ML20151S014
| ML20151S014 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 04/12/1988 |
| From: | Mcdonald R ALABAMA POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| FNP--M-11-1, FNP-0-M-011-01, NUDOCS 8804280152 | |
| Download: ML20151S014 (55) | |
Text
- - - -
INP-0-M-011 i
September 4, 1987 Revision 4 AIABAMA PGs'ER COMPMN JOSEPH M TARLEY NUCLEAR PLNTI' UNITS 1 N?D 2 S
A T
E T
Y OFFSITE DOSE CALCUIATIO1 MNNAL R
Cm L
A UNCONTROLLED COPY g CAUTlON:yg*
- s Approved:
p Do M,
[. O k A/V Technical Manager Date Issued:
'7 - /8'8 7 List of Effective Page Pace
- Rev, 1,11 2
1-8 2
9-20,22-24,28-32,34-38 0
21,25-27,33 3
39,41,42,46,49 1
40,44,47,48 2
43,45,50,51 4
DN ODCM/3 8804280152 Ef 0flA.
PDR ADOCK 05000348
\\
P DCD
)
J
FNP-0-S 011 TABLE OF C0tmNTS f*S!
Table of Contents i
CDO4-Tech Spec. Cross Reference Table 11 Liquid Effluents 1
Gaseous Effluents 9
Noble Gases 17 Radiciodines and Radioactive Materials in Particulate Form 24 i
Dose Assessment for Environmental Radiation Standards 38 Radiological Environmental Monitoring 14 cations 39 Determination of alarm trip Setpoints for Liquid Monitors 48 l
Determination of alarm trip setpoints for Gaseous Monitors 50 l
L l
l l
l 1
Rev. 2
r l
i FNP-0-M-011 i
ODOS-11tCHNICAL SPECIFICATIONS j
CROSS-REFERENCE TABLE i
Radiological Effluert Technical Specification Dose Calculation ODCM Section Methodolooy Page 3.3.3.10 Determination of Alarn Trip 48 Setpoints For Liquid Monitors 3.3.3.11 Determination of Alarm Trip 50 Setpoints For Gaseous Monitors i
4.11.1.1.1 Liquid Effluents 1
4.11.1.1.2 Liquid, Effluents 1
4.11.1.1.3 Liquid Effluents 1
4.11.1.2 Liquid Effluents 1
t 4.11.1.3.1 Liquid Effluents 1
t 4.11.2.1.1 Noble Gases 17 4.11.2.1.2 Gaseous Effluents 9
- l:
4.11.2.2 Noble Gases 17-23 l
[
4.11.2.3 Radiciodines and Radioactive 24-37 Materials in Particulate Form i
4.11.2.4.1 Gaseous Effluents 9
4.11.4 Dose Assessment for Environmental 38 t
Radiation Standards l
4.12.1 Radiological Environmental M5nitoring 39-45 t
6.9.1.9 ODCM All l
6.9.1.10 ODCM All 6.14 ODCM All I
11 Rev. 2 l
[
1
INP-0-M-011 Dose Calculation Due y Liquid Effluents 4.11.1.1.1 4.11.1.1.2 4.11.1.1.3 4.11.1.2 4.11.1.3.1 Liquid Effluents-Dose Calculations a
The dose contributions for the total time period I atl 1-1 shall be determined by the following calculation and a cumulative sunnation of these total body and any organ doses shall be maintained for each calendar quarter. tese dose contributions shall be calculated for all radionuclides measured in liquid effluents released to unrestricted area using the following expression:
m D, = Z[A, lel I at 3
t C, 3 rg3 )
i where:
D, he cumulative dose or dose comitment to the total body or an
=
organ T from the liquid effluents for the total time period m
I at, in mrem.
3 1=1 At1 the length of the 1" time period over which C and r are
=
i1 3
averaged for all liquid releases, in hours.
C,1 the average concentration of radionuclide i in undiluted liquid
=
effluent during time period at from any liquid release, in 3
uci/ml.
A,,
the site related ingestion dose and dose commitment factor to the total body or organ T for each identified principal gama
,and beta emitter, in arenvhr per uCi/ml.
A,, = k,U,Br Dr i
i where:
k, unit conversion factor,1.14 x 105 (year /hr).(ml/1).(pC1/vci).
=
U, adult fish consumption, 21 kg/yr.
=
BT, the bioaccumulation factor in freshwater fish for each measured
=
radionuclide 1, in pC1/kg per pCi/ liter (Table 1).
1 Rev. 2
FNP-0-M-011 the dose conversion factor for nuclide i for adults, in Dr,
=
are W pci (Table 2).
the near field average dilution factor for C during any r
=
3 1
liquid effluent release. Definedastheratioofthemaximum undiluted liquid waste flow during release to the product of the average flow from the site discharge structure to unrestricted receiving waters times 5.
(5 is the site specific applicable factor for the mixing effect of the discharge structure.)
For radionuclides not determined in each batch oc weekly composite, the dose contribution to the current calendar quarter cumulative sumnation may be approximated by assuming an average monthly concentration based on the previous monthly or quarterly composite aaulyses.
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FNP-0-M-011 TABLE 2*
ACULT !'!GE!7?cN 00$E r.tc7*45
(.trem/pGt ingestec)
NUCLI3E 3CN(
({y[q fnfg( gq)y Twyqq{}
({}q(y (ej y g g { -e,( [
14 3
0.0 1.34E-07 l.3eE-07 1.30E-07 t.3GE-07 t.3aE-47 1.3dE-07 a8E 10 3.tSE-06 3.9tE-a7'*7.85E-06 0.0 3.11E-67 3.0 2.bdE-05 6C 13
- 2. Set =09 5.soE=of 5 soE=o?
4.Aar or r,. 6 4 r -6 7 5,60E-07 5.e*E-07 74
-13
- 4. 5-Z E -0 4
$.37E=o9
$. 3 7 E -0 9 A.31E-04
$.375-09
$.37E-04 6.37E-04 98 15 6.2SE 07 3.0 6.93E 05 0.0 0.3 3.0 1.55E=0A
,1144 22 1.74F-05 1.7at-05 7at-os t.7at as 1,7at-45 1,7aE-05 1,747 05 11**
du 2.20E-40 2.2sE-Oe 2.dsE=0e 2.2tE-03 2. / s d. = o n f.2si=0e d.dai-wo 157 32 1.*3E-04 1.2tE-05 7.37E-06 0.0 0.3 1.3 2.17E-05 20!A at 1.57E*0s 3,0
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4.0
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5e 0.0 1.15E-07 2.0$E-os 00
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$5 6.20E-06 2.7'E-05 7.33E-06 0.0 0.0 3.23E-05 1.39t=05 268E 54
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i=0s 27C3 55 0.0 7.d6E-07 1.$7E-66 0.0 3.0 3.0
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$3 1.30E-08 9.32E-16 a.36E-06 0.0 3.3 S.o 1.d8E-0%
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1.346 0$
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!.74E-44 1.0 4.3 3.0 2.54E=ce 3554
$3 J.J J.0 a.02E-04 0.0 3.J a.J i.iiE-0A 3538 ta 3.0 3.0 5.22E-04 0.3 3.3 1.3 4.34E-13 3598 SS 1,1 0
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I Gen. Rev. 2
FNP-0-M-011 GBLE 2*(Continued)
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3.0 a.87E-08 e2 0 #3 3.0 7.52E 66
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- 1. 5 d E -0 4 1.0 g,0*E 44 4.0 1.10E o?
1.6 0.32E-04 dudV 10e 2.156-0e 3.0 3.46E-07 0.0 5.32E-0e 1.0 1.76E-04 458w 105 1.22E-07 1.56E 05 5.83E-08 0.0 3.7bE-07 3.0
- 1. ale-05 3689 107 0.0 1.27?-67 a.att
^2 S.0 1.32E-os i.0
- 9. I'! E -0 7 de*0 139 J.0 t.77E*07 4.30E-06 0.0 1.ats-Ce J.J 1.906-05 47AG !!04
- 1. 3 0 E -0 7 1.a8E-07 9.FCE-09 0.0 2.1tE-47 1.3 6.caE=og 27AG 111 5.82E-04 2.auf-aa 1.2t! ^9 1.6 7.89E
^8 3.1 a.a6E-65.
- eG3 115 J.0 3.14f=0s 1.021-07 1.0 3.50E-as 3.4 2.ioi-^5 uSC3 115*
3.0 1.5aE-06 5.34C-0a 0.0 1.46E-06
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5058 125 6.3eE=oe t.sdf=o7 3.7e!.17 1.3aE-a7
- .a 3.)
- 1. J 4 t. e 4 i.0 s.33E-44 50$N 125
- 9. Jet-05 1.s5E=ce 2.st!-on u.42E-07 0.0 J.0 2.a3E-45 5tSa tis
- 2. ate =0e 5.33E-aa 1,gtr-ng v.73r=43 3,3 2.ter-og 7.a5E=os Stad 12i 2.23F-on 2.40E-06 a.aat-47
- 1. 7 S E -0 4 0.0 2.33E-ou 4.47E-05 5135 126 1.15f-06 2.3aE os a.15E-07 7.05E-04 0.3 7.01E=47 9.J0E-05 5159 127 2.58E-07 5.e4E-0*
4.82f-as 3.ftt-08 1.3 1.93E=of 5.46E-49 52rt 125 2.edE-Ce 8.73i-d7 3.S*E-of 6.07!-07 1.JSE 05 J.J 1.47E-05 527E 127*
$.78E-06 2.37f=06 S. 2.s E-0 7 1.73E-os 2.75E-05 3.0 2.27F=os
$27? !?7 t.tSE-07 3.85E a9 2.3at-na 8.15t 09 a.aAE-a7 3.n 9.tAE=o*
52ft 124=
1.15E-05 4.30E-at 1.'21-06 3.45F=0S d..' 0 E -0 5 1.J 5.78E*05 527! 128 3.15E-08 1.19E 49 7 est-09 2.at!-0S 1.32E-67 3.1 2.37E-06
_32fE e3t*
t.7at-oe 9.27? 47 7.a=(-47 t.3at=0g a, sag-ag 3,3 g,30g-og 52'E 131 1.i7E-06 5.2sE-09 s.22E=0*
1.ad!-oi
- .s F.=qt 1.a 2.454-90
$2f! 112 2.53E-05 1.sdE=ot 1.53E-06
- .3 0 E -0 6 1.5ME-05 1.1 7.*tF=05 127! t33w 2.e3F-69
?.SSE-69
- 2. a* C. 3 a 3.o?? ot
?.37t-at 3,3 a.1*t ao 52rg 13-
- 3. 4 4 r. 0 4 i.13E 04 1.3nt-0*
2.,* 1 E = 4 3 2.JiE-47
).J 4.4ai=0*
53:
12*
3.2 7 E -O s 2.StE-as 4.22E-06 7.23C-01 s.35E-0$
53!
130 7.57?-07
- 2. 24 as e,sig-a7 2,.ast aa 1.44g ag 3,.3 4.4df*07 1.32E ^-
531 13t
- 4. toe =0e
- 5. isE =0 s 3.att-a3 1.45i-65 t.12E-45 1.]
- 1. i r i..s e
$3:
132 2.33E-07 5.23E 07 1.83!-47 7.!$E-05 a.$a! 07 3.3 1.2dE=of 00btained from Regulatory Guide 1.109 (March, 1976) 6 Cen. Rev. 2
- - - - - - - - - " * * " ' ~ - "
)
FNP-0-M-011 WLI ?.*(Continued) myc:,=t 30ttt t.:7En rotA!. noot UTitoc EnttIT tmc CI-t1:
53!
133 1.43E-06 2.a8E 06 7.57E-07 a.77!-ce a.33E-46 0.3 2.18E-06 531 13a 1.3eE-07 2.38E-07 1.03E-07 3.7aE-05 a.59E 07 0.0 2.5tE-10 531 135 3.a3E-07 1.!?f=06 4.2*r-of 1.53E-os 1.56E=ob 3.0 t.3tE=os 55G3 134*
2.13E-06
- 2. die-08 2.30E=08 0.0 2.deE-48 3.o3E-09 1.3dE-08 55CS.13e 6.22E-05 -1.48E os 1.2 t E =0 9. 0.0 a.80E-05 _1.59E-05 2.19E-06 55CS 135 1.95E-05 t.Sof os 9.00E-o6 6.o 4.52r-46 2.05t=o6 a.21!-01 55Cs 13e 3.51E-os 2.57E 05 1.45E-05 0.0 1.43E-05 1.96E-oo 2.42E=0e 55CS 137 - 7.98E-05 1.39E os 7.15E-05 0.0 3.7t!-45 1.23E-05 2.10E-06 55CS 135 5.52E-08 1.00E=of
- 5. ate =o8 0.0 9.325 46 7.o2E-09 a 65E-t3 55G3 134 3.415-06 5.J8E-08 1.65E-06 0.0 d.J7E-06 3.10E-09 0.J 568A 139 4.7tE-08 t 92E-tt 2.saE-09 0.0 e.27E-st 3.92E-tt 1.72E-07 568A tso 2.33E=os 2.55E-49 1.3at-o, o.0 9.68E-o#
1.aeE=oS a.tSE-01 5e6A tot 0.0 3.5el-st 1.59E-09 0.0 3.31E-11 2.02E-st 2.22E-17 568A 142 2.13E-08 2.19E-tt 1.3st-09 0.0 1.35Eatt 1.2aE-tt 0.0 57tA too 2.50F-09 1.26E=0t 3.3at-to 0.0 0.3 0.25E-09 5764 tot
- 3. tie-10 9.9tE*tt 1.edE=tt 3.3 0.J 0.3 1.14E*05 57kA ta2 1.2SE-to 5.321-11 1.45E-tt 0.0 0.0 3.0 d.25E-07 58CE tut o.37E-oo s.3at no 7 t er-t o o,6 2,sar-oo 9. 0_
2.22E=o5 58CE t43 1.oiE-09 1.22E-oe 1.35E-t3 0.0 5.38E-10 6.3 4_." ' " " _ usener 58CE tua 4.9*E-07 2.0aE-07 2.62E-0A 0.0 1.21E-67 3.0
!.s5E=0a 5ese 123 8.2t!-09 3.75r-oo a.57t-to 1.3 2.13! ae 9.3 3.33E oS 5489 Idd 3.02E-tt 1.25E-11 1.53E-12 3.0 7.3et-12 3.J 4.33E-IS
$090 147 t.30E-09 7.2SE 09 a.35E-to 0.3 J.25E-69 3.0 3.49E-05 et** t27 7.55E-08 7.10E-^*
2.!?r-oo 1.0 1.3dr-49 3.0 9.83E 06 013. 146*
3.31E-04 1.ieE-0*
6.3eE-00 0.0 1.2tE-05 0.3 s.lut-05 618* taa 7 !!E-09 1.19E-09 6.00E-to 0.3 2.25E-04 3.0 8.JaF-05 618" 138 1.52E=oe 2.15E-to 9.7er-tt 9.3 a.37E-eo 3.3 a 03E-05 st3* 151 s.4/E-to t.11E-to 5.92!=11 0.0
- 2. J - t o 3.0 3.22E=o5 625M 151 t.9tE-08 1.19E 08 2.86E-09 0.0 1.33E-06 3.0 5.25E=4e 6254 153 9.547-1o 7.16E-to
- 5. 2 3 E'a t 1 0.0 2.37r-to 9.3 2.55E-09 63Ew 152 6.iiE-01 4.ddE=o8 3.9tE 03 0.0 2.15E-07 1.0 2.59E-05 63EU 15e
- t. tee-07 7.57E-08 5.39E-05 0.0 3.62E-07 3.3 5.J8E-05 63EU 155
',6tE=o8 1.22E-49 7 EAE=oo 1.3 5.6er-48 9.4 8.90E-oS e3EV tio
!.3TF-08
- 1. gee-08 1.715-o' 3.4 7.3*E-08 3.3 7.2*E-05
$575 160 J.70E-08 3.3 5.P6E-o*
3.1 1.88E-49 3.0 J.33E 05
$7dC tee
- 2.71r-of 9.JaF=ot
$.dt! 49 1.3 1.26E-17 3.3 3.3 7da 141
- i. int-v9 3.2uE-09 1.deE-tJ 1.J
).J
).J s.setav7 7aa tt$
4.0eE-07 1.35E-07 1.a2E-45 0.0 1.3 3.3 1.5eE-05 faa 197 1.33E-07 _9.52r-oA 3.32E=o4 5.1 1.3 i.3 2.!!E*05
$28S 213 1.53E-02 d.36E-03 5.4dE-04 1.0 1.23E-42 3.1 5.-2E-05
$35! 210 4.o2E-07 3.19E-oe 3.87E-09 1.0 3.So!-05 1.0 4.75E 45 sa70 210 3.57E-os 7.57E-0a
- t. sot-os 3.3 2.52!-03 9.0 e.3eE-oS f
- 0btained from Regulatory Guide 1.109 (March, 1976) l 7
Gen. Rev. 2 I
FNP-0-M-011 1
l i
TABLE 2*(Continued)
NUC.OE 30NE L:YER TOTAL 30DY "HY300 C1'fET
!.::NC GI-tJ.I 84R4 223 4.99E-03 7.66E-06 o.est-Os 0.0 2.17t=0a 3.0 3.2tE=0a 6844 22e t.s2E-03 3.90E-06 3.23E*0s 0.0 1.ttE=os 0.0 3.40E-0a 88ea g25 g,57E-03 7,7gE =ob t.3tE=ot S.o 2.2tE=on 1.3 3.06E-0a SSda 22s 3.J5f-01 i.75E-06 2.21E-41 3.0 1.33E-04 3.0 3.32E-os S8RA 225 1.12E at 3.12E-06 1.2tE-01 0.0
- 4. S a E -o S 3.3 5.adE 05 9*4C !!S 3.utr-6.37F=ot
?.968-07 S.3
- 9. 4 0 E -^ 7
?.0 2.07E-os 594C 227 1.SeE-2.46E=ou
- t. ate-os 3.0 9.03E-05 o.0 1.iuE-05 407* 227 1.37E..
2.a6E-07 3.96E-47 0.0 1.Jtt-ce 3.0 5.40E Os 407W 229 4.96F=0e 9 ale =o6 t.64E-45 6.3 a.b7r-o5 3,3 5,33E-oa 90f* 229 4.JeE-03 L.2tE-04 1.45E=ce 0.0 5.30E=0u a.0 5,t2E=0e 907d 230 2.08E-03 1.18E=0a 5.76t=05 3.0 5.69E-0a 3.a 6,02E-05 407d 232
- 1. 4 0 E =4 3 -l.0tE-44 e.488-45
^.3 a.96E.^o S7 f.2aE=on 90r 23e 3.02E-06 4.72E-09 2.32E=09 0.0 2.37E-0A J.0 1.t3E=04 918A 231 a.tur-03 1.56E=0a
- 1. ate =0a 0.0 0.0 3.0 e.27E-du 918a 233 5.26F-oo 1.36E-64 e.!st-ti 1.3 3.*er-^o 9.0 1.saE-05 92v 232 d.adE-03 J.J 2.95E-04 1.0 4.41E-o#
2.0 s.12E-05 42V 233 S.7?E-0a 3.0 5.2eE-05 0.0 2.0aE=0a 3.0 6.27E-05 eau p3a 9,3;r-os 3.0
- 5. tee =os 1.3 5.*er-no
?.S 6.idE=05 929 235 4.32E-04 2.0 4.86E-05 3.3 1.37E-ou 3.3 7,3tE 05 c2V 236 6.32E=0a 3.0 a.97E-05 0.0 1.91E-on 3.3 5.76E 05 320 237 5.53F=o!
S$
t.stE=o9 1.0
?.27E-o?
.3 t.caE=os 32V 235 7.o1E-od 0.0 4.55E-05 0.3 1.75E-08 3.0
- 1. s e t *0'd 93N8 237
!.38E-03 1.20E-on 5.5aE-05 3.0 a.16E=0a 3.3 7.*aE-05 03N8 !39 t.37r=06
- 3. g a!-t o 2.11E-11 S.3 1.2sf-o*
5.*
3.J3E=o5
- 3%d 234 1.29E-09 1.tSE-13 6.4*E-Il 3.3 3.35E 13 1.0 2.40E 05 SuPU 235 s.73F 0a 9.3tE-oS 1.67!-45 0.0 7.t2E-05 a.3 7.30E 05
- usu !)s 7.ecr-Od t.osE-^u 1.998-15 1.3 7.168 ^5 9.3 9.seE=os
- uAV 280 1.54E=0e 1.caE=ce t ast-05 3.a 7.4eE=05
.3 s.75E=os Sa7U 2et 1.5eE-05 S. a 7E-0 7 3.33E-07 0.0 1.53E=oe 3.0
- 1. 4 0 E -0 6 onAv ?a2 7.22r-os a.e0E-05 1.7er-65 8.3 7.5Ar a5 9.i e.f3f-09 9e#V gua 4.coE=ou t.tsE-Ce 2.13E-05 0. 0, 4.03E-05 3.0 a.13E-05 954* 281 5.10E-ou 2.79E-os 5.26E-05 3.0 3.46E-o#
3.3 7.a2E-05 454w ?o2=
4.32r-os
?.797-os 5.a7t-35 S.S 2.19r-^a a.3 a.3dE=o5 45'a 2u3 3.12E-02 2.13E*0a. 5.2aE-05 S.3 3.*SE-Ou 3.J 8.73E-05 06 w 2u2 1.54E 05
- 1. a d E -0 5 1 Ost-Os 1.0 4.97!-33 3.3 7.92E-05 eeCw 233 s.43E oa 2.att.oa 1,77E-15 i.$
t.79E-ae 5.3 7.81E-05 i
9ec 2ud
- .d5t-o*
2.J1E-os 2.S*E-05 3.0 1.3dE-04 3.]
1.556-05 i
46Cw 295 1.33E-03 2.58E-0a 5.StE-05 3.3 2.71E-44 3.3 7.04E-05 asC= 2ae
.02r-^3 2.38E-od 5.aor=35 3,s
? fir a2
- 3. a t t -oc 4ed-la!
4.4$i-04 2.83E-Ca 5.72E-05 J.0 2.s7E-ou 3.3 4.JSE-05 86CM 2ue
!.27E-03 2.33E=03 a.7tE-os 3.3 2.20E-03 3.J 1.47E-03
- eCF 252 1.9eE-0a 3.0 a.45E-06 3.0 3.3 3.3 2.5SE-04 I
l l
l
- 0btained from Regulatory Guide 1.109 (March, 1976) 1 8
( an.
Rev. 2 1
l l
FNP-0-M-Oll Dose Calculation Due to Gaseous Effluents 4.11.2.1.2 4.11.2.4.1 Gas Effluents-Dose Calculations The dose rate in unrestricted areas due to radioactive materials released in gaseous effluents from the site shall be limited to the following exprersions:
(a)
Release rate _ limit for noble gases:
14 2
i E K, I ((x/Q),0,)
< 500 mrem /yr 1
-et i
v 14 2
10' Z(Li + 1.1 M,)
I ((x/Q),0,)
<3000 mreavyr 1
where the terms are defined below:
(b)
Release rate limit for all radiciodines and radioactive materials in particulate form, with half lives greater than 8 days:
18 2 238 x 10' i
IP I ((x/0),,0,y)
< 1500 mrem /yr i
1 y where:
the factor to convert inhalation dose to 238
=
grass-cow-milk pathway dose.
the total tv.cy dose factor due to gamma emissions K
=
i for epch identified radionuclide, in mrenVyr per pCi/m (Table 3).
the skin dose factor due to beta emissions fo[ each L
=
3 identified radionuclide, in mrem /yr per pCi/m (Table 3).
the air dose factor due to gama emissions fo[ each M
=
1 identified radionuclide, in mrad /yr per pCi/m (Table 3).
9 Rev. O
ENP-0-M-011 the product of the largest inhalation dose factor P
=
i for any organ of an infant for each identified rpdionuclide and the infant inhalation rate of 1900 m /yr, in mreny'yr per pCi/m*. 'Ihe infant age group and pathways are the most restrictive, thus the infant dose factors in Table 4 usually apply.
However, for the kidney and for some radionuclides, the adult inhalation dose factors in Table 5 are applicable.
(x/Q),
the highest value of the annual average atmospheric
=
dispersion factor at the site boundary, for'all sectors, in sec/m'. The value of 7.5 x 10-3 will p used for the plant vent and 1.2 x 10 pec/m sec/m for the turbine building steam jet air ejector.
(x/Q),, = the highest value of the annual average atmospheric dispersion factor at pe distance of 5 miles, fpr all spetors, in sec/m. The value of 7.6 x 10-10 g w/m} be used for the plant vent and 5.1 x sec i1 sec for the turbine building steam jet air ejector.
the average release rate of nuclide i in gaseous -
Q,
=
1 effluent from each vent release point v at the site, in Ci/sec. Noble gases may be averaged over a period of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, and any other nuclides may be averaged over a period of 1 week, i
l l
l 10 Rev. O
t TMP-0-M-011 i
TA 31. E 3 *"""
00!!ac-"t! ~?? 9C ?'. ! 04 5 !! 'a *!3 04*'Gn !15 3
- 41- ?!'2,)
--Geev.,'8 Nuet.
3-48a f38,)
!- n ' a..' 9 ? ; )
4) 1.33E-05 7.!!!-08 (r 43m 2.3SE-04
<r-35m 1.37E-03 1.'4 5 E -0 3 -
1.23 03 1.17E 03
.<r 85 1.35E-03 1.34E 03 1.72E 05 1.51E-0!
(r-37 1.03E-02 3.73E 03 5.17E 03 5.12! 03
<r-38 2.33E-03 2.37E 03 1.52E 02 1.47!-02 (e-41 1.35E 02 1.31E-02 1.73E 02 1.56E-02
(.-!O 7.331-03 7.33!-03 1.!3E 02 1.56E-02.
.. 3 :.
v, -
i.:,:
.4 a
.e-1...
O-s te..
is te-133m 1.43E 03 7.14E-04 3.37I-04
- 2. !1 E 04 In-13 3 1.3fE 03 3.31E-04 3.!3E 04 2.34! 04 3 -
...c 04 3.,.,. e 9.3
.4,y2
.., e.,. 3 e
..,a Xe-135 2.16E 03 1.35E 03 1.12E-03 1.31E-03 te-1.7 1.27E 02 1.32E 0*
- 1. 51 ! '03
- 1. 22 E 0 3 3.33E-03 fe-133 4.7!!-03 4.13E-03 3.31!-03 ar 41 3.23! 03 2.Si! 03
- 3. 30,E 0 3 3.14E 03
., e s e. m -.
sci-yr
..,r..i-3G.=fr
~
2.33E-04 = 2.33 5 10*'
- fo: 2 sed in sat ;cin: 4s14212:10ns
'""*0bt.uned f :s ?.agulac r/ iuida.. 09 Ce2r:n. '. 9 7 5 ',
11 Rev. 0
,.-4---,.,-%.
-,,. -. - - -,~
v-r-.
V
{
NIP M-o n 7A3'.E 4*
p t: :-
- -q :-* - t
--e t r y--
g:rt s:a inneste; NUCL 'E
!ONE LIVr8 TOTAL $3}f 7Mv'0I:
<!)NEY LUNG
~!-8.L!
1M 3-3.0 3.37!-07 3.07!-07 3.07t=07 3.37E-07 3.07E-47 6C to 3.sCE-06 3.60E-06 3.60! de 3.o0E-03 3.6cE-os 3.oCE-0%
!!wa 22 f,83r=05 1,53E-as 7.Y3t-45
?.53t-45 7.53i-05 t.225-as 7.;
si 1.s
.346-0$
i.i?f->l 4.;
3.iti 3.aliavo 27" 60 0.2 6.30E-07 e.35E-of 0.1 3.*SE-03 2.34!-05 g".
3752 to 1,0st-05 3,0 e,atr-47 S.6 i.e5E-63 a.5t!-05 365A 40 4.e=(-03 J.0 5.73L-Od 3.3 1.39(-02
+.a'i-05 397 to 2.13E-07 1.0 5.45E-ce 0.0 1.*SE-00 4.32E-05 b.,..
301 tt 2,???-05
?.S
', tar.o.
i,a i, ear.43 5.!2E=0c acii 45 7.1 E-00 n.iSC-oo 1.38C-03 0.0 L.295-03 6.41i 95 alNS 1.16E-07 a.11E-07 t,st!-07 3.0
,3.stE-04 6.67E-06 as#U ?$3 1.2tr-07 3.S 2. ? a r.,3 e 3,3 2, sag.ca
!,!3C-05
,CI,'
4 Au t>o a.sti-es J.a e.tss-;;
- .0 1.0;i-42 1.isi-sw 50SN 123 2.22E-05 4.ht!-07 7.3cE-07 s.61r-07 2.58E-43 1.2SE-05
- 2rr I?c=
3, ?a r -o ?
t,3st.at 2,23r aa 1, eor.a7 ir;,3 3,5ar.ca o.7tE-06 52;E 127 1.J3E-10 4.Joi-11 2.5et-it t.;oE-t; i.016-90 6.sii si 327E 120" 8.asE-07
- 3. tat-07 1.27E-a7 3.63E-07 t.311-03 5.23E-05:
5;ir t3!
?,?ce-as
'.atr.a.
. ur.aa i,?;r.cs
?,:sr-ao-g.ase-05 53.
1is 2.231-05 1.32i-05 5.s21 05 5.2ti-v2 a.4 2.4ai-47 53' 131 2.58r-c5 3."SE-05
!.72r-05 1.;t!-02 3.0
- 7. t o E -0 7 531 933 2,5*r-04 1,3!F.ac
,' iran = 1 t3r=03
$.0 h
55;3 ;)-
a.
ai-94 5.$it-0 5.43i-45 1.4 1.22i-ci 4.ssi-s7 51*3 137 a.9eE=0c 3.2.qg ao 2E Os 3.15E-05 0.3 6.75E-05 9.45E707 3,24
,2 g,$=g.4g 3,
- ,..y.a7 3,.
e,t-r-a3
_?,
?!.0, 57.4 14 L.J41-co L.24E-04
'.Sti-t3 J.0 1.2tE-Oe s.
<!:E 141 1.30E-06 1.11! 06 1.295-41 1.0 3.78E-oa 1.37E-05 540-4:
3,3ar-as t 3 c r..u s e..s e 3,3 3,3eg.43 1.15 r - u titu 15w 5.99E-0a 4.45E-15 3.721-05 3.J 3.4*( 0 1.;16-45 82U 232 3.91E-02 3.0 2.79E-05 3.0 2.32E 3 0 4.55E-05 o ?'J
?l
- ast-o3 1,0
- ,s r-3a 3,3 3,7:g.43 4, igg.09
- * * 'a 23e 2.;si JC 2.sai-ot 5.Jef=02 J.0 1.51E 03 a.iis-v5 eePy 234 2.33E 00 3.30E-01 5.77!=12 6.o t, alt to 4.51E-05 teP9 seo
?.33r ;o 3,3pr.at c,9er.ap m,e
,,25g eo a,3tg.ac audv 24t
- s. tai 1. tot-aw 2.37E-05 0.0 4.404-ow s.aat-v?
95aa cal 7.6tE-01 2.27E-at 2.96E-02 3.0 5.32E-01 4.36E 05 es - ?c?
4,6?r-o1 a, ant a!
c.*'r
^a i.9 t,2tr-at 9.2er.a5 toc 5 2nd d.43C-01 t..'
- E - o t 2.
51-02 3.J 5.5tE*01 5.J3t-65 Note: 0.0 neans insufficient a:2 r :.-a: :ne :os t fae::e is
.1, E.20,
- 0bcal::ed f:::: Regula:orf Guide ;.109 (March. 1976) e e
12 Rev. O
1 i
0 'ASE ci l
I (H 61 ' v:: t r* ) 601
- f VM /* ::TT.tey :::; paviro w
'C? 3r p 5. a:n t; e s:: an :r. s: r:t: : vat:,a nsw-. sura: CC :::ot j
50-316*r 50-3ti*?
C*C C*C 90-255'l
.l C'(
50-3b;*$
le Act ri.ioc'*
fr.
t.*2 c'r c*e Fi-;;?*)
ta r sc7*t
.te aet s.-3ci'-
be-Si.'c L't l'6 ov-i.6 i's se-str oc not Se=3rt'$
00-?6C'l C*C C*C ll-3ec*!
C*C Cl-3ge*6 se gtti c
s-ce; c r. - ; ? c ' e e*C r*r ri-See'r
- r e r.. ) -.
- 1.
-est --
se-Itt'e t i.- 3 9 2 ' i C's 4*t is-sc6'.
s ('t (0-sei'i ce eggt b s** 3 4 t
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F FNP-0-M-011 Dose Calculations Due M Noble Gases 4.11.2.1.1 4.11.2.2 Noble Gases - Dose Calculations I.
Method A: Real Time Meteorological Input (Normal Mode)
'Ihe air dose in unrestricted areas due to noble gases released in gaseous effluents from each reactor at the site shall be determined by using the following expressions:
(a)
During any calendar quarter, for gamma radiation:
14 n
D, = 110 E M E at) ((x/Q)3,,Qi3y), and i
i j=1 During any calendar quarter, for beta radiation:
14 n
D,, = 110 E N E ot, [ ( xA))3,yQi3,), and i
i j=1 (b)
During any calendar year, for gamma radiation:
14 n
D, y = 110 E M I at [(x/Q)3,yO33,), and 1
3 i
j=1 During any calendar year, for beta radiation:
14 n
D, = 110 E N I ot ((x/Q)3,y013,)
3 i
j=1 where:
D,,
the total beta air dose in sector e from gaseous
=
effluents for the total time period n
I ot,, in mrad j=1 D,*
the total gamma air dose in sector 0 from gaseous
=
effluents for the total time period n
I ot, in mrad.
3 j=1 17 Rev. 0 1
I mP-0-M-Oli ot
,the length of the j'h h WM wu W6 3
releak,es,ndQin Nurs. averaged for all gaseous (x/Q) a are i
For batch releases, no time period at shall be more than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; for continuoubreleases,notimeperiodot shall be 3
more than a week.
i the air dose factor due to beta emissions for each N
=
1 3
identified radionuclide, in mrad /yr per pCi/m (Table 3).
(xA)) 3,,
the average atmospheric dispersion factor for the
=
time period at in sector 0,3 from all vent release pointsatthebite,insec/m. When at is greater than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, the average shall b based on observations of wind speed and atmospheric stability taken at least every hour during at.
3 The turbine building steam jet air ejector is considered a ground-level release at all times. The plant vent is a mixed-mode release (elevated at times, ground level at times, and mixed at times). However, for ease of implementation, the licensee may consider the plant vent to be a ground level release and calculate (x/Q)3,, values using the following equation.
(x/Q)3,, = k,L,,4 L, y - 2.03/r, I,, where I, = ( c', +0.5h*/n)f subject to the condition E, 60, Tne values of L, are provided in Table 6 for the site boundary and food
- pathways, e,
the vertical standard deviation of the plume for the
=
applicable atmospheric stability class (Pasquill Category) determined at least hourly, for the distance r, during the time period ot.
3 r,
the distance from the midpoint between the vent stacks to the receptor for each sector 0, in meters, provided in Table 6.
k, the recirculation factor accounting for spatial and temporal
=
variations in air flow.
For noncontinuous releases, its value is unity. For continuous releases, see Figure 1 for correction factor.
l l
18 Rev. O
{
l
l FNP-0-M-Oll the average wind speed determined at least hourly, during n
=
time period At; in sector 0, at a height of 10 meters for vent releases, in nVsec.
the height of the tallest adjacent structure, which is the h,
=
containment building (=40 m).
Since the plant vent is actually a mixed-mode release, when these effects describedinRegulatoryPositionsC'.1,.c,scalculatedusingmethods are taken into consideration, (x/Q) i C.2.a, C.2.b, and C.2.c of Regulatory Guide 1.111 (March 1976). As an alternative method, the dispersion factor may be calculated using values from joint frequency tables summarizing hourly meteorological observations during release period.
r 19 Rev. O
FMP-O-M-01'.
I 1
e i.
s s e., s., s.~
s s s s. e s..,
i e r e
... i i. > >
i-a w :a ; ;a w w w w ;c a w a w w ;.:
I
- .: ; n = = = n.s =.. -
= = c.,= = j i.
! a. s. e. s... o..r..,r.,r. s. e... s. e.
l i
l
% %% 33% 444m% o3%.%
t I
i s.- s e s s., e s s e s e o e.e
,,..., =
i.i.
a....
.:cawwwwwawwwwwwww
~
~ ~ = =====~~==
~
t =.=.==.==. =. =. =.... =. =.=. =.=. =.
=
,l4sss44sesses44ss l
l s s. s s s e s e s.- s e..- s.,
wwwwwawwwaww wi=~~~==~.eee~
awww
= = ~..
) r.... e. w.
. s. e. e... >. c.
r.r.x e ~r l.,e
.x r r e r e m e.:
>.=
..m.
.n. s s.,e., e e. s s o o o e e s
~
.e N
!, :a w w a w w w w w w w a w a w w
~ m,a 4.- e
.n I
a
-~
. ~..
,4 ~,:,.
.c 4,.:4...-~
w;:
3 44
=
r r.,. r-N N.~rmer a
i
-a
=,
t
~-
.a,
- .-ssosesssssseses t sI i
1
=
. =, = = =, =
=
u.
- =, = = =. = = = = =
. a w a. =~ w w w= w~ w. w. w,,w ~w w= a u. r.
2.
=,
=-
~=
=
. ". S $ ".. #. #.
l W
f 3# ' '. ' ^
h l
~
u
=
l J
= x m.,
a l
JO 44-4 4JJ44 34 J3 M <
.=
I
=c J w
w =
4
= = = = = = = = = = =. =. =, = =,
.1 I
) i i e i a e e
=
- =
yyyggg+ggggg
(
l g..*.
4 4
=
> =
}
=1 r s
.,.r.r s.r
~r s s.r
.~.s
- .. =. =.. =.=. 4 4 4.=. =... =.=.
s u
I
= 4 4 4 = = 4 f 4 r 4 %1 = = 4 J l
T j=-
e l
1 4
=,
k 4 J s1 4 4 4,4 4 4 4 4 s1.J 4 4 4 W
=
0.====
i..
e i e i e i i e i
.c w w M w w a W w w M *w w ;.2 w*4 w a
- a.==
1 P
= = ==== * = 4 4 4 = = %
as* i i
4ssrN N N -r ~r s s t r'
- e. 4 7 s
e 4
=
6 m.
a.
g I
3 I
w l
t
=**
- a u
,=i.,.
1.c.
s-=..=.*.a B -** p - '
@.*
- 9 7O
.e or..i.
e e
~r.
N..r. 4 4 4 r.
e N i
av N
j
.i, O
.3 t
a t
1 i
..r I
l 4
=
1
- =
t :
=..
u.. '
4
=..
=.
=
=-
2.
"1". 3... 4.1
.4.
4 llll :
.e J
j 3.=.**.
=
=
1 k1 l
,s
=
l a
s E
es e
= '.s.,7.
o.
~
TABLE 6 (cont.)
FARLEY NUCLEAR PLANT VALUES OF L IN METERS ~
g LIMITING FOOD PATNWAY DISTANCE l
l l
l VENT l
FOOD PATHWAY L m'
l g,
1 l
1 I
l l
l l
PASQUILL C' TEGORY l
1 l
l l
1 I
i i
i i
lormECTroN l orSTANCE iMi i
A I
e l
C l.
o 1
E I
r l
G l
l l
l l
1 I
l l
l l
s l
4183 l 4.85E-07 l 4.85E-07 l 2.22E-06 l 5.85E-06 l 8.31E-06 l 1.36E-05 l 1.92E-05 l l
NNE l
4023 l 5.0$E-07 l 5.05E-07 j 2.38E-06 l 6.23E-u6 l 8.79E-06 l 1.43E-05 l 2.02E-05 l l
NE l
3862 l 5.26E-07 l 5.26E-07 l 2.56E-06 l 6.65E-06 l 9.32E-06 l 1.51E-05 l 2.12E-05 l l
ENE l
3701 l 5.48E-07 l 5.48E-07 l 2.75E-06 l 7.11E-06 l 9.91E-06 l 1.60E-05 l 2.24E-05 l g
l E
l 4505 l 4.51E-07 l 4.5tE-07 l 1.95E-06 l 5.19E-06 l 7.47E-06 l 1.23E-25 l 1.75E-05 l l
ESE l
4666 l 4.35E-07 l 4.35E-07 l 1.84E-06 l 4.91E-06 l 7.10E-06 l 1.17E-05 l 1.67E-05 l l
SE l
5471 l 3.71E-07 l 3.71E-07 l 1.39E-06 l 3.80E-06 l 5.64E-06 l 9.49E-06 l 1.37E-05 l
.i l
SSE l
ee45 l 2.52E-Oi l 2.52E-07 l 2.09E-07 l 2.04E-06 l 3.22E-06 l 5.63E-06 l 8.34E-06 l l
5 l
6919 l 2 33E-07 l 2.93E-07 l 9.23E-07 l 2.60E-06 l 4.0ts-06 l 6.91E-06 l 1.01E-05 l l
SSW l
4666 l 4.35E-07 l 4.35E-07 l 1.84E-06 l 4.915-06 l 7.10E-06 l 1.17E-05 l 1.67E-05 l l
Sw l
1931 l 1.05E-06 l 2.82E-06 l 8.98E-06 l 2.00E-05 l 2.68E-05 l 3.96E-05 l 5.13E-05 l l
WSW l
1609 l 1.26E-06 l 4.48E-06 l 1.26E-05 l 2.67E-05 l 3.56E-05 l 5.14E-05 l 6.43E-05 l l
w l
2092 l 9.70E-07 l 2.30E-06 l 7.74E-06 l 1.77E-05 l 2.37E-05 l 3.54E-05 l 4.64E-05 l l
WNw l
3379 l 6.01E-07 l 6.56E-07 l 3.232-06 l 8.23E-06 l 1.13E-05 l 1.80E-05 l 2.50E-05 l l
Nw l
2414 l e.41E-07-l 1.60E-06 [ 5.94E-06 l 1.41E-05 l 1.89E-05 l 2.19E-05 l 3.86E-05 l l
NNw l
3218 l 6.31E-01 l 7.62E-07 l 3.52E-06 l 8.89E-06 l 1.21E-05 l 1._ J 2 E-0 5 l 2.66E-05-l Note:
hv 40m
=
Note:
This table must be updated based on annual land census results as required in Tech Spec Section 3.12.2.
M' S':
93 8
O f
ODCM-2/2
,O
~~
w
p.
FNP-O-M-011 i
\\G i,...i.
...i.,.
. gl l
.[
.i_i,i-i 6
ii l-i I
L l
i il ll=
l l
l I
I- -
i I
i l
1 I
I l
- 111, I
I l ll
\\l
\\-
l-4 l
i I
e I
I e
o<
~
_I,s'_t_._,_
l 5
l
~
_i K
- i.0
-l 1 h.,ti t- : : :-: t+:,
S
.-t :-!Pr.
.. _ u 1_,U n.
-.____,___J r.-
s
=.c i
l_J_y_L!.i 5 l i
i i
o i.
a i
i u
i i
i i e is i
e i
li.
I ---.__:
T...".
I i il il h__l-l.f.
I i__.i l
l ll l
I l
l i
- e. -
0.1 1.0 10 1C0 Ot$ tat 4Cf (l;lLO!.1LiTEnC)
FICuaE l'
CMM *tAMLM CCaACCitCN FACTOR
'Obtained frem 249ulat:ry dutJe 1.111 (Marca.1975)
Rev. O
FNP-0-M-011 4.11.2.2 Noble Gases - Dose Calculations (Cont'd)
II.
Method B: This method is to be used when the real time meteorological inputs are not applicable.
'Ihe dose contribution due to noble gases in gaseous effluents shall be calculated using the following expressions:
(a)
During any calendar quarter, for gama radiation:
D, = 3.17 x 10-' 14 E M (x/Q),O, and i
i i
During any calendar quarter, for beta radiation:
14 D, - 3.17 x 10- 2 I N *(x/Q),Q, and i
i i
(b)
During any calendar year, for gama radiation:
14 D, - 3.17 x 10-2 EM (x/Q),Q, and i
i i
During any calendar quarter, fer beta radiation:
14 D, = 3.17 x 10- 2 IN (x/Q),Q i
i i
where:
D, the total gamma air dose from gaseous effluents, in mrad.
D, the total beta air dose from gaseous effluents, in mrad.
=
(x/Q),
the highest value of the annual average atmospheric dispersignfactoratthesitebounpary,frallsectors, in sec/m. The value of 7.5 x 1 see will be used fortheplantventand1.2x10psec for the turbine building steam jet air ejector.
the release of noble gas radionuclides, i, in gaseous 0
=
1 effluents in Ci.
Releases shall be cumulative over the calendar month or quarter as appropriate.
Other terms are defined in Specifications 3.11.2.1.
23 Rev. 0
mP-0-M-011 4.11.2.3 Radiciodines and Radioactive Materials in Particulate Form -
Dose Calculations I.
Method A:
Real Time Meteorological Input (Normal Mode)
The dose to an individual from radiciodines and radioactive materials in particulate form, with half lives greater than 8 days, in gaseous effluents released from each reactor at the site to unrestricted areas (see rigure 5.1-1) shall be the following expressions:
(a)
During any calendar quarter:
18 n
D,,
= 110 I R, 3 I ot [W Q13,)
3 1
i=1 3=1 (b)
During any calendar year:
18 n
D,, = 110 I R, 3 I
ot (W Oi3y) 3 i
i=1 j=1 where:
the cumulative dose from gaseous effluents to the D,,
total body or an organ T of an individual in sector 0 for the total n
time period I ot), in mrem.
j=1 R,,
the dose factor for each identified,radionuclide
=
into sector 9, in mrenVyy per pCi/m for tritium and in mrenvyr per pCi/m -sec for other isotopes, from Table 7.
For sectors with real pathways within 5 miles from the point midway between the Unit 1 plant vent stack and the Unit 2 plant vent stack, the values of R have been determined based on these real pathways,.g For sectors with no real pathways within 5 miles from the point at the midway between the Unit 1 plant vent stack and the Unit 2 plant vent stack, R has been determined u
assuming that all pathways exist at the 5-mile distance.
dispersion parameter for calculation of food W,
=
pathway dose, W, = (X/Q)3,, for tritium (H-3) l (D/Q)g, for other isotopes, W,
=
f, factor which equals 1 if wind in hour t is into
=
sector 9 and is equal to 0 otherwise.
24 Rev. 0
v:-
.---,-e-n- -,,,
-~--
EWP-0-M-Oll 6t,insector0,inmeters[orthetimeperiod relative deposition (areal),
When at is greater (DM ),,,
=
thAnonehour,relativedepositionshallbebased on observation of atmospheric stability taken at least every hour during at.
3 (DA )3,, = 0.3927 r,
[(1-E) 6,,, + E6,,,)
k0 f6 I
O.3927r, = width (are length) of 22.5 degree sector at distance r, in meter.
relative deposition rate (linear) at distance r, in l
6,,,
=
sectoreforstabilityclassofinterestandfor (rigures 3, 4, 5) ground level release in meter relative deposition rate (linear) at distance r, in 6,,,
sector 0forstabilityclaspofinterestand l
release height h, in meter-(rigure 2) fraction of effluent entrained in building wake.
E
=
s E=1 if (W,A,) < 1 or h, 5 h, E = 2.58-1.58 (W A, )
if 1. f (W, A() f 1.5 E = 0.3-0.06 (W 4,)
if 1.5 < (W,4,) < 5.0 E=0 if (W,A,) 1 5.0 s
25 Rev. 3
TABLE 7 DOSE FACTOR R Oi eres/yr per pCi/m for H-3 aren/yr per pCi/m - see for all other isotopes FARLEY NUCLEAR PLANT l
l l
l l
l l
l 1
I l
SECTOR l
N l
NNE l
NE l
ENE l
E l
ESE l
SE l
SSE l
1 I
I I
I l
I I
I I
l l
l l
l l
l l
l l
l DISTANCE l
4183 l
4023 l
3862 l
1701 l
4505 l
4666 l
5471 l
8045 l
r emi i
l I
I I
I I
i l
l i
I I
I I
I I
I I
i l Radienuclid.
l l
l l
l l
l l
l l
l l
l l
l l
I I
I l
n-3 l 4.40E-03 l 4.40E-03 l 4.40E-03 l 4.40E-03 l 4.40E-03 l 4.40E-03 j 4,80E-03.l 6.81E-03 l l
CR-51 l 1.87E+01 l 1.87E+01 l 1.87E+01 l 1.87E+01 l 1.87E+01 l 1.87E+01 l 1.87E+01 l 2.58E+01 l l
MN-54 l 2.57t+03 l 2.57E+0? l 2.57E+03 l 2.57E+03 l 2.57E+03 l 2.57E+03 l 2.57E+03 l 2.60E+03 l g
O' l
FE-59 l 3.04E+03 l 3.04E+03 ) 3.04E+03 l 3.04E+03 l 3.04E+03 l 3.04E+03 l 3.04E+03 l 3.36E+03 l l
Co-58 l 1.35E+03 l 1.35E+03 l 1.35E+03 l 1.35E+03 l 1.35E+03 l 1.35E+03 l 1.35E+03 l 1.43E+03 l l
Co-60 l 2.96E+04 l 2.96E+04 l 2.96E+04 l 2.96t+04 l 2.96E+04 l 2.96E+04 l 2.96t+04 l 2.99E+04 l l
2N-65 l 4.45E+03 l 4.45E+03 l 4.45E+03 l 4.45E+03 l 4.45E+C3 1 4.45E+03 l 4.45E+03 l 2.08E+04 l l
SR-89 l 3.52E+04 l 3.52E+04 l 3.52E+04 l 3.52E+04 l 3.52E+04 l 3.52E+04 l 3.52E+04 l 4.62E+04 l, l
SR-90 l 3.45E*06 l 3.45E+06 l 3.45E+06 l 3.45E+06 l 3.45E+06 l 3.45E+06 l 3.45E+0 6 -l 3.93E+06 l l
3R-95 l 3.05E+03 l 3.05E+03 l 3.05E+03 l 3.05E+03 l 3.05E+03 l 3.05E+03 l 3.05E+03 l 3.06t+03 l l
I-131 l 2.54E+04 l 2.54E+04 l 2.54E+04 l 2.54E+04 l 2.54E+04 l 2.54E+04 l 2.54E+04 l 5.21E+05 l l
I-133 l 3.91E+02 l 3.91E+02 l 3.91E+02 l 3.91E+02 l 3.91E+02 l 3.91E+02 l 3.91E+02 l 5.03E+03 l l
CS-134 l 3.41E+04 l 3.41E+04 l 3.41E+04 l 3.41E+04 l 3.41E+04 l 3.41E+04 l 3.41E+04 l 8.56E+04 l l
CS-136 l 4.29E+02 l 4.29E+02 l 4.29E+02 l 4.29E+02 l 4.29E+02 l 4.29E+02 l 4.29E+02 l 5.72E+03 l l
CS-137 l 3.90E+04 l 3.90E+04 l 3.90E+04 l 3.90E+04 l 3.90E+0f l 3.90E+04 l 3.90E+04 l 8.73E+04 l l
BA-140 l 3.79E+02 l 3.79E+02 l 3.79t+02 l 3.79E+02 l 3.79E+02 l 3.79E+02 l 3.79E+02 l 5.99E+02 l' l
CE-141 l 6.06E+02 l 6.06E+02 l 6.06t+02 l 6.06E+02 l 6.06E+02 l 6.06E+02 l 6.06E+02 l 6.20E+02 l l
CE-144 l 1.30E+04 l 1.30E+04 l 1.30E*04 l 1.30E+04 I 1.30E+04 l 1.30E+04 l 1.30E+04 l 1.31E+04 l y
Z O
M3 e
NOTE:
15 This table must be updated based on annual l a'n d census results as required in Tech Spec Section g
8 3.12.2.
2)
Sector is wind into distance in meters.
U
]
TABLE 7 (cont.)
DOSE FACTOR R gg arem/yr per pci/m' for N-3 mreu/yr per pci/m - sec for all other isotopes FARLEY NUCLEAR PLANT I
I l
l l
l 1
I I
i l
SECTOR l
3 l
SSW l
SW l
wsw l
w l
WNw l
Nw l
WNw l
l 1
1 I
I I
I I
I I
l l
l l
l l
l l
l l
l DISTANCE l
6919 l
4666 l
1931 l
1609 l
2092 l
3379 l
2414 l
3218 l
1 r
<=>
l l
l l
l l
l l
l l
1 l
l l
1 1
I I
l l Radionuclide l
l l
l l
l l
l l
1 l
l l
1 l
l I
I i
l N-3 l 4.40s-03 l 4.40E-03 l 4.40c-03 l 2.40E-03 l 4.40E-03 l 4.40c-03 l 4.40e-03 l 4.40c-03 l l
cR-51 l 1.87t+01 l 1.87t+01 l 1.87E+01 l 7.15t+00 l 1.87E+01 l 1.s7t+01 l 1.87t+01 l 1.s7E+01 l g
l Mu-54 l 2.57E+03 l 2.57t+03 l 2.57E+03 l 2.97E+01 l 2.57E*03 l 2.57t+03 l 2.57E+03 l 2.57t+03 l N
l rE-59 l 3.04E+03 l 3.04E,03 l 3.04E+03 l 3.21E+02 l 3.04E+03 l 3.04E+03 l 3.04E+03 l 3.04E+03 l l
co-Se l t.35E+03 l 1.35c+0i l 1.35c+03 l s.6sc+01 l 1.35c+03 l 1.35E+03 l 1.35 +03 l 1.35m.03 l l
co-60 l 2.96E+04 l 2.96E+04 l 2.96E+04 l 2.73E+02 l 2.96E+04 l 2.96E+04 l 2.96E+04 l 2.96E+04 l l
zm-65 l 4.45c+03 l 4.45c+03 l 4.45c+03 l 1.63E+04 l 4.4sc+03 l 4.45E.03 l 4.45r.03 l 4.45E.03-l l
SR-49 l 3.52E+04 l 3.52E+04 l 3.52E+04 l 1.10E+04 l 3.52E+04 l 3.52E+04 l 3.52E+04 l 3.52E+04 l l
sR-90 l 3.45E+06 j 3.45E+06 l 3.45t+06 l 4.77t+05 l 3.45E+06 l 3.45E+06 l 3.45E+06 l 3.45E+06 l l
zR-95 l 3.05c+03 l 3.05c+03 l 3.05E.03 l
,.5 E-01 l 3.05 +03 l 3.05c+03 l 3.05 +03 l 3.05E+03 l l
1-131 l 2.54r+04 l 2.54c+04 l 2.54E+04 l 4.96:+05 l 2.54 +04 l 2.54 +04 l 2.54 +04 l 2.54E+04 l l
I-133 l 3.91E+02 l 3.91t+02 l 3.91t+02 l 4.64E+03 l 3.91E+02 l 3.91E+02 l 3.91E+02 l 3.91E+02 l l
cs-134 l 3.41E+04 l 3.41E+04 l 3.41E+04 l 5.16E+04 l 3.41E+04 l 3.41E+04 l 3.41E+04 l 3.41E+04 l l
cs-t36 l 4.29c.02 l 4.29E+02 l 4.29 +02 l 5.29c+03 l 4.29c+02 l 4.29:+02 l 4.29E+02 l 4.29E+02 l l
cs-137 l 3.90E+04 l 3.90t+04 l 3.90E+04 l 4.83E+04 l 3.90t+04 l 3.90E+04 l 3.90E+04 l 3.90E+04 l l
BA-140 l 3.79E+02 l 3.79E+02 l 3.79E+02 l 2.20t+02 l 3.79E+02 l 3.79E+02 l 3.79E+02.l 3.79E+02 l l
cE-141 l 6.06c.02 l 6.06E+02 l 6.06E+02 l 1.43c+01 l 6.06c+02 l 6.06E+02 l 6.06E+02 l 6.06t+02 l 1
CE-144 l 1.30E+04 l 1.30t+04 l 1.30E+04 l 1. 2 5 E'+ 0 2 l 1.30E+04 l 1.30E+04 l 1.30E+04 l'1.30E+04 I ns O
2:
N2 NOTE:
1#
This table must be updated based on annual land census results as required in Tech spec section b 3.12.2.
N 23 sector is wind into distance in meters.
b 4
s 9
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FNP-0-M-011 4.11.2.3 Radiciodines and Radioactive Materials in Particulate Form -
Dose Calculations (Cont'd)
II.
Method B: 'Ihis method is to be used then the real time meterological inputs are not available.
The dose contribution doe to radioiodines, radioactive materials in particulate form, with half lives greater than 8 da_ys, in gaseous effluents shall be calculated using the following-expressions:
(a)
During any calendar quarter:
D, = 3.17 x 1014I R, W 0,,
and i
(b)
During any calendar year:
D, = 3.17 x 1014.
I R, W Q1 i
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the cumulative dose from radioiodines and radioactive D,
=
materials in particulate form with half lives greater than 8 days in gaseous effluents in mrem.
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=
in m (mrem /yr) per C1/see or mrenvyr per ciAn from Table 8.
the annual average dispersion parameter for W
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estimating the dose to an individual at the critical location:
W = (x/Q) for the inhalation pathway, in sec/m' from Table 9a.
W=(DG)fromTable9b.for the food and ground plane pathways, in meters' the release of radiciodines, radioactive materials in Q,
particulate,1, with half lives greater than 8 days in gaseous effluents. Releases shall be' cumulative over the calendar month or quarter as appropriate.
32 Rev. O
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TABLE 8 FARLEY NUCLEAR P LANT PATHWAY DOSE FACTORS DUE TO RADIONUCL1 DES OTHER THAN NOBLE GASES Inhalation Ground Plane Fresh vegetables Stored Vegetables Meat Cow Milk Goat Milk Radionue11de Pathway Pathway Pathway Pathway Pathway Pathway
' Pathway H-3 1.12E+03 0.00E+00 2.50E+02 3.76E+03 2.36E+02 2.40E+03 4.90E*03 CR-51 1.70E+04 5.51E+06 1.31E+06 4.55E+06 3.98E+05 4.605+06 5.52E+05 MN-54 1.57E*06 1.62E+09 4.33E+07 5.77E+08 6.09E+06 2.97E+07 3.56E+06 FE-59 1.27E+06 3.20E+08 8.81E+07 5.35E+08 5.19E+08 3.21E+08 4.17E+06 CO-58 1.10E*06 4.43E+08 3.64E+07 3.11E+08 7.60E+07 5.61E+07 6.73E+06 CO-60 7.06E+06 2.53E+10 1.25E+08 1.86t+09 2.9CE+08 1.81E+08 2.17E+07 EN-65 9.94E+05 8.60E+08 1.88E+08 2.42E+09 8.59E+08 1.63E+10 1.96E+09 SR-89 2.15E+06 2.51E+04 4.47E+09 3.03E+10 4.22E+08 1.10E+10 2.31E+10 SR-90 1.01E+08 0.00E+00 2.10E+11 3.17E+12 4.08E+10 4.77E+11 1.00E*12 La ER-95 2.23E+06 2.84E+08 9.06E+07 7.27E+08 4.81E+08 7.01E+05 8.41E+04 I-131 1.62E+07 1.05E+07 2.08E+10 1.96E+09 2.60E+o9 4.96t+11 5.95E+11 1-133 3.85E+06 1.49E+06 3.90E+08 1.97E-11 6.47E+01 4.64E+09 5.57t+09 CS-134 1.01E+06 7.99E+09 1.62E+09 2.33E+10 1.15E+09 5.16E+10 1.55E+11 CS-136 1.71E+05 1.70E+08 1.28E+08 8.65E+07 4.05E+07 5.29E+09 1.59E+10 CS-137 9.05E+05 1.20E+10 1.61E+09 2.43E+10 1.07E+09 4.83E+10 1.45E+11 BA-140 1.74E+06 2.34E+07 1.62E+08 1.01E+08 4.00E+07 2.20E+08 2.64E+07 CE-141 5.43E+05 1.54E+07 7.19E+07 3.10E+08 1.16E+07 1.15E+07 1.38E+05 CE-144 1.19E+07 8.00E+07 6.66E+08 8.77E+09 1.42E*08 1.00E+08 1.21E+C7 NOTE:
This table is applicable for use with Method B when thw rest time meteorological inputs are net evalidhle.
NOTE: Units are area /yr per pC1/m' for N3, and m ares /yr per pCi/sec for other isotopes.
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FNP-0-M-011 4.11.4 Dose Assessment for Environmental Radiation Standards he Radiological Effluent Technical Specification 3.11.4 specifies in the Action that when the calculated doses associated with the effluent releases exceed twice the limits of any one of the Specifications 3.11.1.2, 3.11.2.2 or 3.11.2.3 it is required to prepare and submit a Special Report to the Commission and limit subsequent releases such that the dose or dose commitment to the critical individual from all uranium fuel cycle sources is limited to <25 mrem to the total body or any organ (except the thyroid, whiiEh is limited to <75 mrem) over 12 consecutive months.
% e dose assessment which will be described in a Special Report, shall include dose contributions from direct radiation from the plant and its components. A variety of techniques is available for assessing this contribution. A simple calculation may be sufficient to demonstrat,e that the contribution is unimportant, or conditions may dictate more complex analyses. We most appropriate assessment technique will be determined in the course of preparing the Special Report and will be documented in the Special Report.
l l
l I
38 Rev. O
INP-0-M-011 4.12.1 Radiological Environmental Monitoring Locations Table 3.12-1 and Figures 3.12-1, 3.12-2, 3.12-3, and 3.12-4 provide the Radiological Environmental Monitoring point locations.
39 Rev. 1
. ~.
FNP-M-011 1
ThBLE 3.12-1 RADIOEDGICAL DWIRCNENTAL MONI10 RING IOCATIWS '
EXPOSURE PATitihY AIO/OR SAMPLE SAMPLE LOCATIWS SAMPLE IDDfrIFIChTIN 1.
AIRBOIBE a.
Particulate Indicator Stations:
- River Intake Structure (ESE-0.8)
PI - 0501 South Perimeter (SSE-1.0)
PI - 0701 Plant Entrance (WSW-0.9)
PI - 1101 North Perimeter (N-0.8)
PI - 1601 Control Stations:
Blakely, Ga. (NE-15)
PB - 0215 Dothan, Ala. (W-18)
PB - 1218
- Neals Landing, Fl. (SSE-18)
PB - 0718 C-mity Stations:
Great Southern Paper Co. (SSE-3)
PC - 0703 Ashford, AL. (WSW-8)
PC - 1108 Columbia, AL. (N-5)
PC - 1505 b.
Radioiodine Indicator Stations:
- River Intake Structure (ESE-0.8)
II - 0501 South.Perineter (SSE-1.0)
II - 0701 Plant Entrance (WSW-0.9)
II - 1101 North Perimeter (N-0.8)
II - 1601 Control Stations:
Blakely, Ga. (NE-15)
IB - 0215 Dothan, Ala. (W-18)
IB - 1218
- Neals Landing, F1. (SSE-18)
IB - 0718 F-mity Stations-
' Great Southern Paper
- o. (SSE-3)
IC - 0703
- Not required by Tech Specs. Used as a spare station.
3Not required by Tech Specs. Used for comparison purposes with State of Ga. EPD.
40 Rev. 2 DN ODCM/11
ENP ' M-011 TABLE 3.12-1 (con't)
EXPOSURE PANY AND/OR SAMPLE SAMPLE LOCATIONS SAMPLE IDENTIFICATIN 2.
Direct Radiation Indicator Stations:
Plant Perimeter (NNE-0.9)
RI - 0101 (NE-1.0)
RI - 0201 (ENE-0.9)
RI - 0301 (E-0.8)
RI - 0401 (ESE-0.8)
RI - 0501 (SE-1.1)
RI - 0601 (SSE-1.0)
RI - 0701 (S-1.0)
RI - 0801 (SSW-1.0)
RI - 0901 (SW-0.9)
RI - 1001 (WSW-0.9)
RI - 1101 (W-0.8)
RI - 1201 (WNN-0.8)
RI - 1301 (NN-1.1)
RI - 1401 (NNW-0.9)
RI - 1501 (N-0.8)
RI - 1601 Control Stations:
Blakely, Ga. (NE-15)
RB - 0215 Neals Landing, Fla.
RB - 0718 (SSE-18)
Dothan, Ala. (W-15)
RB - 1215 Dothan, Ala. (W-18)
RB - 1218 community Stations:
(NNE-4)
RC - 0104 (NE-4)
RC - 0204
( DE-4 )
RC - 0304 (E-5)
RC - 0405 (ESE-5)
RC - 0505 (SE-5)
RC - 0605 (SSE-3)
RC - 0703
\\
41 Rev. 1 DN ODCM/11
~
q ENP- ~ M-011 TABLE 3.12-1 (con't)
EXPLYJJRE PA1150LY APO/OR SAMPLE SAMPLE IOCATICES SAMPLE IDENTIFICATICE 2
Direct Radiation (Con't)
&namity Stations (Cont):
(S-5)
RC - 0805 (SSW-4)
RC - 0904 (SW-1.2)
RC - 1001 (SW-5)
RC - 1005 I
(WSW-4)
RC - 1104 (WSW-8)
RC - 1108 (W-4)
RC - 1204
)
(itM-4 )
RC - 1304 (NW-4)
RC - 1404 (ftM-4 )
RC - 1504 (N-5)
RC - 1605 3.
WLFnBORNE a.
Surface Indicator Station:
Great Southern Paper WRI Intake Structure (River Mile-40)
Control Station:
Andrews Lock & Dam Upper Pier (River Mile-47)
WRB b.
Ground Indicator Station:
Great Southern Paper Co. Well (SSE-4)
NGI - 07 Control Station:
Mr. Whatley (SW-1.2)
WGB - 10 c.
Sediment Indicator Station:
Smith's Bend (River Mile-41)
RSI Control Station:
I Andrews Lock & Dam Reservoir (River Mile-47)
RSB 42 Rev. 1 ENV 0D01/11
~
I.
' ENP '^ ^1-U11 ~
.l USLE 3.12-1 (con't) i EXPOSURE PA'!!MP0f AIO/OR SAMPLE SAMPLE IDCATIONS SAMPLE.IDENFIFICATION.
4.
INGESTI(DI A.
Milk Indicator Station:
' g None Control Station:
Ray Lewis Dairy Ashford, Ala. (WSW-14)
MB.1114 b.
Fish Indicator Station:
Smith Bend (River Mile-41)
Game Fish FGI Botton Feeding Fish FBI Control Station:
~..
Andrews Iock & Dan Reservoir (River Mile-47)
Game Fish FGB Bottom Feeding Fish FBB c.
Forage Indicator' Stations:
South Southeast Perimeter (SSE-l'.0)
FI - 0701 North Perimeter (N-0.8)
FI - 1601
- South Perimeter (S-1.0)
FI - 0801
- Northeast Perimeter (NE-1.0)
FI - 0201 Control Station:
Dothan, Alabama (W-18)
EB - 1218 1
- Alternate forage plots.
l 6
.. _. _ _,.,,, _ _ _ _ ~...,. _ _ _ _, ~ _. _ _,.., -. _,.
.,m
r-FNP-0-M-011 L
ll tttu.P fp g
Is i
71-75 VAKE d
/
T-NORMAL.
i15 i
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+
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ENE WNW i
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=
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a A-
$ FOR AGE S A MPLIN G A TLD SAMPLING
@ TLD. PARTICULATES 8 IODINE SAMPLING Eds.A se fL&1 FIGURE 3.12-1 IN DIC ATOR S AMPLING LOC ATIONS FOR AIRBORNE ENVIRONMENTAL RA0lO ACTlvlTY AT THE FARLEY NUCL E AR PL ANT.
Rev. 2
FNp o 5'-011
- b. i I
a f $r i
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C*
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45 Rev. 4
FNP-0-M-011
(
COLUM81A st 52 l
ANDREWS LOCK & DAM
~
- FARLEY 10 MILES j
NgCLEARPLANT
,~
j d
EARLY COUNTY GEORGIA l
L ASHFORD k
l in
%"A G0,RDON :
g-HOUSTON COUNTY 1
ALABAMA e
INDICATOR STATIONS CONTROL STATIONS E
SURFACE AND GROUND WATER SURFACE WATER, Fish and Sedimen:
S FISH AND SEDIMENT GROUND WATER FIGURE 3.12-}.
INDICATOR AND CONTROL SAMPLING LOCATIONS FOR WATER 8ORNE ENV:RONMENTAL RADIOACTIVITY IN THE FARLEY NUCLEAR PLANT AREA, Rev. 1 46
r.
FNP-0-M-011 4
eLausLv g
N l
18 01
/*
j NNw NMt 14 1
03 NW NE weta N_
II
- e 13
\\
03 WNW ENE Q$
ye a
=-c v
e r
ctehe N
1 seeinsa
/,
ll Asaroes b
OS WSW ESE
\\-
f l~ & =\\
\\
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+
i iwe i
e e
a a n a samptme gy, a FIGURE 3.12-4 COMMUNITY (LNDICATCR 2) $AMPt.!NG LOCATICNS FOR AIRSORNC R ADtOACTIVITY IN THE FARLEY NUCLEAR PLANT AREA.
47 Rev. 2 l
r FNP-0-M-011 3.3.3.10 Determination of Alar vrrip setpoints for Liquid Monitors
/
R-18 Trip setpoint will be calculated based on manufacturers single isotope activity response curves for the detector being used according to the following expression; 4=K (F,+F,)
F, where monitor meter response (cp) corresponding to K
=
the source activity (uci/ml) calculated as measured monitor meter response taken from the calibration curve given by the manufacturer.
liquid radwaste tank release flow rate (gp)
F,
=
dilution water flow rate (g p)
F, R-23A and R-23B Trip setpoints will be determined from; 1.
During initial startup the trip setpoint will be taken from tne manufacturers single isotope activity response curves for the detector being used.
Setpoints will be less than or equal to the count rate (cp) corresponding to LX 10-5 vCi/ml in the effluent stream.
2.
After sufficient data is accumulated to permit a calibration against actual representative effluent these monitor trip setpoints may be calculated from the following expression; 4 = h(x) + K (cpm) where The zero intercept on the manufacturers K
=
curve obtained by taking the difference between the (cp) actual response of the detector to the measured pCi/ml.
the function which generates the h(x)
=
manufacturers curve such that 4 =0'lcp )
count rate corresponding to 1 X 1 Ci/ml as measured in the effluent stream.
48 Gen. Rev. 2
INP-0-M-011 ne b1wdown discharges into the service water dilution stream which has a miniaun flow of 10,000 gpm. We maximum bicwdown flow rate per generator is 50 gpm which yields 150 gpa total. he effective dilution ratio in 66.67 which when applied setpoint (1 x 10'pivity allcmd by tKe to the maxiava a:
pCi/ml),giyesan activity approximately 2 x 10 pCiAal which is well below all ape values set by 10 CFR 20. h e blowdown is automatically routed rack to the condenser if there is no dihtion flow.
I n.
l
\\
l 49 Gen. Rev. 1 l
FNP-0-M-011 3.3.3.11 Determination of AlarnVTrip Setpoints for Gaseous Monitors A.
R-15 and R-22 alarm setpoints and R-14 trip setpoint will I
be calculated based on the most restrictive of the following release-dose rates:
14 1)
I K i=1,0, < 500 mrenvyr r, I
1 (X/Q)v 10' pei/pci
- r
- where, i
subscript numbering noble gases in consideration K
the total body dose factor due to gansna
=
i emissionsforidentifiednoblegasisotope 1 (mrem /yr per pCi/m ) from Table 3.
O, i
average release rate of isotope i from
=
release point v (vci/sec) subscript indicating release point in y
=
consideration (turbine building verit or plant stack) r, release fraction allotted to release point
=
in consideration (X/Q),
highest value of annual average
=
atmospharicdispersionfactorapsite boundary for all sectors (sec/m )
7.5x10" sec/m' (X/Q),
=
( ~/Q), 1.2x10" sec/m' X
r safety factor to account for possible
=
sampling and monitoring error and allow advance warning of approaching limit = 2
\\
14
/
2)
I (L +1.1 M,) 0,,<
3000 mreryhr r, i
i=1 (X/Q)v 10' pei/vci
- r Li skin dose factor due to beta emmissions
=
foridentifiednob}egasisotopei i
(mrenvyr per pei/m ) from Table 3 50 Rev. 4 i
i
FWP-0-M-011 air dose factor due to gama emissions fe,r M,
identifiepnoblegasisotope1(mrad /yr
{
per pei/m ) from Table 3 B.
Rather than calculating 3.3.3.11.A.1 or 3.3.3.11.A.2 using real time parameters, the actual monitor setpoints may be calculated for the worse case condition (thus more conservative) count rate based on the worst isotope release-dose rate Q as follows and need not be changed, i
except based on rea,pportioning of allotted release fraction r
from operating experience as mentioned above.
From Table 3, Kr-89 would be the most restrictive isotope in either the total body or skin dose restrictions.
Assuming that the total release consists of Kr-89, the skin dose equation is more restrictive than the whole body dose equation, and the release-dose rate limit would be calculated as:
0, = 3000 mrenVyr r, (X/Q), 10; pei/vci* r* (L,+1.1M,), and Q,, = 6.9x10' uCi/sec (r,)
4.3x10' C1/sec ( r, )
O
=
g Based on maximum flow rate and conservative detector efficiency, the monitor setpoints S, (cpm) may be calculated as follows:
S, =
Q,
+ b, where (c)(f,)
b=
monitor background count rate (cpm) c=
gross monitor calibration factor (vci/ml per net epm) u+ m, where
=
u=
isotope concentration (vci/ml) in the monitor at time of grab sample calibration (Noble gas release rate calculations) f, = maximum effluent flow rate (ml/sec) ma net monitor reading (cpn) at time of grab sample calibration (release rate calculations) 51 Rev. 4 L.
NT-88-0124 Att>tma Power Compa?y 600 North 18th Street -
Post Offee Bon 2641-Dirmirgham, Alabama 35291-0400.
Telephone 205 250-1835 M. P. Mc Donald Af8h8[}]3[DWCf Swnior Vice President Ite Sxtrern eAx:frc sygyn April 12, 1988 Docket Nos. 50-348 50-364 U. S. Nuclear Regulatory Comission Attention: Document Control Desk Washington, D. C. 20555 Dear Sirt In accordance with a request by Mr. E. A. Reeves, attached is an uncontrolled copy of the most recent revision ni the Joseph M. Farley Nuclear Plant Offsite _ Dos _e Calculation Manual (ENP-0-M-Oll, Rev. 4).
If you have any questions, please advise.
Yours very truly, u>. A. Ikh Tu~
R. P. Mcdonald
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RPVFtUtemb Attachment xc: Mr. L. B. Long Dr. J. N. Grace Mr. E. A. Reeves Mr. W. H. Bradford 2
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