - - - - -
i n - - - - - - - - .
o P k C - -
s -
ie re -
AW -
s ny - - - - - - - -
ib -
8 s re -
a1 9
9 nt e de
- - - - - - - - f o
o d y u - - - - - - - -
iM l c - - - - - - - - -
D a .
Ott aic rb u
i t
n o
n e
r e
s/ h t
M n
o nC e
w s
e s
r l p - - - - - - - - - _
ce np r m
a s
s o
y ose t a
c d
a o
s Ci ru i d
n d t
w s
ae t o I
n a
e n
a ec o - -
BP i -
m .
s o
r f - - - - - - - -
s s l t
u s s - - - - - - - -
o r
R e
s E -
T - - - - - - - -
G O - - - - - - -
N -
2 8 -
9 9 0 5
5 4
0 4
5 3
0 3
5 2
0 2
5 1
0 1
5 0
0 0
1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 m@12 5
obo Q E589. -
O 8 e
r u
g i
F
2 5
e
) g ra s s 46 77 - - - - - -
. 83 t
e T t
s e 99 1 1 r r79 88 0 -
V..e3 .
n 3 e e91 - - - - - -
l a o 7bb1 c 91 a
e et mmh e e c r e b
o u W Jnpvroat . 83 u e c r SNMO - - - - - -
i c s l a
e c
. 83 t l e u 67 8 77 7 p 99 9 - - -
r m N. 2 m 7 1 1 r r 4 eeb er 1
- . 33 a S a A t 9 7bb 1
h1 9 mmm
. 83 P
r o c ee e - - - - - -
i a
r a mtppce t lor MMJu SSD ee -
. 83 r
i r t
n -
e o 89 77 0 6
. 53 At r C 4 7
9 1
99 1 1 hh1 8
9 9 8
1 i
nau t s
v JMMJuA
- c n nanr aeinp r e u e
l
. 83 sQ E - - - - - -
c'.. 83 t
n e - - - - - -
a t g .
ny i f
i c l a
c r
u 83 ir ob i S
n e
iNchP i
t r
CCARb cBly
. 23ra n o t e l- -222- - - - - - -
e I I I I r e Y
at e M T"* mmh I 1 ~ C
. 83 &
t rM n c
. 83et r
r a
(t -
- 33Q u
eib - - - - - - - :
c nC u -
- 83 o
r s - - - : 83 Ce p l
e - - - - - l. l .
p -
.E3 as t e m
a
.S3 S
er i r
o
.R3 Bu oe t a
c
.R3 s c idn si - - - - -
.R3 oP i .
r -
.R3 G -
.R3 l - - - - -
a c'
.R3 i - -
r - - - - - - .R3 o
- - . R3 t
s 4
0 5
3 3
0 5
2 2
0 5
1 1
0 5
0 0 _
i 0 0 0 0 H 55 111o$0 8389.C-9 oU e r
u g
i F
1 l
m a
1 o
A : 862zzt w
- suzt 86a utt C4 g .
- 86nin 6
.o
- . : : 86/8vot W . .
Q _
. . . . . 86/tL/0t CU 9 : : : : : :
~
4 :
sum
] : : : :
yy o : :
- 86/st/6
,, g . .
@ l : . l 86/&6 g k . gg g;g
,, g .
06/9/8 co M 6 :
ga y .
e62ut Q g ,x .
. .e e sua ^5 06/8/L &
/n\ CD g k$
g$ l
-06/P&9 2 I kk ! !
ma 86/6/9 sg . . . . . .
QQ d l l - 86/9 &9 v% :h o$ .
g . . . . . '. 06mL/9 m u .
W O a Q 'g@y"
- 86/8&P M z 3
Q }h gg l
l l
l 06/PL/t g e . .
86/LC/C U .2
.-= g o.2 ~ _ . 86/ll/E
, 06/C/C sO Ni i dj
' l l l l - Se'e ta b F , . . . . 06/02 o . . . . . .
2 . . . .
- 86/0VL QQ -
l 06/9/L
& o S S
& h $ $ 8 8 M 6 6 6 6 6 6 o 9
Jelen o!qno Jed sepnooold c w
g a
.t@.
. I;lii l 4
5 e
s O ea s 46 -
e s 77
. 8 u-t s 99 0 . - -
e 1 1 88 t T r r79 l
a n 3 e e91 o 7 bb1 r o 9 a 1 mmh b e
. E u-ee c o . - -
u e et vr W Ju e np SNMO oa c t . -
- : 8 s-c r
a . - -
i e . - -
s :. E s-l c .
t e u 67 8 77 7 r l p N. 2 99 91 . - -
a 1 1 . - -
m t m 7 9 7bb 4 reerb e r . - - . & u-a A P
1 -
9 . -
S r
o h1 c et mmm r t e e e . - -
. 8 u-i a anppc . - -
ue e e i
r l tr o
r MMJ SSD .
- 8 u-r . - -
Ae t C o 4 77 7 199 9
89 1
0 86 8 19 9
- . 5 s-nrau 1 hh1 e rcr cei s l t
n na a np r e u u
- . 8 u-i E
v JMMJ A . - -
. 8 w-sQ t
n . :
n y a t e c ng r . - - .
G aa l l ccd e u .
. 8 w-ob i
n iiiP c t t . -
i i i r r cBly . .
% CCARb
.Ew are t r l - -222
- - n or l ate re I I I I MMMMh TT' I TC e .
. 8w &r Y
- 8w tea OtnM
- . - - r ec i e
- 3 w- Q u
cb l p
nu oC s s t nl o md at e
- 8 w-oap l Ce r u : 8 a-i - . - -
acr e s t t - . - :
e r n a, e ap -
t l
p e6 w - . - - . E u-s m cn99 )o r he S a co1 e z ei ,n
. 8n-pi r r l
pgv e -
u l o mit ni a na - .
". R u-Ao t
a c c s ng - .
ygn i e - . - . R u-id n e l
a si c t
n o, B. ie, v - . - - a7 :
I D'i9 : : R u-sP 6 di t o
r 9 e s 9
1 olps t
o (p t o i
- t1 n -
s4 is7 '
. R u-t - . - 9 M1 G r e n .
ior o
- _ - - . R s-r ei Pwt a r - . - -
l E
Ct n - . - -
. R s-a T OMn Dec - . -
i c N>c o
. R s-r
- . : R s-o 1 8 6 4 2 0 0 0 Q 0 0 t 0 0 Q 0 0 i
s 0 Q, 0 0 552 bo mE 8382.*-
OH 1
1 1
e r
u g
i F
_1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT AQUATIC MONITORING Since radioactive materials are released to the Susquehanna River from routine operations at TMINS and this watershed is used as a source for drinking water and recreational activities, the aquatic environment is monitored extensively for radionuclides of potential TMINS origin.
Recreational activities in the TMI reach of the Susquehanna River include fishing, boating, swimming and other water sports.
Monitoring of the aquatic environment in the vicinity of TMINS was accomplished by collecting and analyzing samples of surface water, drinking water, fish and river sediments. The indicator (downstream) sampling sites were chosen based on studies of travel time and mixing characteristic.e for the Susquehanna River.
Control samples were collected from locations which were not expected to be affected by TMINS operations. The impact of TMINS operations was assessed by comparing control sample concentrations to those measured in indicator samples. As applicable, comparisons with results from previous years also were performed.
O
~
_ Page 55
l 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT l
l During 1998, samples from the aquatic Station Q9-1 (Steelton Water Authority, )
environment were found to contain low Steelton, PA).
concentrations of radioactive materials attributable to routine TMINS operations. Samples of the TMINS liquid discharge They included Cs-137 in sediments and H-3 in (Station Ki-1) also were collected and surface water, drinking water and possibly analyzed. The liquid discharge samples were fish. The concentrations found in these collected from a location where the water was samples, however, were too low to adversely not yet mixed with the Susquehanna River.
impact humans or the environment. As appropriate, data from the liquid discharge Radionuclides attributable tc medical facilities samples were compared with data obtained and their patients, natural production in the from samples collected as part of the TMINS atmosphere and fallout from prior nuclear EfIluent Monitoring Program.
weapon tests also were identifkd in various aquatic med;a. Except for those collected at Station F15-1 (Chickies Creek), all water samples were Sample Collection and Analysis normally obtained by an automatic water compositor. Samples from Chickies Creek Surface (raw / unfinished) and drinking (Station Fl5-1) were collected as grabs twice (finished) water samples were collected at per week. Grab samples also were collected seven stations (three indicators and four when the automatic compositors were not controls) and analyzed during 1998. Indicator operating (e.g. AC power loss, sampler ,
samples were collected from locations along malfunction or frozen sampling line). The the Susquehanna River which were water compositors collected a measured downstream of the TMINS liquid discharge volume of water at a preset interval of time outfall. Indicator surface water samples were (30 or 60 minutes). These samplers were collected at one location, Station J 1-2 (west maintained and calibrated by instrumentation shore of TMI). Indicator drinking water technicians.
samples were collected at two water treatment facilities -- Station G15-2 (Wrightsville Water The composite samples normally were Supply, Wrightsville, PA) and Station G15-3 retrieved biweekly (every two weeks). To (Lancaster Water Authority, Columbia, PA). verify that the samplers were operating properly, a surveillance was performed l Control samples were collected from the weekly. Occasionally, composite samples Susquehanna River upstream of the TMINS were retrieved weekly to close out a calendar l liquid discharge outfall or from its tributaries. month or quarter. The grab samples collected j Control surface water samples were collected from Chickies Creek (Station F15-1) were from three locations - Station A3-2 (Swatara composited into weekly or biweekly samples.
Creek, Middletown, PA), Station F15-1 (Chickies Creek, Marietta, PA) and Station The weekly and biweekly composite samples Q9-1 (Steelton Water Authority, Steelton, from indicator Stations G15-3 and G15-2 PA). Control drinking water samples were along with those collected from control I obtained at one water treatment facility -- Stations Q9-1, F15-1 and A3-2 were analyzed Page 56 i
l
(~'h 1
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT l for low-level 1-131 using a chemical liquid discharge outfall and the YHD (Station separation / concentration technique. Samples 31-2). The control samples were obtained of the TMINS liquid discharge also were from the Susquehanna Riverjust upstream of analyzed for low-level I-131 employing the TMI(Station A1-3).
same technique.
In addition to the routine samples, special All water samples retrieved weekly and sediment samples were collected in 1998.
biweekly were combined by station into Three samples were collected in August from monthly composites and analyzed for H-3 and behind the Red Hill Dam (RHD) as part of the gamma-emitting radionuclides, including fish passage project. In September, four !
l-131. Monthly gross beta analyses also were special samples were collected proximal to the performed on all drinking water samples and York Haven Generating Station (YHGS). l the samples collected from Station Kl-1, The latter samples were taken and analyzed at l Semiannual composite samples were prepared the request of a potential buyer for YHGS.
only from monthly samples collected at Station Kl-1 and then analyzed for Sr-89 and Except for the ones collected at the RHD, all S r-90. sediment samples were collected using a dredge designed for this purpose. Samples Electro-shocking equipment and hook and line from RHD were collected using a shovel and Q
Q were used to collect fish samples in the spring (May and Jund and fall (September and trowel. All sediment samples were dried and analyzed for gamma-emitting radionuclides.
October) of 1998. To monitor the progression of radionuclides through the food s ' ter Results chain, bottom feeding fish as well as predator species were collected. Indicator samples Iodine-131 is produced during the fission were collected from zones or areas process and may be a constituent of TMI-l immediately at or downstream of the TMINS liquid effluents. This radionuclide also may be ligoid discharge outfall, while control discharged to the Susquehanna River and its specimens were gathered from locations tributaries by medical facilities and their ,
greater than ten miles upstream of TMI. The patients via the municipal sewage system.
edible portions were analyzed for Sr-89, Institutions such as hospitals utilize this Sr-90, H-3 and gamma-emitting radionuclides. material for diagnostic studies of the thyroid and thyroid therapy. Iodine-131 from medical As part of the routine REMP, river sediments facilities and their patients is commonly from four locations (three indicators and one detected in REMP samples because the control) were collected in the spring (June) methods used to treat sewage do not remove and fall (September) of 1998. Indicator this material.
sediment samples were collected at a sitejust downstream of the TMINS liquid discharge During 1998, low-level I-131 using the outfall (Station Kl-3), at the York Haven chemical separation / concentration technique Dam, YHD, (Station J2-1) and at a site on the was detected above the minimum detectable west shore of TMI, between the TMINS concentration (MDC)in 15 of 84 control d
Page 57
I998 Ral0 LOGICAL ENVIRONMENTAL MONITGRING REPORT surface water samples and 2 of 56 control I-131 was not detected concurrently in a drinking water samples. Both were quality control sample or the concentration detected control samples. Iodine-131 above the MDC in the discharge sample was slightly higher also was identified in 12 of 28 samples than the concentration measured in the control collected from Station Kl-1, the TMINS sample (s). This may have been caused by the liquid discharge. None of the indicator process used to cool water at TMINS.
drinking water samples collected in 1998 contained 1-131 above the MDC. Indicator Water is continually withdrawn from the surface water samples were not analyzed Susquehanna River for cooling. During one using the chemical separation / concentration of the cooling processes, a large amoimt of technique. water is evaporated. The suspended and dissolved materials remain in the water and, The 1-131 concentrations measured in control therefore, are concentrated. One of these surface water samples ranged from 0.39
- materials may be medically-related I-131 (i.e.
0.29 pCi/L to 4.2 0.4 pCi/L and averaged 1-131 released by upstream medical facilities 1.2 2.0 pCi/L. For comparison, the average and/or their patients). To prevent a buildup of j 1-131 concentration for 1997 control surface these concentrated materials, some of the i water samples was 0.52
- 0.20 pCi/L. water is diluted and then returned or j discharged to the Susquehanna River. It is As mentioned previously, two quality control possible that the dilution water also contains drinking samples collected at control Station medically-related 1-131. !
Q9-1 (Steelton Water Authority) contained I-131 above the MDC. The concentrations The similarity of the control and discharge j ranged from 0.34
- 0.19 pCi/L to 0.79 i 0.19 results along with the possibility that I-131 l pCi/L and averaged 0.56 0.64 pCi/L. The may be concentrated during the cooling medical industry was responsible for the process suggested that medical facilities and presence ofI-131 in all 1998 control surface their patients, and not TMINS, was the source l and drinking water samples. of the 1-131 detected in the liquid discharge j samples. The absence ofI-131 in 1998 liquid
]
Twelve of twenty-eight TMINS liquid effluent samples supported this conclusion.
discharge samples collected in 1998 contained I-131 above the MDC. The I-131 In 1998, H-3 above th- MDC was measured concentrations ranged from 0.35 0.22 pCi/L in 9 of 36 monthly control surface water ,
to 2.6 0.4 pCi/L and averaged 1.3 1.1 samples and 6 of 12 monthly indicator surface l pCi/L. The 1997 results were similar, ranging water samples. Table 7 lists the annual i from 0.31
- 0.22 pCi/L to 1.3 0.4 pCi/L and average H-3 concentrations and the ranges for l averaging 0.72
- 0.68 pCi/L. the samples collected at each surface water station. Also included in the table are the )
Generally, each time I-131 was detected in a annual average concentrations and ranges i liquid discharge sample, a similar based on actual sample concentrations, I concentration of this material was measured in whether positive, negative or zero.
a control sample (s). Sometimes, however, l
Page 58
i998 RADIOLOGICAL ENVIRONMENTAL MONITORING RELY)RT The H-3 measured in the control surface released in liquid emuents in 1997, whereas, water samples ranged from 92157 pCi/L to about 320 Ci were released in 1998.
170 50 pCi/L and averaged 120 50 oCi/L.
These concentrations were consistent with Figure 12 depicts the 1998 monthly trends of those measured previously in control surface H-3 concentrations in surface water samples and drinking water samples. The presence of collected at Station J1-2. Actual H-3 in the control samples was attributed to concentrations (whether positive, negative or fallout from prior nuclear weapon tests and zero) were plotted. For comparison, the natural production of this material in the actual monthly H-3 concentrations measured atmosphere. in the TMINS liquid discharge samples also are depicted in Figure 12. Except for the As expected, H-3, a major component of 1998 biased July sample result, this figure shows TMINS liquid emuents, was detected above that the H-3 concentrations measured in the i the MDC in 50% of the monthly surface water samples obtained from Station J1-2 were j samples collected at indicator Station J1-2. directly related to those detected in the This station is located just downstream of the TMINS liquid discharge samples (Station TMINS liquid discharge outfall where mixing Kl-1). Historical trends of H-3 ofliquid effluents with river water is concentrations in surface water are shown in incomplete. More complete mixing is not Figure 13.
p achieved untilliquid emuents pass over the
{
U York Haven Dam (YHD). A dose estimate was not performed for H-3 in '
surface water because this medium normally is The annual average H-3 concentration for the not consumed by humans. All of the H-3 -
samples collected at Station J1-2 was 2400
- concentrations measured in surface water 6000 pCi/L. The results ranged from 91
- 51 during 1998 were, however, below the q pCi/L to 7800
- 800 pCi/L. The average USEPA Primary Drinking Water Standard of concentration was biased low as a result of a 20,000 pCi/L.
sampler malfunction. Occurring in July, the malfunction resulted in a number of missed in 1998, H-3 above the MDC was measured '
hourly aliquots during periods of high activity in six indicator drinking water samples and i H-3 releases. two controls. Table 7 lists the annual average i
H-3 concentrations for the samples collected For comparison, H-3 was detected in 9 of 12 at each drinking water station. Also included i 1997 monthly samples collected at Station are the annual average concentrations based l J1-2. The concentrations ranged from 100 on actual sample concentrations, whether 60 pCi/L to 12000 + 1000 pCi/L and averaged positive, negative or zero. I 2900
- E700 pCi/L. A lower average concentration was expected in 1998 because a The control drinking water samples collected smaller amount of H-3 was released in 1998 in May and July at Station Q9-1 (Steelton liquid emuents. Nearly 750 Ci of H-3 were Water Authority, Steelton, PA) contained H-3 ranging from 100 50 pCi/L to 130 i 50 O
Page 59
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT pCi/L and averaging 110 40 pCi/L. The samples. Instead ofonly using concentrations concentrations measured in the 1998 control above the MDC, actual concentrations samples were consistent with those measured (whether positive, negative or zero) were used in the 1998 control surface water samples as for the graph. This method eliminated biases well as those measured in control surface and in the data and missing data points. For drinking water samples from previous years. comparison, the actual H-3 concentrations For example, the 1997 control surface and obtained from samples collected at Station drinking water results were 120 60 pCi/L Kl-1 also were included in Figure 14 (lower).
and 120 70 pCi/L. The presence of H-3 in the control drinking water, like control surface Generally, Figure 14 shows that the highest ;
water, was attributed to fallout from prior average indicator concent ations occurred j weapon tests and natural production of this when the highest amounts of H-3 were j material in the atmosphere, released in TMINS liquid efiluents. Th concentrations measured in the indicator One monthly drinking water sample from samples were consistent with data gathered indicator Station G15-2 (Wrightsville Water from travel time and mixing studies. There !
Supply, Wrightsville, PA) and five monthly were a number of months when the indicator l drinking water samples from indicator Station average was similar to or less than the control l
G15-3 (Lancaster Water Authority, Columbia, sample concentration. This indicated that the i PA) contained H-3 above the MDC. The H-3 H-3 measured in both indicator and control j concentrations averaged 2201380 pCi/L and drinking water samples was most likely due to ranged from 89 52 pCi/L to 590 90 fallout or natural production.
pCi/L.
To put the 1998 H-3 results into perspective, The H-3 concentrations measured in the 1998 the highest monthly indicator concentration of indicator drinking water samples were similar 590 i 90 pCi/L represented less than 3.0% of to those measured in 1997, when eight the USEPA Primary Drinking Water Standard samples contained H-3 above the MDC. The (20,000 pCi/L). Furthermore, if an individual measured concentrations averaged 240 280 drank water at this concentration for an entire pCi/L and ranged from 110160 pCi/L to 480 year, the maximum hypothetical whole body i 70 pCi/L. The 1998 results also were dose would be 0.061 mrem. This calculated consistent with those measured in other years. dose is equivalent to 0.020% of the whole For example, eight samples collected in 1995 body dose that an individual living in the TMI contained H-3 above the MDC. The area receives each year from natural concentrations ranged from 110 70 pCi/L to background radiation (300 mrem).
320 90 pCi/L and averaged 200 160 pCi/L. Generally, the H-3 concentrations detected in samples collected at Station Ki-l (TMINS Figure 14 (upper) displays the average liquid discharge) agreed well with those monthly H-3 concentrations measured in the brained from the TMINS Efiluent 1998 indicator and control drinking water Monitoring Program.
Page 60 O
O tQ 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT The monthly composites of all drinking water as a function of the individual system design samples were analyzed for gross beta activit< and operation.
Table 8 lists, by station, the annual averages and ranges for gross beta concentrations All of the drinking water results for 1998 were above the MDC. Averages and ranges based well below the Federal and State Primary on actual concentrations are included for Drinking Water Standard of 50 pCi/L for comparison. The monthly (composite) gross beta radioactivity. The results indicated TMINS liquid discharge samples from Station that gross beta radioactivity detected in all Kl-1 also were analyzed for gross beta. drinking water samples was attributed to naturally-occurring radioactive materials.
Most indicator and control drinking water samples collected in 1998 contained gross in 1998, all but one of the monthly composite beta radioactivity concentrations above the samples from Station Kl-1 (TMINS liquid i MDC. Indicator results ranged from 1.6 0.8 discharge) had gross beta radioactivity pCi/L to 5.8 + 1.4 pCi/L and averaged 2.71 concentrations above the MDC. The gross l.9 pCi/L. Similarly, the controls ranged from beta concentrations ranged from 2.2 i 1.3 1.7 i 1.1 pCi/L to 3.8 t 1.0 pCi/L and pCi/L to 9.4 f 1.6 pCi/L and averaged 5.3 i averaged 2.6 1.4 pCi/L. The 1998 averages 5.0 pCi/L. The 1998 results were consistent were consistent with the 1997 averages of 2.8 with those reported in previous years for
/
- 1.4 pCi/L and 2.8 2.2 pCi/L for indicators Station Kl-1 samples. All TMINS liquid C and controls, respectively, discharge samples, like drinking water samples, had gross beta concentratiors well The monthly gross beta averages for indicator below the Federal and State Primary Drinking and control drinking water are plotted in Water Standard of 50 pCi/L.
Figure 15. Actual concentrations were used for this graph. Generally, indicator and Monthly composite samples of surface and control sample concentrations trended drinking water were analyzed for the presence similarly throughout the year. Minor of garnma-emitting radionuclides. None of the differences were evident, but expected. samples collected in 1998 contained detectable levels of reactor-produced, gamma-The variability in the gross beta emitting radionuclides.
concentrations was directly related to the type of treatment and the overall contaminant The gamma scan of the December composite removal efliciency of each water treatment from Station Kl-1 yielded 1-131 above the facility. For example, suspended solids with MDC. This was not surprising because both adsorbed man-made or naturally-occurring biweekly samples also contained I-131 above radioactive materials are removed from raw the MDC. The presence of this material in the river water by common treatment processes biweekly and monthly composite TMINS such as filtration and sedimentation. The liquid discharge samples was due to medical amount removed by these processes will vary facilities and/or their patients because similar concentrations ofl-131 were detected in
/~
t b
j Page 61 I
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT control samples collected during the same fallout from prior nuclear weapon tests. This time period. conclusion was supported by two other facts.
Very low amounts of Sr-90 were released in Semiannual composite samples were prepared 1998 TMINS liquid emuents. Secondly, from the monthly TMINS liquid discharge excluding H-3, other radioactive materials samples and then analyzed for the presence of released in 1998 TMINS liquid emuents were Sr-89 and Sr-90. None of the 1998 not detected in the indicator fish samples.
semiannual composites contained Sr-89 or Sr-90 above the MDC. Tritium above the MDC was detected in all but one of the 1998 fish samples. Indicator Fish Results H-3 concentrations ranged from 0.094 i 0.034 pCi/g (wet) to 0.20 0.05 pCi/g (wet)
During 1998, fish samples were collected at and averaged 0.1210.10 pCi/g (wet). The one indicator and one control location in the control sample concentrations were slightly spring (May and June) and fall (September lower, ranging from 0.062
- 0.033 pCi/g and October). They included recreationally (wet) to 0.087 0.046 pCi/g (wet) and important predators (Smallmouth bass) and averaging 0.074
None of the fish samples collected in 1998 expected for a number of reasons. First, H-3 !
contained detectable levels of reactor- was released routinely in 1998 TMINS liquid l produced, gamma-emitting radionuclides. As emuents and some of the releases contained expected, naturally-occurring K-40 was high concentrations of H-3. Second, indicator detected in all fish samples. Indicator fish samples were collected in the York Haven l concentrations were similar to those measured Pond (YHP) between the TMINS liquid l in the controls. discharge outfall and the York Haven Dam (YHD). In this region of the YHP, mixing of i Strontium-89 above the MDC was not TMINS liquid emuents and river water is !
detected in any of the 1998 fish samples. incomplete. More complete mixing is not Strontium-90 was measured in both indicator achieved until liquid emuents pass over the samples collected in the fall. The Sr-90 YHD concentrations averaged 0.002210.0004 l
pCilg (wet) and ranged from 0.0021 i 0.0011 Since H-3 was measured at slightly higher '
pCi/g (wet) 0.0024 i 0.0013 pCi/g (wet). concentrations in the indicator samples, it is Both results were similar to the Sr-90 possible that a portion of the H-3 measured in concentration detected in the 1996 these samples was due to routine TMINS control predator sample (0.0039 0.0024 operations. The presence of this material in pCi/g, wet). The presence of Sr-90 in the the control samples indicated that a portion of 1998 indicator sampim was most likely due to the H-3 detected in the indicator samples also Page 62 O
i
O
( 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT was due to fallout and natural production in 0.14 pCi/g (dry) and 0.12 0.03 pCi/g (dry),
the atmosphere. for indicators and controls, respectively.
A conservative dose estimate was performed The highest concentrations of Cs-137 were assuming that an individual consumed fish detected in the sediment samples collected just flesh with the highest H-3 concentration for downstream of the TMINS liquid discharge one year, The maximum hypothetical whole outfall(Station Kl-3). The Cs-137 body dose would be 0.00044 mrem. This concentrations ranged from 0.21 i 0.03 pCi/g calculated dose is equivalent to 0.00015% of (dry) to 0.22 i 0.02 pCi/g (dry) and averaged the whole body dose that an individual living 0.21 0.01 pCi/g (dry). This was expected in the TMI area receives each year from because Cs-137 is typically released in natural background radiation (300 mrem). TMINS liquid efIluents and less mixing of effluents and river water occurs at this Sediment Results location. Also, radioactive materials such as Cs-137 are readily adsorbed by suspended In June and September of 1998, routine particles in the water and bottom sediments.
REMP sediment samples were collected from four sites in the Susquehanna River. Control As mentioned previously, Cs-137 is a fallout samples ere collected from a location product of weapons testing as well as a upstream of the TMINS liquid discharge p/
s outfall. Indicators were collected from three constituent of TMINS liquid effluents. Since some of the 1998 indicator sample sites in the York Haven Pond (YHP) between concentrations were slightly higher than those TMINS liquid discharge outfall and the York measured in 1998 control samples it is Haven Dam (YHD). All samples were reasonable to conclude that an increment of analyzed for gamma-emitting radionuclides. the Cs-137 detected in the indicator samples was due to TMINS operations. The presence Naturally-occurring Be-7, K-40, Ra-226 and of this material in the control samples thorium-232 (Th-232) as well as fallout indicated that a portion of the Cs-137 and/or reactor-produced Cs-137 were detected in the indicator samples also was due identified in all indicator and control samples. to fallout from prior atmospheric nuclear No other reactor-produced, gamma-emitting weapon tests.
radionuclides were detected above the MDC.
Figure 16 depicts Cs-137 concentrations in Indicator Cs-137 concentrations ranged from river sediments from 1984 through 1998. As 0.14
- 0.02 pCi/g (dry) to 0.22 0.02 pCi/g shown in this figure, no discernible buildup of (dry) and sveraged 0.18 0.06 pCi/g (dry). Cs-137 occurred at indicator locations prior Control sample concentrations were slightly to and after 1995. This was primarily due to lower, ranging from 0.080
- 0.023 pCi/g (dry) periodic scouring or removal of bottom to 0.19 0.03 pCi/g (dry) and averaging 0.13 sediments during high river flows (Ref. 47).
- 0.16 pCi/g (dry). For comparison,1997 average Cs-137 concentrations were 0.24
- Page 63
1998 R@l0 LOGICAL ENVIRONMENTAL MONITORING REPORT A temporary buildup of Cs-137 in sediments emitting radionuclides were detected above was noted in 1995. This was caused by lower the MDC.
than normal river flows during the year and especially in the spring months when most The Cs-137 concentrations ranged from 0.11 scouring occurs. In 1996, the average Cs-137 0.03 pCi/g (dry) to 0.23
- 0.06 pCi/3 (dry) concentrations in indicator samples trended and averaged 0.1610.12 pCi/g (dry). Since at downward. The reduction was due to least one of the YHGS sa nple concentrations releasing lower amounts of Cs-137 and having was higher than that measured in the higher than average river flows which increase September control sample and Cs-137 was dilution ofliquid efiluents and promote routinely released in TMINS liquid efiluents, scouring. it is possible that an increment of the Cs-137 detected in one or more of the YHGS samples Based on annual average concentration of was due to TMINS operations. The presence Cs-137 in samples collected from of this material in the routine REMP control Station Ki-3, an estimate of the shoreline samples indicated that a portion of the Cs-137 whole body dose to the maximally exposed detected in the YHGS samples also was due individual was calculated. For this to fallout from prior atmospheric nuclear calculation, the annual average Cs-137 control weapon tests. A whole body dose smaller concentration was subtracted to account for than the one calculated for the Kl-3 samples fallout Cs-137. The calculated whole body would have resulted. ,
dose (0.00018 mrem /y.r) was insignificant and l a small percentage (0.000060%) of the whole in previous years, sediment samples were body dose received by an individual from collected at Safe Harbor Dam (SHD), the first natural background radiation (300 mrem /yr). major sediment trap downstream of TMINS. l The purpose of this sampling was to In addition to the routine REMP samples, determine if radionuclides released in TMINS l several special sediment samples were liquid effluents were present and accumulating i collected in 1998. Three samples were at SHD. The results indicated that a portion collected in August from behind the Red Hill of the Cs-137 detected in the SHD sediments Dam (RHD) as part of the fish passage may be due to TMINS operations since the project. Only naturally-occurring K-40 and concentrations were higher than those Th-232 were detected. collected at control locations. However, the !
absence of other reactor-related radionuclides, In September, four special samples were such as Cs-134, indicated that recent TMINS I collected proximal to the York Haven discharges were not present at significant Generating Station (YHGS). The latter levels and most of the Cs-137 was attributable samples were taken and analyzed at the to fallout from prior nuclear weapon tests !
request of a potential buyer for YHGS. and/or the Chernobyl Accident of 1986. The Naturally-occurring Be-7, K-40, Ra-226 and results also indicated that a buildup of thorium-232 (Th-232) were identified in all of TMINS-related materials was not occurring at the samples. Three of these also contained SHD.
Cs-137. No other reactor produced, gamma-Page 64
s 0 0 0 s 5
0 3 2 e e 31 00 1 7
- - 1 0
8 7
1 9
- - 5 0
9 e
e s
el h p e
6 e
2 -
- s na e ) ) -
- 3. 4 9 42 5
) )
8
- 9. 93 8
- l p
t nmi eas s P a
nR - -2 1 0- (- 8 m a r a s l3 i
o ( (
( s plya n t
a r
l o
r i n no a t d gt e
t n n e na eve o c si ic c o gl nd y l cra p o
Cds it l
ne evD u a
e t
0 0
u q
e ay r e.
l p 2 0 683 7 3 62 763 d sab cn m
a+/-
7894 n nd a i * * *
- i
- a o e s c S e 83 20 3 5 0 s i uf i l r 5 480 64 2 lt t
a ai aa 2 1 u r c n g u r t e 1 s e
t nei c v r e s s c ol r
e AA i s nh a t
ly s ot c csi a e ays a _
n lphh _
T W a e mu o cp .
R g t ass n _
n O a s .
P i k
ic e v s e v e _
E e 0 00 0 lp a a R i n z 3 47 0 1 91 8 3
1 0
9 u i
t i ab h G
r n a - - - 7 -
5 D gst e u N D *R 020 -
0 9
)
Nteb a e, 1 91 I 0 I d C 1 l 9 8 C n g R 1
) . i O
T n
a D
M D
M oma ri r el e I e ( ze va N c > n O a s o r ot)el l f
r n it e aa M ov a v r r u ie t t r
iaguo nve t
L S ad r n t A trd r e e T n nt s e 0 c n e o e 7 0 0 n,kch t
i t 0 a 0 0 m N E s) e c2 a 33 5 0 4 0 o c
t f
E L nL / n - W *
- 6 W i 2 4
- e e
vat no M
V B iC oi o/ e 03 0 0 g
n 0 9 0
l b
il t
ib n t
t C +e c a
293 0 i 1
4 a s r a O A aP r( cr f 1 1 4 k 1 2
t c po otr R T i
par r 2 n e rd o I
V t
n me S u i r
t e enp e a s D d h um N c SA m t
e r oi e
E n u h gr L o m (wkca a s A C in sb no C n I m im iosi ut G u e t a nra O
i ht t L i t
r ) e tri n mn e e d
O A v ee cd I
D T P) o ct n anlu oc e A b a o r c n A g ) ) le, P s ctnei R
l a
r A A i a, l t
eulpo t 7 e P P vi sb s u lpo c mn 9 n, ,t m e ae 9 v nh m e r al s r a 1 A ) o togu s pe A l t
irlo le s a mivt l l 8 P) e p n 9 , Ate nPS,(
teWC e
m tuat s a lu s o 9
1 w S
( (y (y a s
c( e as ger it a
oay l t n t t et i t
i t
ypi po r n o
n oi o nNe l S
t o l e r r uh t . p l o
i t
p di ro d ah oS h r u t d e dse aCm r t l t s t rDa t n
i r
c i
M( Mui Ah ueA At ar e b a
anMl so b ec o s ( t e en e C e k k r f eWta r r . r D e ee et a 'o t ade r a c oh t n t
=
e r e aleW sd s e e eo vc
)
C CrCWo s r
Wir l v e e u gl nc glpoy n
(
a e nh nst -
r a n amb t ri ak oS t tohgc- ri r a ali s s a n o
ai citcs nu t l t ei e rn d o d wh e e SCSW t SWI t a nn a e nlaioq a ut d it t
a s r st an S e
g a e gatc r a r at s a get n s t o
rl r a
) ) ) ) ) )1 eu vs e e vsincl noesu c n CCC
( ( ( ) CI
( ( ( Ar AUc r idn i
o 1 1
( 23 I t 2 - 1 1 - -
a 5 2 - 5S =
t 3 1 9 -l 91 I )
S AFQJ QGG *
- 1
(
6 O
6 e
e 882 3
- 54.
. e e l
o a g
- en lp t r P 1 - - a rhtet n s
n a m i
oR 4.5 5 01 1 a
s t
nec o u voty t
a l
o o r t r cbi ala t
n e s n
eve o c
l pnq u c y mid o nd o at n it s a r a Cds t l
a u
(
s nt s t
e q nel lp 2 1 26 d
oc u ins m/ 221 n t a e a+ * ** a t r cor s S e 984 s nei l r l t
epy l s aa 1 22 u c u r s nml a t
AA cu i e
r s
oan c s a eye s l l pna t
ly a
n moc a glp i
T r e
a e l sa gDnu i
R t t a uar O a ic t cavce e.
P E W e e
882 lp u g an R g n 3 54 D nd ac n - - - i e G a s sf i N
I i
k *C R 796 1 1 1 C
)
Uuia n
. cg R n )
i r D D o es i
O M M r sl coa c T D (
I N n >
s n
o zh is r
o t
s y O i s n i t e ah M n ie ov ra vh p c
L i o t ad t
n e
it a
gsu o n A t a trd c e s e T r ns t 425 n nes v N 8 e o a O
t ) c2 1 21 c ,ah E E nL n ei vb M L e/
ci o /- * *
- lb e i t
sb t
u 695 e N B nC Cer+e 222 t a ist o a e, O A o c png R
T C (p l pra t e
e mr r i a
I V a me a v d e
hi l ev N t e SA m t
e ca E B u h sl wga el L m r s ra e
(
s i A s in ne C
I o
r m i ovaev o G G e t al h O ht r at n u o t
L e g ) e nt O A v e c nt I ar P) o nan a D e ,A b a oetr A v ) l eP s ct el a o R A A i a, l l
t l up 7 P vi sb u s pc m 9 8 nh
,t e mlai 9
1 9
9 ogu m r e
ace s r itc irl o l o a 1
teWC lp m
a u )t e n s n o
S
( (y (y l t a
s t
ct ai a r ta o i t
t a
ypi r n nt r S n t r po o ont un .
i o uh l o
i t
p ho Stu d
e d oed e ccnde t r
t ueA r s a
s n i
r Atare bak olu o e nc c b c C s e . a en D
e t
eWta r
r d a e r l ablpt i =
a eW Wir l
l sd e
gl u s
e omon r
gd s ae
)
C
(
v e n nsd oh t
n a
ri c
n an r u e ra v n eim t
rois t g t o d o dngal t t i e r nn ak gu t
a SWI t m a s re s ces aNr e S t
gea eb g e r
at s a s .l o t
rl r uCp a O
) ) )1 e vs u e vi nDm i c
i n
o CI
( (
23
( Ar e AmMs a d I
n t 1 - -
a 55 =
t 91 1 )
S QGG *
- I
(
7 6
e g
a
- - - . .= .- :::. s: . . P
/G -
c e
i: . .
i:
1 N
c e
D .= ..
=: ..
i:.
3: .L D
- - - . .= . . ::. $: . .
I
- - - . : . . 3::. :: . . ..
- - - . : . . 3::. i:..
- - - . v .: . .
v o o
- - - . N .: . . > g3 i mg aM N _
r -
I
.: .. 3::.
i:..
t e -
t
.=
i: . ...
i: . .
c 5 d7 t
c a - - - .
O ;=
.=
=
ag8ygg ag fe :
O W )
1 p )
.= . .
3::.
s: . .
i:. ...
i:. .
e e g
- e e g
.= . . 3::. i:
l j p e
c r S r
== . .
3: : .
e:
bS S a a . $:
h
- - - , a =: . . .::. E: . .
c - - - . h . . . .::. i: . .
f s - - - .
I c = . ::. e:. ...
r i D
g u
.i D
s .: . .
i: . .
. g uht f o
A .: . . 3::.
A u
Sn -
d
.i u
3: : .
s: . .
i: . .-
o m - - - I q . . . ;::. i: . .
n a - - . .= . . ;::. ...
iM .i i:.
er -
l u 9 8 L .: . .: : :.
jn 8 S
l
.=&g4
.' O Megg M4w;r
?
t u 9 sy s n
J 9 1
N . J 91 nb w - - - . f o M
.: . . 3::. i: . . f o
ore 1
o -
. h T
- = . .
.= ..
3::.
s: . ...
i: . .
h
\J i D - - - .
n u n t
( .: . . ;::. ;:. . t o .a Jn u Mn t (
- t i - -
. - J M 1
- ;= . .
i:. .
o _
aL 2-1 .: . . :::.
i: .
e: . .s rr t e 1
J n
1 K
n
=: . .
3::.
l: . .
i: . .,.
np o y o . . .
- = . .
- . e: . .
y
- a i t
3::. i: . .
i es i
t a
M a .: . . 3::. a: . .
- a
- - - . t .: . . . ::. i: . .
M cie S t
S .: . . . :. i:..e nru a I
O 3::.
i:..
i: . ...
o c r
p
- = . .
3::.
i: . .
I: . . r Cc o -
A .: . .
3::.
3::.
e: . .
i: . . A p
- - - . : . . 1::. ;: . .
i
. I mP
- - - 3::. i: . .
- - - . r .: . . 3::. a: . .
i u i i
t e
v M
a i
t i
e v
- = . .
og $ mjAM gc M
r a
t s a - - - . s o .: . . ::. =: . .
i p - - - .
I p .: . . ::. s: . .
r (
s n
(
s n
.: . . ;::. =: . ...
T b
.: . . 3::. i: . .
i od e - - - . e od ie .: . . 1::. ;: . .
b t t at r o
- - - . F t t at o .: . . ::. ;: . . e t l - - - .
r t l : . . ;: : . i: . . F 8 np e
cre I
np e
cre
. . . . ::. i:..
9 ne ow
. ne ow
== . .
e:. .
9 c e )o n
a c
e )o i: . .
i:. . n 1 l per - - - .
J l per .: . . :.:. e: . .
J a
m a z, -
m z, a
.: . . ::. I: . .
s ev - - - .
l s e v
. . . :::. ?: . .
l ai ai 0 0 0 0 g0 t t aa t g 0 0 0 0 ua g0 t 0 0 c c e An e0 0 8 06 04 0 0 0 0 An0 0 1 E-1 E
0 0 2 0 1 1
- T T 1 O O e N d 3 k . @ s:8 o._'
i _ N mo] '8 ,m 8o_a. _ r u
g i
F
8 6
e g
a
- P
~
~ . - , . - - - -
~ . - , . - - - - - -
- - - :. a w-r ~ . - , . - - - -
. a w-t e ~
a ' .
- - - . s w-s .
- s w-W l e
p m
~
~
e a ' . - , . - - - - - . a u-c S a
l u
- - - - - :. s s-f s ' .
n r s o
- : a s-u C '
~
- I T: a u- -
Sr e ~
~
gt e d
T ;
- a s-nt i r
~
~
- nt
- io ni np a
~ - - . - - - - -
i ge r . a s-su -
- e e_
nQ
- - - B w_ . - - -
o -
der)o e
.su are iy -
t t
-l o z . - - - - - -
- as Y p e, t b 46 - . - - - - - - .
ar t s 77 s 99 e 0 ei v r t ea
- 1. a s te r
qJ t
r et T 1r 1r79 ee91 n bb3 r 88 wge . -
r a
u C n, o
mmh
. i n e . - - -
nL a e ee t c oc r
b -
- Dev . - -
. s w- Q pvoat Mi er ce Wr SNMO a
e e -
- >is
- snpo t .
a u-np l c
u 67 8 77 7
- i o (s a
au r n t _ - - - - - - -
N ose l s
e m 4
99 1 1 1 r e e r e 9
r
-- n en t
o ar Ci ru t
p A 7bb b ct T a u-m r 9
1 mmm e e - nn . - - - - - -
7:
a i o
a nppa et t -
own c . - - - - - -
e ueee :. a s-mo S MJSSD - l e oc - - -
r -
[e - - - - - -
ui c o t
a 4 77 89 0 6 ym- p . - - - - - - :. a s-iP t ic 7 199 9
1 hh1 1 8 9 9 1 8 -
l ns a .
d i
T r I n
E t
s n
e u v
e JMMJuA c c nar ar np e n l
- o, a
- 6 tu
- 9 c 9 a, l .
- A7 M e s-
- e u-l t
n a
c aaeu t
ng r e -
1 to9 r9 6
k:. e u-a l l i
- i o 1_ . - - - - - -
f ic icdiP c
i n t t c ii r r cBly Pi r n . - - - - - -
i i
S o
CCARb o E
- e s-I- -222 n r r I I I I T - . - - - -
k .
o e
MMMMh TIITC O
N I/ . e s-t .
s
- . x s-i 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 H 0 2
1 0
1 1
0 0
1 0
9 0
8 0
7 0
6 0
5 0
4 0
3 0
2 0
1 i5 k 3co89.n.
i i
0 3
1 e
r u
g i
F
9 6
e s
a e
,L -
c e
- .l e e c
D ;:..
y D
s - - - - ,:.. ;:.. ;:..
l e - - - - i ;:.. ;:.. ;:..,.
p - - - - ;:.. ;:.. ;:..
m
- - - - v ;:..
v
- - - o ;:..
o a - - N ;:.. * %6m N r
S - - -
)
t e l o
r I
e g
a r t
n - - - t c a ;
,. t o -
O h ;-
iu ySgg[ 3g^
O c
C -
c ;
W a i
.s D
i g - - - -
p d p
n
- " S e
.i u
l e
i -
.iq ;:..
S L
k - - - - ,:.. ;:..
n i
S N
s g g ih ;:.. ;:.. _
rt e - - - -
,u M ;:.. ;:.. ;:.. _ u l
p A _ A Don T
( ;:.. ;:.. ;:..
m - -
a I 1 ,.
nMy - - - ,:.. ;:.. ;:..
S - - -
8 1 ,: . ,: :..
i r o
lu 9 K ;
- wm ydg7j{fgwmf lu 9 8
t -
J 9 n ; i w- J 9 .
sb a -
- - 1 o ;:.. ;:.. ;:..
1 nre i d
c -
1 f
h o i t
a f
h o .
ot i n - - - -
n t
n S t
n u n t
i i mU ta L m L-
/ -
i u
J M o n
- ..o
- .. J M o
r r C-p-e 0 -
1 t p 0 n
- - y ;:.. ;:.
2 y
- 0. -
- - a ;:.. ;:.. ;: ..
a ee s 0- ;:.. ;:..
2 -
M ;:.. ;:..
,= M t
ci r )
o n-u-
- - - )
o nu e r i i-t 1
r e
occo e z,
v T-r r -
fo-A r
p z,
e v
A r
p CiP i t
a g
e it m
l i
t a
g e
n, i
- - - - n, ;:.. ;:.. ;:..
m ev I
r -
e -
- r e
v r
u a a i i .
t ,
i t
s a- - - -
M i
t s
o
_ wg ,pC , M i o p W-g-p
(
t (
s n- - - - s ;:.. ;:.. ;:.
i n i 1 n ;:.. ;:.. ;:.
r i o
t k -
i-n r
- i t
o ;:.. ;:.. ;:.
T a b a b r
r t
n D- - - -
F e t n
F e
A-e c P-
- " e c
8 n o E-S
- - I n
o c
9 c e U- - -
- c 9 l pd mte E-T -
n a
ipg m ;,
n a
1 at s o O- - - - J a; s ;o ;:.. ;:.. ;:. J l
N- - -- - p a p l - - t ;:.. ;:.. ;: .
uer t -
ce 0 0 0 0 0 0 0 m,,0 A,0 0 0 0 Aw0 0 0 0 0 5 4 3 2 0
0 0
0 0
0 0
1 E
1 1
- E 0 0 4 nd 1
T T 0 1 1
( O N -
O N
1 6o* *
'b ,,38o n .
e r
3a 88 5 u -
g i
F _
o 7 _
e -
g O
pa c
- - - - - - e
- - - - D r -
t e -
v o
a s N
e W l p
m t
g a -
O c
n S
i i v - - - - -
iu k cn p
i n C S
e r a -
Dhn t - - - - - - - g
- - - - - - - u no -
A iMs y u 8 nb l
9 J 9 o
- - - - - - - 1 i r - - - - - - - . .
f o
e OtrL t
ai t
r
)
o r
e z,
Ju M ht n on ne ep i t
e v
a g
y cs e s e
n e,
- M a
ni r e v - - - - - - -
ou l p
m i
i t
s o
Ce co S a (
p s
n A
r p
r o - - - -
taiP t
o i t
a a r - - - - - - - . .
e i c
t n
e c
. r B d h
n o
c
- M a
s a l.
e
- d- .
s e - - - - - - . .
o wto-l t - -
b e
r l
p- - - - - - -
F m
a e-r - - - - - -
G E c
Aw- .
e-8 T O
n a
9 N - - - - - - - . J 9 -
1 0 1
9 8 7 6 5 4 3 2 1 i
%3. 5 g382o.
O 5 1
e r
u g
i F
o b l l
\
l
. . . . . . . 861nr g . . . . . . .
{
1 c :
8eW I
.Eiii m . . . . . . . . .
261nr ,
, . . . . . . I M ' '
g .
- 16 W 9einc
.Um m l l .' : , : : : 96W
(
g j ! : ! . { { { seinc l
3 o : : : . :
. sew Q .
. 4 t61nr i j
e . . . . . . .
. . . . . . . . . t6 W l
. . . . . . . . . l
.Ym% m .
.C61nr {,
M T b . . .
. . . . . . C6 W l
dv . . .
.E61nr l
g . . . . .
' l
- l l l l l l . 26 W h i
& CU . . . . . . . . . >- '1 g
bTM .
i L61nr WI M V i
g
[ . . . . . . . w W g t
. . . . . . . . L6 W 8 g .
. 2 g . . . . . . . .
. Minr Q . . . . .
g ,]b
. . . . . . . . 06-uvr R : '. .
l 681nr 3
Qu g
. . . . . . . . . 68 W g . . . . . .
(
b ,U : : : . . :
881nr M .O 88 W g g s l l : : : : : . 481nr
] $ . . . . . . . .
g .
ts w
.Em l<
W.
- : 9Binr W t 98 W
@ t . . . . . . . .
j Q h e
sBinc m ,
. gsq M
g . . . . . . . . 781nr y l l l l l l l l t0 W o a v e m w m o O W en 6 6 6 6 6 6 6 os 6
e 6 6
.m (AJp) weJe Jed sepnooo!d m e e
a
.at
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TERRESTRIAL MONITORING Radionuclides released to the atmosphere may deposit on soil and vegetation. They may eventually be incorporated into milk, meat, fruits, vegetables, or other food products. To assess the impact of TMINS operations to humans from the ingestion pathway, primary food product samples such as green leafy vegetables, fruits, grains and milk were collected and analyzed during 1998. '
The ingestion pathway also is normally assessed by collecting and analyzing deer meat samples.
No deer meat samples were analyzed in 1998 because indicator samples were not available.
In addition to edible products, rodent carcasses were analyzed as part of the TMI-2 Post-Defueling Monitored Storage (PDMS) Rodent Collection and Analysis Program. The purpose of this program is to determine if radioactive materials have been transported by the movement of animals from radiologically-controlled areas to unrestricted areas.
l l
O Page 72
l 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT The radiological contribution of TMINS The purpose of the residence and garden operations was determined by comparing the censuses was to locate the nearest residence results of samples collected in prevalent and garden in each of the meteorological downwind locations, primarily to the south sectors, respectively. Only gardens of greater and east of the site, with control samples than 500 square feet producing broad leaf collected from distant or generally upwind vegetation were included in the garden census.
directions. Comparisons with results from The results of the residence and garden previous years also were performed, as censuses are listed in Tables G-2 and G-3 of applicable. Appendix G, respectively.
The analytical results of samples collected The results of these censuses provide a basis during 1998 indicated that there was no for modifying the radiological environmental discernible TMINS contribution to monitoring program and the model used for radioactivity levels in locally-produced food calculating offsite doses. Based on the 1998 products. As expected, Sr-90 was found in land use surveillance, only minor changes to milk and broad leaf vegetable samples. The the dose model were required.
concentrations observed in samples collected near TMINS (indicators) were similar to Sample Collection and Analysis levels observed in samples collected from the I distant sites (controls) and consistent with During 1998, samples of raw cow milk were data from prior years. The presence of Sr-90 collected biweekly from local farmers at one in both indicator and control samples was control and four indicator locations.
attributed to fallout from prior atmospheric Indicator samples were collected at locations nuclear weapon tests. that have a high potential for impact by TMINS operations. These locations generally As part of the REMP, a surveillance was were proximate to TMINS and in dominant performed to identify relevant changes in the wind directions. Conversely, the control use ofland (unrestricted areas) around TMI. station was located greater than 10 miles from This land use surveillance consisted of a dairy TMINS in a non-prevalent wind direction.
census, a garden census and a residence The samples collected at this site should be census. unaffected by operations at TMINS.
The dairy census was performed to determine A gamma isotopic analysis and a low-level the location of the nearest milk animal within 1-131 analysis were performed on each five miles of TMINS in each of the sixteen biweekly milk sample. The biweekly milk meteorological sectors. Prior to 1997, all samples were then composited quarterly by milk animals within five miles of TMINS were station and analyzed for Sr-89 and Sr-90.
included in the dairy census. The results of the 1998 dairy census are listed in Table G-1 Terrestrial vegetation - fmits, grains and of Appendix G. vegetables - were collected when ripe from one indicator and one control garden.
Page 73 O l l
l
r C i998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT Maintained by GPU Nuclear, the indicator measured in the indicator samples were similar garden was located at the TMINS Visitors to those measured in the controls.
Center (Station El-2). The control garden was located at Milton Hershey School (MHS). Strontium analyses were performed on 20 This garden was maintained by MHS students quarterly composite samples. None of the in cooperation with GPU Nuclear. samples contained Sr-89 above the MDC. As expected, Sr-90 was measured in a number of Like indicator milk samples, indicator milk samples. Twelve of sixteen indicator terrestrial vegetation samples were collected samples (75%) and three of four control at a location having a high potential for impact samples (75%) contained Sr-90 above the l
by operations at TMINS. Controls samples MDC.
(
were obtained from a distant site where they l should be unaffected by TMINS operations Strontium-90 concentrations in the indicator samples ranged from 0.67 0.32 pCi/L to 1.7 Tomatoes, cabbages and sweet corn were 0.6 pCi/L and averaged 1.1 0.7 pCi/L.
collected in 1998. All samples were analyzed Similarly, the control samples ranged from for gamma-emitting radionuclides, including 0.80 t 0.44 pCi/L to 1.6 0.6 pCi/L and 1-131. Cabbage samples also were analyzed averaged 1.1 0.9 pCi/L. The Sr-90 for Sr-89 and Sr-90. concentrations measured in 1998 milk samples h)/
\ When available, GPU Nuclear analyzes a were consistent with those measured in 1997 when sample concentrations averaged 1.0 i limited number of rodent carcasses as part of 0.5 pCi/L.
the non-routinc REMP. During 1998, three mice carcasses were analyzed for gamma- The milk collected from Indicator Station emitting radionuclides. No other rodent G2-1, the dairy farm located 1.4 miles carcasses were found in 1998. southeast of TMINS, contained the highest annual average Sr-90 concentration.
Milk Results Strontium-90 above the MDC was detected in three of the four quarterly composite samples.
During 1998,129 biweekly milk samples were The concentrations ranged from 0.7210.47 collected and analyzed. One biweekly pCi/L to 1.7 i 0.6 pCi/L and averaged 1.2 i indicator sample was unavailable due to an 0.9 pCi/L. Milk samples collected in 1998 oversight by the dairy farmer. from the other farms had similar Sr-90 concentrations. Additionally, the milk lodine-131 was not detected above the samples collected in previous years from this minimum detectable concentration (MDC) in and other dairy farms contained similar Sr-90 any of the milk samples. Gamma isotopic concentrations, analyses yielded only naturally-occurring potassium-40 (K-40). It was detected in all The results indicated that the Sr-90 measured 1998 milk samples. The K-40 concentrations in the 1998 milk samples was unrelated to operations at TMINS. Its presence in this O
(Vl l Page 74
1 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING RE1DRT medium was primarily due to the transfer of vegetables (cabbages) contained Sr-89 above this long-lived fallout product from soil to the MDC. Low-level Sr-90 was detected animal feed (fresh or stored) to cow to milk. above the MDC in both the indicator and the control sample. The measured concentrations Figure 17 depicts the trends of Sr-90 were 0.0074 0.0021 pCi/g (wet) and 0.0047 concentrations in indicator and control cow 0.0020 pCi/g (wet), respectively. !
milk samples since 1979. The data plotted for 1996 through 1998 were based on actual in previous years, similar Sr-90 cou. entrations sample concentrations because many of the were detected in both indicator and control results were below the MDC. Usin, actual samples. For example,1996 indicator concentrations eliminates biases in the data cabbage samples contained Sr-90 and missing data points on graphs. concentrations which ranged from 0.0043 0.0019 pCi/g (wet) to 0.0071 0.0025 pCi/g As shown on Figure 17, the Sr-90 (wet) and averaged 9.0060 0.0030 pCi/g concentrations have trended downward. This (wet). The 1997 indicator sample contained decrease is directly related to the cessation of Sr-90 at a concentration of 0.0044 0.0028 atmospheric nuclear weapon testing and the pCi/g (wet). This radionuclide also was radioactive decay and depletion of both measured in the 1996 control sample at a atmospheric and terrestrial Sr-90 associated concentration of 0.0043 0.0021 pCi/g (wet).
with prior weapon testing.
As in previous yeau, the data indicated that Terrestrial Venetation Results the Sr-90 measured in the 1998 cabbage samples was attributed to fallout from prior A total of six terrestrial vegetation samples - nuclear weapon tests and, therefore, was broad leaf vegetables (cabbages), fruits unrelated to operations at TMINS. The (tomatoes) and grains (sweet corn) - were detection of Sr.90 was not unexpected collected and analyzed in 1998. Red beets, a because measurable amounts of this long-lived root vegetable, are normally collected and fallout product are still present in the analyzed as part of the REMP. None were terrestrial environment. Additionally, analyzed in 1998 because the indicator cabbages have a tendency to absorb Sr-90 samples did not mature. residing in the soil.
Naturally-occurring K-40 was measured in all Rodent Results terrestrial vegetation samples. No gamma-emitting radionuclides (including I-131) During 1998, three rodent carcasses were attributable to TMINS operations were analyzed for gamma-emitting radionuclides.
detected above the MDC. All three rodents were mice. Two of the mice I l
were found in the TMI-l Plant Preservation Strontium may be incorporated into plants by Lunchroom, a restricted, but radiologically either uptake from soil or direct deposition on ' clean' area. The third mouse was obtained foliar surfaces. In 1998, none of the leafy I Page 75 O
- r. .n
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT from Building .222, an unrestricted area of TMINS.
Gamma-emitting, reactor-related materials were not identified in two of the three carcasses. One of the carcasses found in the TMI-l Plant Preservation Lunchroom contained Cs-137, a radioactive material that may be due to TMINS and/or fallout from prior weapon tests.
Since the source of the Cs-137 is unknown, no definitive conclusion can be made on whether radioactive materials are being transported by rodents. However, since the rodent collection and analysis program began, only one of the carcasses collected from either restricted, radiologically ' clean' rr'as or unrestricted areas have contained radioactive
,O materials attributable to TMINS operations.
V The data suggest that rodents are not transporting radioactive materials to unrestricted areas.
A pest control program is in place at TMINS.
This program minimizes the potential for rodents to transport radioactive materials to unrestricted areas.
\
Page 76
n e
g O . - - - - - -
ea t
s . - - - - .
s e 08 - - - - - .
T 9 . - - - - -
8 u-k l
n 1r e e n
a bo i e t - - - - - .
W c O
- - - - - - - '. k u-M s l
r a
e c 8 u 7
- 8 u-e - - - . -
w lp N. 91 . - - - - . -
o m r . - - - - . - .
e m A t
b - - - - - - -
8 u-a - -
C r m . - - - - -
o e S i a ce
' E u-o M D l
n t
r . - - - - - -
i n 9 - - - - - - -
o 7 0 6 9 8 8 8 u-s C 1 9 9 nre 1
t s h1 c l r ei r n anp . - - - - .
e u . - - - - -
i ot r E t
v n
MJ A -
- 8 u-t a a e - - - - - .
au c g - -
r - - - .
- 5 u-i f
u i
n hP - - - - .
trQ ig cB1y c _ - - - - .
S - - - - - -
A R a.
ny 22- -
I I m
- 1 8 u- a e
r eb m "IM6 C .
Y Ocr 8 u-nt e - - r t
e r
d a oi L C E
'tt o
- . 8 u-Q u
Cr e D e'l M l'pe p
0p > amir - - - - - . E u-s s'w 9- s e s nl oao it ur
) -
e at r ce - -
8 u-mi l
r p n a,i t
'e - - - - - -
ucu m e6 c9i v a n9 o
t a
g
. $ u-io S c 1' n' e - - - - - - -
t c r e o l p ig'n, - - - - r - -
niP t a
i n'e wiv
. E u-o ni i
c s n'i t
s . - - - - - -
yigo t
r d I
n l
nep o, B (s 8 u-n S 6 .
9 9
d o ed - - - - - - - -
t' a t
1 r - - - - - . - 8 u-l ot a ol Pd _ - - - - - - -
t i . - - - - - -
r orecn i
c ie r P W'c o
. E u-r E l
~
t o T O
N
~
~
~
8 u-i s ~
~
~
- R s-H 0 1
9 8 7 6 5 4 3 2 1 0 m2.QGo gC2oo2n.
O 7
1 e
r u
g i
F r
un R@l0 LOGICAL ENVIRONMENTAL MONITORING REPORT GROUNDWATER MONITORING Three Mile Island (TMI) is located in the Triassic lowland of Pennsylvania, a region often referred to as the Gettysburg Basin. The Island was formed as a result of fluvial deposition by the Susquehanna River.
. It is composed of sub-rounded to rounded sand and gravel, containing varying amounts of silt and clay.
Soil depths on TMI vary from approximately six feet at the south end to about 30 feet at the center. The site is underlain by Gettysburg shale that lies at an elevation of approximately 277 feet (Refs. 31 and 32).
The Island has two different water-bearing zones.
One is composed of the soils overlying the Gettysburg shale (bedrock). The other is the bedrock. Relative to the natural soils, the movement of groundwater is much quicker in the bedrock. Groundwater from TMI migrates to the Susquehanna River, but does not impact onshore groundwater supplies. The migration of TMI groundwater to onshore supplies is prevented by the higher levels and the opposing flows of groundwater that exist beneath the surrounding terrain on the opposite sides of the Susquehanna River. The estimated travel time for groundwater to reach the river from the central portion of TMI is approximately 12 years (Ref. 48).
O Pege 78
d 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REEDRT A groundwater monitoring program (GMP) The 1998 TMINS GMP results indicated that was initiated in 1980 to detect leakage of the concentrations of radioactive materials water, if any, from the TM1-2 Reactor and measured in onsite and offsite groundwater Auxiliary Buildings and outside storage tanks. were too low to have a significant adverse Since 1980, the TMINS GMP has been impact on humans or the environment.
expanded and now monitors activities associated with both TMI-l and TMI-2. As part of the TMINS Groundwater Protection Plan, an aboveground tank During 1998, most of the onsite groundwater monitoring program (ATMP) was established samples contained H-3 above the minimum in 1997. The purpose of the program is to detectable concentration (MDC). The detect tank or component leakage at an early presence of H-3 in these samples was stage so that impacts to the local environment, attributed primarily to routine TMI-l such as soil and groundwater, can be operations and previous TMI-2 operations. minimized.
Additionally, it is possible that a pipe leak may be contributing to elevated levels of H-3 in in 1998, four aboveground tanks were certain onsite wells. In March of 1999, a monitored by collecting and analyzing sponge project was started to repair or replace the and precipitation samples. Periodic pipe ifit was found to be leaking. inspections also were performed at one of the tanks. No discernible tank or component Tritium above the MDC was detected in 3 of leakage was identified in 1998.
8 offsite groundwater samples and 3 of 4 onsite storm water samples. Its presence was Sample Collection and Analysis due to a combination of routine TMI-l l operations, natural production in the In 1998, several changes were made to the atmosphere and fallout from prior nuclear TMINS GMP. Collection and analysis of weapon tests. surface water from Station EDCB (an onsite, storm water collection basin) and All H-3 concentrations measured in the grcundwater from onsite Station MS-20 wru groundwater collected from the onsite stations reestablished. A sediment sample from were below the USNRC 10 CFR 20 effluent Station EDCB was collected and analyzed in concentration limit. Additionally, the onsite the fall. Onsite, groundwater Station OS-18 and offsite groundwater used for drinking and offsite, groundwater Stations A2-2, Dl-4, contained H-3 at concentrations that were J3-3, Ki-6, L1-3 and Ll-4 were added. A 1 wel' below the USEPA Primary Drinking few special groundwater samples - onsite, Water Standard of 20,000 pCi/L. Stations AIT and MS were collected and analyzed. Groundwater from onsite Station None of the groundwater samples collected in RW-2 was not collected and analyzed.
1998 contained Sr-90 or gamma-emitting Finally, the collection frequency for onsite, radionuclides related to TMINS operations. groundwater Stations MS-22, OSF and RW-1 The same can be said for storm water and was reduced from monthly to quarterly. The sediment collected from Station EDCB.
Page 79 O
O
) 1998 RADIOLOGICAL ENVIRONMENTAL MON 110 RING REEDRT changes are discussed further in Appendix C. gamma-emitting radionuclides and some were combined into annual composites and Groundwater from 20 onsite and 8 offsite analyzed for Sr-90.
stations were sampled in 1998. Of the 20 onsite, groundwater stations,13 were The monthly storm water samples collected monitoring wells (MS-1, MS-2, MS-4, MS-5, from Station EDCB were combined into MS-7, MS-8, MS-19, MS-20, MS-21, quarterly samples and analyzed for H-3 and MS-22, OS-14, OS-18 and RW-1),2 were gamma-emitting radionuclides. The annual drinking water wells (OSF and 48S),3 were sediment sample collected from this station industrial wells (NW-A, NW-B and NW-C) was analyzed for gamma-emitting and I was a pipe / tunnel where groundwater radionuclides.
occasionally infiltrates (AIT). The other onsite, groundwater station was the TMINS Sponge and precipitation samples were Pretreatment Building clearwell (NW-CW). collected month!y after the first significant Added in 1997, the clearwell is a holding tank precipitation ever.t The precipitation and for the water pumped from the industrial water extracted from the sponges were I wells. All offsite stations (A2-2, Dl-4, El-2, analyzed for H-3.
33-3, Ki-6, L1-3, L1-4 and N2-1) were drinking water wells. Storm water and Groundwater Results p sediment were sampled in 1998 from one
\ onsite station (EDCB). During 1998, H-3 was the only radionuclide consistently detected in samples collected The locations of the onsite groundwater from the onsite monitoring wells, the stations sampled in 1998 are shown on industrial wells and the clearwell. The results Figures J-l and J-2 (Appendix J). Figure J-2 are summarized in Table J-l of Appendix J.
also shows the location of Station EDCB. For comparison, Table J-l also includes 1997 The offsite groundwater stations are depicted station averages. The presence of H-3 in the on Figures 4 and 5 (Radiological samples was attributed primarily to routine Environmental Monitoring). operations at TMI-l and past operations at TMI-2. Additionally, a suspected pipe leak All groundwater samples were collected using may be the source of H-3 in a few of the standard plumbing, a dedicated, in-well onsite groundwater samples. A project was pumping system or a bailing device. Most initiated in March of 1999 to test the line for groundwater stations were sampled either leakage. If the line is found to be leaking, it weekly, monthly, quarterly or annually. A few will be repaired or replac, i were sampled on an as needed basis. Storm water and sediment from Station EDCB were Generally, the H-3 concentrations measured in collected monthly and annually, respectively. most onsite monitoring well samples remained the same or trended downward in 1998.
All groundwater samples collected in 1998 Additionally, the annual average were analyzed for H-3. Some of these concentrations generally were similar to or samples were analyzed individually for below those calculated for the period just Page 80
1998 RADIOLOGICAL ENVIRONMENTAL MONITOR]NG REPORT prior to the operations of the TMI-2 The 1998 MS-22 H-3 concentrations Evaporator (January 1991 through August averaged 3,60019,300 pCi/L and ranged 1993). from 1,200 i 100 pCi/L to 18,000 2,000 pCi/L. For comparison, the 1997 The highest H-3 concentrations were concentrations averaged 4,000 i 13,000 measured in the onsite groundwater samples pCi/L and ranged from 1,300 100 pCi/L to collected from Stations RW-1, MS-22, 30,000 i 3,000 pCi/L.
OS-18, NW-A, NW-B, NW-C and NW-CW.
The concentrations measured in the 1998 The RW-1 well was originally drilled to MS-22 samples were within the expected recover oil from a past pipe leak. After the oil range based on the location of this station.
recovery process was completed, the well was The presence of H-3 in these samples was included in the TMINS GMP to provide attributed to routine airborne releases of H-3 additional monitoring coverage for TMI-l from the TMI-l Station Vent. A portion cf activities and systems (e.g. tanks, components the H-3 detected in the samples collected and pipes). during the beginning part of the year was possibly due to a small spill of BWST water in The 1998 RW-1 H-3 concentrations averaged September of 1997. The spill occurred during 1,100 2,200 pCi/L and ranged from 160
80 pCi/L to 3,400
- 300 pCi/L. For Based on the results of the aboveground tank comparison,1997 concentrations averaged monitoring program, no leakage and, 7,000 21,000 pCi/L and ranged from 490 therefore no contribution from the TMI-l 110 pCi/L to 45,000
- 5,000 pCi/L. BWST or its components was indicated.
1 In the past, the groundwater collected from In August of1998, Station OS-18 was added i RW-1 was impacted by leakage of system to the TMINS GMP. The well was originally components that migrated to the ground near installed to investigate alleged past spills of the well. The decrease noted for the last six photographic waste. It was not sampled for ,
months of 1997 through 1998 was the result several years and was never sampled for of repairing components at the end of 1996. l radioactive materials. The well was added to Most of the H-3 detected in the 1998 RW-1 the TMINS GMP because ofits proximity to samples was due to normal atmospheric two pipes that transport water containing releases of this material from TMI-1. radioactive materials, including H-3. These Monitoring for leakage on a monthly basis will pipes were the last significant potential continue in 1999. unidentified sources of H-3 to the .
groundwater.
Station MS-22 was installed in November of 1996 to monitor the TMI-1 Borated Water The 1998 OS-18 H-3 concentrations averaged Storage Tank (BWST). The station is located 11,000 13,000 pCi/L and ranged from 3,800 near the TMI-l Station Vent, a re! ease point f 400 pCi/L to 31,000 i 4,000 pCi/L. The where the largest emount of airborne H-3 is hi h i dh l ft vented to the environment. , 'g est concentrat ons occurre s on y a er Page 81
i l998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT 1
water was transported in one of the two pipes. of winter, The colder temperatures could lead i The data indicated that there may be a leak in to a frozen hose.
one or both of the lines. A test to determine the integrity of both lines began in March of The H-3 concentrations in water collected '
1999. Like p Wous data, the test results also from NW-A averaged 2,300 i 1,200 pCi/L indicated a leak, but in only one of the pipes. and ranged from 620 100 pCi/L to 3,400 i 300 pCi/L. The concentrations for NW-B Testing to determine the exact location of the were somewhat higher averaging 9,400 pipe leak is ongoing. When the leak location 5,400 pCi/L and ranging from 3,300 i 300 is identified, the pipe will be replaced or pCi/L to 16,000 2,000 pCi/L. The 1997 repaired. No releases are permitted in the results for NW-A and NW-B were similar.
subject pipe until the leak is isolated and ftxed.
The 1998 NW-C H-3 concentrations averaged Industrial Wells NW-A, NW-B and NW-C 56,000 t 76,000 pCi/L and ranged from were installed in the latter part of 1995.
32,00013,000 pCi/L to 230,000 i 20,000 Sampling of these wells was initiated in 1906.
pCi/L. For comparison, the 1997 NW-C Beginning in June of 1997, water from the results averaged 23,000 t 14,000 pCi/L and l mdustrial wells was used to supply water t ranged from 13,000 i 1,000 pCi/L to 37,000 l vious TMI-l systems. Pn,or to this penod'
+ 4,000 pCi/L p]
to ' water used in these systems was obtamed l g
, from the Susquehanna River' The 1998 NW-C H-3 concentrations decreased with time, starting at 66,000 Industrial Wells NW-A and NW-B supplied all service water to the plant durin6 F998. 7,000 pCi/L in August and ending at 32,000 Industrial Well NW-C was turned offin the 3,000 pCA in October. The data collected in latter part of 1997 beccuse ofincreasing H-3 1998 suggested that pumping NW-C on a concentrations. Pumping and sampling of continuous basis shielded or protected NW-A NW-C resumed in August of 1998 to 1) and NW-B from higher levels of H-3.
determine current H-3 concentrations in NW-C well water, 2) determine, if possible, The presence of H-3 in the water collected peak H-3 concentrations in deep aquifers,3) fr m the mdustnal wells was not unexpected reduce, if possible, H-3 concentrations in deep because the wells are located in an area that aquifers and 4) determine the effect on NW-A can be impacted by past TMI-2 operations. A and NW-B well water. Portion of the H-3 detected in the samples also was due to routine TMI-l operations.
The water pumped from NW-C was not used in the plant. Rather, it was sent via hose to a The magnitude of the H-3 concentrations location where it was monitored, diluted and measured in NW-C water, however, was then discharged to the Susquehanna River, higher thm expected. The higher than Pumping and sampling of NW-C was expected results m NW-C along with discontinued in October because of the onset somewhat steady concentrations in NW-A and NW-B suggested that another source of H-3 O Page 82
in8 RADIOLOGICAL ENYlRONMENTAL MONimRING REPORT mcy exist. It is likely that the indicated pipe at TMI-2 (e.g. prior airborne releases from the .
leak discussed above may be affecting the H-3 TMI-2 Evaporator). A portion of the H-3 concentrations found in the industrial well detected in the onsite well water also was water, attributed to natural production in the atmosphere and fallout from prior nuclear All of the H-3 concentrations found in water weapon tests. All of the H-3 concentrations collected from the onsite monitoring wells, the detected in the onsite drinking water were a industrial wells and the clearwell were well small fraction of the USEPA Primary Drinking below the USNRC 10 CFR 20 (Anpendix B, Water Standard of 20,000 pCi/L.
Table 2) effluent concentration of 1,000,000 pCi/L. A conservative dose estimate was performed !
I assuming that a TMINS employee drank OSF Tritium also was measured in the water water at the 1998 average H-3 concentration collected from the two onsite drinking water for one working year. The maximum wells, Stations 48S and OSF. In 1997, the hypothetical whole body dose would be well at Station 48S was established as the .0.0095 mrein. This calculated dose is primary source for drinking water on TMINS. equivalent to 0.0032% of the whole body To a lesser extent, water from the OSF well dose that an individual living in the TMI area also was used for drinking. Occasionally, receives each year from natural background water from this well also was used to supply radiation (300 mrem).
water for various TMI-l systems.
Offsite groundwater samples were collected The 1998 48S H-3 concentrations averaged annually from eight locations. Six of these 280 170 pCi/L and ranged from 200 80 locations were added to the TMINS GMP in pCi/L to 380 70 pCi/L. The concentrations 1998. Tritium above the minimum detectable measured in 1998 were consistent with those concentration (MDC) was detected in three of measured in 1997 (Table J-1). The 1997 48S the eight samples. The H-3 concentrations H-3 concentrations averaged 220 110 pCi/L ranged from 140 60 pCi/L to 180 i 80 and ranged from 180 i 80 pCi/L to 300 i 100 pCi/L and averaged 160 40 pCi/L.
pCi/L.
The concentrations were similar to those The 1998 OSF H-3 concentrations averaged detected in 1998 control surface water 520 i 160 pCi/L and ranged from 410 90 samples. Therefore, the H-3 detected in the pCi/L to 670 i 100 pCi/L. As shown on 1998 offsite groundwater samples was Table J-1, the 1998 OSF concentrations were attributed primarily to natural production in somewhat lower than those reported in 1997, the atmosphere and fallout from prior nuclear weapon tests. It also is possible that a small j The H-3 detected in the 1998 onsite drinking portion of H-3 was due to routine operations !
water samples was attributed primarily to at TMI-l (e.g. routine airborne releases). I routine operations at TMI-l (e.g. routine Like the onsite groundwater used for airborne releases) and possibly past operations drinking, all of the H-3 concentrations detected in the offsite groundwater were a Page 83 O
I i
\ 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT small fraction of the USEPA Primary Drinking reactor-produced, gamma-emitting Water Standard of 20,000 pCi/L. radionuclides were detected above the MDC.
The Cs-137 concentration was 0.18 0.03 Some of the 1998 groundwater samples pCi/g (dry). Since the fall control sediment (individual or composite) were analyzed for sample contained a similar concentration (0.19 Sr-90 and/or gamn,a-emitting radionuclides. t o.03 pCi/g, dry), the Cs-137 measured in None were found to contain detectable Sr-90 the sample collected from Station EDCB was or gamma-emitting radionuclides related to most likely due to fallout from previous TMINS operations. Naturally-occurring weapon tests and not TMINS operations.
potassium-40 (K-40) was found in one onsite sample.
Storm Water and EDCB Sediment Results Storm water from Station EDCB, an onsite collection basin, was collected monthly. The monthly samples were then combined into quarterly samples and analyzed for H-3 and gamma-emitting radionuclides.
Gamma-emitting radionuclides above the MDC were not detected. Three of the four quarterly samples contained H-3 above the MDC. The concentrations averaged 280 i 250 pCi/L and ranged from 130 i 70 pCi/L to 360190 pCi/L. Since these concentrations were higher than those typically measured control surface water, a portion of H-3 detected in the 1998 storm water was attributed to routine operations at TMI-l (e.g.
routine airborne releases). A portion of the H-3 also was due to natural production in the atmosphere and fallout from prior nuclear weapon tests.
A sediment sample from Station EDCB was collected in the fall and analyzed for gamma-emitting radionuclides Naturally-occurring Be-7, K-40, Ra-226 and thorium-232 (Th.
232) as well as fallout and/or reactor-produced Cs-137 were identified. No other
~
Page 84
1998 RADIOLOGICAL ENVIRONMENTAL MONimRING RELY)RT RADIOLOGICAL IMPACT OF TMINS OPERATIONS I
i An assessment of potential radiological impact j indicated that radiation doses to the public from 1998 operations at TMINS were well below all applicable regulatory limits and were significantly less than doses received from natural sources of )
radiation. The 1998 whole body dose potentially received by an assumed maximum exposed individual from TMI-l and TMI-2 liquid and airborne effluents was conservatively calculated to be about 0.0429 mrem. This dose is equivalent to 0.0143% of the dose that an individual living in the TMI area receives each year from natural background radiation.
The 1998 whole body dose to the surrounding population from TMI-l and TMI-2 liquid and airbome effluents was calculated to be 7.77 person-rem. This is equivalent to 0.00118% of the dose that the total population living within 50 miles of TMI receives each year from natural background radiation. l I
I O Page 85
I 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REIDRT Determination of Radiation Doses to the predicts doses that are higher than actual doses Public received by people.
Dose assessments can be performed by using The type and amount of radioactivity released either emuent data and an environmental from TMINS is calculated using measurements transport model or environmental sample data. from effluent radiation instruments and eBuent !
To the extent possible, doses to the public are sample analyses. Once released, the dispersion based on the direct measurement ofdose rates of radionuclides in the environment is readily 1 from extemal sources and the measurement of determined by computer modeling. Airbome j radionuclide concentrations in environmental releases are diluted and canied away from the media which may contribute to an internal dose site by atmospheric diffusion which continuously ofradiation. Thermoluminescent dosimeters acts to disperse radioactivity. Variables which (TLDs) positioned in the environment around affect atmospheric dispersion include wind ,
TMINS provide measurements to determine speed, temperature at different elevations, I external radiation doses to humans. Samples of terrain, and shift in wind direction. A weather !
air, water and food products are used to station on the north end of TM1 is linked to a determine intemal doses, computer terminal that permanently records the meteorological data. Computer models also are The quantity of radioactive materials released used to predict the downstream dilution and during normal operations are typically too small travel times for liquid releases into the to be measured once distributed in the offsite Susquehanna River. Actual monthly environment. Therefore, the potential offsite Susquehanna River flows are obtained from doses are more effectively calculated for TMINS GPU Genuation, Inc. at the York Haven operations using a computerized model that Hydroelectric Station.
predicts concentrations ofradioactive materials in the environment and subsequent radiation The human exposure pathways also are included doses based on measured emuents. Another in the model and are depicted in Figure 18. The reason for using effluent data and a transport exposure pathways considered for the discharge model is that environmental sampling data ofTMINS liquid effluents are consumption of cannot provide enough information to calculate drinkmg water and fish, and shoreline exposure.
population doses. The exposure pathways considered for the discharge ofTMINS airbome emuents are GPU Nuclear calculates doses using an plume exposure, inhalation, cow milk advanced " class A" dispersion model. This consumption, goat milk consumption, fmit and model incorporates the guidelines and vegetable consumption, meat consumption and l methodology set forth by the USNRC in land deposition.
Regulatory Guide 1.109. Due to the conservative assumptions that are used in the Numerous data files are used in the calculations model, the calculated doses are generally higher that describe the area around TMI in terms of than the doses based on actual environmental population distribution and foodstuffs sample concentrations. Therefore, the model production. Data files include such information .
as the distance from the plant stack to the site Page 86 9l
b 1998 RAlbl0 LOGICAL ENVIRONMENTAL MONIH] RING REPORT boundary in each sector, the population pounds ofleafy vegetables,1389 pounds of non-groupings, milk cows, milk goats, gardens of leafy vegetables and fmits and 243 pounds of more than 500 square feet, meat animals, meat produced at the locations with the highest downstrearn drinking water users, and crop predicted radionuclide concentrations.
yields. Consumption ofgoat milk is not included, since this exposure pathway does not currently exist.
When determining the dose to humans, it is Doses to the population within 50 miles ofTMI necessary to consider all applicable pathways for airbome effluents and the entire population and all exposed tissues, summing the dose from using Susquehanna River water downstream of each to provide the total dose for each organ as the plant also are calculated.
well as the whole body from a given radionuclide. Dose calculations involve Results of Dose Calculations determining the energy absorbed per unit mass in the various tissues. Thus, for radionuclides The maximum hypothetical doses due to 1998 taken into the body, the metabolism of the TMI-l and TM1-2 liquid and airbome efiluents radionuclide in the body must be known along are summanzed in Tables 9 and 10. Table 9 with the physical characteristics of the nuclide compares the calculated maximum hypothetical such as energies, types of radiations emitted and individual doses to the USNRC 10 CFR 50 half-life. The dose assessment model also App. I guidelines. This table also compares the i
contains dose conversion factors for the calculated doses (to an individual of the public) q radionuclides for each of four age groups from effluents and direct radiation to USEPA 40 (adults, teenagers, children and infants) and eight CFR 190 dose limits.
organs (total body, thyroid, liver, skin, kidney, lung, bone and GI tract). Table 10 presents the maximum hypothetical whole body doses to an individual and the total Doses are calcula:ed for what is termed the population from 1998 TMINS effluents (i.e.
" maximum hypotheticalindividual" This TM1-1 and TM1-2 liquid and airborne effluents individual is assumed to be affected by the combined). For airbome releases, population conoined maxunum environmental doses are calculated for all people living within concentrations wherever they occur. For liquid 50 miles ofTMINS. For liquid releases, releases, the maximum hypothetical individual population doses are calculated for all people would consume 193 gallons of Susquehanna using Susquehanna River water downstream of River water per year from the first downstream TMINS. The maximumindividual and drinkmg water supplier, eat 46 pounds of fish population whole body doses presented in Table each year that reside in the plant discharge area 10 are compared to the doses received from and stand 67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> per year on the shoreline natural background radiation.
influenced by the plant discharge. For airborne releases, the maximum hypothetical individual As shown in Table 9, the doses calculated for would live at the location of highest radionuclide 1998 operations at TMINS were well below the concentration for inhalation and direct plume Federal dose limits (USEPA 40 CFR 190) and exposure. Additionally, this individual each year the guidelines of USNRC 10 CFR 50 App.1.
A would consume 106 gallons ofcow milk,141 This conclusion was supported by radionuclide Page 87
l l
1 l998 RADIOLOGICAL ENVIRONMENTAL MONITORING RE19RT concentrations detected in actual environmental Appendix I of this report contains a more samples. detailed discussion of these dose calculations. !
l l
Doses from natural background radiation in conclusion, radioactive materials related to j provide a baseline for assessing the potential TMINS operations were detected in i public health significance of radioactive emuents. environmental samples, but the measured Natural background radiation from cosmic, concentrations were low and consistent with ,
terrestrial and natural radionuclides in the human measured emuents. The environmental body (not including radon), averages about 100 sample results verified that the doses received mrem /yr. Additionally, the average individual by the public from TMINS emuents in 1998 !
living in the United States receives an annual were well below applicable dose limits and !
dose of about 2,400 mrem to the lung from only a small fraction of the doses received natural radon gas. This lung dose is considered from natural background radiation.
to be equivalent to a whole (or total) body dose Additionally, the results indicated that there of 200 mrem (Ref. 29). Therefore, the average was no permanent buildup of radioactive i person in the United States receives a whole materials in the environment and no increase l body dose of about 300 mrem /yr from natural in background radiation levels. I background radiation sources. ]
Therefore, based on the results of the j As shown on Table 10, the hypothetical radiological environmental monitoring j maximum whole body dose potentially program (REMP) and the doses calculated j received by an individual from 1998 TM1-1 from measured emuents, TMINS operations and TMI-2 liquid and airborne emuents in 1998 did not have any adverse effects on combined was conservatively calculated to be the health of the public or on the environment j 4.29E-2 mrem. This dose is equivalent to 1.43E-2 percent of the dose that an individual living in the TM1 area receives each year from natural background radiation (300 mrem).
The hypothetical maximum whole body dose i to the surrounding population from all 1998 j TMI-l and TMI-2 liquid and airborne {
emuents was calculated to be 7.77E+0 I person-rem. This dose is equivalent to j 1.18E-3 percent of the whole body dose that !
the total population in the TMI area receives each year from natural background radiation.
The low doses calculated for 1998 TMINS operations were the result of efforts by GPU Nuclear to maintain releases "as low as reasonably achievable"(ALARA).
Page 88 i
D U 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE 9 Calculated Maximum flypothetical Doses to an Individual from 1998 TMI-I and TMI-2 Liquid and Airborne Emuents Maximum Hypothetical Doses To An Individual USNRC to CFR 50 APP. I Calculated Dose Guidelines (mrem /yr)
(mrem /tr) TMI-l TMI-2 From Radionuclides 3 total body, or 3.25E-2 8.30E-4 in Liquid Releases 10 any organ 4.52E-2 1.31 E-3 From Radionuclides in 5 total body, or 5.33 E-5 0 Airborne Releases (Noble Gases) 15 skin 1.02E-4 0 From Radionuclides in Airborne 15 any organ 9.66E-3 1.30E-4 Releases (todines, Tritium and Particulates)
USEPA Calculated Dose 40 CFR 190 (mrem /)r)
Limits TMI-I and TMI-2 (m rem /vr) Combined
- Total from Site 75 thyroid 3.79E-l 25 total body 4.17E-1 or other organs
- This sums together TMI-I and TMI 2 maximum doses regardless of age group for different pathways.
The combined doses also include a calculated dose due to direct radiation from TMINS. The direct radiation dose is calculated from emironmental TLD data. For 1998, the direct radiation dose from TMINS operations was 3.61E-1 mrem. This was based on a maximum net fenceline dose rate of 3.94E+0 mrem /std month and a shoreline /fenceline occupancy factor of 67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> (Regulatory Guide 1.109). Therefore, the maximum potenaal dose (to any organ or the total body) from TMI-l and TMI-2 efIluents and direct radiation combined was 4.17E-1 mrem.
b t
Page 89
1 l
[
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE 10 1
Calculated Whole Body Doses to the Maximum Individual and the )
Population from 1998 TMI-1 and TMI-2 Liquid and Airborne Emuents l Calculated Maximum Individual Whole Body Dose (mrem /yr)
TMI-1 TMI-2 From Radionuclides in Liquid Releases 3.25E-2 8.30E 4 From Radionuclides in Airborne Releases 5.33E-5 0 l (Noble Gases) l From Radionuclides In Airbome Releases 9.35E-3 1.30E-4 (lodines, Tritium and Particulates)
Individual Whole Body Dose Due to TMI-1 and TMI-2 Operations: 129E-2 mrem /vr O
Individual Whole Body Dose Due to Natural Background Radiation: 3.00E+2 mrem /vr Calculated Population Whole Body Dose (person-rem /yr)
TMI-1 TMI-2 From Radionuclides in Liquid Releases 7.31E+0 6.48E-4 (Downstream Susquehanna River Water Users)
From Radionuchdes in Airbome Releases 4.50E-1 9.07E-3 (Population within 50 Mile Radius of TMINS)
Population Whole Body Dose Due to TMI-1 and TMI-2 Operations: 7.77E+0 person-rem /vr Population Whole Body Dose Due to Natural Background Radiation: 6.60E+4 person-rem /vr Page 90 O
Figure 18 Exposure Pathways For Radionuclides Routinely Released From TMINS
,v \ ,-
3( // )
Al RNE P EXPOS E A REL ES ANIMALS HALAT (MILK, MEAT) ggggy E
'T --
2 '- "db PEOPLE ..
N N .
.s REL S l
B i'i BY y R R CONS D IN 9 FISH IX % 9
\
Y /
PREDOMINANT RADIONUCLIDES NOBLE GASES (Xe,Kr) ACTIVATION PRODUCTS (Co 60, Mn-54)
Plume exposure Shoreline exposure RADIOIODINES (I-131, I 133) RADIOCESIUMS (Cs-134, Os-137)
Inhalation and consumption of milk, Shoreline exposure and consumption of milk, water, fruits, and vegetables meat, fish, water, fruits, and vegetables RADIOSTRONTIUMS (Sr-89, Sr 90) TRITIUM (H-3) s Consumption of milk, meat, Inhalation and censtimption of water, fruits, and vegetables milk, fruits, and vegetables Page 91
i 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REEY)RT 1
REFERENCES l
- 1. Three Mile Island Nuclear Station, Unit 1, Technical Specifications, DPR 50.
{
1
- 2. Three Mile Island Nuclear Station, Unit 2, PDMS Technical l Specifications, DPR 73. !
1
- 3. Radiation Management Corporation. "Three Mile Island Nuclear Station, Preoperational Radiological Environmental Monitoring Program, January 1,1974 - June 5,1974."
l RMC-TR-75-17, January 1975. 1
- 4. Radiation Management Corporation. " Radiological l Environmental Monitoring Report for the Three Mile Island Nuclear Station, First Operational Period, June 5 through December 31,1974." RMC-TR-75-02, February 1975.
- 5. Radiation Management Corporation. " Radiological Environmental Monitoring Report for the Three Mile Island Nuclear Station." RMC-TR-75-13, August 1975.
- 6. Radiation Management Corporation. " Radiological Environmental Monitoring Report for the Three Mile Island Nuclear Station,1975 Semi-annual Report II, July 1 through December 31." RMC-TR-76-01, February 1976.
- 7. Radiation Management Corporation. " Radiological Environmental Monitoring Report for the Three Mile Island Nuclear Station,1976 Annual Report, January 1 through December 31." RMC-TR-77-01, March 1977.
- 8. Teledyne isotopes. " Metropolitan Edison Company, Radiological Environmental Monitoring Report,1977 Annual ,
Report, January I through December 31." IWL-5990-427, 1978.
O Page 92
l l
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT l
l
- 9. Teledyne Isotopes. " Metropolitan Edison 20. GPU Nuclear Corporation. "1989 Annual Company, Radiological Environmental Radiological Emironmental Monitoring Report Monitoring Report,1978 Annual Report." IWie for the Three Mile Island Nuclear Station." May 5590-443, 1979, 1990.
- 10. Metropolitan Edison Company. "Three Mile 21. GPU Nuc! car Corporation. "1990 Radiological Island Nuclear Station Radiological Environmental Monitoring Report Three Mile Environmental Monitoring Program, Annual Island Nuclear Station." May 1991.
Report for 1979." April 1980. j
- 22. GPU Nuclear Corporation. "1991 Radiological {
l1. Metropolitan Edison Company. "Three Mile Environmental Monitoring Report, Three Mile J island Nuclear Station Radiological Island Nuclear Generating Station." May 1992. l Environmental Monitoring Report,1980 Annual i Report." March 1981. 23. GPU Nuclear Corporation. "1992 Three Mile j Island Nuclear Station, Radiological j
- 12. GPU Nuclear Corporation. "1981 Radiological Environmental Monitoring Report." May 1993. l Emironmental Monitoring Repon for Three Mile l Island Nuclear Generating Station." May 1982. 24. GPU Nuclear Corporation. "1993 Three Mile !
Island Nuclear Station, Radiological !
- 13. GPU Nuclear Corporation. "1982 Radiological Emironmental Monitoring Report." May 1994.
Emironmental Monitoring Report for Three Mile Island Nuclear Generating Station." May 1983. 25. GPU Nuclear Corporation. "1994 Three Mile Island Nuclear Generating Station, Radiological
- 14. GPU Nuclear Corporation. "1983 Radiological Environmental Monitoring Report." May 1995. j Environmental Monitoring Report for Three Mile Island Nuclear Station." May 1984. 26. GPU Nuclear Corporation. "1995 Three Mile Island Nuclear Generating Station, Radiological
- 15. GPU Nuclear Corporation. "1984 Radiological Environmental Monitoring Report." May 1996.
Environmental Monitoring Report for Three Mile Island Nuclear Station." Msy 1985. 27. GPU Nuclear Corporation. "1996 Three Mile Island Nuclear Generating Station, Radiological
- 16. GPU Nuclear Corporation. "1985 Radiological Environmental Monitoring Report." May 1997.
Emiromnental Monitoring Report for Three Mile Island Nuclear Station." May 1986. 28. GPU Nuclear Corporation. "1997 Three Mile Island Nuclear Generating Station, Radiological
- 17. GPU Nuclear Corporation. "1986 Radiological Emironmental Monitoring Report." May 1998.
Environmental Monitoring Report for Three Mile Island Nuclear Station." May 1987. 29. National Council on Radiation Protection and Measurements. Report No. 93. "lonizing Radiation
- 18. GPU Nuclear Corporation. "1987 Radiological Exposure of the Population of the United States."
Emironmental Monitoring Report for Three Mile 1987.
Island Nuclear Station." May 1988.
- 30. CRC Handbook. "Radioecology: Nuclear Energy
- 19. GPU Nuclear Corporation. "1988 Radiological and the Environment." F. Ward Whicker and Environmental Monitoring Report, Three Mile Vincent Schultz, Volume I,1982.
Island Nuclear Station." May 1989.
Page 93 O
i
\ 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT
- 31. GPU Nuclear Corporation. " Final Safety Analysis 41. National Council on Radiation Protection and Report, Three Mile Island Nuclear Station, Unit Measurements. Report No. 62. " Tritium in the 1." 1994. Emironment." March 1979.
- 32. GPU Nuclear Corporation. " Post-Defueling 42. United States Nuclear Regulatory Commission Monitored Storage Safety Analysis Report, Three Branch Technical Position. "An Acceptable Mile Island Nuclear Station, Unit 2." 1993. Radiological Environmental Monitoring Program." Resision I, November 1979.
- 33. GPU Generation,Inc. " York Haven Monthly Hydro Report." January 1998 - December 1998. 43. United States Nuclear Regulatony Commission Regulatory Guide 4.15. " Quality Assurance Er
- 34. 1990 Census Information provided by The Radiological Monitoring Programs (Normal Pennsylvania State Data Center. Operations)- Elliuent Streams and the Environment." Revision 1, Febmary 1979.
- 35. National Climatic Data Center. " Preliminary Local Climatological Data,1998 Middletown, 44. American National Standards Institute, Inc.
Pennsylvania". " Performance, Testing and Procedural Specifications for Thermoluminescence
- 36. National Council on Radiation Protection and Dosimetry." ANSI N545-1975 Measurements. Report No. 22. " Maximum Permissible Body Burdens and Maximum 45. United States Nuclear Regulatory Commission.
Permissible Concentrations of Radionuclides in Regulatory Guide 4.13. " Performance, Testing and O)
Air and Water for Occupational Exposure."
(Published as National Bureau of Standards Procedural Specifications for Thermoluminescence Dosimetry: Environmental Applications."
Handbook 69, Issued June 1959, superseding Resision 1, July 1977.
Handbook 52).
- 46. L. F. Toke, B. H. Carson, G. G. Baker, M. H.
- 37. I.iternational Commission on Radiological McBride. " Performance Testing of the Protection. Publication 2. " Report of Committec 11 Environmental TLD System for the Three Mile on Permissible Dose for huernal Radiation Island Nuclear Station." Health Physics Vol. 46, (1959)," with 1962 Supplement issued in ICRP No. 5 (May), pp.1013 - 1020,1984.
Publication 6; Publication 9, " Recommendations .
on Radiation Exposure," (1965); ICRP Publication 47. United States Nuclear Regulatory Commission.
7 (1965), amphfying specific recommendations of NUREG-0683. " Final Programmatic Publication 9 concerning environmental Environmental Impact Statement Related to monitoring; and ICRP Publication 26 (1977). Decontamination and Disposal of Radioactive Wastes Resulting from March 28,1979 Accident
- 38. Federal Radiation Council. Report No.1. Three Mile Island Nuclear Station, Unit 2."
" Background Material for the Development of Docket No. 50-320, March 1981. I Radiation Protection Standards." May 13,1960.
- 48. Ground / Wales Technology, Inc. "Hydrogeological
- 39. National Council on Radiation Protection and Investigation, Three Mile Island Nuclear Station, Measurements. Report No. I16. " Limitation of Londonderry Township, Pennsylvania." December Exposure to lonizing Radiation." March 1993. 1981.
- 40. GPU Nuclear Corporation. "Three Mile Island Nuclear Generating Station Offsite Dose Calculation Manual (ODCM)." 6610-PLN- j 4200.01, Rev. I1. !
\
Page 94 4
O un umotocicn esviaosuesra nosironiso nenar I
i 1
APPENDIX A 1998 REMP Sampling Locations and Descriptions, Synopsis of REMP,
""d sampiing O and Analysis Exceptions 1
1 O Page Al
I ll 1 1 b
(
l e
v o
a 2
A e
g O
l a a ft P u
o p
d I y a M e o h
s d #.
i d R r
T. r i
t n
o e
H.
db i
u iq s e
g a
e a t e
l a Z S
t e S o d r s tr Nt I d n e dS a ht al ol Mn 0
)
8 a e n I RM i
Tef r 3
9 W wM r e e h r n 2 e
9 to T. ledn dt af d w t rh s e lia n o 1
et iv or l
- d g
Meu Ro o. . r a l t
e Roun o
s RN i r d ny nee e - eS d d ) ( t h n te INI s
n a o BI ) avh u i d ) .tet o o
nt d . s ear s H o gM M R d erbeiat nt n a
h ce 3
8 H.h noM r T t
e H 4. .
tot h T.e en i M. n o
i T t a e uj a n2 wet fi e N e. k Re u laHer oba H. B.e d
e e mk al d k
e e
t hb u R c qd t poi rker E.S d oa o otutaod dl k O
P L o s a ue S c t
e R lef nd o S,d pI Hci h e l
d o
l l
s o AWf ot s i
d n oi o Wdec oufrd l
l n o gl r seo f r aRS (
n w
a i k d
e CateV fMek o r in fne ai todf p h o ynt oMfSWy ca. L, e o adNt t
o rS 00 E oc trf h re imt e if Li pc t o r L d h e npo(
R l p
1 MWitnaMi r a k x gt.inon T.
t
. r e (of ooh si nJt nuea cruhra)0
. ff eNon a g1 nd O ,R d1 e oRdNw o n5 s r ngooL lea 4 Ct sRf tot G TnMu ateEPe r.
-- nr 4 o oe o an a o2 m ii4 s e N f o ogtyt ecee S et r e e pd t loi nadi G te al nte gw@Cf n onL h ni ah dll o. a nR c eGdResnok s t r e oin c I a iipnn e l
- o ol i
udi c t i
e n nl le uo ge l
r e oigoinPd si t
cl .
. a R S _
d ur at r tr t ih s utr n f i. ri t e u ud mHaRi s . r t n B gV l la-
.t oS arSShgB o u eb a- li Ruid t
O t .
- taBai s r g e d nl - ne P-. hi<d nrMK . N's iaHe l
oi m l at eei rNS L M gB id u r rL erfa T
a tr u obi r unt t nt t to t
. mgto nt t lof nI loMBr iumHrHr gt ege a fnotrTMSwVinkl f
I N r Doc a oa aa lo to t nt t t t nt t e a ee e
- a s c o a aa oaTrf nnnn naet eee a
g s ets ts ts teea aceteeei aoa t t ac t otaat loio e O o foc e a e aaa ee oaiRiiiiie eefffffffi s s t
tsRint i DiRinhiii t
o t s s s teee e eta tee ee s s s ta lai ts M P r h et sRiiiiio s ts ts tss fffffffEEEEEEE oooooI t
oooooo fffff s s s -
afffffff S c oooooooiRiinio k o t
s s s s s t f L g oooooooNNNNNNNEEEEEl ol NNNNNNNoooooo l c l EEEEEEEffffffE l
S A
T 1 n NNNNNNNNNNNNNNNNNNNADAEEEEEEEEEEEEEE O
i N
E A r o
M E i t
N L n ht B o u O a R A M hz '
c545533 85 568681 2221 1854828 403535358361 6 71 I
V T l a A 33 2235444 - - 7676766999988 1 t
N n E e _
L m A n
- e C
I o r
r p
a im G i v
t s 5326531 648984.1 7365 2 2661 7 2.9.4 2 1 9685 _
O n i
D 001 22480001 49 1 001 47 -0 -
0001 1 5 1 001 1 460 0 _
L E O
I l D a c
A i g
R o 8 l 9 o y M 9 i d ay 6 35 7 482 I 7 6 3 62 3 794 1
a MB 1 I I 1 5 904 344 221 I43 1 46 1 I 51 1 11 446 - -
3 869 1 $2 3 1 709 481 1 1031840 1 462 R
I S
N I
M T 1 2 l
o l
o r 1 n e 3421 21 3I 241 1 - - t1 - 241 21- --
iod t o lAAAAAAABDBBBBBCCCCCC l 2335 9I-I -I 25 - -1 00 1 21 l I1258
- - - - n 1 tro -
ol I 1 2261 - I- 22571 r
CDDDDDDDEEEEEEF 5 24231 1 1-l t
S aC P
J W
e a G.
m D D O
l p
um s e 1 l J
I SMa S A. A F D A.
Q D WPW DDDD AIDDDPDDDDD AQ A P. W AI GASI I I I I I FI I I I I GIDD GMIDDD I I I P AI D MIDDDDI I I
ll i ll i{jlI y, e d r a I 3 li c l l
M A a fa T, e F t g g g u a n o m P ig e d l
a g i t
a r r u S h eB e c I v t
s a
i s
M i=
s d T, R. =
W id l
a
.d
.A lh ui e d
i l
el iq r a L2 c
S o
r e
n o ih S r d e uum qr a t
sUD i
m
- t t
a lsN iI l
lo u f ir S r S o n WM I
t e
n s
- ir c s d e
,T t
o n ins v l
ts I n
e 8 n g f, t c ah c. l fta jkuI u n s s le otf ..
9 l t
i r d a
d at at E R o u I, or 9 i S
p o oe d
, o 2Y 1 w R Rria m a om oa e, ge2 y r gh e l
- a p r e s
a w
g e o e
s M, a nl t
S t wr et s e ht n
a nt hif n
e n d u
I n o b sa d r a t n d n n o w "os u cd o isd vst i
o n M D, d n nlt I ihM Ra d ol aP nRP nP t l a n a
. l w S t
ot a t
t i
w d Ba um lah krI ig f
T e T. da ay a s e d d ic d if er c t
a ki e T. T, T. a et e nte em ;. .
d Sd uot oI R
O P
c o f d
o k
i d
f ot t a ReW s
gali r
eee kkk dddiii d dig agma br o r tar t
e :..- hI a.
'u ;,.S,h S
.t v
r ad a e i raln ted inNt lc I c
'saToMl e
e iqts sp l
S pt ou Y, ag d
a o
L no oew l
p e fff a iln T e Tr e. o N .u .s E o iop dainr M, Se r sId ca r c of c I j
Rn o e ooo o iBlaestet re tare t t t o t oe R l n tat d o pk 9oop pR h nt aoOe rd s ar M r e r p s n aRS efS e o v G
N m o
g n
bugR*lo o aCo4n4 r i 1 t t r oonnnkd e si t e ggge on cEWleW g
e oc a f
gt naWt a lok Rf a e e hc aw of a
o h r rl ts nsi ef imne TMRl e
ht i yv n- CRa o ie C, d
I a ld i
S Vdl mlg-e ne ct n g
ai l
S gcif minre t nd f o o nnR mimBRonrdlniv~
t
^
na ohse uddd e o g e o R S u r a es d r D
1 m h
h E
r ki 0 uEADc 0 DgggueR iuuumc -. ml 5 r nnnCi n gB B B r e l t r ol i i o ke aamh ll ob ts
- r or ug- i I Wd MFaGnnh aS r reair ugt e e nne rh e eih tsB-,kt t
mm ad" el ri u
I I
v a* an a
l C
a 1
N )
a r t o
t c
a nt l ic a o o o o laa a a onrtot r l t t e o aBMfCWt rf nt a Tibn yloiwh aas t twwI e s s n ri os g e n O d g
o e e a et et et e s s s tee lac c c aoa taa t t t t ngnnMwrSYr ioTdo ot nt t lo R s - t aa a e eee ee ti t ittaa t s tee s se stead se iooo t
iRiiiiie e e et t t i isrffff c i t t e ts eiiiii t t ci aaa M u r f fffffff i sRRRiia s s s s s s t t t P o e ccaae t t e aet eee t t te L n ooooooofffffffffff ooooo lopo ul los iiR s eii s s s s i
A i g EI EEEEEEE oooooooooooEEEEE l oll ll fffffff SMSSSSSSSEEEEEEEEEEESSSSSl ooooooo
/ T t
n n ETEEEEEEESSSSSSSSSSSSSSSSAgAASSSSSSS r N o i r
t E C
( t o
M i n
N 1
- o h t
u O A m R
I E M is r
9 10 5507223394i55I 01 1 I 201 1 1 1 1 21 748479737565 4244233222265 4892892 V L l
a A 1 1 1 1 I 1 1 1 1 1 1 1 1 1 1 1 1 - - 8888788I 1 1 I I 1 I N B t
n E A e L m A T n
- e C o c n i I r a i
e G i v
t 61 O
L n Di s
3 2
6327421 63334788434468.531 001 49 1 2 00001 1 49 1 1 1 0247 432 1
- - 0001 224
- 8. $ 3 5 7 3. 9 O E I l D a c
A i g
R o 8 l r 9 i o yub e
9 as 1 d 8 945 99046 1 7 a Mu N 1 1
145346882 1 1 96322 Il 3403 1 I 107456 1 56888 3 1 287 4568 - - - 62 31 2I 1 45 3115 3
R S
N I
M r r r T 1 I 1 l 1 23 1 ta o oo t t aa n e 2- 341 1 - - 23561 41 - - - - 1 1 1 1 - - - 5 i- c cc o
id 1 1 25 - -1 055 1 2 - I - I - I - - - -1 O555 I 22SI 1 l1 - H1 358I dn idd i1 231 - - 31 -
t o taC F FFFFFFFGGGGGGGGGGG111 1 1
HI nn1 iI 2335 I I 1JJJJJJ S
e im lpim D S e d me I M.
P I,
l Q
I P AI DDDD I I I SI WI DDDDDI I I I A.DDDD AI I I I WW SSI AI DP DDD AQ AO I I GRID SI W DAIQDGI WD i
d l
n a
4 A
e g
O I
s a y P l
e l
e h
S n d w i m w I a e r o I M o r
i V n a t y
r M R e r Id n r T. r v nw s
e r Mas e T.e r
e e
i iv e l b t w ioos Ri v t
R.
t I w a a o I
M
- Z, el R T.
e h c c e g n M W I h n
I r i 5 ig a ne N. u e T. _ 9 e M - m fe e B d s . b T. nuet B 2: .
eg 2We T.r h
ah r
a lawf a o ;
. l s
l f
d n
s t
ug e ue y o R u I. n a 8
9 o
hS u u s nRd oni w o
qu s q us s o
RJ mip yr t
e s
eye t iv rr re J. I.
g
)
2 e r n 6 ri n T
al l
wdi S u d
.N be m
a r et 9 g n S a t Db S i d 2 1 g a to s aB nu n o ween rox di s n e n
nl d i Wnda ed r na e i
l o
in di nd Rwhn.
n: c2 wbM. oRS o J.. .
owi a S u I B t
u o
s ioiu dl s inI iotn r o an o -
r t sd m loeMl t u
t n R n t tab h y t
S.R rCe C lslas l s -- huUbled n oa n S f fd r e (
bnh on Um I i d
o S eg ble e d e t
f a yI W' fcf odn G,
- t o i a fo aet a
o T
i t e e l
a #e- ra r
!ch c d ". ror a yw
. o sr ot d R a rh e
s c
- i Sh o D e e el e Ro a r r
R c t
h p taA e d R i CN- h e SB n . a nsi k
- a. de c e at e y a
c gn o neR Nt y O o cib s r foo n l yk d
l 4 c h
nn r, u :, rC;weM.
j a
oi e% l e
Ce e l
i7 e . R 4E
. d o c1 n
l a
- Df vp e a P L .
oCC wC t f r h
eM o o
-.hc7 S
Ld a e l
am fhe e V E e nio ort n uf e c
S: ut r e -
%f c a d 2 n a/Ad nn t
2f of st o o n o Ro en n
R V,Winhda N. a Whi f aI oin6 o l
p ta---- o- l s goeRWd +2f h uo on ed f naRo 1, I l N g 2a t
e 6 o C o gf F i s gg G
t gaI 2y6 w n s ds2 nn 2 m n e
trkr n S --
e-s n e a nsRno nMk8 o o mi n te ydd u s r r eorfi detodia pl s g r N a o S oi' mrl e2 n dokl rl i ee ie ol dt o3e- lel i o e uuRm i d .l l eY a t
mlAI l i I t iadI Yt S s ? i.S l
.et o-
. h eiusin yd nwd u- hBBgt l
R .Be moc fh usRiB o i l
u- ~ . od e e i
r pd a
E M t= r ggah e .
a.. R s rwa c agel Jl o r r nn O M7 B u.h R C c r a pe L nl l o e iudOR .Sntoooi S n nLt f oB I m s e t L o oo
_ g nL no A gW ot nd j t
h B :o r oc c laat t a l oat nnt nac oa ee a laS rGe ng a. e a a e D f nt ta nl nt t o
I N r oMeMica oaaa et teeeeeee t l ooaaaae elaoet t t tee t nt o f lo;t e et te foin t Re
) g f t f t i t t t t t e e e eRiiii s s s soc aoa asRRii s s O d e o e e a isRiiiiiinee s s s s s ss t t t t t fffffffff iiiiis s s s s t t t iiifffff s s s te et a eeeeooooo fffff M u P r t ii s
t teoooooooooffffffff oooooiRinii s s s s s t t L n g ff siWWWWWWWWWooooooooWWWWWffffffWWWWW s
oonSSSSSSSSSWWWWWWWWSSSSS ooooooNNNNN A
T i
t n n SSOSSSSSSSSSSSSSSSSSWWWWWWWWWWWWWWWW O
i N o r E C t o
(
M 1 i
n ht N - o u O A R M iz m
70928302064851 64785591 3 9200280430435 780001 00090032222222445 4477666799888 I
V E l a A 1 1 22222221 22223322222222222222222222 L t N B n E A e L T m A n
- e C
I o
r c
n i a m G i v
t s
526.23281 1 0 4.7 8. 1 58791 0. 7.1 533671 2.9 8 0 4.4 2 1 99 O n i
D 6 1 00001 257 22 1 1 00001 48 I
I 001 48001 47 1 0001 4 L E O
I l D a A i c
R g 8 l o r 9 i o ymb e
9 a L d 98 30 2 6 689351 I 24 93 4 2 1 1 43 400 7 4 26 4620 u 2 5735 281 68 a M N 68 1 579 29 1 2553579 1 1 3571 2 1 35791 31 35 R
1 1 S
N I
M T 1 2 1 I- 31 I .1 - 5l 2
n e iod 1
1 5 1 - 3 46I 1 1 1 -S5 -
I- 2341
- - - 1 I- l 21 5 I-I - 1 -
259I 1 25 S1 I -I- -I- -25
- 231 1 t o 7- 1 l i ii2358I JJKKKKKKKKKKLLLLLLLLMMMMMNNNNNNPPPPP 1 I 1 1 1 258i t
S aC n
e u D O
l pk I, md a
e S
l A
W SM WQ W WW G.
AIDDDDDDDDDD I I I I I I I I I SI W DD DD P.
I I EAI D GIDDDDD MIDD GGI DDDDDD I I I I I I I I I I I
fG 5 A
e g
a P
tskr hgPa iela 1
4 Hi n 4 drl o d eof o n
a tu o re C, )
s Rt hd a l I M le 8 % l d uo b a
9 -
T. la n a R,R t e
9 -
-. A.
1 H et a sl g 1
t l v ei e ir rte on
. a s
- w e
N, S
- i c
oI M n wenhC DS lo V,
t s
n s r
- d. .
S.p T, t iu o d e a s t
tod6d r6 n F, r
T i
t oe ReR, Wr f e r i
e r .e p /_ D r s
e e dGn2 l
a d a
n a o R c k ovi r ehwg v ee .
rf i d ga2 i nye i
t O o rd o a Wgt oiHC FW i M,rpei no ut t a
e P L Yo enf c o wg n g E l Rn d nl ot r o SDR V e
f da mSWiantee tavl d ta off e e e e ie o n if R l p Oed g s,nna r
t r a gas o n on.o. f y
G n saoo us g *r raeA-. tot mIsdi a
r ciio c n o l nF l v e
N m o la-.I sd oe t
o l I a i t
s m Elel yin- tr t d n-.l e ed yft r s m -. n e
R S p g SeWunwr i r gl e r ne iu- o1 e '.. Borl el Ciib a rt ek. &
r D fa ohBgr nn G I m w e t aa l Soor aninh Ltc oaa nt at tat
(
I a r D tee nt oc laa t l ot t aaLa e teee a N ) g ii t
s s e t aet teeeeeRiiiii et t t te Y eh O d e o oos fffffffs s ts s s oooooo ffiRiiiiiffffff t t s s s s s E nar s M r hs idPt u P WWoooooooWWWWWW K i f I o d en L n g NNWWWWWWWNNNWNN inr i od oo A
i t
n WWNNNNNNNNNNhNN N FAFR T n i O = = = =
N o r E C t o I T F D 2-M ( i A QI PO I M
r N 1 n ht AAFR T
O
- o n C d R A M m iz i
327805885528900 991 1 1 21 003333 43 I
F n
a I
V E l a A 223333333333333 I I L t T I M
N B n N T E e E f L A m D o
A T n
- e I s
g m
C n c i d I m a m d G i ) u
- 705287.0535.27691 2 t
v e b O n I 68001 358 1 00248 I l ti s r o
L E ffont t c
O ( e a I
D l
a t r
eit ade me) r a e e
r e
c ht A i g WSWam n R o r d
ntictnG e(
e e
8 l ua ut a 9 i o pmb e
o qf r ul e t w
e 9 am GAEM f b
1 d 5 43 5 7 15 96747 7 079 y a Mu N 771 2 1 3 1 5791 2 0 1 679 = = = = a R S D d w
S WQWA im N GAEG i s
I t a
ht M t T n i
o
- I 1-21 - -1 1 5 1l - 21 1 I 1 -
se e
id 1
7S
- 1 I -24S9l l - l- - 35e15 p
a t
t o aC PPQQQQQQQRRRRRR m S ) o fr D :
L T
(
e s
o r e e Dt e t
l a m n a )w u e oWox r r
a i.a nCt ( a e a n fk rl r u i i P -
lpia D l,
' SMA d mi ud s e l DI = = = =
a A, l,A l l
SM A MIDDDDAI I I I P
D SAI WP,DDDDDDI I I I I DW I SMA P
I l
l l
l 1998 RADIOLOGICAL ENVIRONMENTAL MONIR) RING REPORT TABLE A-2 Synopsis of the 1998 TMINS REMP*
Number of Number of Number of Sample Sasupling Coueetion Samples Type of Analysis Samples h Imations Freemency'* Couected Analysis Freemency Analyzed
- Air lodine 9 Weekly 468 I-131 Weekly 467"'
Air Particulate 9 Weekly 468 Or-Beta Weekly 467"'
Or-Alpha Weekly 259"'
Oamrna Quarterly 36 Sr-89 Semiannually 10 Sr-90 Semiannually 10 Fish 2 Semiannually 8 Gamma Semiannually 8 11-3 Semiannually 8 l
Sr-89 Semiannually 8 l Sr90 Semiannually 8 I
Aquatic Sedunent 4 Senuannually 8 Gamma Semiannually 8 l l* Annually I Gamma Annually 1 l Discharge Water i Weekly 4 I-131 Weekly 4 l lhweekly 24 I 131 Biweekly 24 Gamma Monthly 12 Or-Beta Monthly 12 11-3 Monthly 12 St-89 Semiannually 2 St90 Semiannually 2 Fruita 2 Annually 2 Gamma Annually 2 Orains 2 Annually 2 Oamma Annually 2 Broad leaf 2 Annually 2 Oamma Annually 2 Vegetables Sr-89 Annually 2 Sr-90 Annually 2 Oroundwater 4 Weekly 165 11-3 Weekly 165 3 Monthly 36 11 3 Monthly 36 4 Quarterly 16 11 3 Quarterly 16 14 Annually 14 103 Annually 14 5* As Needed 30 11 3 As Needed 30 Gamma Quarterly 28 Gamma Annually 2 Oamma As Needed 4 Sr-90 Annually 7 Dosuneters 90 Quarterly 2l06 Immersion Quarterly 2100"'
(FLD)* Dose NOTE: See Notes at end of table.
Page A6 O
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE A-2 Synopsis of the 1998 TMINS REMP'"
l i
l 1
Number of Nanber of Nurnber of Sample Sampling CoDection Samples Type of Analysis Samples h laications Freeuency Collected Analysis Freeuency Analyzed
- l Milk 5 Biweekly 129 Gamma Bi*eekly 129 l-131 Biweekly 129 Sr-89 Quarterly 20 Sr90 Quarterly 20 Storm Water i Monthly 12 Gamma Quarterly 4 11 3 Quarterly 4 Surface / Drinking 7 Weekly 28 I-131 Weekly 2 4'"
Water Biweekly 168 I 131 Biweekly 144'"
Gamma Monthly 84 Gr Beta Monthly 36 11-3 Monthly 84 Rodent i When Available 3 Radiological When Available 3 Frisk or Gamma NOTES:
l (1) This table is a synopsis of the prunary (base) program only. It does not include the quahty control (QC) program-(2) The total number of analyses does not include duplicate analyws, recounts, or reanalyses. J (3) A dostmeter is considered to be a phosphor (element).
(4) T1us is the total number of samples or elements (TLDs) used for data analysis.
(5) Water samples collected from Station Ji-2 were not analyzed for low level I 131. l (6) Weekly means once per week, biweekly means once every two weeks, morthly nuns once per month, quarterly means once per three
~
months, semiannually means once every six months and annually means once per year.
(7) Oroundwater samples were collected on an as needed basis from Stations AIT, MS-7, MS-8, OS 14 and NW-C- 6 (8) This reDects the sample collected from Station EDCB.
l v
i a
1 1
\
Page A7
1998 RADIOLOGICAL ENVIRONMENTAL MONimRING REPORT TABLE A-3 Sampling and Analysis Exceptions 1998*
Period of Deviation Descrintion of Deviation and Corrective Action February 3,1998 to The circuit breaker tripped at the control air sampling station (Q15-1) in February 10,199 the beginning of the sampling period. Only 35.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of sampling occurred during the week. Due to the low sample volume, the charcoal cartridge was not analyzed for 1-131 and the particulate filter was not analyzed for gross alpha and beta radioactivity. The particulate filter was included in the quarterly and semiannual composite samples that were analyzed for gamma-emitting radionuclides and strontium, respectively. The circuit breaker was reset for the new sampling period; the unit resumed normal sampling.
May 27,1998 to A total of 53 hourly water samples were missed during the period at the June 8,1998 indicator surface water station (31-2R). This intermittent problem ;
possibly was caused by blockage in the inlet line or the inlet end not bemg ;
in water due to low river conditions. Closer observation of this station ]
was performed to help ensure that there is continued composite sampling. ,
1 June 29,1998 to Over 39 hourly samples were missed during this period at the indicator July 14,1998 surface water station (J1-2R). Missed samples were due to a crack in the suction tube. In this condition the sampler was unable to draw samples.
The suction tube was replaced and sampling resumed normally. ;
I i
1 July 14,1998 to The valve for the source water was shut off or became blocked at the i July 28,1998 upstream control drinkmg water station (Q9-lF) at the end of this l sampling period. The source water was tumed back on and the valve will ]
be flushed each week to prevent blockage. !
During the same period,123 hourly samples were missed because the inlet end of the supply line was coming out of the water at the indicator surface ;
water station (31-2R). A strainer was fastened to the inlet end and the line l 1
was repositioned to prevent recu Tence of this problem.
i Page A8 Ol I
N 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT l
TABLE A-3(Continued)
Sampling and Analysis Exceptions 1998*
Period of Deviation Description of Deviation and Corrective Action July 28,1998 to The above listed problem at Ji-2R was not corrected until July 31,1998 August 11,1998 so three days of sampling in the beginning of this period also were missed.
A boat was deployed to access the inlet end of the supply hose and i reposition it into deeper water.
September 1,1998 to Towards the end of this sampling period, a crack in the suction tube September 15,1998 rendered the compositor incapable of drawing samples at the closest downstream drinking water station (G15-2F). As a result, about 19 hourly samples were missed. The suction tube was replaced on September 16,1998 and normal sampling continued.
September 15,1998 to Because the above listed problem at G15-2F was not corrected until September 29,1998 September 16,1998,25 hourly samples were also missed at the beginning of this sampling period. As mentioned above, the suction tube was replaced to correct the problem.
December 1,1998 to During this sampling period a combination of mechanical problems and a December 15,1998 frozen inlet line caused multiple missed samples at the indicator surface water station (31-2R). On the last day of the period normal, sunpling resumed by replacing the inlet line, working on the internals of the ISCO Compositor and applying new insulation to the inlet line. Also, a 2L grab sample was collected and added to the available composited water to obtain adequat; vriume for analysis and to account for a longer sampling period.
t
/
Page A9
Q nu mmotocica enviaosuenru nomwamo newar APPENDIX B 1998 Lower Limit of Detection (LLD)
Exceptions O !
l i
l l
O Page B1 1
I 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REMRT During 1998, all analysis results met the lower limits of detection (LLDs) required by the USNRC. The USNRC-required LLDs are listed in the TMINS ODCM.
{
l 9
Page B2 O
l l
l 0 nn aawivazcat suviaosusurat noszwaisc as, var l
APPENDIX C 1998 REMP Changes O
O Page Cl
I998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE C 1998 TMINS REMP Changes January,1998 The collection and analysis of water and sediment from the East Dike Catch Basin (EDCB) was initiated. The EDCB is the final holding or settling basin for all storm water and soil runoff (sediment) within the plant site. Water and sediment from the EDCB is discharged into the east channel of the Susquehanna River under the Station NPDES Permit when the water level !
exceeds the height of the concrete discharge weir. Monitoring of this station j was initiated because the TMl Chemistry Department deleted their routine l I
sampling of the EDCB. Water samples were collected monthly and analyzed as quarterly composites for tritium (H-3) and gamma-emitting radionuclides. Sediment was collected in the fall and analyzed for gamma-emitting radionuclides.
Annual collection and analysis of groundwater from Station MS-20 was initiated to monitor an aboveground tank at TMI-l. The sample was collected in June and analyzed for H-3.
The collection of groundwater from Stations MS-22, OSF and RW-1 was !
reduced from weekly to monthly. Decreasing H-3 concentrations prompted this change.
June,1998 Six offsite stations were added to the TMINS Groundwater Monitoring Program (GMP). The new stations were located: at a marina just north of i TMINS (Station A2-2), at two summer homes on Shelley Island (Stations i Kl-6 and L1-3), at a summer home on Beech Island (Station L1-4), at a residence on the east shore Station (Station Dl-4) and at a residence on the west shore (Station J3-3). Monitoring of groundwater at the new sites was initiated to supplement the TMINS GMP. The samples were collected annually and analyzed for H-3.
August,1998 Onsite Station OS-18 was added to the TMINS Groundwater Monitoring Program (GMP). Originally installed to investigate alleged spills of photographic waste, Station OS-18 was added to the TMINS GMP because ofits proximity to two pipes that transport water containing radioactive materials, including H-3. Generally, samples were collected and analyzed weekly for H-3. One of the samples also was analyzed for gamma-emitting radionuclides.
Page C2 8
O i,,, aaviotocicat saviaosussrat nosiroazso usevar i
l APPENDIX D 1998 Action Levels O
O Page DI
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REEDRT Analytical results of environmental samples were routinely reviewed and evaluated by the staff of GPU Nuclear Three Mile Island Environraental Affairs (TMIEA). The results were checked for LLD violations, anomalous values, UGNRC reponing levels, main sample and quality control (QC) sample agreement (Appendix E), and action levels.
Established by GPU Nuclear TMIEA, the action level is defined as that level of reactor-reiated radioactivity which when detected in environmental samples initiates an investigation and subsequent actions, as necessary. An action level is reached if either of the following two criteria is met:
m The radioactivity concentration at an indicator station reaches or exceeds those concentrations listed in Table D-1. (With the exception ofl-131 in food products and water and St-90 in milk, water, fish, food products and airbome particulates, all concentrations listed correspond to 10% of the USNRC reporting levels.)
e The radioactivity concentration at the indicator station reaches or exceeds 10 times the mean concentration for the control locations. (This criterion applies only to those media and analyses which are not listed in Table D-1.)
Action levels for gamma exposure rates measured by TLDs have also been established. For ,
TLDs, an action level is reached if any of the following three criteria is met: I E The exposure rate at an indicator station not on the owner controlled area fence exceeds three times the mean of the control stations.
5 The exposure rate at an indicator station on the owner controlled area fence exceeds 135 mR/std month (50% of the 40 CFR 190 limit of 25 mR/yr adjusted by a 67 hour7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> recreational factor).
5 The exposure rate at an indicator station not on the owner controlled area fence exceeds either two times the previous quarterly result or two times the historical average far the station.
If an action level is reached, an investigation is initiated which consists of some or all of the following actions:
E Examine the collection or surveillance sheets for an indication of any equipment malfunctions, collection or delivery errors.
E Examine the running tables (prior data) for trends.
5 Review control station data.
5 Review QC or duplicate sample data (if avaliable).
5 Review TMI-l and TMI 2 effluent data.
I Page D2 l
m l t \
gj 1998 RADIOLOGICAL ENVIRONMENTAL MONimRING REPORT i a Recount and/or reanalyze the sample, a Collect and analyze an additional sample.
The results of the investigation are then documented on the form provided in the GPU Nuclear I j
TMIEA procedure 6510-SUR-4523.05. As appropriate, site personnel are apprised of plant-related radioactivity that exceeds the GPU Nuclear TMIEA action level. Ifit is concluded J that the detected activity is related to TMINS operations and also exceeds the USNRC reporting 3 limits as defined in the ODCM, a detailed report will be issued to the USNRC. l l
During 1998,2 indicator sample concentrations equaled or exceeded an action level. They are l summarized in Table D-2. For each investigation conducted in 1998, it was concluded that the {
action level concentration was caused by normal TMINS operations. However, none of the 1998 action level concentrations were reportable to the USNRC.
Two monthly surface water samples collected at Station J1-2 contained H-3 at concentrations ;
equal to or greater than 2000 pCi/L, the GPU Nuclear TMIEA action level concentration for H-3 1 in surface water. The presence of H-3 in these samples was attributed to TMINS operations. l 4
Tritium at concentrations greater than background levels is not unexpected in surface water collected at Station J1-2 because 1) H-3 is normally present in TMINS liquid effluen.s and 2) the j y/ samples are collected just downstream of the TMINS liquid discharge outfall wisere mixing of l liquid effluents with river water is incomplete. Complete mixing is not usually achieved until the !
water passes over York Haven Dam (YHD), a structure downstream of the sampling site. Dose estimates for ingesting water were not performed because these samples were non-potable water. I The H-3 concentrations that equaled or exceeded the GPU Nuclear TMIEA action level were not reportable to the USNRC.
i I
I i
l Page D3 l
1
J 4
D e
P g
a O _
) _
t -
e _
w _
/
r _
i _
C _
o
(
s
- *' 1 2 5 5 _
t _
c 0 0 _
u d _
o r _
P d _
o _
T o _
R F -
O -
P E )
R L G y /
i t
N i s C p 3 6 7 0 I
- 3 R it c
( 4 D
1 as oc k l
ii i I d p N am M O Ra M eS vl )
t L ia it t e A
T s n w ae .
N Pm r 2 *5 O
/
E 1
- r n oo i
Cp 3 1 3 1 1 2 M D f r 0 N E l si v (
O L en v h s
R B eE i F
7 V A Ln N T ns i
E i on t o s ci e L t t a ')
A Aa r l C
I Pt n u/
ci m
G Me Ec i
t r C
)
- 9 O n a D 5 0 1 2 L Ro P (s 0 O SC ee I
D N I
n s r a A M oC b r R T r i o r 8 e 9 A 'a 9 wl .
1 gv e
) i
- e L
/
il k g inn iC ' ' ri
(
n 0 0 00 0 40 00 0
- 0
- 3 5 0 d rt 0 1 1 3 3 4 4 1 2 dnpo "re 2 are e
t a cC aR f
W rN uS sU s
ef s 5 0 d o i
s 4 9 8 0 5 0 9
- 1 4 7 4 u
y 5 3 3 l cn0*/.
n e o o 4n 4 3 5 5 9- b l
a I r N-3 1
1 1
- l a
- s s - i 5 n I M F C C Z S r l C C a A Z B ) )
ab
( (
O
S 3- ep f e o D f l o t m e ht t S Hmtogenhun eo mh f t w of eh e
ut e
g d f a d s detoob t
ot d o a eNo s e i t x e et gee n P s s a ieea t
t I c s w n al a n c s s l
uMnim mn s
eTi oh i e i odt l ltu i 3- pmin o a sS mix xid w n r t t
xrS au s e rNHa iS o e man oe . r,er I f s rom.,lat i
ot ri rh e eMos pr e te e rs u t
a l
prf nd pwt e et e l
pT s h i et e ig ml aa e tedl c c el lpwT si r net a af mr ah m amo ntint daehe lpwe a r t
s e opct s oi r a t wmrh v r aeCxelo ou cnie et oevd. rf rd el cl oeT ol a c v n t a m er. es ei r t e la nt t
a t
ni r .d a c s t f is) e .
I f w o ei s iv si ri a e g ri s )e l u . wie r c ei u e npeoiet t
a l cC et a o xi erblaC l laR h t
n hhRl rb o t tf esha e ct a t mC es ger auR t t
s in o a. r o i w p tcN n i s at o e n a r a olcN u d mti t ad id n o S i s i r . aioh wpaS l
c ie 7. a nU dh et vle s cs e ot U t
c r n c n f ns e fifi o tiLdrim k d ;n o q ( ah i el oRvle od ei vnoe d ir( nht C e nvapm1 s d wwt o i eal cid eS n ar nt t
egnd eq n u a ws ao T
R did adh Na i
3 eh eb a e I sit sb t si o d i a r
le 3 hc ha ut n nhi l a r wte si snlob oeSt J
Y Ht ht e u sMtne elp egt a s e r r HiuguNe lps r s neia t t I
E emo vaTu h ot ocef mip l no e d qk aI u h e s c c h ua eMl mgp l e o R Tfi r nb abtehf es aoe t r Tt SbbTl si er a n e G
N I
g nI R ri O t o de w e T aeL I 8 N 9 ic x c n O 9 1
dEo n st i 1 1 M g I n fiA c c L ir op A
T u # at mhe N D S 2- d E e
^ M D t c e e f N E u ht r ht r O L d o o B n f 3 f 3 d R o o - d Hl e o Hl e t t I A C a a .
V T s d e
m ae na qC a/L ui d e a m n a/L ui N n t e a qC E i o c rd ep t
c r d e p L
t a let l
s eh nnc0 let nn eh s
g ic0 A
C I
i t
s o ed owi i0 n c ot ah0 nw2 lowiah0 c ot ed n 0
t l o )w f2 n pt so) fL o l
G m pt s cL o O I r g
i mu ajl c,/ l l i e mu l,/l i e L i sd aCv ajl O t s sd r efaCv I e r ef plet t ple D v et a u0 n t t et a u0 no A n ac o0 o a co0 R
I r
wloe4i g* c t w l, o e8i g t c
o e ,r a e r a 8 f c2 a 0 c2 a0 9 fa 1 hc0N a -
9 1
n o rJ u s 9,U f I rJ u
hc0N s 8, U s s ni d3 P a o (
G s onid7P n G
(
e teid eid R i st ain t
uo e t t is tai uo e oS qiht t oS qih t p i rl rd a p i rl rd t
a moSt ot nd e moSt ot nd e
c cI aNee c e c cI aNec e e hei ndMnc ox h ei dMox n e nc TiTce TiTc 8
e 9 t 9 8 a 1 9 D 8 8 9
, 9 1
n 9 9 2 o 9 9 r 7, 1
i t
1 e 2 c 9 o8 ,
b mtoreb l
e 2 t l 2 e o e y t o C nu l u
p e
t c
J J S O 1 2
ms asmotocica enviaonnenra uomronwa aemar s
l l
1 APPENDIX E 1998 Quality Control Results O !
O Page El
I998 MDl0 LOGICAL ENVIRONMENTAL MONITORING RELY)RT A quality assurance (QA) program is an essential part of any radiological environmental monitoring program (REMP). It provides reasonable assurance that the results of radiation measurements are valid. To be effective, elements of quality assurance must be evident in all phases of the monitoring program. These include, but are not limited to, sample collection, preservation and shipment, receipt of samples by the analysis laboratory, preparation and analysis of samples and ,
data review and reporting. An effective QA program will allow for the identification of !
deficiencies in all monitoring processes so that appropriate investigative and corrective actions can l be implemented. l The United States Nuclear Regulatory Commission (USNRC) published Regulatory Guide 4.15,
" Quality Assurance for Radiological Monitoring Programs (Normal Operations)- EfIluent Streams and the Environment", which defines an acceptable QA program (Ref. 43). The guidance contained in Regulatory Guide 4.15 has been adopted by GPU Nuclear. To meet the objectives of this position document, procedures and plans have been written and implemented.
In the laboratory, samples are typically analyzed one time. Therefore, laboratory personnel must be reasonably confident with the analytical results which are generated. One means of achieving confidence in the results is through the analysis of quality control (QC) samples.
During 1998, two independent laboratories analyzed the GPU Nuclear TMINS REMP samples.
The primary (or base) program samples were analyzed by GPU Nuclear Environmental Radioactivity Laboratory (ERL). Separate or split samples were analyzed by Teledyne Brown Engineering (TBE) Environmental Services. Three types of QC samples were analyzed routinely by the laboratories. They included intra laboratory split samples, cross check program samples, and inter-laboratory split samples. A discussion of each QC sample type is provided below.
Intra-laboratory Solit Samples Each laboratory is required to split at a minimum every twentieth sample and perform an analysis (or analyses) on each portion. The samples which can not be split (e.g., air particulate filters) are counted twice. Staff scientists check the results of the two analyses for agreement. Agreement is determined using the criteria listed in USNRC Inspection Procedure 84750, " Radioactive Waste Treatment, and Effluent and Environmental Monitoring" Prior to 1998, agreement was considered to be acceptable if the coefficient of variation for the two results was eighty-five percent or less. Non-agreement of the sample concentrations may result in recounting or reanalyzing the sample (s) in question. During 1998, all but two of the paired intra-laboratory split sample results were found to agree. The non-agreements are explained in Table E-1. l Cross Check Program Samples The laboratories analyzing environmental samples inicipate in at least two separate cross check programs. Both laboratories participate in the cross check programs conducted by the United States Environmental Protection Agency (USEPA) and Analytics, Inc. During 1998, water Page E2 l l
l
O
\
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT samples were supplied by the USEPA; non-water samples (e.g., milk, filters and cartridges) were supplied by Analytics, Inc. The GPU Nuclear ERL also participates in the cross check program conducted by the Environmental Measurement Laboratory (EML) of the United States Department of Energy (DOE). '
All samples are sent to the laboratories as unknowns. Participation in these programs provides an independent check on the ability of each laboratory to perform analyses on various kinds of samples containing detectable concentrations of radioactivity. The results submitted by the i laboratories are compared to 1) control limits established by the USEPA,2) control limits l
established by the DOE EML or 3) agreement criteria used by the USNRC in their Inspection !
Procedure 84750. If the results are outside the established limits or agreement criteria, the laboratories are requested to perform an investigation and take corrective action, as necessary.
The 1998 cross check program results from each laboratory are listed in Appendix F. Explanations are provided for those results which were not submitted and/or which were not within the established limits.
Inter-laboratory Solit Samples The third type of QC sample is the inter-laboratory split sample. These samples are the ones that i j are collected routinely for the REMP. After or during the collection process, the sample is thoroughly mixed (as necessary) to ensure that, as much as possible, the distribution of .
radioactivity in the sample is homogeneous. The sample is then split into two portions. One !
portion is sent to the GPU Nuclear ERL and the other portion is sent to TBE Environmental Services.
Since it is impractical to split airborne materials (filters, charcoal cartridges, etc.) separate samples frein independent, but co-located, samplers are collected and then sent to the analysis laboratories.
Unfortunately, this practice of using distinctly different samples may result in higher than normal concentration differences for the two samples.
Analysis results from the GPU Nuclear ERL are then compared to those reported by TBE Environmental Services. The agreement criteria are the same as that used for the intra-laboratory split samples. Corrective action for disagreements may include recounting or reanalyzing the sample (s).
l Table E-2 outlines the 1998 inter-laboratory split sample program. During 1998, all but nine of the paired inter-laboratory split sample results were found to agree. An explanation for each non -
agreement can be found in Table E-3.
b Page E3
i l
1998 RADIOLOGICAL E . /lRONMENTAL MONImRING REM)RT l
TABLE E-1 1998 Intra-laboratory Split Sample Non-agreements Sample Collection Medium Date Station Analysis Action and/or Resolution
- 1. SW 03/30/98 - Q9-lQF G r-B The original and duplicate QC analysis results were 1.8 i 0.7 04/27/98 pCi/L and 4.4 i 0.9 pCi/L, respectively. A new sample was prepared and analyzed by the QC laboratory. The Gr-B result for the new sample (1.610.7 pCi/L) agreed well with the original analysis result. There was no apparent cause for the higher duplicate analysis result.
2.AP 08/19/98 - BI-4 Gr-A Re original and duplicate analysis results were 0.0018 i l 08/26/98 0.0006 pCi/m' and 0.0032 i 0.0007 pCi/m', respectively. I Recounts were performed. The recount results (0.0048 i 0.0009 pCi/m' and 0.005710.0009 pCi/m') agreed, but as >
expected, were higher than the original and duplicate analysis i results due to in-growth of natural alpha emitters. Here was l
no apparent cause for the initial non-agreement.
l 1
l 1
l i
l i
i l
@\
- 8. . \
l
)
l 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE E-2 1998 Inter-laboratory Split Sample Program No. of Percentage of Primary Primary No. of QC ';amples Submitted for Sample Medium Stations Stations QC Analysis Air Particulate (AP) 9 1 1I percent Air lodine (AI) 9 1 11 percent Surface / Drinking Water (SW) 7 1 14 percent Milk (M) 5 1 20 percent TLDs (ID) 90 10 11 percent Groundwater (GW) 7(1) I 14 percent Aquatic Sediment (AQS) 8(2) 1(2) 13 percent j Fish (AQF) 8(2) 1(2) 13 percent g
Food Products (FPF,FPG FPL) 6(2) 2(2) 33 percent Meat (GAD) 0(3) 0(3) Not Applicable Rodent (ROD) 3(4) 0(4) Not Applicable (1) This refers to the total number of groundwater stations sampled quarterly in 1998.
(2) This refers to the total number of samples collected and analyzed in 1998.
(3) Deer meat samples were not available in 1998.
(4) Rodent samples are not split with the QC laboratory.
O V
Page ES
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REIDRT TABLE E-3 1998 Inter-laboratory Split Sample Non-agreements Sample Collection Medium Date Station Analysis Action and/or Resolution
2.AP 03/31/98 - El-2 K-40 The primary and QC sample results were < 0.012 pCi/m' and 06/30/98 0.00367 i 0.001% pCi/m', respectively. The non-agreement was due to counting the QC sample longer than the primary sample.
No further action was taken because the QC sample concentration was below the estimated minimum detectable concentration (MDC) reported for the primary sample. Potassium-40 is a naturally-occurring radionuclide. Its presence in the QC sample was unrelated to TMINS operationr.
The reanalysis result (< l.1 pCi/L) agreed with the original QC sample result.
- 4. SW 07/28/98 - Q9-l F G r-B Re primary and QC sample results were 2.5 i 1.1 pCi/L and 6.4 09/01/98 i 1.1 pCi/L, respectively. The QC sample was recounted and reanalyzed because it yielded the higher of the two sample concentrations. Both the recount result (2.610.9 pCi/L) and the reanalysis result (3.5 i 0.9 pCi/L) agreed with the original primary sample result.
!1/23/98 0.19 pCi/L, respectively. The QC sample was recounted twice and both recount results agreed with the initial QC sample result.
Additional actions (e.g. reanalysis) were not possible due to the short half-life of I-131.
Page E6 O
O I998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE E-3 1998 Inter-laboratory Split Sample Non-agreements Sample Collection Medium Date Station Analysis Action and/or Resolution 7.AP 12/22/98 - El 2 Gr-B He primary and QC sample results were 0.025 i 0.003 pCi/m' 12/29/98 and 0.01710.002 pCi/m', respectively. No follow-up actions were requested because the results were similar to each other and similar to historical Gr-B concentrations.
8.AP 09/30/98 - El-2 K-40 He primary and QC sample results were < 0.017 pCi/m' and 12/29/98 0.00685 i 0.00237 pCi/m', respxtively. He non-agreement was due to counting the QC sample longer than the primary sample. No further action was taken because the QC sample concentration was below the estimated minimum detectable concentration (MDC) reported for the primary sample.
Potassium-40 is a naturally-occurring radionuclide. Its presence in the QC sample was unrelated to TMINS operations.
- 9. M 10/07/98 - G2-1 Sr 90 The primsry and QC sample results were < 0.5 pCi/L and 1.8 i i 12/30/98 0.3 pCi/L, respectively. Reanalyses were requested and
\ performed. The reanalysis results (0.7210.47 pCi/L and 1.5 i 0.2 pCi/L) agreed per the established agreement criteria.
Page E7
0 nu umotocica enviaosuesrn uomwaisa sen,ar 1
APPENDIX F i i
1998 Cross Check Program Results O
k i
l l
I 1
O Page F1 l
l 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE F-1 1998 USEPA Cross Check Program Results
/PA Control GPUN-ERL TBE Collection Limits Results Results Date Media Naclide (A) (B) (B) 01/16/98 Water Sr-89 8.0
- 8.7 8.33 0.58 5.00
- 1.73 Sr-90 32.0
- 8.7 34.33
- 1.15 31.67
- 0.58 01/30/98 Water Alpha 30.5
- 13.2 21.00
- 2.65 33 00
- 2.65 Beta 3.9
- 8.7 7.23 i 0.32 5.60 0.90 02/06/98 Water 1-131 104.9
- 18.2 103.33
- 5.77 110.00 0.00 (C) 104.9
- 18.2 106.67
- 5.77 (D) 03/13/98 Water H3 2155.0
- 603.8 2166.67
- 57.74 1833.33
- 57.74 04/21/98 Water Alpha 54.4
- 23.6 46.67
- 2.08 50.00
- 1.73 Beta 94.7
- 17.3 87.33
- 11.02 102.00
- 6.56 Co-60 50.0
- 8.7 50.00 i 1.00 52.33
- 1.53 Sr-89 6.0
- 8.7 4.67
- 0.58 4.67
- 1.15 Sr-90 18 0
- 8.7 17.33
- 2.31 21.67
- 1.15 Cs 134 22.0
- 8.7 20.00
- 1.00 21.00
- 1.00 Cs-137 10.0
- 8.7 11.00 1.00 11.67
- 0.58 06M5/98 Water Co-60 12.0
- 8.7 13.00
- 0.00 13.00
- 1.00 Zn-65 104.0
- 17.3 105.67
- 7.51 111 67
- 2.52 Ba-133 40.0
- 8.7 40.00 A 2.00 35.00
- 2.65 Cs-134 31.0
- 8.7 29.00
- 1.73 32.33
- 0.58 Cs-137 35.0
- 8.7 34.33
- 1.15 37.67 2.08 b7/17/98 Water Sr-89 21.0
- 8.7 21.67
- 2.31 21.00
- 1.00 Sr-90 7.0
- 8.7 6.67
- 0.58 6.33
- 0.58 07/24/98 Water Alpha 7.2
- 8.7 6.43
- 0.12 5.43
- 0.64 Beta 12.8
- 8.7 14.00
- 0.00 14.67
- 2.08 ,
l 08/07/98 Water H3 17996.0
- 3122.9 19000.00 0.00 16000.00
- 0.00 09/11/98 Water 1 131 6.1
- 3.5 7.00
- 0.53 5.93
- 0.55 l (C) 6.1
- 3.5 6.60
- 0.26 (D) 10/20/98 Water Alpha 30.1
- 13.0 25.33 1.53 21.67
- 2.31 Beta 94.0
- 17.3 84.67 3.21 74.67
- 7.64 (E)
Co40 21.0
- 8.7 22.67 2.52 22.33 1.15 Sr-89 19.0
- 8.7 19.00
- 1.00 18.33
- 1.53 Sr-90 8.0
- 8.7 5.00
- 0.00 8.33
- 1.15 Cs-134 6.0
- 8.7 6.67 + 0.58 6.67
- 0.58 Cs-137 50.0
- 8.7 53.67
- 2.52 56.33
- 3.79 O
Page F2
r 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE F-1 1998 USEPA Cross Check Program Results EPA Control GPUN-ERL TBE Collection Limits Results Results Date Media Nuclide (A) (B) (B) 11/13/98 Water Alpha 47.2
- 20.4 29.33
- 3.21 23.67 4.04 (E)
Beta 3.5
- 8.7 8.67
- 1.53 5.50 i 0.87 11/6/98 Water Co40 38.0
- 8.7 38 00 i 1.00 39.67
- 2.52 Zn.65 131.0
- 22.6 146.67
- 5.77 140.67
- 10.97 Ba 133 56.0
- 10.4 59.67
- 1.53 46.33 2.52 i Cs-134 105.0
- 8.7 103.00
- 6.08 103.00
- 2.00 I Cs-137 111.0 10.4 116.67
- 5.77 115.33
- 1.53 l
l A. The EPA Control Limit is the known concentration
- 3 sigma for three determinations. The units are pCi/L.
l B. The GPUN-ERL and TBE results are the average of three detenninations i one standard desiation. The units are pCi/L.
C. The analysis was performed by first concentrating 1-131 on a resin. De resin was then counted by gamma spectroscopy.
, g D. The analysis was performed by gamma spectroscopy. %c I 131 in the sample was not concentrated prior to l
( countmg.
E. An investigation is underwa). The results of the investigation will be available shortly.
Criteria are listed in EPA 600/4-81-004.
Page F3
4 F
eg a
P T
N F G E e te M S S S S S S S S S S S S S S S E E E E E Oo E E E E E E E E E E OtoE S S S S S S S EEEEEE S S S S S S S S E E E E E E E E E
E R
YYYYY NN e e
Y YY YY YYYYY NNe YY YYYYY Y YYYY YYY S
e G S A
t.
O a T I 2 0 4 0 3 3 1
33 3 121 3 5 6
71 373 94 429 1 5 2 5 5 0 5 3 6
2 2 4 7 7 0 9 7 35 6 8 3 33 0 5 6 9 7 6 4 3 3 9 7 3 1 5 2 1 M A R 2 1 1 1 1 1 1 1 1 1 I 2 2 3 2 1 1 I 2 1 1 1 2 3 1 1 1 6 1 1 O 9 4 71 672 7 2 7 0 6 9 6 6 3 9 6 5 0 6 4 9 3 0 5 5 4 3 5 0 0 0 mT I 1 1 1 7 6 6 7 7 7 7 6 6 8 8 8 5 8 7 6 5 4 4 2 7 4 6 8 7 3 5 4 M AR 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 T
R O 6 8 0 0 2 7 1 9 9 4 3 o2 1 9 3 6 8 3 2 1 9 1 3 6 6 6 0 4 0 2 0 6 O I T 0 3 9 0 9 9 7 2
%7 6 9 8 0 t
2 5 3 8 4 0 2 1 6 9 3 0 5 2 9 2 9 0 9 8 6 4 7 0 9 0 0 1 5 6 3 5 9 8 P A 1 1 9 2 9 8 2 0 0 0 1 1 1 E t s R 1 0 0 1 0 2 0 0 0 0 1 0 1 1 1 1 4 1 1 0 1 0 1 0 1 0 t 1 1 1 0 0 R l G u N s Y I e '
I' N
R R I A ) 3 6 6 2 0 7 0 0 5 3 2 1 2 3 1 4 2 0 0 3 9 2 2 8 1 6 6 1 7 5 4 1 D
1 T f( 0 9 4 3 8 5 0 7 8 7 3 9 0 0 8 0 0 5 1
3 4 0 0 1 4 0 0 0 0 0 0 0 1
2 6
2 5
1 5 7 0 5 5 2 2 8 5 8 5 6 0 4 0 0 2 1 8
9 0 3 5 2 1 0 1 m R E 0 0 0 0 1 0 0 G 0 0 0 1 0 0 0 0 0 9 0 0 0 0 2 2 0 0 0 7 4 2 0 0 6 N a r L C 1
O g M N M E U o
r E
L O A P D T E 0 0 0 0 N k )
UD 96 0 0 0 0 0 4 6 0 0 0 0 2 0 6 8 1 0 3 8 0 0 5 1
9 3 0 0 3 0 0 5 4 5 7 0 0 6 0 0 5
E 2 c L A 0 2 1 09 79 5 1
1 0 6 4 7 6 4 9 4 0 0 1 5 3 3 6 7 0 0 0 7
6 5 5 0 9 3 3 0 1 9 6 0 7 1 1 5 5 5 1 1
7 0 7 9 F- e 1 7 M h V A C( 0 8 1 9 1 1
1 1
1 1 5 0 0 2 1 1 0 0 0 2 2 3 3 1 5 3 1 3 1 1 3 6 4 1 2 0 1 8 0 0 7
1 5 3
N 1 O
R E
L C I
V B ss Y N A o T E T r N L C I A )
T B(
8 0 0 0 0 0 0 0 0 0 0 0 0 0 0 6 6 0 0 4 4 0 0 0 0 0 0 0 01 0 0
0 0
0 00 0
0 00 00 00 00 0 0 0 0 0 0 0 0 0 0 80 0 0 0 0 0
A L R 0 9 0 0 0 0 1 2 6 0 0 30 0 0 0 0 1 0 0 0 35 0 0 02 0 02 800 00 03 0 C
I E
C 0 0 1 1 2 3 0 0 0 0 0 1 0 0 0 5 4 4 1 7 4 4 3 G M N O
L E U P U
O I E G D O )
A E 0 0 0 0 0 0 0 0 R D U D 76 0 0 00 000 00 0 L & 0 7 0 00 0 07 0 09 03 60 60 00 002 030 230 360 6 0 0 0 0 3 0 0
0 0
0 0 0 00 00 00 00 70 0 0 0 7 0
0 0 0 0 00 00 0 0 8 0 0 8 8 A 1 8 3
0 1 0 0 1 7 9 2 1 2 1 1
5 5 1
7 0 V A 0 7 1 1 5 0 0 2 0 0 0 7 8 5 1 2 9 8 0 1 0 9 9 (
1 1 1 2 1 1 3 3 1 2 3 6 1 1 7 3 9
1 9 1
e 1 4 7 1
7 1 4 7 8 9 5- 60 34 37 a a 45 8 3 9 5 t 9 0 4 8 t 4 0 d
h 4 4 2- h 3 2 90 343 8 a 4 2- 3 0 3 a 4 2- 2 6 3 0 3 3 0 4- 2 2 9 U- UU Am C s - 2PuS 9 3 3 Ammc 4
lp te n- 2 2 - 2 2- -N r- 2- N 1 1 1 1 1 1 c - -
o o s- -s -
-K UUU N
a ACm e-C C CC AB MbPu- -b S S r
C o C-s K NPuS r
r n e
a e i
t i l ua d b i o t e e S g M Ar e V
n 8 8 8 o 9 9 9 it e 9 9 9 l
lo c ta e
D 1
/
1
/
1 1
/
/
1 1
/
7 C 3 3 3
5 F _
e g
a _
P _
T N 1 1 I i K K K L E e e e e e e e M S OaSE OoS t
NE SE S S ES ESE SE SE SE S SE SES T. S S S S S t E E E E E E E E E O dS OtoOtoOo S E S Od E
R Y NNYN e e
e e
Y YY YYYYYYY Y YiY YY YY N NE e e
Y NNNNNN e e e E
Y Y NN e G S S S e e e e S S S S A
. IO -
x 2 0 5 1 1 0 0 4 5 6 6 2 9 8 8 2 7 5 7 2 0 4 3 3 2 1 5 2 3 6 -
a T 5 2 2 5 3 6 8 2 2 3 5 4 2 4 5 3 3 5 6 4 4 4 4 9 9 6 3 3 5 6 MAR 1 1 1 I 1 1 1 1 1 1 1 1 1 1 2 1 1 1 1 1 1 1 1 1 1 2 3 1 1 3 _
L H T MAR O
I 2 0 7 8 0 0 0 2 8 2 0 0 2 3 9 0 6 0 5 0 0 7 5 5 6 8 7 8 7 8 8 4 0 0 0 0 0 0 0 0 0 0 3 5 3 0 2 6 4 6 7 7 7 5 7 7 7 7 6 0 0 0 0 0 0 0 0 0 1 1 6 8 0 0 3
8 0
4 0 8
0 3 8 0 8 7 6 0 0 0 T _
R O 2 0 2 9 6 0 9 5 0 0 6 O I T 4 5 5 2 5 0 9 0 9 3 1 1 1 6 6 7 3 0 51 9 0 6 6 3 81 2 8 7 3 2 4 4 6 3 9 9 6 8
0 2
9 8 5 9 4 1 7 P A 1 2 1 5 0 0 0 1 9 0 2 1 1 1 9 0 9 0 9 0 0 0 4 8 7 8 7 0 I. 4 E s R 1 1 1 1 1 1 1 1 0 1 1 1 1 1 0 1 0 1 0 1 1 1 1 0 0 0 0 1 1 0 R l t -
G u Y -
N s I e T N
R R I A 0 0 0 1 0 0 0 0 5 0 0 2 7 7 7 0 0 0 ) 5 0 0 2 0 0 0 0 6 6 9 2 3 6 1
8 0 0 0 0 0 5 6 0 0 0 0 0 0
3 0 0 0 0 1 T E( 0 2 7 9 0 8 3 6 71 0 0 0 5 5 1 1 2 -
1 R 0 0 56 91 0 0 1 0 0 0 0 5 0 0 4 0 0 5 0 0 0 0 0 1 m E 0 1 1 2 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 8 3 0 N a L C 1 1 3 1 _
O r MN M g E U _
L o E r O A P D E )
6 00 0 0 0 0 0 0 0 0 0 00 0
, 2 kc 0 0 0 6 0 7 6 6 0 0 0 0 0 0 0 0 _
U D 0 1 0
6 7 5 6 2 6 2 9 0 0 0 0 e
L A A C 2
2 63 0 8 6 2 0 1
2 000 83 0 52 6 34 030 30 8 0
7 2 5 5 9 9 0 1 5 1 4 6 1 9 4 4 8 2 6 1 2 6
2 3
5 0 4 4 0 6 3 -
2 Fh V (
1 1 4 0 2 4 2 1 2 1
2 5 1
0 9 2 1 2 4 0 0 8 1 0 0 0 5 9 3 1 9 3
O, EL C R -
I V B s s Y NAo T N
ETr C
I 0 00 0 0 L A ) 0 0 0 0 0 0 00 00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 00 A T R (
B 1 0 0 0 0 0
0 00 0 00 030 02 6 96 0 0 5 0 0 0 0 0 5 4 0 0 6 0 2 2 9 0 0 0 0 2 3 0 3
0 0 0 0 0 .
C I
L E C
0 2 5 3 0 1
0 2
0 3 6 0 0 0 0 0 0 1 3 0 0 0 0 0 2 0 0 0 0 03 1
7 G
O M N L E UP U O
I E G
D O 0 0 00 0 0 0 0 0 0 0 A E UD
)
0 0 0 00 0 0 D 0 0 0 0 0 0 0 0 0 0 0 0 0 R
0 0 0 0 0 0 8
8 L &
A 0
4 0 7 0
0 3
0 0 0 0 0 0 00 50 07 03 646449 50 03 020 70 00 0 08 44 4 0 03 0 0 40 3 2 0
0 0 0 2 1
2 2
4 0
0 0 0
0 0 _
V (A I 1 1 5 0 0 0 0 9 1 2 5 0 0 1 0 0 0 0 5 9 9 1 5 3 5 2 2 6 2 1 0 3 1 9 9 1 2 1 1 9 _
1 _
e 1 7 1 4 0 hap ea 3 8329 2 7 a 4 8 9 5 7 t
d 5 a 4 0 0 4 8 i
2 6 3 5 3 90 34 38 2- 6 3 h a 5 3 3 2 9- 32 3 ta 3 04 09 r 2 2- N t
du - - 1
- - 1
- 2 - -
1 N 1 N A C mo C F s- e lA B1 MP 1
n - P- - U- UU A CC lp u uS -
mo s A teMP B n u- Pub 2S S r
U-2-
U U- C-s KS r
r -
a r e i e h l d t i i e a F o M W i r S .
A _
m a
8 8 8 e 9 9 9 t 9 9 c t 9 e a 1 1 I l
lo D /
1
/
/
l.
/
C 3 9' 9
e 6 b l e f F l
l b I s e g
af nyt
. uth i .i w tp oir al t a s
e eld c e rBf s s qr s e o P lp cMge T m a
taE o e raeis49 nc s72 N M s nht tysl ny00 E y s i i a1 1 e
M S S S S S S S S S S S S S S S S S S S S t ih i enon na* s E
E E
YiYYY TE E i Yi E TE T E YYYYTE E EYYYYNN TE E EYYY E OtoE E E i i
t v )
1 t
gweigt e0 rw5 c
a R e c o oa e e e a qi G S h Bt a m er'n 61 lu a A g r h o ih 5
a r tfh"da,vL I*s r o i- t
. O f o t haff s2M d nqu o e4
( d e 0. Ee x I 0 2 6 0 2 4 9 3 9 02 6 3 2 4 5 5 9 0 0 6 2 d a T 7 6 4 4 4 9 5 3 4 2 5 3 5 7 2 3 5 4 2 4 e s e nt ua se rere1i th M AR 2 1 1 1 I 7 1 1 1 1 1 1 1 1 I 1 1 1 1 1 1 u lat t h s
- e. sr vl us t o a1 u s d e de sel e h w0 sr l pc s6 e O ic ka r tr l mai s 1 v 8 4 9 0 9 6 8 0 5 0 0 4 u nBe o a a eye s mT I 6 4 6 8 7 6 6 5 1
7 8 8 4 6 5 8 7 8 7 5 0 8 0 5 0 0 7 8 8 6 pn ei shl r e M A 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 h .
c n re igilowa i anwl t
e u R a o r e s v a
oS T ei De er t
.hl o. eaueser t
r s id R O 2 2 0 1 0 9 4 7 0 2 0 7 5 19 0 4 2 2 4 o e f g y t i g r
t O os a ). r o I 1 I i T 0 5 5 5 3 3 1 5 2 3 4 5 0 4 0 6 1 2 6 2 sd n dt P A 2 8 0 0 1 8 9 9 1 0 0 I 9 9 0 0 0 7 9 9 9 iogn t u rdtsl) pd e s la del E s R 1 0 1 1 1 0 0 0 1 1 1 1 0 0 1 1 1 0 0 0 0 tai uqe r sBd 0 R t mu r hei men r0 e n9 ouf l t l G u s Y md rd e e in isb isd s2isI r o N
I e T te a t o )g any*
n l a
no- ean N d n is1de n0 R R I 0 0 00 00 00 70 70 00 0 0 l i a a6(nm A ) uam uqzh3 we 0 0 0 0 0 0 0 0 0 0 0 O T E( 6 7 0 0 0 0 0 0 8 0 0 0 0 0 00 04 1 4 8 3 5 8 l
cBi n rt 1 a T
I m R 0 0 1 0 0 0 2 0 0 0 0 2 7 0 0 1 2 06 60 1 0 0 0 0 0 1 0 0 0 0 0 0 idtn i6 e o rh E ivo o1 lv b (e al 1
2 2 4 r N a L C d c f
)
- puasl u eu mgn O r MN inne ee 8 2.d, c a vi ru g
M g E U ht b 9 5 e r
r o E 9( i eL o a L r DO f v e
1- lt d rBMewh oa nu r - .E A P s. yh Jusi me Ta T E 0 0 rt e nt s - er a ah nrt ei
.h t N
t
) 0 0 k UD 0 3 60 00 0 0 0 00 0 0 0 00 00 0 0 0 0 0 0 0 0 0 0 l iua i
f t fh e a ght luw I
E 2 c L A 3 7 00 00 00 3 7 1 2 0 6 2 94 0 0 930 0 5
0 00 40 0 1
1 4
1 1 5 5 0 2 5 r enpe r m ot f4i a e o4 wvl b M A C 1
iacl ted Fhe 8 2 2 2 9 6 0 3 0 0 0 ans0md .La 1
da 1 1 1 2 1 N V ( 2 3 4 6 4 5 1 0 4 3 1 1 r
oum .Mp e t
f a a d a n a. E c O
R E L C qns Bger d
e ut se ga .e c e0 r
9 eh a I l iHs (
u0 4 r g t n V B ss Y ta o o L q20 ah e e ne N Ao T N
t dndtwy s.
i Mrlye E sa te eb e
rl wb E Tr I s
e a w a t.r aev L C A ) 0 0 6 0 00 00 00 05 00 00 0 0 0 0 00 00 0 00 0 0 0 0 0 e
. a elt a hoix w ms t
p e. h T B( 0 0 0 3 0 0 00 0 0 00 00 0 0 2 60 1 2 d nr n o opa t
sc e A 8 0 0 0 6 00 t ssioliyc 1 1 1 1 i R 0 l
C L 4 50 0 0 ia el l 0 0 3 c 0 5 5 0 0 dlyr e apnaa sduo t
E 5 2 1 3 0 0 0 0 0 u r a em 1
I C n t e nnpai aw n G M U N h c
gh ig e t 6ef aa I ht e5 O E U vf r a o r o4il 9 L
O P
G fo e
r r o e f)o reh s 4Ass 2mewb t c
E o1 ori +11 t
be8.isAn f
I s . te utah 0 n s o D n n A O E )
0 0 0 0 0 0 00 0 0 0
0 0 0 0 0 oa e (wqwi s t e sl 4 cfLo as nt R D UD 8 0 0 0 0 0 0 0 0 O 0 0 0 0 0 iam.ih t
ges edMir a L & 0 05 00 0 4 0 00 0 00 000 0 t
n e aipe h 0 0 6 0 2 4 0 0 0 0 D 0 0 5 5 7
4 0 7 5 9 e s t er l o set a oi m u ewde I
8 8 A 1 1 2 4 L1 imh n qf og i
V A 2 0 3 8 9 2 1 2
1 1 6 8 1 0 0 0 t ot a 5 5 3 3 a a otio r s sh al B, m l
( 4 5 5 1 9 rf 9 s eLz o ist t
9 1 te t et r 1 9 e r niuu a i t h o d oio s s sed . w c p te r m r e r e)DMs edi e a re ef 1 El eh r r toh s ta8 . e ptr ws a icdte)f r is m99 )g D mo a p 6, w lpad yoy= r t a 1 1 s e8) e 1 4 r n or na n - q . e )r0t o (go leeJu 2iB n ngD t 1 q 1
d 4 4 2 0 73 0 3 8 9 0 4 0 7 5 s 4 8 9 5 3 3 0 4 8 t a edst I4d f a
- 6 1 4 2- 3 2 6 3 5 h *a - 2 3 3 ot i
l 9 - - - - p e 1
n - 2- 2 N 1 e rr c q f B s.
u u2 S 9r 812 ar sB o 5i a c -
ne mmc -C K PuP uS AmoC Cs eF lA B MP u o s r - - - ah f qa ef N AC P UUU et migro s e B, s uhi qTd n m0i a 2 eya ed*h dr e8 o 0 W ra 0. r6*
t g2 to 5 b.
e et a1 9 ht r t si avwttah t ne ia r te s sea c c si rpo6 7 iw0*e60 0 a se se s ( a m t er enoy i ud e2l 0. h uta u u c qd( r e(bato 17) lac
&e a
t t
a t r
e a
l anstir vui af tne a nl ut aul e t
a p2 (1q v 6 en e
cc ml u Bsi t
g e qtr sad s e v M W LLuBe we V
e MMl a e c n rLa fo e8 r s2 he hc t i EEVa r EEUtsUl yc2Edi6 ns ui s a4Mie r ns nI s
z01 2.foh n w it n
o 8 9
8 9
OOPiP a DDGuGm n n s.
.At 2 mhe a l eo*e pC 7 ml 7 a e.di c te 9 9 e e e e e . eh4 c n D T W D A g.hi9 me 4 e a r t l
l e
o D
1
/
1
/
1
/
h T w 1 a sD1 ( th nu C 9 9 ABCDEF . . . . .
G I
I
t e s h n n 7 ht . s n- ohh s ut s i F ety a. a iUr utg s e e e.
d e w e loh hi v v ye r ve s a ht s
e cr see n r w s o d
nL e. s
, e . e t
n g
e t t i r hi dt nc acg tc t n r i l aM e, uh e a bs in a ar o s aht r e ss edt ht e iEss n
s e P dt h r yne heb h Ki ei etroi t r r e5 u5 - le h wf to dd pte s f
nh 5 o r p lae bt a ehe eT h i
at i 2. dbei nl s c a e r
vF t t t t e la enn t e orAr ne eo l t
ow ut lmt t hi t s
a s
d r eof pumdi uq d rfLhl3 0i t i i ql t
< u 2, bmtenta t
t r oclat t i e ;
e tet eTC i s lse m a B o s c nr i s s ph is c is t t
.iodT r r u i l
e r u s r oh s 5 s pee et gs t
os ur r es l o
s e et Ts0 F, ka et r nah r e qe p t r
e r n hd t c e od . a1 f e ei t labe i t a o o iLr o a pb mh a ah lawTp c os ta sh r
oR Kuie a yoit gt ef e .o e e ne esr u u t
aE it gt les r ot r ipr) r ine s v l
e ht bo e hid e u v laT h t l oa wd e eb e r c ee2 r -
e8 ea n3epr e wp ui e d hc Bmei. urh s e f o
d mol ug t
ph e isl 2 .w l gU s a a s oleca ,
lyo e. ml o a
. a a h e r
hhei dn kea t I r to m
o lylvba o nl e .gms r v t f f r al n a tpr t
s Ob t iyor4aglp s. r e ame e h
u s
e
.y e a oyu=A ma r
mix m n a
f rub2i e3- nr seu t
ed pr s o e s cd h e a o c r 6e l
bm dir aM n pmUfe an t h n r t ui n r r d o u wid T h ) npm6d a
ee i
t n (s rleb e
f o o es ht e
is se ig t R h q d h h a h2 ea e5d s etna s
t ye mis O
P ht e
A
@B 8 et lyo zf tnh at s e u1 eb- u s e.d rc i lch i tp e e c
lyu a e nb it ua y ivDsl t e n a
d n
a .
E d t o2 a ehta nct rSi o umt r dc a ml el im1Lt h a l ta8 a 9 R e s N02 a nr h arh t r o csio nd r iw e d a e n d 1 9 u
a e( s.dnwne s a te d tcfi ad a apc n e wurla3dl e h md ae Ato s 7. d io ic -
G c r e e e0l 9 . qu t r wl u ur e yb gge a3 s n)i neCi ye hf o iei to 91 N e ar t yd 4 v g - taaistsnh dl ah nCurr tTr d s . 4l a
! v 7i f d is 9 a t ood a R h dLn bnwugui o ani0 sr dt i n r nra a fo i hsra h1 s
ak nmbTef stx 3l yi g r y n i r e f r a s e M a aMiul a(h e t hgugCni el a o al e
r gs e ad ed t e I m s gE n e tno i neD apuozcytcd ps e t e
n s us f y oe N
l r ea ei wie b nrn ns nia a ra, e i r ri nht O d i
mh at t
c ohhd. ee aol ot r s eiTe uar tur es lovigrb c oe o i r l
c - ch uw o odtxuhi l
e af o tai yi clt e t lore u h mcl e e f os Whf e c t M a m ht t t
r ae s n eupc . t r s h1 t
t p
qsl au d u s L e s yi ued sh f nf tde ceti r
o )g M L aBwoh la n vo A
T h e iewtcel lei db e aiarot si1 d to d m g5 i aAl.ieowde qE an2 ts -
r f
1 s8 a
w1 0 l) mtso ei e bu t
vei t, t r T
b t
ainde mt- e ye nlib c e r r S
omoyr sh3 gn y pd sBf eea o e u2 2 5q u (i
Dns t 5 ps r a t il s s c0 n laI ) i e uo e l 5
c
- c1 t cTi m ;e Lrhc fodeutinluna ul h o .kc ar osu qepn*c y
t e wop c u r 0. si 0 s d2 v I. ea me 2 9 ta 9
d a
F r
A ). on met Ke bhe rula es lpe ee3 oe r e sl uz ki os i 1 d O>
R f o etmihh r t e qe mt i hi c o nnmreb 6 p r ipevt a s lu 2 o f
I V R L b mtoWt l
e e .hah t l ebefif pe oa cs we9 c3 re hea v uw t h o
q 8 s 9 e N E 7,wB 4 i lwh d oa nt nist t l l t ehd n isLn( i et u u t eLil t e 1
( t d
n nt oaHMs t
E ht e le2 b( s nmi ciw
-.d s o )
uf sMaa tc u . cer eis a a t e i d *. . E sl aar aErlai L n a4 tp9 udGs awfic .a . ce nat e4 0k i el aidt d s eh voF ate h tnL .e c
be ei d e p
Ti i %m hmll i
A d e1 c1 s t
s e c r pr pa1 pmgeMl s sw n C
I e
z y
c AsPl n9a e geg rl bi e ie c g (- yr o aEba hu1 . gu ah t o s
if r G l aAs a a n e el r myg f e et s q d d r wQwh a e r r a rh p e O n e o ciGwlApe eb e e i wt e rBiens a e e6 us re a so r c t a p s wildn a ht e .eth e r vnd eh c d o L
aMad ns u e6l t t nia lb0 s O ler 7 r b gt feh meem Awsi a iD icel
.n E L aemo ana r igo tp* s y r e v
I w.l dnb en
- 8 an r aKai yhh D 4 eiMd sc tod r e c 5. ad l .
.- PM5Et e e e mcDt ;e ul ei g et oa a c ne s re A y 5 al
- e u pW roc ah met ri tp4 asI az i h e R n Ae a iyah l u e8 e a erly f h ehl m.f vw a v sd esieele odlasehtoo a Qt Ft a a s c9 o w c et An e ul s 8 e n ri s eh e e s a0 sI I hcsu gy .a il deV t
9 Lluuwlyuhls yrmh tntoof t
k ie t 9 i l ul a s a r r o n t, ai n e tn L tttLl n cious ve r nadi a eri nll t
1 a u a eX qqqqq u e.t reoh vn e e ni ot s ps u to egei s sit BBBDB i s
M Edee v . F d.
p ct eeded d telAc) i il egva d a n c -
rP e
pA h tr le x ler 9%9%6 eean s d D. ni a na lu. e. rp1 n rcI o
3 f s
e 1 8 i r t o pob
_ i 3 n iave pb e m
Q m
32223 t a
m t e y a, R h waet t
s t I dl u aCiklul abo cl qw f a el s e rl o or a r id r a n frfs min ah w gM etivoTe kn i
ts *r s r t
r te vi7 iyDf o i w lsWat f
e e u t dt o t e wd ous w ee* e v e uTd n ffl a l t ei if t
a e r"d e n nmro e r e 9 h a n s. n e o u hs nu d
e .i w
s 5 ne sh 5- ab a c eb r a os or inmh 1 t a s eewk nsleos krf(h t
y t
ai sk iq mlyal a hl bl o a me nhi z a r rh e ws nla" ci c ck ua te e ly n
ilmmmmmin i ii lat e" FAv eya vLe Lork eiuh u uw s eo ina t nb n ts t e no a e pnf%l r t aa / / / / mi d" a uadnhM Esd Mpa ea ri oe t o o s a c s r o iiiiiid hl a c e t a
n C C' C C C ns e t e4 s vdb uCE ua i r o trh ny whe e
e uuuuue ri r
o 1
phediLe e
ae yrar"y h tewhhAm* sa s t r rd ol o ln tp T Las t
66665 ata r u g, b
s : 00000
- - - - - s n et rf t uRDh sE t Gr ah e y t hl P ig
.Es _. M h fof rde c n o e .
c4 ha re EEEEE h o biib wfrtak(1 e n6 le a 9 S 9 9.I s s 0000O e e rd uc ieOPe s
r .Ath et n e8i
. od h 1 aN o pp a
ele 0 ;r n 1 E )g i
t s si a
w eu u utor r o5 c -
L ph s
- * * *
- ei toeQyeu g
hmnde a,D 1L r min;0 q Lr ei qc c t mu al e imM a s s e 66666 00000f u h lc t
r a s ls c a e o v uusht .fMt s a si a -
. c ah t r 9 B r3 Mwlaeo hE n b ooyc a u goEa rk cwmS*
El,r r t ies r - - - - -
EEEEEo l e laLiv eiva Me ci at sl mo e pt e 2 e e n 9 oe mgm r e lmrpo 60808.l h ehvs i irHh rh0 r o t 2 c *=sdW3 hh 8 E pPr dr T ta 3h . e
( eT3l f a r r
TT 88789AT 1 e l a wrE eO L 1 K L M HD l}jlllll
8 F
g e
T a N P E S S S S S S S S S S S S S S S S S S S S S S S S S S S S O)C o)D S S M
E E
E E Y Y E
Y N (E E EEE EEE YYYYYYYY E E EEE E E Y YYYYYY N(EYY E E EE Y YY E
Y E EE E E E YYYYYY R
G A - -
xI
.O 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 3 6 3 3 3 6 3 3 aT 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 3 6 3 3 3 6 3 3 _
MAR 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 I 1 1 1 1 1 1 1 t
s .I O 5 5 5 5 5 5 l int 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 6 7 7 7 6 7 7 u MAR 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 s
e T R O I 8 5 2 4 7 6 1 5 1 8 0 9 7 6 1 6 4 0 7 8 2 4 5 9 0 9 9 3 2 R T 8 8 0 3 9 0 1 %. 7 1 0 0 8 2 0 9 0 9 0 0 4 0 9 1 0 8 9 %. 1 9 0 0 0 m
O A 0 0 1 1 0 1 1 0 1 1 1 0 1 1 0 1 0 1 1 1 1 0 1 1 0 0 0 1 0 1 1 1 R
r a
r _
R g N G o O N r I T
I P J I
0 0 0 9 5 0 0 0 1 0 0 5 0 0 4 6 0 5 6 5 0 3 0 8 0 0 4 3 0 8 2 0 4 R L 1 0 9 8 6 3 3 4 2 7
$ 6 6 5 6 3 3 3 6 7 0 7 9 6 7 2 3 7 1 1 7 7 0 713 15 2 22 5 3 2 9 21 D k O 5 6 5 5 6 6 5 5 5 5 6 6 6 6 6 5 6 2 3 1 c S E
1 e R N h O C M s
)
A L s M 8 4 5 4 6 5 6 6 A
T o YI S G 7 3 0 3 0 7 2 2 0 3 0 0 3 0 2 1 2 1 2 3 7 7 2 0 0
1 0 7 3 7 31 1 0 1 1 2 1 7 7 0 3 2 2 0
1 3 0 1 1 0 0 :0 0 0 0 0 0 0 0 0 0 0 0 0 N 3 r T 0 0 0 0 0 0 0 0 E FC N( I I
A _
M E a l
T N Lt R E -
O B n S C) A R e CN I
V A Tm TUM I
X G 2 0 1 6 8 6 4 6 3 7 9 8 2 3 3 5 7 5 4 5 2 6 7 3 4 3 7 9 7 5 8 3 9 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1
0 -
N n I I
S 0 0 0 0 0 0 0 0 E o A N
3
(
L r A A
C i
v I
G n
O E E 5 4 5 L S U)
LA 4 0 81 57 3 4 6 4 5 1 8 9 0 7 9 2 5
9 70 %5 2 3 7 7 0 2 8 5 4 8 3 1 5 6 7 0 1
O I C A( 3 0 2 1 1 1
1 8 2 1 5 4 1
7 1 1 6 4 6 6 9 3 1 1 4 2 4 1 1 6 7 6 I.
0 0 0 1 1 0 1 0 1 0 0 0 0 2
D I V A
R T 8 Y 9
9 L 1 A E UU) 1 N P LB GA(
0 3
0 7
0 0 2 1 2
0 9 04 1 8 2
5 0 0 7 8 7 0 3 4
2 7
3 7 %4 0 6 4 8 7 0
1 36 0 0 3 4 5 7
0 1 8 5 4
1 T1 . 3 1 1
5 1
7 0
8 1
1 2
A 0 L0 0 0 0 0 0 1 1 1 1 1 1 1 1 1 1 1 V
8 -;
9 9
1 e d
i l 4 c 3 7 4 u a 1
4 1- 31 5 - 95 5 0 9 0 1
4 1 34 37 45 9 5 0 9 0 1
4 1 4
3 73 4 5- 59 5 0 N hp ta 1- 51 Ss s- n e- n44o 8 1 3
1 1
- 5 1 1 - 5 44 3 1
8 1 5 1 1 46 -
e e r r r 1 31 e r- s s n -e n o 1 r r e- r- s-s - n -e n o LAD CC CCMF Z C S S I 1
CCCCMF Z C1 -
S S CCCCMF ZC r r r e a e t
e e g i
li h i
h d k k k l d F F i
F n l l l i o
e i i i M Ar r r t
r a M M M S iA A C n 8 8 8 8 8 8 8 8 o 9 9 9 it e t / / 9 9 -
9/ ? 9 c a 1 1 1 1 1 1 I 1 e l 1 l
l o
D /
6 6
/
1
/
6 1
/
6 1
6
/
1 6
/
1
/
6 1
6
/
C 0 0 0 0 0 0 0 0
l lIifIl II l r
9 8 n e F
=- r o a w e o nit in o g
- t c
e wca r tei h inl r a e on ev fo t nth e P Dkie tc cwi bo t sr w el wt u e hte h t r e cl nel l a wei e s
c o
D int o or tp( wg r c a
- 4. i sC t
o .
e9 s e c0 an o 3 ei c t e a1 we 1
etrb al eoh ch g =-
f ht i ih t
o de ap d a T8 h =
l e
u s h ec e e c
. 9 wt 00 8, as -
a dl v i pa 4 om 0. eci 1 d}a n lcua rs a w
o ns w fo fr1 s nel e.
aib c o
n r
n nis7 leu J, u T i a i k eh0 t m
o vt e r I a ot ee p v ht nti iae ca t s fo as t c ee. d r wa rh i w
hede w t
gt ohk n *g d r io o tr u e n ts il ed su n r p t
r e t
e pa ol k emsui o i n
T a fr hrse cvs toulaic nal t ti u
r o
R Co de v9 8 seu l t os in O dni o t ei ig dt y t n5 - 8 r e o P o we - c r r M
E
- e. atr raa ge ihl h cun s
a poFYk e n6d e g
n.
1 R dh i a nA frk9 nh ac a.
irF s ev wa e oe9 4, .
mht h1 0 s s e G tr ar i Cfog 8
r mo ot i ohe6 or ,r N
I di i s oat t go t
at r s T C k oc .
a R nCh a pT c
e ri a io e ni l .
ir v
t e a t
st n D
1 rl e a i
. eh r Dt r e
vrbag al om n h e E -
idt ni d it ttoc e l t 1 F d lp mel o t ga pi r n N r na o fHf r
i ish ce ec um5e m9- f o a t
O f i o at l o t e .i n hlpa sF l e n e
i u M CpS o )a u vI laL e5- Lab mtu et c x b
t a l Tt L v r i s hg-a n e g E a ogm l r 4C Cs n A t ofi s h0 t
r 6 e phi i t e i w
d n
t )
d y3r ut h )tar sh ~
ht o nd(
a(8 foat )
47 mfo a = i igs wo t l l
o ta, n
hte39 s det a c, ne e f
il g* 1 9 e oU 7 - nk a ht m ys 1 3ih t a
SC5 hwdC a(r (l tc O, r p1 fo, s 2 u2 iot ta e i n e r
R )l k a n na ye 5* n. 1
- 3. b l rb ie t
r n w
T te yMe i w w o vst s lil
-. a c I awi o s V r n ea 4 t u a e wgno d s h
( rol u kn5 kl a l
o s N 'gf a . wgeni s s %
e E i v u41 ai erl ui rt c r e t u v L Cli pCi sc l s i tat e r ueaua h vDe v e.m ht oi i
t c
t lat a A vo s t i l,py k
I 1 r c .i ie t
o c nah C i eal e 4 ee .sc eikt tyea e c ia r t i
d nh iDla pr r n I
G MaA r s lu 1 ct ty a e al . n v or t e m bh ot h R a
O ot e vCa tp v as t
- L fi lUn3 ny wb e s ceAme neAeC k oiws t a ni 0 5
ih9 s tyt 7 O
I i
C s. i od c c ne a an etco0 t 9l eu inol bl a 4 8
pnC e nh uHet 1 a kd e a of D op tr t o e A
e r
a s l.
l a h ont ut si ld .. ivioev t at t h gh e ei c ut a d r
u R
t it J t o tpbi h luie r ni nl ar u ve e
c 8 n .
2 a st sCzk r ai oh a h o 9 U t m3 :s lewwe r pyid l
e mcf st P
r
. e 1 v oyl k 4 la meh t t gti o t n
U nd
- h e l e c 3 n anla n isly e e n
632.I.
3 5 8 o
u0 ewhe*
e ie0 u sk e s i ui e nl au r1 s
e c3 a9 c g n a m 5 0 6. 1 1 1 ti c
eo2 2 ar ss6 e 221 - - - e oms
.r a r
e la3 v s w5l - am ect s l u :
oAv d ge e
r - - - 5 05 a 45.6788 p
s mow D ea e th ic oaleF r wp eti e c s e nh t it al A 000000 I n se
- m es e c . s . r1 h r s mhl r 5 - ic -.if Ci t c ri5t e i
t -
r wehit c s) at7 se ugy ; o s g~
a Rni h t sC7i lysi9 r r e Nat wf nt ly2a1 im r 1 f
995 nee r
a s ;
aer - S r o on uor t
ieteh1 f i naH1 n ( -
s s r t o; Uce inun neat h dtoiA .r es le iy cr g k g a o 08. dof T n6 - r t o52 aFi 5
e eth b
i b e h a d e he ed rt . -a9 Cd1 y s s et n e g t v r emze r e -
0t e t o s D. t a o n u yi t r s a s at oy x a.c l
y hl ieu anof rl a
h w r me onW8.l a n t
r ab v
si eh p en -
fr e ; 0r e o s e;;
u 0 s t o i lais re gaiiiih : ). iacl ; n 1 0 h w Vee nsCCCCcrageh sl uu r wl l l a a ppppea gf uo lt t m g ;;. i --
e i c .
t y v io 81 0$2 t s on
< < <- <- 0 f . t f
laU u ic Vvoetooooi t
y a lan aaa lah inanisf 1 ilpt t t t t t t t t
wetak9 r r ne e ger r a g e
ee nr r al a e
r e AG nP ;- l o
s 4482- 32 e
- 61 0 t o a
ilr d.
laU5 ra m54I 0 e eh a5 -na cl re t s hh -,
c c. R<22222 i e.
m n P r- aa6658 ewt AGCis r* * *
- gs ebFsse er n a e p b. a h aa r
a ruluD t
t yn i m n eeU e e P s
e r e m
e ee te i45 s 43 e aoe a a c s nTTcT21 hhih1 r 975l 1 2 l
acvwDticnh o ai r a c r te iddG v i e ay t
e i vih nt te o d DDT t e c o
NARC. D T 1 . 23
. . nti Ca c I
l' lll '
T N
E S S S S S S S S M E EEEE E EE E E
E Y YYYYYYYY S S S EE OC)ES SESE O)E D YY N (Y Y Y N (Y Y YYYYYYYYY N(N(
S S E S S S S S S S S S E E E EE E E E E O)O)
E E R
G A
.O xI 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 aT MAR 12 12 2 2 2 2 2 2 2 1 1 1 1 1 1 1 2 2 2 1 1 1 2 2 2 1 1 12 1 2 2 1 1 2 2 2 2 2 2 2 2 2 1 1 1 1 1 1 I 1 1 2
1 2
1
.O nI iT 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 MAR 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 T O 6 4 9 1 2 8 6 3 6 R s T)
I B 9 1 1 9 1
0 9 7 5 3 6 3 6 9 7 0 9 8 9 9 9 %05 495992 2 7 2 1 7 9 O l t
R A( 0 90 1010 11 1 0 1 1 0 1 0 0 0 1 0 2 1 1 1 1 1
1 11 0 0 0 0 0 0 1 0 0 0 0 3
P u E s R e N G
N R O I
T I U 5 5 3 0 4 0 0 9 8 0 4 6 0 5 6 5 0 3 3 5 9 0 0 9 4 0 3 0 5 R m L 1 2 0 3 0 7 7 0 3 6 5 6 6 6 5 5 6 6 7 9 6 7 2 3 7 1 1 3 0 9 0 1 0 3 0 9 9 1 O a r
O S
6 5 5 5 5 6 6 6 6 5 6 5 6 6 6 6 6 5 6 6 T E I g R N o O r M P )
A L k M A
T c YI S G 3 1
3 3 3 7 3 7 3 1 3 1 2 2 1 2 13 0 7 3 1 1 2 7 3 7 1 1 I 70 0 3 2 2 3 23 6 3 7 0 3 3 3 0 0 1
3 3 2 2 2 3 1 7
0 4 e 1 1 N h TI h(
E M FC E
i A
T N L ss R E
O R Bo C) A N
I V Ar UM N TC I G
S 4 4 0 1 4 8 7 5 7 4 3 5 7 5 4 5 2 6 7 4 7 9 3 4 1
1 9 7 7 7 9 3 2 E S S 3
(
C L
A C I
I T
C Y I
G T L A
O Y N A E L L U) 2 1 1 3 2 2 6 2 3 6 9 0 3 2 8 0 8 8 70 0 4
0 1 A LA A( 2 8 6 1
3 1
5 9 4 1
5 8
7 9 6 0 1 3 5 9 70 0 1 5
4 2 1
4 1 71 7 49 72 12 8 4 4 4 7 1 1 1 1 9
6 1
4 D
A N V R A 8
9 8
9 9 9 E m
1 1 E U 0 0 0 0 0 6 2 7 6 1 2 3 7 B L 8 6 2 5 8 8 3 1 8
8 4 7 6 9 9 0 9 7 1 8 5 4 5 5 6 4 7 00 00 77 6 3 5 63 62 9 20 6 T A 2 1 1 I 1 1 1 1 1 6 9 2 1 1 1 1 1 1
V e
d il c
u 1 4 7 4 1 4 7 4 4 7 3 45 9 5 0 1
N 1 3 4 1 3 1 5 1 3 5- 95 5 1 6 60 1 4 1 1 3
1 1 3 5 -9 5 5 0 6- 6 1 4 1 1 5 1 1 3
- 5 6 6 8 9 0 e- r- s -s - n - e -n -o 3 3 9-s- s- n - e 1 1 c r n o c- r- s -s - n -e -n o -r CCCCMFZC 1
l I
a i
d lk k l k l
e i i i M M M M n 8 o 9 8
9 8 it e t / 9 c a 2 1 4 e
l l
o D !
3 1
6
/
1 2
1 C 0 0 ll
1 1
F s
s a
s a a e g
T w w r fo a N w E n n P S S S S S M E EEEE O) D O)E E YYYYYN(N(Y E
F S S E
Y ih l
t o
u o
s tos i
l t
o u
o s
t n
u o
c c
R e e r e a G r e
r e o A ht ht e ht t
s t
f if if n e
.O ie e le xI 5 3 5 5 5 5 5 5 5 l
b l
b b tm a s aT 2 3 2 2 2 2 2 2 a a t uj MAR 1 1 1 1 1 1 21 1 1 tp e
tp e
p e d a
c c c c c c r a a a o s s s n a a a i
.O 5 w w w m inI T 8 7 8 8 8 8 8 8 8 l t t l t
u ht MA 0 0 0 0 0 0 l
0 0 0 u s u s i
s w R e e e r
r r e "g e e h n h h i r
T O 8 6 3 5 2 9 2 7 2 t,
o t,
o t,
o .
o t
R I )
s s s s n in TA( B 0 1 2 9 2 2 3 0 9 l l
A o o O t l R 1 1 1 0 1 1 1 1 0 lA A i t
u M P u e e
l o
E s d g
ble le b
l b s e
1 R e N i
r a tp a t a
p r
g G R I O
C t
r a e c
tp e
c e
c n .
N I
F U 5 1 0 8 0 4 8 5 0 d c
a c
a c
a "a. .
r m
-m R m L 0 2 4 7 0 2 6 4 6 5 6 6 8
5 2
6 0
6 n
a ly ly ly y n n
a O r l
a l
a l
a c a. E M
I r
g S
E h i
e ip c
ip c
ip y
m d
n R F y a N o r t
e ty e
t e e o
t n
O r f o r e
r e
r e
ht r
e u
M P A
) i C w w s s w
s f o l f
f L lp h le E k M 7 a h
u h
u u -
A 7 36 02 27 7I 7 7 0 s b d -
c G 8 1 2 9 t o s e
s e e a n 4 e YI T S 1
1 9 t r r r t g
d n
1 9 5 n ta.
h NI ( 5 5 6- n FC i
I a r n w e A l e m E T io C F . Z lo -
r r lyr l ta fo R S e e e Ls s e -
t r h r h r O Bo E
f o
to h
ec ot h o n e T R C )A N )y e e s e o ht te I
V Ar UM 9 r s u
s u
e su i
t u m s
a TC 6 9 l m
G 6 8 5 5 5 6 9 d a a b a l o n W N 2 4 ( -
I 2 c c a c s :
S E S S 3 i
/g b e
b e
lab i e v d e
r w
o e v
=
C ( C d d e .hs i C a e t L I p 2
e et s ht io t s c a
A T C
I G
I T
Y L
A k,
d M + @iq e b e H u we bh t
nt ai ia rel m i i
d R
o a
~
~
O Y N A E f r
o r
s a
r s
a ns oa r ot eh ont 0
L L U) 4 7 8 4 0 4 8 5 0 t wnw iw t
a tytiam t h 5
7 O
I A LA A(
2 8 2 5 6 1 5
1 0 0 1 1 9 2 1
8 9
5 i
C p o
n o igno t i ia tnoi tr t ow t 4 8 -
N i i D V e t
c t c
s t e c s e
r A r s. a a v a n e el u u A
c d at p p ip nl ula ~
R t s luu s u e u uavo f e c
o
+
8 8 in er w .w.h w. a i r -
9 9 9 Uslo yt l o tnol t
yf loy tn mca gi st r
P n
m
+
9 . icl oioisfoinl a ty e ;a 3 5 8 63 21 o -
1 E mtf y taf tat l isl h i 1 E U 0 a ore or e u otre e at -. 5 0 6. 1 1
-. 1 t n
B L T A 6 0 8 7 2 4 6 0 5 4 213 9
2 4
3 0 5 i. lnNcNc sNc n nre eu .n n nf oAo u 221 -
5 05 c
e p
m V
5 8 1 1 1 1 1 5 aA .
e.u e . u e d ge u r n 45 678 8 s n .
mto g g g gh ngai nnnnT n g g te nl ad ia A 000000 I s e v c n v ai a m -
i Ci t ~
onr n fr udf t R in tn ooe tn . r ;
cif ner o uo o e o uo e r
s ph s s t Na S re t
wnu et ct cc ot t c e aef e
oiot ot s u ds u uos a s ri o ;.
r Uc n di l ngn yi yi n yi t
l e t iyc in u c L l dl d ol d b -
4 1 3 34 7 45 9 1
u t b eh ; .
de eg N
5 6-0 6-I e Et h wl h nh nch n nga iga giga t
is s et 1- 5 u yr e s ar 1 - 5 t n -e 3- t o o o s usltsuis l k eunls hs i
e r s s n i lab ga i l CCCCMF Z C 11 is e r s s t
r v e leh e a s eb r sa e o s un s a
r te r luBa a nt E ew r w Ei wr E t
n cl i as n o
1 0 65 2 0
h ow ti e it vi tonso t
e V yl uBl u BnlouB t y 81
< < <- <- 0 i l i i t d t m t u
e F a sd sTsTisT e laEn tr ti +
re he t l nBe o W ice e herhe gea M r c -
r ATme s 4481 61 0 a a -
l ,.,
i t e r A
l lyt 1 t 9 t i5 t e e i r -
mne t
af 5 n5 ns6 n t
m hh r R<2 2 2 22 ,
n o r- o - o e - o e c cu nZdv n n e n a e as ea is c o AoCdFd i e e e e
r n a o 8 8 ei e e e ei e e m it e t 9 9 tah s aha s nhas c c
e a 4 1
4 h TRTbTbATb r
e t
iidd v vm e a y _
nD 2 1
2 e iih DDT r n o 1 1 d itetm t C ABC . . . D EF
. . o . .
i r c T I . 23 Ca
l 0 un asmotocicat avwwumrat uomronwa newar l
l I
APPENDIX G l l
1998 Land Use Census O
l l
O Page G1
l j!I)jlj<l l ljIl1 l
i r
o r
py dsh e
d e
fe n
r o
c y
n w
o s w r
gwr n
o n
o e t n
o r
e n i n
o e
s
&o e
r h
e m
o h
d y
a t
s 2
G e
g 9
n r.
t s t -
og e a iyo we h a a c e- m wi n
e n t
s n o fe m r P m w rf a d
o rl el ob r o su a gm n g ht oo e d f i
r pna gt c h i o g m o c n s e r k e tri o eO lp skh uin l m
r r u
(
no i w o l i
P hos 5 t m o I u d ui t r s m lpm o 1 ur e g s ac ot h e e r
r e d)
( y ( r) ppo ht s u d n c b r r a r e e y o e i
z f rO o nn ouJ m b e sa eh b b a oh Kl ua l (
l p l p
s e mwd b m& m t r r m
r e .
G z a o rid n . e r e o az v e cona v
oye e e vg e) v y Ole t(wms) cd b
e o
b e
o a
s Nh to ba mluee gae e wg t
s ra N r o la oa gsd t cd tc y s t f o Nd za Ni s Oefe O )e 1:
l a roe pv o
c rs I t
t orogr o t o& 5& 1 z pf a t o og l a
u m xi e y l f t t d ye r lng ng e l e rfah t n ta g n e e lkf i rd gl g yw l e
i c i ie a p e'ond e a o pl a pl a of a u a o a s yi r
Atoer MH M Afdf e e Mts Ai s Ai s Nlab o Mgr M& ht e
w s e
f s n l u
a a t oi
)
p e a tod e e
s s e e e s T s n s s t s u U U n U U U s s R d e
y a s n n a g n n i
x e
O s di w w r w w n e P U wi k O O O O O w n E
l y e s O o R f & & r a dm, r f
- i a s p p e
m s s s
& i(
G S e o p e e y U D me k o
- o o r ae k k k e r S I
N S ol r
k L
a C o o
F s a a a i
a N R N fi C C la U L L L D I E e m O v o y y nn O O O s M O mf J o o ew r e
T T
I C t n
I d
n t
. Jt Jt ts O dna a
d n d n t t
f o
K a r es a a a u N ai L M M M N& L L L R s e
O C ut qn r
lu M O sd u t e u n r
foco L T a ak - - - - - - - O -
e v
S Noi l A
T E GM en r g i
f f
N 1
- I V s ei h er o e
E GL t a
t pf o s e c n
M ED o e o i n a N LN G k t - - - - - - - n -
t s
lyro a i O BA o N d R A N lae ct 2 a
I V TY R di t o s a
r 1
m.
ht i rs N I A d ne 0 i a E . s e et pn 0 0 0 wff D owk 2 1 4 9 $ 2 0 2 5 6 sA L Nol e i - 6 $ 6 5 r CM srdpep i 1 5 1 1 4 ol A L a 9 t a C A ei ct e
s e n
I G
U sh r s l u O N s o sefr s s s & a m N w o
h n e srse s fer s s r
s e s e s
r s
r s fe r s s c i
g m L
O A C dnt h wi oc wf wie oi oc v wi f wif se wif wie oev s
w s e wlv s oi v I 8 o.
ae pr CII CeH Cli la Cl oe l CH oe oe CH Cl l
la C
o oa er lon rE D 9 9 N ea 00 20 0
1 5 00C 00C CCf 62 e i o ed A 1 e s 1 1 i 7 50 1 1 & 50 76 00 62 00 73 52 1 1 & 9 0
44H t e n R hl s a
,m mls a 8 s 9 si d s 6 I ta n e i e
9 d oAe w n 1 e y r l
1 e r
g
,s .l f
i a te n i n
e e m m e
mr ei e m e
neS ir yeinninh ego s m ey i
n e hM t
ei B t h t e
sk e tsh s wrk or s es t t t f we m t t t s s s s s s s s oe r oem sl
>Tr ouih el l l o
l io )T o l l o o o r o l or e l
o hh Cwa H H H H H JeHABGMS l
iA t I J f
I c aT e,ss er et me ob ne n ae
- i li N a drh m " " " "* " mf s
- d Pu * *
- r a nmr
- A&N fye o a f ht r rk r ats al u o de * * *
- 4
- * ' *
- d em i
i m&tco eC 3A 5" 3
C 5D 6
3E 9 0 F 3G 0 0 0K 2
8 0
2 K 5 9 P 3 9 P t
s sd e
s ee z S 1 1 2 2 s rl A l od p cd m e a a i) )
hd t ny s
e n ) ) ) ) )
i) i) m ) i s al r c o i i i i i 8 e s a n i m m m m m E m m
- 4. E 9. W 2W imW 7. mW du el u a&e t
c I.
N 1 E 1 E 1 E 2. S S 4 S 1( S 7.
3 N 6 N l mg t
s r 2 4N l N l 3
( E S
- a e Di i
D m
( (
m (E
m
(
m m l(
m (S
m k m
(
m W
k (m W InNR k k k k k k k 6 k 8 3
3 6
6 7
1 8
1 2
5 3
2 8
7 0
2 6 O. 0 1
l
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE G-2 1998 Annual Residence Census
- Azimuth Azimuth Distance and Name, Address ** Distance and Name, Address **
and Sector & and Sector &
Direction Code Telephone No. Direction Code Telephone No.
6,000 ft. 5* 12,000 ft. 186* ,
(1,839m) A (3,658 m) J !
N S 3,800 ft. 28* 3,400 ft. 213.7*
(1,158m) B (1.036 m) K l NNE SSW l 2,800 ft. 48* 2.850 ft. 226' (853 m) C (869 m) L NE SW I 2,450 ft. 67.5* 2,500 ft. 250*
(747 m) D (777 m) M i
g ENE WSW 2,300 ft. 80* 1,850 ft 272*
\
l (700 m) E (564 m) N P. W 5,800 ft. 123* 1,900 ft. 293*
(1,770 m) F (579 m) P ESE WNW 3,750 ft. 145' 2,150 ft. 306*
(1,143 m) G (655 m) Q SE NW 3,750 ft 152* 3,500 ft. 337.5*
(1,143 m) H (1,067m) R SSE NNW
- Census identifies nearest residence in each of the sixteen meteorological sectors.
" Names and addresses are on file at Three Mile Island Environmental Affairs.
O Page G3
1 l
l
{
l
)
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT 91 TABLE G-?
Annual Garden Census 1998a l "Name, Meteorological Distance Address Sector and & Phone flow Used and Distribution < f Dehnation Direction Arimuth Number Type of Vegetation Consumees A(1) 2.4km (l.5mi) 4' Pumpkms Tomatoes, Squash, lettuce, Garbe, ()wn Use N Zucchini,Com, Potatoes, Cabbage, Peppers, 3 Adults Okra, Eggplant Also given away to other fanuly l members, fnends & neighbors. Squash was sold.
B(2) 1.4km (0.9nu) 24' Wmter Turnips, Cauldlower, Peppers. Own Use NNE Cabbage. Tomatoes, Asparagus, Horse Radish, 3 Adults Onions, Bluebemes, Rhubarb, Broccoli, Beans, Also given away to fa,iuly, friends &
Potatoes neighbors.
C (3) I .3km (0.8nu) 34' Lettuce, Radishes Tomatoes, Peppers, Apples, Own Use NE Strawbemes, Asparagus, Cuitaloupes, 2 Adults Horseradish, Cucumbers, Deans, Peas Also given away to fanuly, friends &
neighbors.
D (4) 1.7km (l. Inu) 63' Broccoh, Cauldlower, Pumpkms, Cor n. Own Use ENE Cabbage. Tomatoes. Peppers, Cantaloupes, 5 Aduha l Watermelon, Potatoes, Orspes I Child 1 Teen Also given away to family & friends E(5) 0 7km(0 Snu) 94' Cabbage, Tomatoes Com Grown pnmanly for GPUN REMP.
E Excess consumed by GPUN personnel and their families.
F (6) 2 Okm (l.3nu) Io7' lettuce. Spmach, Strawbemes, Tomatoes. Own Use ESE Peppers, Potatoes. Beans, Peas, Carrots, 2 Adults Watermelon, Cucumbers, Cantaloupe Soy 5 Ctuldren Heans Also shared wi'h family a fnends G(7) 1.0'un (0 Anu) 135' Wide assortment of food products mcludmg Own Use SE broad-leaf segetables (cabbage) 3 Adults. Also given away to reist6 s &
sold along R* 441 st the Red Hill Farm Produw Stard, at the Farm Show Building Fanner Market and at the Humetown Market ir Hazeltm Ems:
goes toleola Produce Aue4n H (8) 1.3km (0.3nu) 152' Oregano, Basil, Cluves Corn, Strawbemes, 0% Use SSE Spinach, Tomatoes Lettuce Peppers, Egg 2 Adults Plant Parsley, Pumpkins Onions Potatoes. Also given away to family & neighbors.
Cilantro, Sunflowers J(9) 3.7km (2.3nu) Ig6' Tomatoes, Peppers, Cabbage, 5trawbemes, (hvn Use S Potatoes, Zucchini, Beana. Onions, Cucumbers, 2 Adults Peas Peaches, Pears 2 Teens Also given rway to friends.
K (10) 1.4km (0 9nu) 20g' Pena, Tornatoes, Strawbemes, Peppers. Om Use SSW Cucumbers Spinach, lettuce, Carrots, Onions, 2 Adult Corn, Squash, Watermelon, Cantaloupes, Vegetables also canned & frozen for Beans, Sunflowess, Radishes, Parsley, Cilantro, future use.
Oregano, Hwne IJ11) 2.5km (l .6nu) 232' lettuce. Tonatoes, Peppers, Egg Plant, Squash, Own Use SW Zucchini, Corn, Cabbage, Broccoli, Grapes, 3 Adults Orvons, Raspbemes, Cucumbers 2 Children Also shared with riesgh:xrs, friends &
family.
M (12) 2.lkra (1Juu) 253' ~ Endive, Potatoes, Beans, Cabbage. Tumips. Own Use WSW Peaa, Zucchini, Onions, lettuce, Tomatoca, 2 Adults Peppers, Egg Plant, Strawberries, Corn, Neck Also some given away to fnends &
. Pumpkins fanuly.
O Page G4
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT
==i TABLE G-3 Annual Garden Census 1998*
.we, Heteorological Distance Addresa Sector and & Phone flow Used and IMstribution of Deaf w don IMarction Asianuth Nuanber Type of Vegetation Consinners N (13) 2 3km(1.4nu) 267* Lettuce, Cabbage. Tomatoes, Peppers, Corn, Own Use W Cucumben. Cantaloupes Strawberries. 2 Adults Turnips, Raspbemes, Ikans Also given away to neighbors & fanuly P(I4) 2.7 kin (i.?nu) 286* Cucumbers, Ikussei Sprouts Swiss Chard. (hn Use WNW Strawbemes, Peppers, Pears, Tomatoes, 2 Adults Asparagus, lettuce. Apples, Cantaloupes, Also given away to family & neighbors.
Com, P;mpkins. Peaches. Squash Q(l5) 2.4 kin (1.5nu) 310' Peppers, Rhubarh, Cabbage, Ra.ydemes. Om Use NW Grapes, Apples, Pears, Peaches, Zucchini 2 Aduhs I Child Also given away to family & fnends.
R (16) 3.Nc,(2.4nu) 343' Tomatoes, Peppers, lieans, Peas, Cucumbers, Own the NNW Grapes Onions, Potatoes, lhussel Sprouts, 3 Aduha Zucchini, Basil. Dill Also given away to fanuly, neighbors &
fnends
- Census identiSes nearest garden (greater than 500 ft and having a portion of broad-leaf vegetation) in each of the sixteen meteorological sectors.
Y ** Names and addresses are on file at Three Mile Island Environmental Affairs.
Page G5
1 0 ms wnowatca enviaosuesta uomionusa aeroar i
APPENDIX H l
1 1998 Data Reporting and Analysis l O
1 l
1 l
1 O Page HI 1
)
i
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING PORT Environmental samples frequently contain very little, if any, radioactivity. Even when very sensitive, state-of-the-art counting equipment is used, many of the sample count rates can not be differentiated from the background count rate or the count rate of the blank sample. When this occurs, the sample is said to have a radioactivity level or concentration at or below the sensitivity of the analysis method. In this case, the analysis result is reported as less than a numerical value that corresponds to the sensitivity of the analysis method. Sensitivities are influenced by parameters such as sample volume, background or blank sample count rate and efficiency of the counting device.
The terms used to describe the sensitivity are the lower limit of detection (LLD) and minimum detectable concentration (MDC). For this report, these two terms are considered to be synonymous. They are dermed as:
- V
- 2.22
- Y
- exp (-A At) where:
Sb =
the standard deviation of the background counting rate or the counting rate of a blank sample, as counts per minute, E =
the counting efficiency of the equipment, as counts per disintegration, V =
the volume or mass of the sample, such as L, g or m',
2.22 =
the number of disintegrations per minute per picocurie, Y = the chemical yield, if applicable, A =
the radioactive decay constant for the particular radionuclide and At =
the elapsed time between sample collection (or end of sample collection period) and counting.
The applicable LLD or MDC for each radionuclide and analysis is listed in Table 3. A large percentage of the 1998 sample results were reported as less than the LLD or MDC. Unless noted otherwise, the results that were reported as less than the LLD or MDC were not included in the calculations of averages, standard deviations and ranges (by station or group)in the text and tables of this report.
The data from samples that contained concentrations above the LLD or MDC were used in the calculations (averages, standard deviations and ranges) contained in this report. The individual sample results were generally reported to two significant figures. Each result also included a two-sigma counting uncertainty (95% confidence interval) to the same decimal place. At a minimum, a counting uncertainty equal to 10 percent of the measured concentration was reported. The counting uncertainties were not used in any statistical calculations in this report.
Page H2 O
r 1998 RA DIOLOGICAL ENVIRONMENTAL MONITORING REli)RT The data used in a few tables and all annual graphs were actual sample concentrations. For historical graphs, actual sample concentrations were used for 1996 - 1998 data points on:y. The actual concentration is calculated by subtracting the background count rate or the count rate of a blank sample from the count rate of the sample. The net count rate is then converted to a net sample concentration which is either positive, negative or zero.
There are several advantages of using actual sample concentrations. Biases in the data (averages, ranges, etc.), such as those caused by averaging only sample concentrations above the MDC, are eliminated. Missing data poir.ts on graphs also are eliminated. It should be noted that negative sample concentrations are ir:portant to the overall overages and trends in the data, but they have no physical significance. A negative sample concentration simply means that the background or blank sample count rate is greater than the sample.
All sample data were analyzed using S AS, a statistical analysis package developed by SAS Institute, Inc. The data were grouped by station, time period and by control and indicator status.
Minimum, maximum and average values were calculated for each of these groups as well as standard deviations (2a, 95% confidence interval).
Quality control results (inter-laboratory and intra-laboratory) were not statistically analyzed with other data. Including quality control data would introduce a bias at selected stations while providing little additional interpretive information.
O l
1 1
Page H3 l
ll
O 1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT 1
i i
/
APPENDIX I 1998 Dose Calculation Methodology and Results O
lO Page !!
L- _-_____
l l
1998 RADIOLOGICAL ENVIRONhfENTAL MONITORING REPORT l
To the extent possible, radiological impacts were evaluated based on the measurement of j exposure rates or radionuclide concentrations in environmental samples. However, the radioactive materials released from TMINS during 1998 were often too small to be measured once dispersed in the offsite environment. As a result, the potential offsite doses were estimated j by using computerized models that predict concentrations of radioactive materials in the environment and subsequent radiation doses on the basis of radionuclides released to the environment. GPU Nuclear calculates doses using an advanced class "A" dispersion model called SEEDS (simplified environmental effluent dosimetry system).
This modelincorporates the guidelines and methodology sct forth in USNRC Regulatory Guide 1.109, and uses actual monthly Susquehanna River flow data and hourly meteorological information matched to the time of releases to assess the dispersion of effluents in the river and the atmosphere. Combining this assessment of dispersion and dilution with TMINS efIluent data for each unit, postulated maximum hypothetical doses to the public are calculated. The maximum individual dose is calculated as well as the population dose to the total population within 50 miles of TMINS for gaseous effluents and the entire population using Susquehanna River water downstream of the station for liquid effluents. Values of environmental parameters and radionuclide concentration factors were chosen to provide conservative results. As a result, the doses calculated using this model are conservative estimates (i.e., overestimated).
The dose summary tables, Table I-1 and 1-2, present the maximum hypothetical doses to an individual resulting from TMI-l and TMI-2 efiluents, respectively, during the 1998 reporting period. Population doses for both units also are presented in Table 1-1 and Table 1-2.
Liauid Undividual)
The first two lines of Table I-l (TMI-1) and Table 1-2 (TMI-2) present the maximum hypothetical doses to an individual from liquids. Presented are the total body and critical organ doses for the age groups most affected. As recommended in USNRC Regulatory Guide 1.109, calculations are performed on the four age groups and eight organs. The pathways considered were water ingestion, shoreline exposure, and fresh water sportfish ingestion. The latter two pathways are considered to be the primary recreational activities associated with the Susquehanna River in the vicinity of TMINS. The " critical receptor" would be that individual who drinks water from the Susquehanna River, cats fish that reside in the plant discharge, and stands on the shoreline influenced by the plant discharge. Actual monthly Susquehanna River flows were used in dose calculations for liquid effluents.
For the 1998 reporting period, the calculated maximum hypothetical total body dose received by anyone from TMINS liquid efiluents would have been 0.0325 mrem (TM1-1) and 0.000830 mrem (TMI-2) to an adult. These represent 1.08 percent and 0.0277 percent, respectively, of the USNRC 10 CFR 50 App. I annual guidelines. The maximum hypothetical organ dose from TMI-and TMI-2 liquid effluents would have been 0.045'2 mrem to the liver of an adult and Page12 O
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT 0.00131 mrem, to the liver of a teen, respectively. These represent 0.452 percent and 0.0131 percent, respectively of the USNRC 10 CFR 50 App. I annual guidelines.
Gaseous (Individual)
There were six major pathways considered in the dose calculation for gaseous efiluents. These are (1) plume exposure, (2) inhalation, consumption of(3) cow milk, (4) fruits and vegetables, (5) meat, and (6) standing on contaminated ground. Ingestion ofgoat milk was not considered because this pathway did not exist in 1998. Real-time meteorology (the actual conditions that existed at the time of releases) was used in dose calculations for gaseous efiluents. Default values were used if data were missing or invalid.
Lines 3 and 4 of Table I-l (TMl-1) and Table 1-2 (TMI-2) present the maximum plume exposures from noble gases at the site boundary. The notation of" air dose" is interpreted to mean that these doses are not to an individual but are considered to be the maximum dose at a location. The location is not necessarily a receptor (individual). The tables present the distance in meters and the affected sector (compass point). With respect to the noble gas releases for the 1998 reporting period, the maximum plume exposure (air dose) would have been 0.000156 and 0.000213 l
millirads (mrad) for TMI-1, gamma and beta, respectively. The TMI-l exposures represent !
[]
V 0.00156 and 0.00107 percent of the USNRC 10 CFR 50 App. I annual guidelines, respectively.
Since TMI-2 did not release any noble gases during 1998, the gamma and beta air doses listed on I
Table 1-2 are zero.
Lines 5 and 6 present the calculated dose from noble gases to the closest receptor (individual) in the maximally affected sector (s). The location of the receptor is described by both distance (meters) and direction from the site. Plume doses to an individual, regardless of age, from gaseous effluents (noble gases only) during the 1998 reporting period were 0.0000533 mrem and 0.000102 mrem for TMI-l total body and skin dose, respectively. These represent 0.00107 percent and 0.000680 percent of the USNRC 10 CFR 50 App. I annual guidelines for the total body and skin, respectively. As mentioned previously, TMI 2 did not release any noble gases during 1998. Therefore, the total body and skin doses listed on Table 1-2 are zero.
Line 7 of Table 1-1 and Table I-2 represents the dose to the maximally exposed organ due to airborne releases ofiodines, tritium and particulates. This does not include the whole body plume dose that was separated out on line 5. The doses presented in this section again reflect the maximum exposed organ for the appropriate age group.
During 1998, iodines, tritium and particulates released into the atmosphere from TMI-l would have resulted in a maximum dose of 0.00966 mrem to the thyroid of a child. The corresponding dose from TMI-2 was 0.000130 mrem to the liver, total body, thyroid kidney, lung and GI tract of a child. No other organ of any age group would have received a dose greater than this from Page 13
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT either TMI-l or TM1-2. These doses are 0.0644 percent and 0.000867 percent of the USNRC 10 CFR 50 App. I annual guidelines.
Liauid and Gaseous (Ponulation)
Lines 8-11 of Tables 1-1 (TMI-1) and Table I-2 (TMl-2) present the population doses (in person-rem) resulting from the liquid and gaseous emuents. These doses, total body and maximum organ, are summed over all pathways and the affected population. The population doses from liquid emuents are based upon the population encompassed within the region from the TMINS outfall extending down to the Chesapeake Bay (approximately 5,000,000 people). The population doses due to gaseous emuents include the population out to a distance of 50 miles around TMINS (approximately 2,200,000) as well as the much larger total population that can be fed by foodstuffs grown in the 50 mile radius (up to approximately 13,000,000). The population doses are summed over all distances and sectors to give an aggregate dose.
Based upon the calculations perfonned for the 1998 reporting period, TMI-l and TMI-2 liquid and gaseous emuents resulted in a combined population dose of 7,77 person-rem to the total body. This is more than 80,000 times lower than the dose that the population living within 50 miles of TMINS receives each year from natural background radiation (660,000 person-rem).
O l
l Page 14 l
k 1998 RADIOLOGICAL ENVIRONMENTAL MON 110 RING REPORT TABLE I-I Summary of Maximum Individual and Population Doses from TMI-1 Emuents for 1998 Individual Doses Esthmated Imation Percent of 10 CFR 50 Dose / year Age IMst Dir 10 CFR 50 AppI Emuent Organ (mrem) Group (ni) (Toward) App.I Annual Annual Guideline Guideline (mrem /yr) i Liquid Toul Body 3.25L2 Adult Receptor i 1.08E+0 3 2 Uquid Uver 4.52E-2 Adult Receptor i 4.52E 1 10 3 Noble Gas Gamma Air Dose 1.56E-4 -
610 SE I .56E-3 10 (mrad) 4 Noble Gas Beta Air Dose 2.13D4 - 610 SE 1.07E-3 20 (mrad) j S Noble Gas Toullkxty 5.33E 5 All 1140 SE 1.07E-3 5 i 6 Noble Gas Skin 102E4 All 2300 NNW 6.80E4 15 l 7 lodmes, D)toid 9.66E-3 Child 2000 SE 6.44E-2 15 Tntium &
Particulates i
\ l Population Doses Estimated Population Emment Applicable Organ Dose (Person-rem) 8 Uquid Total Body 7.31 E +0 9 Uquid Uver 7.32 E +0 10 Gaseous Total Body 4.50E-1 11 Gaseous nyroid 4 60E-l
\
Page 15
I998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE I-2 Summary of Maximum Individual and Population Doses from TMI-2 Efiluents for 1998 Individual Doses Estimated Imcation Percent of to CFR 50 Dose / year Age Dist Dir 10 CFR 50 App.1 Emuent Organ (arem) Group (m) (Toward) AppI Annual Annual Guideline Guideline (mrema/yr) i Uquid Total Bod, 8.30E-4 Adult Receptor i 2.77E-2 3 2 Uquid Uver 1.3 l E-3 Teen Receptor i 1.31 E-2 10 3 Noble Gas Air Dose 0 - - - 0 10 (Gamma-mrad) 4 Noble Gu Air Dose 0 - - - 0 20 (Deta-mrad) 5 Noble Gas Total ikxty 0 - - - 0 5 6 Noble Gas Skm 0 - - - 0 15 7 lodmes, Uver, Total Body, 1.30E-4 Child 2000 SE 8.67E-4 15 Tntium & %)toid, Kidney, Particulates Lung and GI O
Population Doses Estimated Population l Emment Applicable Organ Dose (Person-rem) 8 Uquid Total Body 6 480-4 9 Uquid Bone 2.t OE-3 10 Gaseous Total ikxty 9.07E-3 11 Gaseous Uver, Thyroid, Kidney, 9.07E 3 Lung and GI i
l l
Page16
Q z,,, aaniotocicat esvisosusurat uusironisa nzir,ar APPENDIX J 1998 Groundwater Monitoring Results O
l O Page
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE J-1 1998 Tritium Concentrations in Onsite Groundwater and Storm water (pCi/L) 1997 Average 1998 Average Station (Well Type)
- 2 std dev*
- 2 std dev* 1998 Range
- MS 1 (Monitoring) 260 170 **
MS-2 (Monitoring) 380
- 160 310 90 270 - 370 MS-4 (Monitoring) 220 1,000 "
MS-5 (Monitoring) 230
- 140 340
- 210 260 - 460 MS-7 (Monitoring) 190 320
- 70 300 - 350 l MS-8 (Monitoring) NS 450
- 30 440 -460 OS-14 (Monitoring) 250
- 160 300
- 170 210 - 410 OS-18 (Monitoring) NS 11,000
- 13,000 3,800 - 31,000 MS 19 (Monitoring) 250 210 "
MS-20 (Monitoring) NS 380 "
MS-21 (Monitoring) < MDC 150 "
MS-22 (Monitoring) 4,000
- 13,000 3,600
- 9,300 1,200 - 18,000 RW-1 (Monitoring) 7,000
- 21,000 1,100 2,200 160 - 3,400 NW A (Senice Water) 3,200 700 2,300
- 1,200 620 - 3,400 NW-B (Senice Water) 6,800
- 1,400 9,400
- 5,400 3,300 - 16,000 NW-C (Senice Water) 23,000
- 14,000 56,000
- 76,000 32,000 - 230,000 NW-CW (Clearwell) 5,000 3,600 4,500
- 2,000 2,200 - 5,900 OSF (Drinking Water) 1,000
- 800 520
- 160 410 - 670 48s (Drinking Water) 220
- 110 280
- 250 130 - 360
- = Averages, standard deviations and ranges were based on concentrations > the minimum detectable concentration (MDC).
" = Only one concentration in 1998 was > MDC,
< MDC = Measured concentration (s) was equal to or below the MDC.
NS = Station was not sampled and, therefore, no data were available.
(Refer to Figures J l and J-2 for locations of onsite groundwater and storm water stations. Refer to Figures 4 and 5 for locations of the offsite stations).
Page J2 O
1998 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE J-2 1998 Tritium Concentrations in Offsite Groundwater (pCi/L) 1997 Average 1998 Average Station (Isation)
- 2 std dev*
- 2 std deva 1998 Range
- A2-2 (Tri County NS < MDC -
Marina)
Dl-4 (Residence, East NS 180 "
Shore)
El-2 (TMINS Visitors < MDC < MDC -
Center)
J3-3 (Residence, West NS < MDC -
Shore)
K1-6 (Summer NS 140 "
Residence, Shelley Is)
L1-3 (Summer NS 170 "
Residence, Shelley Is)
Ll-4 (Summer NS < MDC -
Residence, Beech Is)
N2 1 (Goldsboro Marina) < MDC < MDC -
- = Averages, standard deviations and ranges were based on concentrations > the minimum detectable concentration (MDC).
- = Only one concentration in 1998 was > MDC.
< MDC = Measured concentration (s) was equal to or below the MDC.
NS = Station was not sampled and, therefore, no data were available.
(Refer to Figures J-1 and J-2 for locations of onsite groundwater and storm water stations. Refer to Figures 4 and 5 for locations of the offsite stations).
O Page J3
._ l;l!ll llC :1{tttill i.i O
3
. ll 8-s y
~
L;,_ e u g o 1 r i_
L
%, &4 1 S -
O -
l -
l -
r -
2o t e it c
- na UeR l
s n .
3(v o
i t
- 9 t
a -
. p e S t i2o r
t a S
ra Vr mUpitn o a
r s ee t r aA a
o c
c s
.' e oo Ev rf F
a M
O w -
dd 1 net
- uc ,.
N Joe e rt o .- j rGr u
gP P
. y
/
. _ .s r l iMeh F
a -
- DW N g le Et u En r Re e n
iU A -
- Gi to d b" - Ei Si s r u it - L no Nn I I T" 1 U n -
- M M
J $
it 2 n r 2-T g U .
1 ot s-M q
- it c 8 1 na -
9 w n
UeR -
9 -
1 -
_ I I
_ gg _
. I al r..
. eg I b.w _
1 cn i
/
ivd rl _
_ i eu .
cV,-
~ SB _
E) 9
~ -
L9 A3 C( A SE
/
O
-l; lt_ OI M NT llttI lII'l\ l
,l1 '8 I ' -
$Cg '
O d n
- \d - I nw Mao 5 T s, h s J
- ee e e g
, - h mr a oa O
t
- P ta h s
- l
- rl
- dee
- f temw -
ame
- - - c
- - - l ous s e pi h -
- - eet
. I 0p1 -
r e ar f
- h o d .
- st
,sn
- ll es
- _ wantio
- g @' _ ri ra c _
te a 3' o k
~
- - l a ml d o he .
- ~ w T
G
- 6 s T ~
l
~~
~
nwT 5 ut o r,.dn r
] ~ ge t es a N_E e e nc4n s s'
C '^ "
t isCe D '~" 0 ,
rl f
f si s u d er oro eg s _ _ et ri -
n _
1
_ h is o F Tiwn o
i 7
_ ' i f' : I ,
i 'l l
- Vt o t _
,f 0 b :
a _ . 0 m
- a U Y' ]910 t _
~
0 S* _
i M Y* '1l0
.~
r a ' .
ee g"- 'Cl
~__ j -
t r j _'-
'W aA ig1' _ _~ N
~
_" s ~_
w ' _
f~
d d -
C w _
O e ~_
2- nt uc .
,'t 2 h-Joert t o-w
~ W rGrPo gI "
e m
, "._ G u
gP e h'~. '
[ '
iMh F gI'1 -
Et -
Red -
/
I
- J -
" L L ;
j/
- E Si s -N Nt
= o~ 1 :
W ,
v n
io t
I u -
l le - a r MO - W: ;.2 lt
- W lef i T Dn e r l nn NwtWae nI I -
- le ur E g 8
._ s c W Te t 9 ,
e 4 L c Gnr g l
le la ee k v 9 oE . .
Ei o n w ir t
ad 1
o Lt i k r s tn n t
i n n a ud u s ... o le ir o
- N' $*
ir r "s
- e. . h u D C S AU G A %
I n iAG
..C O: -: .
T <:
A<* k-S .,