ML19246A800
| ML19246A800 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 06/21/1979 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML18024A875 | List: |
| References | |
| PROC-790621, NUDOCS 7907060357 | |
| Download: ML19246A800 (86) | |
Text
TEN'iESSEE VALLEY AUTHORITY BLOWNS FERRY NUCLEAR PLANT TECICiICAL INSTRUCTION 47 0FFSITE DOSE CALCULATION MANUAL (ODCM)
Approved: eg f g a plant Superintendent Date: June 21,1979 bb 7907060257
- 1 IABLE OF CONTENTS 6/21/79
- 1. Caseous Effluents.......................... .................... 1 1.1 Al a rm / T r i p S e t p o i ; t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 1.1.1 Release Rate Limit Methodology pCi/s ................. 1 A. Noble gases-assu=ptions and equations................ 1 B. Radionuclides and particulates- assunptions and e q ua t i o n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 1.2 Monthly Dose Calculations................................ 15 1.2.1 Noble Cases........................................,15 .
1.2.2 Iodines and Particulates.......................... 20 1.3 Gasecuc Radvaste Treatment System Operation.............. 22 1.3.1 Sys t em Des crip tio n . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . 23 1.3.2 Dose Calculations................................. 23 .
- 2. Liqu J Effluents............................................. 49
~ ..
2.1 Concentration............................................ 49 2.1.1 RETS Req u1r ece n t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 9 2.1.2 Prerelease Anclysis............................... 49 2.1.3 MPC-Sua of the Ratios............................. 49 2.2 Instrunent Setpoints..................................... 50 2.2.1 Setpoint Determination............................ 50 2.2.2 Post-Release Analysis ............................ 51 2.3 Dose..................................................... 51 2.3.1 REIS Require =ent.................................. 51 2.3.2 Monthly Analysis.................................. 52 -
2.3.2.1 Water Ingestion.......................... 52 2.3.2.2 Fish Injest1on........................... 53
~
2.3.3 Annual Analysis................................... 54 2.4 Operability of Liquid Radwaste Equipment................. 55 2.4.1 Release Lin1t..................................... 55 7R. -
7-) C)J7 JUi
4 11 6/21/79 TABLE OF CONTEMIS Gont'd) 3.0 Radiological EnvironI::en tal Monitoring. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 56 3.1 Monitoring Progra::2..........................................56 3.2 Detection Capabilities...................................... 57 esp e
h e
e e
sum 9
'me=, ..
?cA
.) <.
- 1. Caseous Effluents Page 1
- BF TI 47 1.1 Alar =/ Trip setpoints 6/21/79 Specification 3.8.B.1 re, quires that the dose rate in unrestricted areas due to gaseous effluents from the site shall be limited at a.1.1 tines to the following values:
- 1. 500 cres/y to the total body and 3,000 mres/y to the sk.in fros n.oble gases.
- 2. 1,500 cre=/y to any organ from radioiodines and particulates.
~
Specification 3.2.K.1 requires gaseous effluent monitors to have alar =/ _
trip setpoints to ensure that the above dose rates are not exceeded. This section of the ODCM describes the methodology that will be used to detare.ine these setpoints. -
The methodology for determiaing alarm / trip setpoints is divided into two cajor pcres. The firs: consists of backcalculating from a dose rate to a release rate li=it, in~pCi/s, for each nuclide and release point. The second consists of using thu release rate limits to determine the physical settings on the conitors. The cethodology for the latter is contained in Technical Instruction 15.
1.1.1 Felease Rate Linit "ethodology - UCi/s Step 1 The first step involves calculating a dose rate based on the design
~
obj ective source tern mix used in the licensing of the plant. Historical ceteorological data used are in thic calculation.
Doses are detc .cined for (1) noble gases and (2) iodines and particulates.
~
Depending on the pathway involved, either air concentrations or ground concen-trations are calculated.
A. Equations and assu=prfa~ f ar calculating doses from noble gases ar as follows:
. f} L
-- ; - ,_ _ - , _.- _ , . -- - . . - . . - .- - - _ . - ~.~y._--. ... -
Page 2 BF TI 47 6/21/79 Assu ptions "
- 1. Doses to be calculated are total body and skin.
- 2. Exposure pathway is subnersion richin a cloud of nobic gases.
- 3. Noble gas radionuclide nix is based on the erpected source tern given in Table 1.1.
- 4. Basic radionuclide data are given in Table 1.2. ~
- 5. Releases are treated as ground-level, split-level, or elevated.
- 6. Eeteorological data are expressed as joint frequency distributions .
(JEI)'s) of vind speed, vind direction, and at=ospheric stability for the period January 1974 to Dece=ber 19'S (Table 1.3). Releases from the turbine building arc treated as 100 percen; ground level, whereas stack releases are considered 100 percent elevated. Releases fro = the reactor building and radvaste building are treateH as split-level; i.e. ,
partly elevated and partly ground level.
7.
E2v ceteorolos;ical data for ground-level releases consist of vind speed and direction ceasure:ents at 10 m and temperature =easure=ents at 10 =
and 45 n. The ground-level portion of the split-level JFD vas based on v'2d speeds and directions reasured at the 10 m level and te=perature ucasurerents at 10 and 45 c. The elevated portion of the split-level 7 was based on vind speeds and directions ceasured at 46 m and te=pera-ture reasure ents at 45 and 90 n. k'ind speeds and directions for elevated releases were reasured at 93 m. Stalility class D vas assu=ed to persist _
'during the entire period for elevated releases.
8.
Dose is to be evaluated at the offsite exposure point where naxi.nus coucentrations are exp-cted to exist.
- 9.
Poten:ial taxinua-exposure (Table 1.4) coasidered are the nearest site boundary points in each sector.
3i04 3 r3
~
mr !~3 ; . w. .o.
m-
,,9 (
m b, *
' {bJ I6 p; fi.1. , '
udhNb gT 3<
, i m! \ m:
',i ,i ', g' d l nQ'5 ~~~ ~
.6
~
Page 3 BF TI 47 6/21/79
- 10. Asemi-iofinitecloudcodegisused.
- 11. Nc. credit is taken for shielding by residence.
- 12. Plu=c depletion and radioactive decay are considered.
- 13. Building vake effects on effluent dispersion are considered. .
- 14. A sector-average dispersion equation is used.
- 15. The vind speed classes that are used are as follows:
Nu=ber Rance (c/s) Midpoint (c/s) 1 <0.3 0. ' '
2 0.3-0.6 0.45 3 0. 7- l. 5 . 1.10
'4 1.6-2.4 1.99 5 2 5-3.3 2.80 .
6 - 3. 4-5. 5 4.45 7 5.6-8.2 6.91 3 >10.P -
13.00
- 16. The stability classes that vill be used are the standard A through G classifications. The stability classes 1-7 vill correspond to A=1,~B=2, . . ., G=7.
- 17. Terrain elevations are considered.
Equations To calculate the dose from radioactive effluents discharged from a given release point for any one of the 16 potential =aximum-exposure points, Ithe following equations are used.
For determining the air concentration of aay radionuclide:
9
- wn
.i
. Page 4 BF Tl 47 9 7 . 6/21/79 f P. .x q ,, j k _0 1 ,xp u
0 Eg u (2rx/a) ( jp j= k=1
=
exp . -h * ~
(1~1)
\ , /2 d i -
dere 3
g = air concentration of radionuclide i, pCi/n .
_ f = joint relative frequency of occurrence of vinds in vindspeed Jk -
class j , stability class k, blowing toward this exposure point, expressed as a fraction.
Q = average release rate of radionuclide 1, pCL/s.
f p = fraction of radionuclide renai '.ng in plune, Figure 1...
E g = vertical dispersion coefficient ~for stability class k d ich 1/2 includes a building vake adjustnent, E, = f0 2 + 0 .~5 A f r ,
where a is the vertical dispersion coefficient for stability class k (c), and A is the ninicun building cross-sectional area (2,350 m2 ), n.
u = cidpoint value of vind speed class interval j, n/s.
x = devavind distance, n.
n = nunber of sectors, 16.
A = radioactive decay coefficient of radionuclide i, s -1 2rx/n = sector vidth at point of interest, n.
h, = cffective release height, n.
For effluents exhausted fro = release points that are higher than twice the height of adjacent structurer. (elevated releases) the effective release height is determined by b =h +h -h -c (1.la) e a pr t
[@ /7D t9 [] Q P n q ,r -,-
ij _
Page 5 BF TI 47 6/21/79 where c = correction for low relative exit velocity, c = 3(1.5-Wo/u) d, where Wo - vertical plu=e exit velocity,(m/s), u = cean windspeed (m/s), and d - inside dia=eter of the release point, m.
h " plume rise above release point, m.
pr h, = physical height of release point, m.
hg= maximum terrain height between release point and receptor location (h can be any real number), m.
For ef fluents released from points less than the height of adjacent structures, a ground level release is .msumed (h,= 0).
For effluents released ~ from points' at the level of or above adjacent structures, but lower than elevated release points, releases are treated as follows:
Case 1 - elevated if W /u > 5 _
Case 2 - grcund-level (h, = 0) if W /u < 1.
Case 3 - split-level if 1 < W /u < 5.
o Under Case 3 a split-level dispersion approach is icplemented using a model that requi res for each release point two JFD's, one for elevated
, releases and one for ground-level releases. The sumation of the elevated and ground-level JFD's account for the t.otal period of record. Releases _
are considered to be elevated 100 (1-E ) percent of the time and ground-level 100 E percent of the tice where the entrainnent coefficient, E, is defined by Ee = 2.58 - 1.58 (Wo /u) for 1 < Wo/u < 1.5-(1.lb)
Ee = 0.3 - 0.06 (Wo/u) for 1.5 < Wo/u < 5 -
(1.lc) 9 U"; m n
Fd 53
); !I N, p3l;'g F' 'G - '\ n 1
Ubi q3 f-
,) ! ;
s .3 ; s : m y., . ?; . a
{
d d h3 \ . U s- 'l
Page 6 BF TI 47 6/21/79 For deter =ining the total body dose rate
. D = 1xlo' q DFB (1.2) 73 s '
where i .
D = t y se rate, n es/y.
TB _
g = air concentration of radionuclide i, UCi
-- .DFB g = total body dose factor due to ga-2 radiz... , =res/y per pCi/m3 (Table 1.5).
1x10' = pCi/pci conversion factor.
For determining the skin dose rate ,
D, = lx10' q [DTS + 1.11 DPt ] (1.3) where i ,
D, = skin dose rate, cre /y.
g = air concentratica of radicauclide i, ',:Ci/s'.
DFS g
= skin dose factor due to beta radiation, cre /y per pCi/n' (Table 1.5) .
s DPy a gm-to-air dose factor for radienuclide i, =re=/y per pC1/c' (Table 1.5). i
~
1x10' = pCi/pCi conversica factor.
The above dose calculaticas are repeated for each release point (vent or stack) and then su ed to obtain caxinum total body and skin dose rates.
The maxi =un total body and skin does rates vill then be.used in step 2.
o 4
- \%
w.S$*w,%) e Y'
p ~[A -(fg[, (('t%g 4', >
9/,$>- /4 y V imiee ev <u 1,0s TEST TARGET (MT-3) 4
'IO t N'"
3, T2B r36 i E iii p,:=_o I.l t
!!M l.25 I l.4 till.6 j --
II L = =
< 6" -
5N
,9 2>p s p 4 N%
- 4
.<4 9, .
h+o m;g
- h f
z v' -; y :<
q
\
O>
p> %' ' o s.\h/[, s.,
Q':\9
'*h / ,f884
////
%,,/'hf" gy+f - , ,- T -
%p; TEST TARGET (MT-3)
Ill "2 8_ N25 1.0 u<, -
u.-_ia i %l 2.2
'g g l&= =
l,l b bb IS8 =
1.25 1.4 1.6
< 6" -
B??h Wy?'&,,,,, A.
/f4%
w, 4 ,, 4,m#a//A e6s ,...
Q f 'p , y e
<.y
(
.ab e
e?>
v'e e, <&> 0 .
'{;+ I ,h* ,
'/
)f/p'(k~b*ff'gpp g)/r y gf N(g*/};[
p fj
\ IMAGE EVALUATION %
TEST TARGET (MT-3) 1.0 152?3E22 12 E33 2.2
{""l=*
't a l,l h
bb LE l' l.25 ' l.4 1.6 i -- l .
4 6" eff.{r$/'~'
- d *qq
'y V
-3 i
- N).)>
s W ',
g%{,, g?,'g f'g ' ,y '
<p s
q@ JS / /,
- / J. /,
,g ,s Gk ,
gr n .
R';,
l#'
4/'3 Vl, /c$'
5, &'A b(4'/@:?
g////gf 4 - , , - -
TEST TARGET (MT-3) iz%'ff i
I ", "" Z 8 "? 2 5 l.O v. ~ :=
!2 "33 I il 2.2
- [a g
.g a=s t sc Ll;il2.0 1.1 e.
==
I'lil I.8 llre =
1.25 IA l ,,, l 1.6-
&- 6" _4l QQ 7, / Yu nw'V ////
,, .,a%
O,s it' <;s of'/ \d f J
,p
\
~
' Page 7 BF TI 47 6/21/79 B. Equations and assu=ptiens for calculating doses from radioiodines and particulates are as follows: .
Assu=ptions
- 1. Dose is to be calculated for the critical organ, thyroid, and the critical ge group, infant.
- 2. Exposure pathways from iodines and particulates are ellk inges-tion, ground conta=ination, and inhalation. .
- 3. The radioiodine and particulate' mix is based on the -
expected source term given in Table 1.1.
- 4. Basic radionuclide data are given in Table'l.2.
5 .- Releases are treated as ground-level, split-level, or elevated.
- 6. Meteorological data are expressed as joint frequency distri-butions (JFD's) of wind speed, wind direction, and atmospheric stability for the period January 1974 to Dece=ber 1975 (Table 1.3). Releases from the turbine building are treated as 100 percent ground level, whereas stack releases are considered 100 s
percent elevated. Releases from the reactor building and rad-vaste building are treated as split-level; i.e. , partly elevated and partly ground level.
- 7. Raw meteorological data for ground-level releases consist of wind
~
speed and direction reasurecents at 10 m and temperat'reu measure-ments at 10 m and 45 m. The ground-level portion of the split-level JFD vas based on wind speeds and directions measured at the 10 m level and temperature ceasure=ents at 10 and 45 m. The elevated portion of the split-level JFD was based on vind speeds and directions =casured at 46 m and temperature censurements at 45 and 90 m. Mind speeds and directions for elevated releases 7 n '._
JVi fiO' i l f
h hh0($
em {. l h, ,, hlIk dhi > ~d' '
Page 8 BF TI 47 6/21/79 vere ceasured at 93 m. Stability class D was assumed to persist during the entire period for elevated releases.
- 8. Dose is to be evaluated at the potential of fsite exposure point where caximum concentrations are expected to exist. .
- 9. Real cov and garden locations are not considered.
- 10. Potential maximus-exposure points (Table 1.4) considered are the nearest site boundary points in each sector. -
- 11. Terrain elevations are considered.
- 12. Building wake effects on effluenu dispersion are considered.
- 13. Plume depletion and radioactive decay are considered for air-
. concentration calculations.
- 14. Radioactive decay is considered for ground-concentration calculations.
- 15. Deposition is calculated based on the curves given in Figure 1.2.
16.. A milk cow obtains 100 percent of her food from pasture grass.
1T. No credit is taken for shielding by residence.
Equations To calculate the dose from radioactive effluents discharged from a given release point f or any one of the potential maximun-exposure points, the following equations are used. .
- 1. Inhalation Equation for calculating air concentration, X, is the same as in the Noble cas section, 1.1.1.A.
For determining the thyroid dose rate:
T n '.t aut f r R '1
- .- 3 hf Q g'"3 w, ;., 7p% ygo ,, ..
Page 9 BF TI 47 6/21/79 (1.4)
~
pg = 1x10' g DTI BR where: 1 Dg = thyroid dose rate due to inha12tica, crc =/y.
g = air concentration of radionuclide 1, VCi/n'.
DFl{ = inf ant inhalation dose factor, xxre=/pCi (Table 1.7).
ER = inf ant breaching rate,1,400 ::'/y.
g 1x10 = pCi/aCi conversion factor. -
- 2. Crou 2d Cont.ninatica For determining the ground concentration of any nuclide:
Gi = 3.15r10' b.91 [1-exp
-(A i tb)) (1.5) jg y i
k=1 _. . ,,
vbre G = ground concentration of radicnuclide i, pCi/n2 ,
E = ctability class.
f k= j ) int relative frequency f ccurrence of vinds in staM 11ty class k. bicying toward this exposure point, expressed as a fraction.
g = average release rat.e of radionuclide i, UCi/s.
DR = relative deposition ra:. o-I (Figure 1.2). The choice of figure is governed by the effective reler e height
- ' calculated by equation 1.la. A linear interpolation is used for effective release heights that fall in between the given curves.
x = dovavind distance, s.
n = nunber of sectors, 16.
2rx/n = sector vidth at point of interest, m.
T n '- in JGr (1 ;
..:- e -
'i~q
[,*?. ,; [a L:.w ,, ... .
l L}ig D @md'.d O!L u o L U d'2
.. t e Page 10 BF TI 47 6/21/79 A = radioactive decay coef ficient of radionuclide 1, y'.
g = tice for buildup of radionuclides on the ground, 357.
3.15x107 = s/y conversica factor. .
For deter =ining the thyroid dose rate fro:: ground contanination:
Dgg - (8,760) (1x1G') (1.6)
CfDFC
~ I vbere: .
D TEG
= thyroid dose rate.due to ground centa=ination, cre:/y.
C = ground concentration of radionuclide i, pCi/n*.
DFG = dose factor for standing on conta:inated ground, tren/h per eC4/n (Table 1.8) .
8,760 = oc.upatica time, h/y. .
1110' = pCi/pci conversion factor
- 3. Milk Incestien For deternining the concentration of any nuclide (except C-14 and H-3) in and on vegetatien:
7 CV = 3,600
'k 9 1 f r [1-era (-ki 'e ]+ (1.7) i (2nx/n) g Yy Ag r.=
Bg [1-exp (-1;tb)l T
PA 1 j where:
~
CV g = concentration of radionuclide i in and on vegetation, UCi/kg.
k = stability c?. ass.
f = fregaency f this stability class and vind direction k
conbination, expressed as a fraction. } [] [] f h n D @ n O N i li d u n u lla
Page 11 BF TI 47 6/2.1/79 Qg = average release rate of radionuclide i, pC1/s.
_1 The DR = relative deposition rate, m (Figure 1. 2.
choice of figure is governed by the effective release
~
height calculsted by equation l'.la. A linear interpolation
- is used for effective release heights that fall in between the given curves.
~
x = downwind distanca, c. .
n = nu=ber of sectors,16.
2rx/n == sector vidth at point'of interest, m.
r = fraction of deposited activity retained on vegetation (1.0 for iodines , 0.2 for particulares).
A Ei
~ "ff*'ti" #** ##1 ##t* c stant, AEi 5 i + v' i
~
is the radioactive decay coefficient, h *, and Ay is a ceasure of physical loss by weathering (A y
= .0021 h 1), h-1, e,= period over which deposition occurs, 720 h.
Ty = agricultural yield, 0.7 kg/m 2, B = trasfer factor from soil to vegetation of radionuclide 1 fy (Table 1. 6) .
A = radioactive decay coefficient of rajic ..ide i, h *.~
5 t = tice for buildup of radionuclides on the ground, 3.07x10 b
h (35y) .
P = effective surface density of soil, 240 kg/c 2, .
3,600 = s/h conversion factor.
T n 's .:, .
J u c. t, .,
- I T ff H; ,' ! ,'4 L3 _ h-,^ E m r, >
ly. lh S Q:; a a u .. d c_. a hh
Page 12 BF TI 47 6/21/79 For deter =ining the concentration of C-14 in vegetation:
5 (1.8) cV 14 = 1x10 x1, (0.11/0.16) vbere
~
CV y4 = concentration of C-14 in vegetation, pCi[kg.~ ~ ~
Xy4
= air concentration of C-14, pCi/m3 . -
0.11 = fraction of total plant mass that is natural carbon.
0.16 = concentration of natural carbon in the atmosphere, .
g/m3 .
lx10' = g/kg conversion factor.
For deter =ining the concentration of H-3 in vegetation: .
(1.9)
CVT = 1x10' xT (0.75)(0.5/H) -
CV = concentration of H-3 in vegetation, pCi/kg.
7 3
xT= air c ncentration of R-3, pCi/m .
0.75 = fraction of total plant = ass that is water.
0.5 = ratio of tritius concentration in plant water to. tritium oncentration in atmospheric water.
E = absolute hu=1dity of the at=osphere, g/m'.
lx103 = g/kg conversion factor.
e em f En l l
J i) L \; 'l d
Page 13 BF Tl 47 6/21/79 For determining the concentration of any nuclide in cow's milk:
CM = CV FM Q exp ( i Uf
- f
=
where _
CM = concentration of radionuclide 1 (including C-14 and H-3) in cow's mi:
i pC1/1.
CV = concentration of radionuclide i in and on vegetation, pCi/kg.
FM = transfer facter from feed to = ilk for radionuclide 1, d/1. ,
Qf = a=ount of feed consu=ed by the cow per day, kg/d.
A = radioactive decay coefficient of radionuclide 1, d l.
tg = transport time of activity from feed to milk to receptor, 2 days.
For determining the thyroid dose _ rate from inges, tion of cow's milk:
Dg = lx10' CM DFINGj UM (1.11) where Dg = thyroid dose rate due to milk ingestion, mres/y.
CM = concentration of radionuclide i in cow's milk, pCi/1.
DFING = infant ingestion dose factor from Reg. Guide 1.109 (Rev. 1) ,
cre=/pCi (Table 1.7)
UM = infant ingestion rate for milk, 330 1/y.
lx10' = pCi/pci conversion factor.
- 4. Total Thyroid Dose Rate For determining the total thyroid dose rate from iodines and particulates:
Dg
=DTHI + THG " THM (* }
where D =t tal thyroid dose rate, crea/y.
TH
Page 14 BF TI 47 6/21/79 D
737
- thyroid dose rate due to inhalation, cres/y.
D ~
7# 8" ## * "" E " """ " "' I*
THG D = thyroid dose rate due to milk ingestion, mrem /y.
IHM The above dose calculations.are repeated for each ralease p~oint and then su= red to obtain thyroid dose rates. The maximum thyroid dose rate will
,then be used in step 2.
~
Step 2 The dose rate limits of interest (10CFR20) are Total Body = 500 mrem /y Skin = 3,000 mres/y s
Maximum Organ = 1,500 cre=/y Dividing the above limits by,the appropriate dose calculated in step 1 yields a useful ratio. ,
Dose limit.= R Dose step 1 This ratio, R, represents how far above or below the guidelines the step 1 calculat !on was. Multiplying the original source terms by R will give release rates that should correspond to the dose limits given above.
Release ta e limits in pCi/s for each nuclide and release point are now available.
h h h Ju. .
Page 15 BF TI 47
. 6/21/79 1.2 Monthly Dose calculations Dose calculations vill bd perfor=ed conthly to determine co=pliance with specificatiens 3.8.B.3 and 3.8.B.5. These specifications ire that the dose rate in unrestricted areas due to gaseous efflucats fros each reactor at the site shall be limited to the following values:
For noble gases,
- 1. During any calendar quarter, 5 mrad to air for gn ,ma radiation and 10 mrad to air for beta radiation.
- 2. During any calendar year, 10 crad to air for gnern radiation and 20 crad to air for beta radia, tion. .
For iodines and particulates,
- 1. During any calendar quarter, 7.5 crem to any organ.
" ~
- 2. During any calendar year,~15 cret to any organ.
This section of the ODCM describes the cethodole'y that will be used to perform these conthly calculat ons.
Doses vill first be calculated by a rimplified conservative approach (step 1). If the.se exceed the specification licits, a core realistic calculation vill be perforced (step 2).
1.2.1 Noble Cases Step 1_
Doses vill be calculated using the cethodology described in this step.
If any licits are exceeded, step 2 vill be perforced. ,
Equations and assunptions for calculating doses froc releases of noble gases are as follows:
T (\' RRO j u <. L;. /
e Page 16 s BF TI 47 6/21/79 Assumptions
- 1. Doses to be calculated are ga==a and beta air doses.
.2. The highest annual-average X/Q based on licensirg meteorology for ground-level releases for any offsite location vill be used
- 3. No credit is taken for radioactive decay.
- 4. For gamma doses, releases of Xe-133, Xe-138, Kr-85m, and Kr-88 are considered.
- 5. For beta doses, releases of Xe-133, Xe-138, Kr-85m, and Kr-88 are considered.
- 6. Dose factors are calculated using data from TVA's nuclide library.
- 7. The nuclides considered are expected to contribute at least 90 percent of the total dose. However, the calculations extrapolate doses assuming that only 90 percent of total dose was contributed.
- 8. A semi-infinite cloud model is used.
- 9. Building vake effects on effluent dispersion are considered.
Equations For deter 11ning the ga==a dose to air:
(y/Q')
, D =
0.9 i Y
i
(* }
i where:
D = gnmna dose to air from continuous releases, mrad.
X/Q = highest annual-average relative concentration, 2. 26 X 10-6 s/m 3 0.9 = traction of total gne,n dose expected to be contributed by these nuclides (actually 0.94) .
Q = monthly release of radionue.lide 1, Ci.
DFY = gamma-to-air dose factor for radionuclide i, mrad /s per Ci/m 3 (Table 1.5). _ ft c, r 4 Ju-r)
,')\ ' '
Page 17 BF TI 47, This equation then reduces t 6/21/79
~
D = 2.51x10 ' Q LFy (1.14)
B 1
For determining the beta dose to air: -
m .
D = (X 9 - Qi DFS i (1.15)
S 0.9 )
.. Ls i
~
where:
Dg = beta dose to air, trad.
~
X/Q = highest annual-average relative concentration, 2.26x10 '
s/m3 . -
0.9 = fraction of total beta dose expected t, be contributed by
'these nuclides. (actually .0.90). . .
Q = ronthly release of radionuclide i, C1.
DFS = beta-to-air dore fact.cr for radionuclide i, nrad/s per 3
C1/m (Table 1.5).
This equation then reduces to:
8 D 2.51x10 Q DFS (1.16)
S 1
Step 2
. This methedology is to be used if the calculations in Step 1 yield doses that exceed applicable 10:1ts. .
i '
J U <.
Page 18 BF TI 47 6/21/79 Equations and assu=ptions for. calculating doses to air from rele ases of noble gases are as follows:
Assu=ptions
- 1. Doses to be calculated are ga==a and beta air doses.
- 2. Dose is to be evaluated at the nearest site boandary point in each sector. .
- 3. Historical onsite =eteorological data for the appropriate months from the period 1974-1975 vill bn used.
- 4. All ceasured radionuclide releases are considered.
- 5. A semi-infinite cloud model is used. *
- 6. Radioactive decay is considered. -
- 7. Building vake Effects on effluent dispersion are considered.
- 8. Dose factors are calculated using data from TVA's radionuclide library.
Equations Equation for calculating air concentration, X, is the same as in Section 1.1.1,. step 1, part A. Air concentrations are calculated for t'.e site boundary in each sector.
For determining the gamma dose to air D =t Y DF (1.24)
Yn m Ni yi where:
D =
gamma dose to air for sector n , orad.
')
~
- f. A
~/ 0 '\\ .
J u t-
Page 19 B T 47
- 6 21 79 X g = air concentration of radionuclide i in sector n, C1/m'.
DFY = ga=na-to-air dose factor for radionuclide i, mrad /s per Ci/n' (Table 1.5). .
t = ti=e period considered (1 conth, but nucher of s/co is variable), s.
For determini ; the beta dose to air: -
D ~ t Xni DFB (1.25) 6n m i .
where: ,
Dg = beta dose to air for sector n, trad.
Xni = air concent ation of, rad,ionuclide 1 ,in sector n, Ci/='.
DF5 g = beta to air dose factor for radionuclide 1, crad/s per Ci/n'. .
t = ti=e period considered (number of seconds in this conth),
s.
The sector having the highest total dose is then used to check conpliance with specification 3.S.3.3.
e e *
. ~
- u ,.
Page 20 BF TI 47 6/21/79 1.2.2 Iodines and Particulates Ster 1,.
Doses will be calculated using the cethodology described in this step.
If any limits are exceeded, step 2 vill be perfor=ed.
Equations and assu=ptions for calculating doses from releases of iodines and particulates are as follows:
. Assumptions
- 1. Dose is to be calculated for the critical organ, thyroid, and the critical age group, infant.
- 2. Exposure pathway considered is milk ingestion
- 3. The hi'ghest annual-average D/Q based on licensing ceteorology for ground-level releases for any real cow location will be used for I-131 and I-133 doses. -
- 4. The highest annual-average X/Q based on licensing teteorology for ground-level releases for any cov location will be used for C-14 doses.
- 5. No credit is taken for radioactive decay.
- 7. The radionuclides considered are expected to contribute at least 99 percent of the total dose. However, the calculations 0
e su'.
Page 21 BF Ti 47 6/21/79 Lxtrapolate doses assu;ing that only 90 percent of the total dose was contributed.
- 8. Releases of C-14 are based on the expected source term.
- 9. The cow is assumed to graze on pasture grass for the whole year.
Equations ~
For deter =ining the thyroid dose frem milk ingestion of I-131 or I-133:
9 0 131(133) 131(133)
~
- 131(133) 3.15x10 7 vbere: ,
DTH 131(133)
= yr sefromI-1}1(I-133),crem.
Q = conthly release of I-131(133), C1.
137(733) dow fator to infan ,
.DF;37(733)
=
1-131(133} y ingestic
"~
oren/y per Ci/m 2 -s.
D/Q = relative deposition rate, 5.66x10 'n-2, 7
3.15x10 = s/y. .
For determining the thyroid dose fren milk ingestion of C-14:
DF x/Q DTH =014 74 (1.27)
'~~5.15x10; where:
UTHy4 = thyroid dose from C-14, crem.
Q 4 = conthly release of radicauclide i, C1.
DF = C-14 milk ingestion dose factor, crea/y per C1/m'.
14 _
X/Q = relative dispersion factor, 2.26x10 ' s/m'. .
3.15x107 = s/y.
For deternining the total thyrcid dose f rom releases:
!, i !
J u <f
Page 22 BF TI 47 6/21/79 MH =- DTH131 + DTH133 + DTH14 (1.28)
0.9 where
DTH = thryoid dose, cres.
DTH y31 = thyroid dose from release of I-131, nrem.
DTH y33 = thyroid dose from release of I-133, mrem.
DTH y4 = thyroid dose frcm release of C-14, mrem.
0.9 = fraction of total thyroid dose expected to be contributed by these radionuclides (actually 0.99).
Step 2 This methodology is to be used if the calcul'ations in step 1 yield doses that exceed applicable limits. '
Doses for releases of iodines and particulates ,shall be calculated using the methodology in Section 1.1.1, step 1, part B, with the following exceptions:
~
- 1. All measured radionuclide releases will be used.
- 2. Dose vill be evaluated at real cov locations and will consider actual giazing information.
The receptor having the highest total dose is then used to check compliance with specification 3.8.B.5.
1.3 Caseous Radvaste Treatnent System Operatica The gaseous radwaste treatnent system (CRTS) described below shall be maintained and operated to ::ecp releases ALARA. ,
Jh.. ,, i )"
Page 23' BF TI 47 6/21/79 1.3.1 Systen Description A flow diagram for the CRTS is given in Figure 1. . The system includes the subsyste=s that process and dispose of the gases from the main condenser air ejectors, the startup vacuum pu=ps, rad the gland seal condensers. One gaseous radvaste treateent system 1,s provided for each unit. The processed gases from each unit are routed to the plant
_ stack for dilution and elevated release to the atmosphere. The air ,
ejector of f-gas line of each unit and the stack are continuously monit. 2d by radiation conitors.
1.3.2 Dose Calculations --
Doses will be calculated conthly using the methodology described in Section 1.2. These doses will be used to ensure that the GRTS is opera-
"~
ting as designed.
S e
O g j I J u <. !!
, EXPECTEDANNUALROUTINEATMOSPilNYCRE5bASESFROMONEUNITATBROWNSFERRY Page 24 BF TI 4,
, NUCLEAR PLA% (Ci/v/ unit) STACg 6/21/79
~
REACTOR RALWASTE TUhBINE CLAND CO."J L EX BUILDING . BUILDING SE/.L AND ISOTOPC VE'iT VD~r VENTS OFFCAS MVP re-85s 6 <1 2 1.10 E4 0 Kr-87 6 4 . 95 873 . O.
TJ-88 9 4 102 1.22 E4 0 Kr-89 1 34 503 0- O.
Xc-133a 0 60 , 0 633 0 Xe-133 103 294 $81 '5.40 E4 3 CO.
l'e-135a 111 667 464 1212 O Xe-135 173 328 672 868 '
, 200.
.Xe-137 78 113 386 .0 O.
Xc-138 12 2 1179 1483 0
- -131 I 0.0594 0.0050 0.0156 0.0041 0.0055
-132 I 0.594 0.050 0.1786 0.0469 0.0973
- -133 I 0.297 0.025 0.1231 0.0323 0.0671 2-134 I 1.485 0.125 0.0267 0.0070 0.0145 I-135 I 0.594 0.050 0.1231 0.0323 0.0671_
~
- -131 0 0.0316 0.029 0.0065 0.0332 0.2741
- -132 0 0.316 0.290 0.0744 0.3801 3.1364
-133 0 0.158 0.145 -
0.0513 -
0.2619 2.1626
- -134 0 0.790 ~
0.725 0.0111 0.0568 0.4687 Z-135 0 0.316 0.290 0.0513 0.2615 2.1626 Cr 51 3 E-3 '
9 E-4 1 E-3 1 E-4 0
!:n 54 3 E-3 5 E-3 -
2 E-3 4 E-5 -
O_
., Co 53 2 E-3 4 E-4 9 E-5 2 E-3 O _.
'Ee 59 1 E-4 8 E-4 4 E-4 -
2 E-4 0 Ca 60 3 E-2 6 E-3 3 E-3 1 E-5 0$
In 65 3 E-3. 2 E-4 4 E-4 9 E-5 O_
Sr 89 , ,
1 E-2 3 E-1 *
- O_
. Er 90 2 E-3 4 E-3 *
- O_,
Fa 95 3 E-4 2 E-4 9 E-6 8E. O_
~ Ir 95 1 E-4 1 E-4 8 E-6 8 E-5 0 Ea 103 3 E-5 1 E-4 2 E-4 1 E-4 0.
/; ll&a 7 E- 6 * *
- 0.
55 120 3 E-5 3 E-4 6 E-5 8 E-5 0 Cs 134 5 E-3 3 E-4 5 E-4 2 E-5 O_
Cs 136 2 E-3 5 E-5 1 E-4 9 E-8 O_
C3 137 7 E-3 4 E-4 2 E-3 7 E-4 O_
2a 140 4 E-3 . 5 E-4 '
2 E-2 8 E-3 0.
C2 1*1 4 E-4 2 E-4 2 E-3 2 E-5 O_
Cc 144 5 E-6 *
- 4 E-6 0.
h-41 -
25 . 0 0 0 C.
C-14 0 0 0 .
9.5 O.
T.- 3 0 9.5 0 0.
/0 dNat available ' '
'n < r; I dcnctes nonorganic iodine (elcaen:al, particulate, !!IO) ;jc ,J ' t >
0 denotes organic lodine
huCEIDE LAMOA 7 C 6E7A GAMMA WASH S
>&EF-E{FE (OAYS) (1/5) (Mtv/ DIS) (MEv/0IS) (1/S) BF TI 47 1 TA!TIEN let 4.*SE 03 1.79F-09 2 1 5.68E-03 0.0 2.86E-07 6/21/79 2 C-!* eo 2.09E Oe 3.86E-12 2 1 5.17E-02 0.0 0.0 3 N-13 1 32 6. 9 4 E - 0 3_J . l e E- 0]__2 1 4,y1C-01 1.02 LQ0 1.00E_02-4 0-19 s e34 3.JeE-04 2.34E-02 2 1 1.02E 00 1.05E 00 1.00E-02 5 F-l e , 912 7.62E-02 1.95E-04 2 1 2.*lE-01 9.F9E-01 1. 0 0.E-3 4__
6 AA-24 1734 s.33E-01 1.27E-05 5 1 5.55E-01 4.12E 00 1.00E-04 7 P-32 1504 1.43E 01 5.61E-07 5 1 6.95E-01 0.0 1.00E-04 o AA-41 1805 7.63E-02 1.05E-04 2 1 3.63E-01 1.2eE 00 0.0 9 CA-51 2405 2.78E 01 2.89E-07 5 1 3 t 75E-03 3. 2 e t _0.2 1. 0.0 E - 0 4__
10 WN-54 2508 3.03E 02 2.65E-Oe 5 1 4.11C-03 d.36E-01 1.00E-04 11 wN-56 2509 1.07E-01 7.50E-05 5 1 7.93E-01 1.76E 00 1.00E-04 12 FE-59 2604 4.50E 01 1.7ed-07 5 1 1. lee-01 1.19E 00 1.00E-04 13 CC-58 2706 7.13E 01 1.12E-07 5 1 2.05E-01 9.7eE-01 1.00E-04 14 CC-60 27C8 1.92E 03 *. lee-Oy 5 1 9.oeE-02 2.50E 00 1.00E-04 15 ZN-e9M 3007 5.75E-01 1.39E-05 S 1 0.0 4.15E 00 1.00E-0*
~~f6 ZN-69 300e 3.9eE-02 2.03E-04 5 1 3.19E-01 0.0 1.00E-04 17 OA-84 ?S16 2.21E-02 3.63E-04 ' 1 1.2bE 00 1.6ME 00 1. 0 0 E_- 0 4 18 64-85 351e 2.0eE-03 3.etE-03 2 2 1.04E 00 8.40E-01 1.00E-04 19 KA-85M 3611 1.a3E-01 4.39E-05 1 2 2.53E-01 1 59E-01 1.00C-Il 20 KR-65 3e10 3.93E 03 2.0*E-09 1 1 2.51E-01 2.21E-u3 1.00E-11 21 KA-87 3612 5.2PE-02 1.52E-04 1 1 1.32E C0 7.93E-01 1. 0 0 E - L L_
22 KW-ed 3t13 1.17E-01 6.86E-05 1 1 3.75E-01 1.9eE 00 1.00E-11
_sil KR-99 3614 2.21E-J? 7.63E-03 1 1 1.23E 00 2.0eE 00 1.00E-11
< 24 AB-e8 3713 t.2*c-02 e.47E-c4 5 1 2. gee 00 6.eeE-01 1.00E-0*
Q 25 AB-89 3714 1.07E-02 7.50E-0* 5 1 0.0 2.40E 00 1.00E-04 C 26 SH-e9 3806 5.20E 01 1.54E-07 5 1 5.73E-01 1.36E-0* 2.67E-07 m 27 S4-90 lala 1.03E 04 7.79E-10 s 1 1.96E-01 0 . 0_ 2,6]E-07 d 2 tt 5H-91 Jell 4.03E-01 1.9sE-05 5 2 6.5CE-01 6.95E-01 2.67E-07 a 29 50-92 3812 1.13E-01 7.10E-n5 5 1.95E-01 1.3*E 00 1 2 5_7E-07 E 30 54-93 3el3 5.5eE-02 1.44E-03 5 1 1.61E 00 6.2eE-01 2.6tE-07 ri
% 31 Y-90 3916 2.67F 00 3.ccE-Oe 5 1 9.36E-01 0.0 1.00E-04 iT j
% 32 Y-91M 3919 3.47E-32 2.31E-04 5 1 0.0 5.56E-01 1.00E-04 y- l P 33 Y-91 3918 5. FEE 01 1.36E-07 5 1 6.06E-01 3.61E-03 1.00E-04 d 34 Y-92 3920 1.47E-01 5.*eE-05 5 1 1.4*E 00 2.50E-01 1.00E-04 "
U 35 Y-93 3921 4.29F-11 1.F7c-0' 5 1 1.17E 00 8.94E-02 1.007-0* '
36 29-95 4014 6.5CE 01 1.23E-07 5 2 1.dCE-Oi 7 35E-01 1.00E-04 m!
d 37 he-95w 4115 3.75E OC 2.1*E-Oe 5 2.65E-01 5.47E-02
('[
1 1.00E-04 36 he-95 4114 3.:CE 01 2.25E-07 5 1 4.30E-02 7.6*E-ul 1.00E-04 39 90-99 4209 2.79E 00 ?.87F-Ot 5 2
(
" 3.96E-01 1.62E-01 1.00E-04 -
~i0IC-99" 4314 2.5CE-01 3.21E-05 5 1 *.d5E-03 1.436-01 1.onE-0* I. ~ - ill 1 TC-99 4313 7.7 c7 1.n4F-13 5 9.34E-02 0.0 l3 w , 7 72 TC-104 4320 1.25E-02 6.42E-0* 5 1
1 0.0 0.0 1.v0F-04 1.00E-U4 [
-J d 43 GU-106 4407 3.e 7E 02 2.19E-OF 5 1 1.01E-02 0.0 1.00E-04 e ?
% ** TE-132 45 I-129 5223 c315 3.2*E OC 6.21E na 2.*dE-Oe 1.29E-15 5
3 1 1.cCE-01 2.05E-01 1.00E-04 (;_7 1 4.02E-02 3.77E-03 5.00E-06 46 1-131 5317 e.05E 00 4.9eE-07 3 2 1.94E-01 3.81E-01 5.00E-G6 ,s -
47 WI-131 15317 F.05E nc 9.9'E-07 4 2 ,,7 1.94E-01 3.AIE-Cl 5.00E-05 l 4M I-132 531e 9.5eE-02 8.37E-05 :O 49 p!-132 1531e 9.'eE-02 3 1 5.14E-01 2.33E 00 5.00E-C6 7 J 50 I-133 5319 6.75E-01 8.37E-05 9.17E-Ce 4
3 2 1 5.14E-01 4.0eE-01 2.33E 00 6.10E-01 5.0CE-06 5.00E-06
(; -
51 9r-133 15319 8.79r-cl 9.17E-Ge
- d 4.0*E-01 6.10E-01 5,00E-06 52 1-134 532C 3.61E-C2 2.22E-C- 3 1 6.10E-01 2.59E 00 5.00E-06 (V _- 7]
51 wI-134 15320 7. Alf -f 2 2.2pE-64 4 1 6.10E-01 2.59E 00 5.0CE-Ot__ / ^
- 54 1-135 5321 2.79E-Cl 2.H7E-05 3 2 3.68E-01 1.5dE 00 5.CCE-06 7;7 55 p!-135 15321 2.79E-Cl 2.47E_05 ' 2 3.efE-01 _1.5eE 00 5.0CE-06 So JE-131N 5412 1. lee 01 6.80E-07 1 1 1.43E-01 2.01E 02 1.0CE-11 57 xE-133M 9414 2.2eE OC__3.55E-06 1 l__1,30E-OL 4,16E-02 1,00E-11__
5e x E - l'3 3 5413 5.27F CC 1 52E-Ce 1 1 1.35E-01 4.5*E-02 1.00E-11
.50 XE-135M 5416 1.0eE-02 7.43E-0* 1 1 9.50E-02 4.32E-01 1.00E-11 t, 0 )E-135 5415 3.e3E-cl 2.09E-05 1 1 3.17E-01 2.47E-01 1.00E-11 El )E-137 5417 2.71E-03 2.4eE-03 1 1 1.64E 00 1.9-E-01 1.00E-11
~ 62 xE ll3g 5s15 1. lee-c2 6.nCE-G* 1 1 6.0$E-01 1.ldE 00 1.0CE-11 63 C5-134 5510 7._4eE_C2_ l.07t-ce 5 1 1.57E-01 1.04E 00 1.00E-0*
~54 CS-135 1.lCE C9 7.29E-15 5$12 5 1 5.14E-02 0.0 1.00t-04 65 CS-136 5514 ;1_3 c (,01 6.17E-O' S 1 1.01E-01 2.20E 00 1.00E-04 66 C52T3 7 5515 1.lcf C' 7.>*E-10 5 1 2.526-01 5.9TE-01 1.00E-04 67 CS-13a 5516 2.24E-02 _3 . 5 5 t - 0 4 5 1 1.23E 00 2.30E 00 1.00E-04
~ 6A P aZ139 Se15 5.7eE-02 1.39E-04 5 1 6.6*E-01 5.05t-02 1.00E-06 69 EA-140 5616 6 27E-07 5 1 3.15E-01 1.95E-01 1.00E-0* _ I n' 3 t I ' '/
5715-11.eeE 2tE 0[01
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~7. sp-239- 5913--2.35E CC l**lE-Ce 9310 ~5 1 1.d4E-01 2.0dE 00 1.00E-04
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Page 35 BF TI 47 6/21/79 TABLE 1.4 BROWNS FERRY NUCLEAR PLANT LAND SITE BOUNDARY DATA Elevated Elevated Ground Grourd I D/0 2 Sector Distance (m) Y/Q D/0 2 yfq t N 1,550 1.88(-10)3 9.55(-10) 2.26(-6) 5.66(-9)
NNE 1,400 4.06(-11) 7.71(-10) 1.'02 (-6 ) 2.05 (-9)
NE 1,370 3.51(-11) 5.72(-10) 7.93(-7) 1.65(-9)
~
ENE 1,400 1.65(-11) 4.14(-10) 9. 34 (-7) 3.' t-9)
E 1,570 6.03(-11) 4.73(-10) 8.04(-7) 3.34(-9)
ESE 1,470 2.79(-11) 4.27(-10) 6.81(-7) 3. 39 (-9)
SE 5,460 9.33(-9) 3.18(-10) 1.11(-7) 3.83(-10)
SSE 2,740 1.82(-9) 5.99(-10) 7.03(-7) 1.90(-9)
S 2,380 ,8. 4 3 (-10). -
5.47(-10) . 1.19 (-6) 2.51(-9)
SSW 2,410 1. 08 (-9 ) 6.61(-10) 1.32(-6) 2.40(-9)
SW 2,160 4.93(-10) 5.60(-10) 8.50(-7) 1. 4 5 (-9 )
WSW 3,120 1. 87 (-9 ) 3.16(-10) 4.90(-7) 6.11(-10)
W 2,350 5.23(-10) 2.82(-10) 8.83(-7) 1.37(-9) b7 N 3,120 2.66(-9) 4.34(-10) 6.16(-7) 1.38(-9)
NW 3,440 7. 9 7 (-9) 9.76( 10) 1.29(-6) 2. 84 (-9 )
NNW 1,620 1.73(-10) 1.09(-9) 2. 20 (-6) 4.84(-9) 3
- l. s/m
- 2. m2
- 3. 1.88 (-10) = 1.88x10- t e in0 09O JG. ll! l
,f"
?
TABLE 1.5 Page 36 BF TI 47
,' 6/21/79 *
,/
DOSE TACTORS FOR SUEMERSIO:i IN ';03LE CASES
~
s ,
2 I Dry
- DTS 3
DT3 DFB Kr-85s 1.17 (+3) ' 1.21(+3) 1.4 6 (+3) 3.86 (+3)
Kr-85 1. 61(+1) 1. 69 (+1) 1.34 (+3) 3.83 (+3)
~
Kr-87 5.92(43) 6. 05 (+3) 9.73 (+3) 2.01(+ 4)
Kr-88 1.47 (+ 4 ) 1. 50 (+ 4 ) 2.37(+3) 5.72(+3) ,
Kr-89 1. 66 (+ 4) 1.59(44) 1.01 (+ 4) 1. 88 (+ 4)
Ie-131m 9.15 (+1) 1.53 (+2 ) 4. 7 6 (+2) 2.18(+3)
Ie-133a 2. 51(+2) 3.17 (+2) 9.94 (+2) 2.90 (+3)
Ie-133 2. 9 4 (+2) 3.46 (+2 ) 3.06(+2) 2.06 (+3)
Ie-135n 3.12(+3) 3. 30 (+3) ,
7.11(+2) 1.45 (+3)
Ic-135 1. 81 (+3) 1.8S(#3) 1. 86 (+3) 4. 84 (+3) le-137 1.42 (+3) 1.4 8 (+3) 1.2 2 (+ 4 ) 2.50 (+4)
Ic-133 8. 8 3 (+ ' 9.00 (+3) 4.13(+3) 9. 25 (+3)
Ar-41 S. 84 (+3) 9. 7 6 (+3) 2.69(+3) 5. 5 4 (+3)
- 1. cret/y per UCi/c3
- 2. nrad/y per pC1/c'.
- 3. 1.17 (+3) = 1.17 x10 ' .
=
Ju_ I, d
f' TA3EI 1.6 Page 37 BF TI 47
. 6/21/79
/
STK?t E E1 Ev EAT T7AMF P *ATA B,
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~-
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TAELE 1.7 F TI 7 6/21/79
. INTE?.NAL COS*. TACTCF.S - 157M.T THYEDID - .
Radionuclide Inhalatien (cre /:C1) Icgestien (crc:/pCi)
B-3 4.62 (-7) 3.03(-7) c-14 3.79(-6) . 5.06(-6) cr-51 4.11(-s) 9.20(-9)
Te-D 2 1.9 9 (-7) 1.52'(-5) 1-131 1.05(-2) 1.39 (-2) 1-D2 1.21(-4 ) 1.5 s (-4)
I-D3 2.54(-3) 3.31(-3)
I-134 3.18 (-5) . 4.15 (-5) 1-D5 4. 9 7 (-4 ). . 6.49(-4)
- e 9
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Table 1.8 -
fif tr44 DOSE F AC1 CSS FOR STA'F Pa C1 (CMTAMf DA1CD C 70U'l 0 Page 39 (crea/hr per gcl/n2) BF TI 47 6/21/79 El ere n t Total fody Skin 14 3 0.0 0.0 C-14 0.0 0.0 hA-24 2.5CE-C8 2.9C E-C 8 P-32 0.0 0.0 Cr-51 2.;CE-10 '
2.6CE-10 Kn-54 5.ECE-09 6.ECE-C9 Ka-55 1.lCE-CS 1.3CE-CS Fe-55 0.c 0.0
. Te-59 E.CCE-09 9.4CE-09 Co-58 7.CCE-C9 8.2CE-09 Co-60 1.7CE-03 2.0CE-03 Ni-63 0.0 0.0 Nr-65 3.7CE-C9 4.3CE-09 Cu.( 1.!CE-0) 1.7CE-09 -
2n-65 4.CCE-Os 4.6CE-09 -
2n-09 0.0 0.0 Bi-63 6.4CE-Il 9.3CE-11 Br-54 1. CE-C3 1.4CE-CS Be-E5 0.0 0.0 Rb-E5 6.2:E-10 7.20E-10 Rb-E8 3.5CE-07 4.CCE-09 Rb-E9 1. 5's E - C 3 * .SCE-CS
(~ S r-B ) 5.E:E-13 6.5CE-13 Sr-91 7.1 C E - C9 8.3CE-09 Sr-92 S.C;:-C9 1.00E-03 T-50 2.' E-12 2.6CE-12 T-91M 3.EC:-C9 4.4CE-0)
Y-91 2 20E-11 Z.7CE-Il Y-92 -
- 1. C : E -0 ~s 1.9CE-09 T-93 5.70E-10 7.ECE-10 Zr-95 5.CCt-C9 5.SCE-09 Zr-97 5.ECE-03 6.4CE-09 hb-95 5.1 E-C) 6.0 E-09 Eo-59 1.51E-07 2.20C-09 Ic-51M 9.6:E 'n 1.lCE-09 Tc-101 ?.7CE '3 3.00E-0)
Ru-103 3.C^E-;3 4.20E-C9 n Ru-105 4.5CE-C) 5.10E-09 El-- -- j Ru-1C6 1.5DE-CJ 1.80E-03
- A;-1104 1.E::-C3 2.10~-03 b__;.
Te-125M 3.50E-11 4.COE-11 --
Te-127.M 1.1CE-12 1.3CE-12 % i Te-127 1.C:E-ll 1.10E-11 li Te-121M 7.7CE-10 9.00E-10 E-Te-123 7.1CE-10 8.4CE-10 __: -
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(( " ' '
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C s - 113 2.10:-03 2. 4 C E - 00 Da-131 2.4::-09 2.7CE-09 /C Sa.143 2.1:~-C9 2.40E-09 k' Ea-141 4. s E.C J 4.50E-09 Ba-142 ~ .
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l 10-8 l fj 0.1 1.0 10.0 100.0 200.0 PLUME TR AVEL DISTA CE (KILO.*.1ETERS)
Re ative Deposition for Com Releases (Letters denote Pasquili Stab;lity Clas:)
- <; rt
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FIGURE 1.2 (CCNTINUED) Page 47 BF TI 47 6/21/79 s
104 ' ' '
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i , , , ,
l l 4 I , i I l i j I I l 0 6 l { O I t ii1 I f i I I I i il ' t ii i I )
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0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)
Relative Depcsition for 100m Releases (Letters denote Fasquill Stability Class)
T,'
Jo .
[1'1
.- Page 48 BF TI 47
. > ^/21/79 4
s .
g
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ea.; "r s , 2 4..
s . 'L.I a g y" as E a o M 1 w3 c .~:,.a 5. -
sm
- ":,ri k.r' ' f. x 33
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=*
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Page 49 BF TI 47 6/21/79
- 2. Liquid Effluents 2.1 Concentration 2.1.1 RETS Tsequire=ent,
' Specificatica 3.8.A.1 of the Radiological Effluent Technical Specifi-cations (RETS) requires that the concentration of radioactive material released at any tice from the site to unrestricted areas (see Figure 2.1 -)
shall be limited to the d.axi=um Permissible Concentration (MFC, attached as Appendix I) specified in 10CFR20,~ Appendix B, Table II, Colu=n 2 for nuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concen?'.ation shall be limited to- 2x10 " pCi/nl total activity. .To ensure co=pliance, the following approach will be used for each release. --
2.1.2 Prerelease Analysis Prior to release a grab sample will be analyzed for the concentration
~
of each radionuclide.
. n ,
C= C (2.1) 1 A
vbere: i=1 C = total concentration in the liquid effluent, pCi/ml.
C = concentration of radionuclide i, pC1/el.
f 2.1.3 MPC-Sus of the Ratios The sum of the ratios (R ) for the release vill be calculated by the _
following relationship.
C C C C^ +. . . . (2.2)
R = MPC + MPC . + MPC . + MFC A B i n l .
g , d ,.
Page 50 BF TI 47 6/21/79 where: ,
C = undiluted effluent concentration of radionuclide i, as g
determined in Section 2.1.2, pCi/ml.
MFC = the MFC of radionuclide 1, ,Ci/ml.
R = the sum of the ratios for the release.
Tor prerelease and post-release analysis each Cf is first assu=ed ,
to be unknown and the MPC is then 1x10 -7 pCi/ml for each radionuclide i. If the R calculated is too large for equation 2.3 then the appropriate MFC will be used for each C . There is one liquid release point into the discharge canal by one of 3 possible codes.
open -3 pacps 0 200,000 gpa/purp -------
Radwaste
^
s helper - 3 pu=ps 0 150,000 gp= /p ucp ------*-Dis cha r ge conduit closed - 50,000 gpa ---- -
The follewing relationship will assure concentrations are within allowable limits.
f(R-1) < F (2.3) where:
f = the radwaste flow rate (gallons /tinute) before dilution.
R = the sum of the ratios of the release as determined by Equation 2.2.
F = mini =um dilution flow rate for prerelease analysis.
2.2 Instrurent Setpoints 2.2.1 Setpoint Determination r, . r '
l );
jb. 't
- Page 51 BF TI 47 6/21/79 The respective alar =/ trip setpoints at etch release point vill be set such that Equation 2.3 is satisfied. The cathodology describing the setpoint determination is contained in Technical Instruction 45.
2.2.2 Post-?clease /malysis *
~
A post-release analysis vill be done using actual release data to ,
ensure that the IL its specified in Section 2.1.1 were not exceeded.
A cc=posite list of concentrations (C.),
1 by isotope, vill be used with the actual liquid radvaste (f) and dilution (F) flow rates (or volunes) during the release. The data vill be substituted into Equation 2.3 to de= castrate cc=pliance vi .h the licits in Section 2.1.1. This data and setpoints vill be recorded in auditable records by plant personnel.
2.3 Dose 2.3.1 RITS Recuirerent Specificatica 3.8.A.2 of the Radiological Ef fluent Technical Specifi-cation (RITS) requires that the dose or dose co=rittent to an individual fres radioactive caterials in liquid effluents released to unrestricted areas frca cach reactor (see Figure 2.1) shall be li=ited:
a.
During any calendar quarter to j[ 1.5 =re= to the total body and to j[5 tres to any organ, and b.
During any calendar year to j; 3 nre: to the total body and to,j[ 10 mres to any organ.
To ensure co:pliance, cu=ulative dose calculations will be perfor:ed at least once per nonth according to the fellowing nethodology.
"a f 8
)U_ !' s)
Page 52 BF TI 47 6/21/79 2.3.2 Monthly Analysis Principal radionuclides will be used to conservatively esticate the monthly contribution to the cu=ulative dose. If the projected dose exceeds the above li=its, the cethodology in Section 2.3.2 vill be imple=ented.
The following radionuclides contribute at least 93 percant of the total esticated dose based on four years of operational source terms.
Percent of Fish Dose Percent of Ingestion Dose Total Body GI Tract Total Body Thyroid B-3 - -
8.5 1.0 Na-24 - -
2.5.
.3 Co-60 -
.5 1.8 .2 2n-65 5.0 3.9 3.7 .4 Sr-90 .9 -
32.2 ~3.8 Nb-95 -
67.4 - -
I-131 -
.1 1.2 81.1 I-133 - - -
5.9 Cs-134 40.4 8.3 20.7 2.4 Cs-136 2.4 3.3 1.7 .2 Cs-137 51.0 14.5 26.1 3.1 99.7 98.0 98.4 98.4 A conservative calculation of the conthly dose vill be done according to the following procedure. First, the conthly operating report containing the release data will be obtained and the activities released of each of the above 11 radionuclides will be noted. This information will then be used in the folleving calculations.
2.3.2.1 Water Ingestien The dose to an individual from ingestion of water is described by the following equation.
n ^- O
' '3
- u.
. Page 53 BF TI 47 11 6/21/79 D = '
95 ij
- i vhere: i=1 th D = dose for the j organ from 11 radionuclides, ren.
j = the organ of interest (thyroid or total body).
. 95 = conservative correction factor, considering only 11 radio-
_ nuclides.
DCF = adult ingestio1 dose co==ittent factor for the j organ from the i radionuclide rea/pci, see attached Table 2.1.
I = monthly activity ingested of the i radionuclide, UCi.
f I is described by f
365 A V I
i
=
12 U d * (2.12) vhere:
365 = days per year A = activity released cf i radionuclide de-ing the =onth, f
DC1.
V = average rate of water consu=ption (730 ml/d ICRP 23, p. 358) 12 = conths per year u = total cooling tower blowdown during releases, nl.
d = minimum diffuser pipe dilution (5)
The dose equation then becoces 11 .
D = 4. 6 x10' xA crem (2.13) j u (DCF)13 1 i=1 .
2.3.2.2 Fish Ingestion The dose to an individual from the consumption of fish may be described by Equation 7-11 where i is deccribed by q3 q e _<
I) )- '
Page 54 BF.TI 47 6/21/79 I =
A 3it i
pCi (2.14) ud vbere:
A g = activity released of ich radionuclide during the conth, pCL .
Bg = fish concentration factor of i radienuclide fj[ see attached Table 2.1.
H arount of fish cates conthly (1.9x103 ga) ~
U = total cooling tower blovdown during releases, nl.
d = cinitun dif fuser pipe dilution (5)
The dose equation then becones 11 5
Dg = 4 x10 A I B x DCF orea (2.15)
If these calculated conthly doses exceed litics specified in Sectica 2.3.1, then a core accurate and co:plete calculation vill be donc as described in Section 2.3.3. An annual check vill be cade to ensure that the conthly dose esticates account for at least 95 percent of the dose. calculated by the cethod described in Section 2.3.3. If less than 95 percent of the dose has been esti=ated, a new list of principal isotopes vill be prepared.
2.3.3 Annual Analysis A ce=plete analysis utilizing the total source release vill be done at least annually (conthly if necessary). This analysis vill replace previous estL=ates calculated in Section 2.3.2 and consists of the -
following approach. The dose to the j th organ fron a radionuclides, D ,
J is described by 4 O .
f
- (* % f J b '- \' ')
- Page 55 BF TI 47 m .
6/21/79 D = D (2.16) j ij , rem i=1 .
m .
- (DCF) x I , rem (2.17) i=1 where: .
th radionuclide, rec.
organ from the i Dg ) = dose to the j
- j = the organ of interest (bone, GI tract, thyroid, and total body). .
(DCF) = adult ingestien dose co=mitment factor for the j organ th radionuclide, rea/pC1, see attached Table 2.1.
from the i I for water ingestion is described by A Vn f -
(2.18)
I i
u d , pCi and for fish ingestion I is described by A B M
=
f f , pCi (2.19)
I i ud where:
th radionuclide during the release A g = activity released of j period, pC1.
V = average rate of water consumption (730 ml/d). .
n = nu=ber of days during the release period (d) .
U = cooling tower blevdown during the release period, cl.
Bg = fish concentration factor of the i radionuclide, fj H = amount of fish caten monthly (1.9x10' go).
d = minimum diffuser pipe dilution (5).
pO Q 49 Ju..
Page 56 BF TI 47 6/21/19 2.4 Operability of Liquid Radwaste Equipment Specification 3.8.A.5 of the Radiological Effluent Technical Specifi-cations requires that the liquid radvaste systes shall be used to reduce the radioactive caterials in liquid wastes prior to their discharge when the projected dose per unit due to liquid efflient releases to unrestricted areas (see Figure 2.1. ) when averaged over 31 days vould exceed 0.06 mres to
~ the total body or 0.21 cres to any organ. The following cethodology will be t=ple_=ented to assure cc=pliance.
2.4.1 Release Limit The liquid radwaste operability limit is an activity release limit based upon four years of operational releases excluding tritiu=. The curie linit is dependent upon the future operational mix being similar to past operational nix. The ccst restrictive pathway is to the C1 tract by ingestica of fish. The individual dose fro = the operational source terna was calculated to be .04 crea/co. This dose is a factor of 5below the cperability limit of 0.21 crem to any organ. The total activity released excluding tritius is 0.10 curies. The allowable release without exceeding 0.21 cre /co is 5 times 0.1 curier., or 0.50 curies /co excluding tritium-A =
0.50 Ci/co. excluding tritius The value of 0.50 C1/co will correspond to the linits specified in secticn 2.4 if the =Lxture of isotopes is similar to the historical mixture.
h Ju_ '. -
TAliLE 2.1 [
Mh@"
ar
~
OfJ i
QM n "
pi DOSE CALCULATIC!! DATA
. ~
J t- t .d au-, ,
Fl%H OIOLCO, 8ADIOLC, OtnLnOfCA(. EfiECT!VF U U " .*M OUSE C rnllM hi TMi%9 (MEP/UCI)
,_h n W (nNCEhlHAI!ON FA?In niLF-Liff~"
HTLi-Lift itALF-L(FE HatF/L!Ft
$1AutE R A0 !!!L O . (day 5)
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1,106 01 5.9)l-01 1,7M-03 5.321-02 1.73C-03 1,7 3 E .0 3 13 00F_02 1,00E ,02 0.0 Pl 3 -L' 6 3_11( r 1 1.00E 05 0.0 1 4 J f. C1 2.5/E Q2 1.3)E 01 1 9 9 t -C l. 1.240-01 f.g/E-03 1. 4 / L - 0 3 1.00t 0)
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Page 59 BF TI 47 6/21/79
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o page 60 EF TI 47 6/21/79 3.0 Radiolo ! cal Environmental Monitoring , .
3.1 Pon i_t o r i: - pro c ra s
. An environmental radiological =onitoring progran shall be conducted as descrite4 in Tables 3.1-1, ,3.1 -2 and 3.I; 3, and in Fij;vres '
3.1-1, 3.1-2, 3.1-3, and 3.1-4 . Results of this progran shall be reported in accordance with Technical Specifications 6.7.1.d and 6.7.2.c. -
The at=ospheric anvirennental radiological monitoring proh;ran shall consist of 11 paitoring staticas 'rc= vhich sa:ples of air partic-ulates, at=ospheric radloicdine,'rainvater, and heavy particl( fallout shall be collected. - ' ~
The terrestrial coditoring progra: shall consist of the coll.tction of milk, soil, ground water, drinking water, and food crops. In additica, direct ga=a radiation levels will be reasured in the vicinity of the plant.
9r The reservoir sanpling progra shall censist of the collection of
' samples of surface water, sedi:ent, and fish.
Deviations are pernitted fron the required sa=pling schedule if specimens are unobtainable due to ha:ardous conditions, sample unavail'-
ability, or to calfunctica of sampling equiprent. If the latter, every effort shall bc =ade to conplete corrective action prior to the end of the next sampling period.
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Page 61 BF TI 47 6/21/79 3.2 Detectio3 Cacabilities ,
Analytical techniques shall be such that the detection capabilitics listed in Table 3.2-1 are achieved. .
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TABLE 3.1-1 (Continued)
Exposure Pathway Sampling and Type and Frequency and/or Sampic Sample Location- Co11cetion Frequency of Analysis 1 sample at the next 2 Monthly grab sample Gross beta and gamma scan monthly.
downstream potable surface Compositeguarterlyfortritium, unter supplies (greater than Sr, and 'Sr.
10 miles downstream) (TRM's 274.9 and 254.3) 1 sample at a control Monthly grab sample location (TRM 306.0)
Sediment TRM 307.5 Semiannually Camma ocan, Sr, and Sr analyser (Figure 3.1-4) TRM 393.7 ,
semiannually TRM 288.8 ,
TRM 278.0 i
INCEST 10N ,
Milk 1 sample from milk Sem1 monthly when animala ts I analysis semimonthly or monthly (Figure 3.1-3) producing animala in each are on pasture. ' Monthly on collection. Camma nean, Sr.
of 1-3 areas indicated by when animals are off and Sr monthly.
the cow census wnere doses pasture.
are calculated to be highest. If samples are not available from an aren, doses to that area vill bc estimated by projecting the doses from concentrations detected in milk from other t,, sectora or by sampling vegeta-c;3 tion where milk is not avail-able ggym n
- Z) 1 unmpic from a control location Cd
~1 Ql ~a $
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- Samplo locationn are shown in Figures 3.1-1, 3.1-2, 3.1-3, and 3.1-4.
TABLE 3.1-1 (Continued)
Exposure Pathway ,
and/or Sampic j Fish 1 sampic cach of a commercial and a Scmc species in Cuntersville Reservoir above the plant 1 nample cach of a commercial Semiannually Camma scan semiannually.
and a game species in Wheeler Reacrvoir near the plant 1 sample each of a commercial I and a game species in Wilson Reservoir below the plant Food Products 1 sample each of principal Annually, at time of harvest. Camma scan on ediblo portion food producto grown at The types of foodn ava: lablo private gardenu and/or farms for cumpling will vary.
in the immediate vicinity of Following is a list of typical the plant. Selection of foodo which may be available:
locations to be based on the cabbage and/or lettuce, corn, land use census. green beans, potatoco, and t omil t o c S .
1 sample cach of the same good products grown at control locations. e R R$ 2
$!d5
- Sample locations arc shown in Figures 3.1-1, 3.1-2, 3.1-3, and 3.1-4. 2 $
t' ,
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.~ 'D
%Q
TABLE 3.1-2 Page 66 BF TI 47 6/21/79 AEOSPEERIC A'O TERRESTRIAL MOSITCRISG STATICS LOCATIONS BRC'a7;S TERRY NL* CLEAR PLAST Location and Approxicate Distance and Direction frc= Plant LM-1 BF 1.0 mile N L+2 BF 0.9 ciles 53T LW3 BF 1.0 miles hT .
LW4 BF 1.7 niles hSW LM-5 BF 2.5 niles WSW FM-1 BE (Rogersville, AL) 13.8 niles NW PH-2 BF (Athens, AL) 10.9 niles NE PM-3 BF (Decatur/ Trinity, AL) 8.2 niles SSE
~ ~
PM-4 BF (Courtland, AL) 10.5 niles WSW RM-1 BF (Muscle Shoals, AL) 32.0 miles W RM-2 BF (La.renceburg, TN) 40.5 niles hTJ Fars B 7.0 miles hTJ Farm S 4.8 ciles N Far= Bi 4.5 niles EST Fara L 5.8 ciles D;E Farn T 7.0 miles E;E Fars N (control) .
27 niles I;V Fars J (control) 40 miles hTJ _
Farm C (control) 32 niles N Far: Ca (control) 32 ciles W I n ') f':;
su_ ,
r)
Page 67 BF TI 47 TABLE 3.1-3 6/21/79 L15 TING OF IENSESSEE RIVER SURFACE WATER SUPPLIES TO BE SAMPLED IN ENVIRO:OENTAL MONITORING PROGRAM' Distance from Plant Supply Source (miles)
Courtland (Champion Paper Co.)# Tennessee River 11.6 (mile 282.6)
Decatur Tennessee River 12.0 .
(mile 336.0) .
Wheeler Hydro Plant Tennessee River 19.1 (mile 274.9)
Sheffield Tennessee River 39.7 (mile 254.3)
- a. First potable water supply downstream of the plant. Sample collected automatically and analyzed conthlq. ,
~
- b. Decatur is upstream of the Browns Ferry Nuclear Plant.
=
\
_,. u. '
Tablo 3.2-1 . , .
e OrTrning CAP Antt.tTir t ten rW1 paw 7m At. S et 1* ANAiV313 C A. S pe l f t e An a l y . e s_
WoHIN A1. Int'in t THtt ns' rfirrTinN (t t t))_a
,,.h mm Vegatetton soll and clan flesh. Foods, east, N Air SeJteent plankton. Clam shelle poultry. Millt Particulates Charcos! Tallout Water and grain pct /p. dry pCtrt. dry pCl/Fre. wet pff/l pCf/e 8 JCf[e' aCl/Ka' pCf/1 @ f,, dry gCt/g, dry 0.01 1.5
"" Total a 0.05 0.35 0.1 0.7
- 0.005 0.05 2.0 9 Cross a
- 2.3 0.20' O.70 0.1 0.7 +
25 e
ID Crose $ 0.01 .
330 0.5 CIZTOj] 'H, 0.01 0.5 5.0 40 10 p,L?
y 5r 1
0.005 to 0.25 0.05 1.5 0.3 0.1 1.0 8 2 2
' 5r 0.001 gy
- NZ',1 f.ha . .
'ng -
fA._Oh B. Camras Analysea p- y U N0H!NAt. LOLER LIMIT OF DETECT!09 (11D)
Vegetation 5011 and -
Clas flesh Foods, tomatoes Heat end Air Wter particulatie and allk and r. rain
8 ' 8 ' '"Ce 0.03 8 0.55 0.35 0.35 0.35 38 90 c.06 40 0.22 0.06 0.06 0.35 33
Ce 0.02 33 0.56 0.60 0.10 60 44 200 to
Cr 0.07 0.03 60 44 1.10 0.47 0.60 0.10 0.60 0.10 .
20 88't 0.01 0.01 15 0 0.35 0.09 0.20 0.02 0.20 0.02' O.07 0.20 0.02 15 8 50 0.45 0.45 0.45 40 150
''Ru 0.04 40 0.65 0.51 0.11 0.11 0.74 0.11 40 90 8Aw 0.03 40
'8'Ce 0.01 0.02 10 26 0.20 0.33 0.12 0.09 0.12 0.00 0.48 0.12 0.08 10 26 40 50 .
0.12 0.02 0.08 0.12 0.02 10 5 40 15
Cs 0.01 0.01 10 5 0.20 0.06 0.12 0.02 0.12 0.12 10 40
' ' 7 r -W 0.01 10 0.20 0.12 0.11 0.03 0.03 0.15 0.0) 10 20
2r 0.01 10 0.05 0.01 0.01 0.07 0.01 5 15
'%b 0.01 5
$g
Co 0.02 0.01 15 5 0.23 0.05 0.20 0.01 0.20 0.01 0.07 0.20 0.01 15 5 55. 15 c7 0.02 0.0L 10 .5 0.20 0.05 C.15 0.01 0.15 0.01 0.03 0.15 0.01 10 5 40 15 N g
th
' '2 n 0.02 0.01 15 9 0.25 0.11 0.23 0.02 0.23 0.02 0.17 0.23 0.02 15' 9 70 20 CH w
b' Co 0.01 0. 0 L 10 5 9.17 0.06 0.11 0.01 0.11 0.01 0.0S 0.11 0.01 10 5 30 15
- "e $
0.90 0.90 0.90 150 400 c3 r 0.10 150 2.50 0.15 0.15 c, 0.15 15 50
' ' ' B a - 1.4 0.02 15 0. f. 8
' ~i 0.07 0.07 0.30 0.07 25 50
es 0.02 25 0.34 0.02 0.02 0.10 0.02 7 15
La 0.01 7 0.03 i
s
e y
Page 69 BF TI 47
/
TABLE 3.2-1 (Continued)
TABLE NOTATIONS
- The Nal(T1) LLD valoes are calculated by the cethod develope'd by Pasternak and Harley as described in RASL-300 and Nucl. Instr. Methods, 533-40 (1971).
These LLD values are expected to vary depending on the activities of tbc coc-ponents in the samples. These figures do not represent the LLD values achievable on a given sa=pic. Water is counted in a 3.5-L tbrinelli beaker.
Vege ta t ion , fish, soil, and sed'i=ent are counted in a 1-pint container as dry weight. The average dry weight is 120 grams for vegetation and 400-500 gra=s for soil sedi=ent and fish. Meat and poultry are counted in a 1-pint container as dry weight, then corrected to wet weight using an average coisture content of 70%. Average dry weight is 250 grs=s. Air particulates are counted in a well crystal. The counting syste= consists of a =ulti-channel analyzer and either a 4" x 5" well NaI(Tl) cry;tal. The counting ti=c is 4000 seconds. All calculations are perforced by the least-squares cc=puter progra= ALPHA-M. The assu=ption is made that the sa=ples are analyzed within one week of the collection date.
- The Ge(Li) LLD values are calculated by the =ethods developed by Pasternak and Harley as described in RASL-300. These LLD values are expected to vary depending on the activities of the ca=ponents in the sa=ples. These figures do not represent the LLD values achievable on given samples. Water is counted in either a 0.5-L or 3.5-L Marinelli beaker. Solid sa=ples such as soil, sedicent, and clan shells are counted in a 0.5-L Marinelli beaker as dry weight. The average dry weight is 400-500 gra=s. Air filters and very small volu=e sa=ples are counted in petrie dishes centered in the detector endcap. The counting syste= consists of a ND-4420 cultichannel analyzer and either a 8%, 14%, or 18:: Ge(Li) detector. The counting ti=e is nor= ally 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. All spectral analysis is perforced using the soft-water provided with the ND-4420. The assumption is =ade that all sa=ples are analyzed within one week of the collection date.
- a. All LLD values for isotopic separations are calculated by the =ethod developed
' by Pasternak and Harley as described in RASL-300. Factors such as sample size, decay t !=es , chemical yield, and counting ef ficiency may vary for a given sample; these varia tions =ay change the LLD value for the given sa=ple. The assu=ption is =ade that all sa=ples are analyzed within one week of the collection date.
The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95 probability with 5% probability of fasely concluding that a blank observation represents a "real" signal.
e av .
t
- Page 70 BF TI 47 6/21/79 TABLE 3.2-1 (Continued)
TABLE NOTATION For a particular =easure=ent systes (which =ay include radiochemical separation): , ,
4.66 s b LLD =
g,V 2.22 y exp(-Alt) where LLD is the lower li=Lt of detection as defined above (as pCi pet unit = ass or volu=e) .
s is the standard deviation of the background counting rate or of
- t. e counting rate of a blank sa ple as appropriate (as counts per ninu te) .
E is the counting efficiency (as counts per transfor=ation)
V is the sample size (in units of = ass or volu=e) 2.22 is the nu=ber of transformatica per minute per picocurie Y is the fractional radiochc=ical yield (when applicable)
A is the radioactive decay constant for the particular radionuclide at is the elapsed ti=e between sa:ple collection (or end of the sa:ple collection period) and ti=e of counting The value of s used in the calculation of the LLD for a detection system b
shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance.
0 W
,mt
., u . 4
Page 71 I /~/ BF TI 47 Ticurc 6/21/79 Arowns Fcery !:oclear Pl.mt ATMOSPHERIC AND TE.RRESTRIAL MONITORING NETWORK Au 2BF
- s AsEENCEBU7C 4 PUL ASNI F AYETTCv!LLE 77 pu lar wtL5CM wwggtga ,n ,5 c.
FLCRCSCI g A ,[ ATIENS
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- f ' Ct LC".v 4G S a 'A DLES AAC CCLLECrEO ikC4 EACH STATaON' AIR PARTICu( AT(5 R AINWATC A R AOiO'CCihE SC'L
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~.r .f^
M AVY PARTICLE FALLovt VECETATION .,
, y j . . . f,;
Q Q, a ~
w:ncs a
. fsp a 3./- z [7;,72 LOCAL MONITORING STATIOA'S'"
BROWNS FERRY NUCLEAR PLANT
/
i
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-6 -
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RIVER Legend 0 Air Monitor >ng Station O TLo station Scoto O g 2 y k- -
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Page 73 Ff;; . .t 3./. 3 BF TI 47 6/21/79 LOCAL MONITORING STATIONS BROWNS FERRY NUCLEAR PLANT O N
ATHENS
/
U _ U S. HWY 72 / ~
. /j O
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- 3. / ~ Y Page 74 FIgute LF TI 47 Browns Ferry Nuclear Plant
. R ESERVOlP, MONITORING NETWORK __
Q N
Sk River .
WHEELER DAM mile 274.90 h
-mile 277.98 ,
Rogersville f
O mile 282.e
( mile 291.76 Athens O 4 mile 285.2 -
f 8 F. NUCLEAR PL AN._t O-D Champion [ G Paper Co. %
mile 22S.76 .,
mUe 293.50 mHe 305.0 O g Courfland mile 293.70 0 .
Deccier
. i mile 307.52 Sccie of Miles ,
o - Automatic Somo!er _5 5 0 Q
rns
~.
Page 75 BF TI 47 6/21/79
~
~
Appendix I
~~ This appendix contains 10CFR20, Appendix B. The values in this appendix are the maxi =um per=issible concentrations (MFC) in air and water above
~
natural background.
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