ML19325C675
| ML19325C675 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 09/25/1989 |
| From: | ALABAMA POWER CO. |
| To: | |
| Shared Package | |
| ML19325C629 | List: |
| References | |
| FNP--M-11, FNP-0-M-011, NUDOCS 8910170167 | |
| Download: ML19325C675 (9) | |
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Septenicer 25, 1989 y
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i Revision 8 e
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W ALABAMA POWER COMPNu'
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c, JOSEPH'M. FARLEY NUCLEAR PIJWP a,
FNP-0-M-011
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S A
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Y
<'W OFF-SITE DOSE CALCULATION MANUAL i
R E
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N T
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D U
Approved:-
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~ 'INichnical Manager P
l[4 Date Issued::
i " MFI F
L
~ List o'f Effective Puges l3 a
l Page-Rev.
i.to V 7
1-L to 2-10,'3-1 to 3-16 7
1~
ft:;.&
3-20 to 3-23, 3-26 to 5-2 7
l5-4 to.6-9 7-2-11,'2-12, 3-17, 3-18,-3-19 8
Jh 3-24, 3-25, 5-3 8
l Appendix 7
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Liquid Effluents FNP-0-M-011 y
b i
@n
- r' ' '
LIQUID EFFLUENT DOSE COMMITMENT FAC'IORS Q'
Nuclide Bone Liver T. Body Thyroid-Kidney Lung GI-LLI m+
H-3 0.00E+00 2.26E-01 2.26E 01 2.26E-01 2.26E 2.26E-01 2.26E C-14 13.13E+04 6.26E+03-6.26E+03 6.26E+03 6.26E+03 6.26E+03 6.26E+03 n
NA-24 4.07E+02' 4 07E+02 4.07E+02 ~4.07E+02 4.07E+02 4.07E+02 4.07E+02
'X CR-51 0.00E+00 0.00E+00 1.27E+t.0 7.61E-01 2.81E-01 1.69E+00 3.20E+02 1
MN-54 0.00E+00 4.38E+03 8.35E+02 0.00E+00
- 1. 30E+0's 0.00E+00 l'.34E+04
]
E 56.
0.00E+00 1.10E+02 1.95E+01 0.00E+00 1.40E+02 0.00E+00 3.51E+03 FE.55-6.58E+02 4.55E+02 1.06E+02 0.00E+00 0,')0E+00 2.54E+02 2.61E+02 FE-59'
-1.04E+03 2.44E+03 9.36E+02 0.00E+03 0.00E+00 6.82E+02 8.14E+03 co-58 0.00E+00' 8.92E+01 2.00E+02 0.00E+00 0.00E+00 0.00E+C0. 1.81E+03 H
Co.0.00E+00 2.56E+02 5.65E+02 0.00E+00- 0.00E+0 0.00E+00 4.81E+03 11I-63) 3.11E+04 ~2.16E+03 1.04E+03 0.00E+00 0.00E+00 0.00E+00 4.50E+02 NI-65:
-1.26E+02 1.64E+01 7.49E+00 0.00E+00 0.00E+00 0.00E+00 4.17E+02 CU-64
-0.00E+00 9.97E+00 4.68E+00 0.00E+00 2.51E+01 0.00E+00 8.50E+02 ZN-65E 2.32E+04.7.37E+04 3.33E+04 0.00E+00 4.93E+04 0.00E+00 4.64E+04 BR-BO 0~00E+00 0.00F+00 4.04E+01 0.00E+00 0.00E+00 0.00E+00 5.82E+01 RB-86 0.00E+00 1.01E+05 4.71E+04 0.00E+00 0.00E+00 0.00E+00 1.99E+04 i
<-p SR-89 2.21E+04 0.00E+00 6.35E+02 0.00E+tJ 0.00E+00 0.00E+00 3.55E+03 4
b SR-90'-
5.44E+05- 0.00E+00 1.34E+05 0.00E+00 0.00E+00 0.00E+00 1.57E+04 M
SR 4.07E+02 0.00E+00 1.64E+01 0.00E+00 -0.00E+00 0.00E+00 1.94E+03 SR-92 1.54E+02 0.00E+00 6.68E+00 0.00E+00 0.00E+00 0.00E+00
- 3. 06E+03 -
.Y-90
.5.76E-01 0.00E+00 1.54E-02 0.00E+00 0.00E+00 0.00E+00 6.10E+03 Y-91=
18.44E+00 0.00E+00 2.26E-01 ~0.00E+00 0.00E+00 -0.00E+00 4.64E+03
- Y-92
'5.06E-02 0.00E+00 1.48E-03 0.00E+00 0.00E+00 0.00E400 8.86E+02 Y-93 1.60E-01. 0.00E+00 4.43E-03 0.00E+00 0.00E+00 0.00E+00 -5'.09E+03
+
ZR-95 2.40E-01 7.70E-02 5.21E-02 0.001;+00 1.21E-01 0.00E+00 2.44E+02
.ZR-97
>1.33E-02 2.68E-03 1.22E-03 0.00E+00 4.04E-03 0.00E+00 8.30E+02 NB 4.47E+02 2.4AE+02 1.34E+02 0.00E+00 2.46E+02 0.00E+00 1.51E+06 MO 0.0GI+00 1.03E+02 1.96E+01 0.00E+00 2.34E+02 0.00E+00 2.39E+02
'K-99M 8.87E-03 2.51E-02 3.19E-01 0.00E+00 3.81E-01 1.23E-02 1.48E+01 RU-103 4.43E+00 0.00E+00 '1.91E+00 0.00E+00 1.69E+01 0.00E+00 5.17E+02 f
RU-105-3.69E-41 ' 0.00E+00 1,46E-01 0.00E+00 4.76E+00 0.00E+00 2.26E+02 RU-106 6.58E+01 0.00E+00 8.33E+00 0.00E+00 1.27E+02 0.00E+00 4.26E+03 P
D 110M 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TE-125M 2.57E+03 9.30E+02 3.44E+02 7.72E+02 1.04E+04 0.00E+00 1.02E+04 TE-127M 6.48E+03 2.32E+03 7.90d+02 1.66E+03 2.63E+04 0.00E+00 2.17E+04 Units are mrenVhr per peiAi0 l
-Table 2-4.
Liquid Dobe Conunitment Factors Ai 2-11 Rev. 8 p
%.} '
1
?='-
~.-
p y
Skhi i
- n 41
,o' o
p.v;.
b-2' Liquid Effluents t
FNP-0-M-011
'j/
p"\\~y
?
Nuclide Bone Liver.
T. Body ~
'IhyroM Kidney Lung GI-LLI.
'TE-127-. 1.05E+02 3.78E+01 2.28E+01. 7.80rt+01 4.29E+02 0.00E+00~ 8.31E+03
- TE-129M 1.10E+04' 4.11E+03 1.74E+03 3.78E+03 4.60E+04 0.00E+00.5.54E+04 TE-131M 1.66E+03 8.10E+02L 6.75EF02 1.28E+03 8.21E+03 0.00E+00- 8.04E+04
~TE-132 2.41E+03 1.56E+03 1.47E+03 1.72E+03 1.50E+04 0.00E+00 7.38E+04' I-130 2.71E+01 8.01E+01 3.16E+01 6.79E+03 1.25E+02 0.00E+00 6.89E+01 9:
'I-131-1.49E+02 2.14 E+02 1.22E+02 7.00E+04 3.66E+02 0.00E+00 5.64E+01 I-132
- 7.29E+00. 1.95E+01 6.82E+30. 6.82E+02 3.11E+01 0.00E+00' 3.66E+00
,I-133
- 5.10c+01 8.87E+01 2.70E+01 1.30E+04. 1.55E+02 0.00E+00.7.97E+01
-I-135 1.59E+01' 4.17E+01 1.54E+01 2.75E+03 6.68E+01 0.00E+00 4.70E+01 CS-134 2.98E+05 7.09E+05 5.79E+05 0.00E+00' 2.29E+05 7.61E+04 1.24E+04 CS-136
- 3.12E+04J 1.23E+05 8.06E+04 0.00E+00 6.85E+04 9.38E+03' 1.40E+04 CS-137-3.82C+05 5.22E+05 3.42E+05 0.00E+00 1.77E+05 5.89E+04 1.01E+04 BA-140 1.94E+02' 2.44E-01 1.27E+01 0.00E+00 8.30E-02 1.40E-01 4.00E+02
-LA-140 1.50E-01.7.54E-02 1.99E-02 0.00E+00 0.00E+00 0.00E+00.5.54E+03 5
Cc-141, 2.24E-02 -1.52E-02 1,72E-03 0.00E+00 7.04E-03 0.00E+00 5.79E+01 CE-143:
3.95E-03'^2.92E+00 3.23E-04 0.00E+00 1.29E 0.00E+00 ' 09E+02 H-
-CE-144 1.17E+00 4.88E-01 6.27E-02 0.00E+00 2.90E 0.00E+00 3.95E+01 1'
PR-143 5.51E-01 2.21E-01 2.73E-02 0.00E+00 1.27E-01 0.00E+00 2.41E+03
'W-187 2.96E+02 2.47E+02 8.65E+01 0.00E+00 0.00E+00 0.00Ee00 8.10E+04 7
M
[
.NP-239 2.85E-02.2.80E-03 1.54E-03.0.00E+00 8.74.;-03 0.00E+00 5.75E+02 Units are areWhr per uci/mi P
k 1
l Table.2-4. Liquid Dose Conuitment FactorE Ai (continued) i l
2-12 Rev. 8 g
AJ r
' ~.y m
ur es
-u-me--
s=-i--
m
---m--
m 3:fg $p
. f.;di~-
A
.)
g:ge.-m 4
s j
'Dil, vJ
\\
? $u I
s -
FNP-0-M-Oll-
, [y-l-y, Gaseous Effluents-j i
3.3 E SETPOINTS FVR GASEOUS MONI'IORS~
{
l 3.3.1 Alarm setpoints - for the gaseous monitors R-14, R-15, l.
i and -R-22 will be~ calculated based on-the -more 1
restrictive of the dose rate limits. for noble gases j
for whole body and skin. -"hese limits are expressed as
_500 mrenvyt F, J
m
[ Ki 0, - <
(3.17)-
3 (X/Q), x F s-e t
-where I
- F.7 i - subscript numbering noble gases-in consideration, and the sum is over all noble gases K; = the total. body dose factor due to gamma emissionsforidenpifiednoblegasisotopei (mrenVyr per uci/m ) from Table 3-3.
I Og, = average release rate of isott,pe i from relerse point v (uci/sec) x.
d b
500 = the site' dose rate lintit in mrenVyear v.-
v = subscript indicating release point in consideration (turbine building vent or plant stack)
F, - release; fraction allotted to release point in consideration..
y (X/Q), = highest value of annual. average atmospheric dispersion facpor at site boundary for all f
sectors (secA ).
+
(X/c), = 1.08x10-' sec/m' for the stack
.-t ;
(X/Q)c = 4.87x107 secA for the turbine building-8 vent F=
unit' apportionment factor for conpliance witit 10CFR20 limits for a multi-unit site.
F=
the number of reactor units that can be operating 3-17 Rev. 8 k,'
- {
i
'h w
-m e--
..., - - +.
.--n.-.-m.,
w-,,.
--e
.w
---<---,v------
~
,g,; N f ',
~i c.-
a 3
, u
-f FNP-0-M-011 y(%.
Gaseous Effluents l
~
sinultaneously.
~
~
3000 mrenvyr r,
,}(L-+1.1M,);Q,'<
(3.18) 3 3
(X/Q), x F l
where y
L = skin' dose factor due to beta emissions for i
ident uciAn}fied noble gas isotope 1 (arenVyr per
-) from Table 3-3.-
-s.
M - air do3e factor due to ganuna emissions for 3
.ident}fiednoblegasisotope1.(mred/yrper uCIAn )- from Table 3-3.
We factor of 1.1 i
are e rad coiaerts air dose to skin dose-(see Ref. 1, page 22).
^
2e, actual monitor setpoints will be adjusted for a lower (thus more conservative) count rate based on-the worst isotope release-dose rate Q as follows and need not be changed, except based on, reapportioning i
3 of allotted release-fraction from -operating experience'as mentioned above. Frce Table 3-3,. Kr-89 p(
would-be the most restrictive isotope in either the
?,,
a;: '
. total body-or skin dose restrictions. Assuming: that the. total release consists of Kr-89, the whole body p.
~ dose equation is more restrictive than the skin dose equation, and the release rate-limit would be calculated as:
500 mrenvyr F, J
Q, =
(3.19)
(X/Q), x F x Kg his yields:
Q, = 1.39x10' uC1/sec (F,) for the stack, and Q, = 3.09x10 pC1/sec (F, ) for the turbine building
. vent.
Based on maximum flow rate and conservative detector efficiency, the monitor setpoints S, (cpn) may be calculated as follows:
.S, = E,(Q,/F,) + b (3.20) 3-18 Rev. 8 g
N^);
x ni bl\\
h, :_
J a
t
., a a,a
- j
- x.
l~7 ',
FNP-0-M-Oll i
Gaseous Effluents bre
(
V
.b = monitor background _' count rate (cpm)
E, = gross monitor calibration factor (cpm per uC1/ml)-
F, - maximum effluent flow rate (ml/sec)
. Setpoint calculations win be made for radiation monitors R-14, R-15, and x-22 on this basis. %e limitir,9 release rate Q (uci/sec) is based on the value satisfying the reIationship 3.17 for total body dose. We setpoint-S (cpm) corresponding to this release rate may be d, scribed as e
if;,
S,'= E, (Q,/F,) + b (3.22) where zv F, =' maximum release flow rate (ml/sec) 3.3.2'
-R-24, while not a gaseous effluent raonitor, monitors an effluent release source to the plant vent stack.
. We maximum setpoint'for R-24 will be calculated
-based upon the monitor response curve and the alarm t
setpoint specified in the Technical Specifications.
N.
l 1.
);
Sg = (F )'(A,,,)
3 where i
S,
= maximum monitor alarm setpoint in epm F
= gross monitor calibration factor (cpm per 3
pCi/cc) 4, - maximum setpoint allowed by 'Iwchnical i
specifications in vC1/cc To provide early detection and termination of an abnormally high containment purge release, the R-24 setpoint may be reduced per Section 3.3.1 above.
X 3.3.3 R-13 monitors the supply to the waste gas decay tanks from the waste gas con ressor. We alarm setpoint for R-13 is based on. expected buildup in the waste gas system and the Technical Specification limit for waste gas. storage.
(F ) ( B,,, )
S
=
g t
where n-i B,,, = maximum expected buildup of radioactivity in pCi/cc 3-19 Rev. 8
-p
, ;,3, H w.
3_,y 1
's y
4.-. j.
FNP-0-M-011 1
y y Gaseous Effluents
_j
-Q:
h VALUES FOR AN INTANT l
>tsotope Inhalation Ground Plane Cow Milk' Goat Milk i
1 H-3 6.47E+02 0.00E+00
.2.38E+03 4.86E+03 C-14 2.65E+04-0.00E+00 2.34E+09 2.34E+09 l
P-32 2.03E+06 0.00E+00 1.60E+11 1.92E+11 1
-CR-51 1.28E+04-6.65E+06 4.70E+06 n.00E+00 MN-54 1.00E+c6 1.10E+09
~3.90E+07' O.00E+00 TE-55' 8.69E+04-0.00E+00:
1.35E+08 1.76E+06
",y TE-59i 1.02E+06 3.89E+08 3.92E+08 5.10E+06 Co-58 7.77E+05 5.26E+08 6.04E+07-0.00E+00 co-60 4.51E+06 4.40E+09 2.10E+08 0.00E+00 H
NI-63 3.39E+05 0.00E+00 3.49E+10 0.00E+00 ZN-65 6.47E+05 6.88E+08 1.90E+10 0.00E+00 l
RB-86 1.90E+05 1.28E+07 2.23E+10 0.00E+00 SR-89 2.03E+06 3.07E+04 1.26E+10 2.64E+10 SR-90 4.09E+07 0.00E+00 1.22E+11 2.55E+11 Y 2.45E+06 1.51E+06 5.25E+06 0.00E+00 ZR-95 1.75E+06
- 3.43E+08 8.26E+05 0,00E+00 1'
NB-95 4.79E+05 1.95E+08 2.06E+08 0.00E+00 Rt'-103 5.52E+05 1.54E+08.
1.05E+05 0.00E+00 Rti-106 -
1.16E+07 2.99E+08 1.45E+06 0.00E+00 i
p.
AG-110M 3.67E+06 3.13E&O9 1.46E+10 0.00E+00 t
1 L
TE-125M
'4.47E+05 2.19E+06 1.51E+08 0.00E+00 M
-TE-127M
~1.31E+06 1.18E+05 1.04E+09 0.00E+00
.TE-129M-1.68E+06 2.82E+07 1.39E+09 0.00E+00 I-131 1.48E+07-2.46E+07 1.05E+12 1.26E+12 I-133'
-3.56E+06 3.50E+06 9.61E+09 1.15E+10
-I-135 6.96E+05 3.61E+06 2.00E+0?
2.41E+07 CS-134 7.03E+05 2.81E+09 6.80E+10 2.04E+11 CS-136 1.35E+05 2.16E+08 5.81E+09 1.74E+10 CS-137 6.12E+05.
1.15E+09 6.02E+10 1.81E+11 BA-140
-1.COE+06-2.93E+07 2.41E+08 0.00E+00 CE-141 5.17E+05.
1.95E+07 1.37E+07 0.00E+00 L
CE-144 9.84E+06 5.85E+07 1.33E+08 0.00E+00 PR-143 4.33E+05 0.00E+00 7.84E+05 0.00E+00 ND-147 3.22E+05 1.20E+07 5.74E+05 0.00E+00 L
Values are calculated from equation in ref. 1, with parameters from ref. 4.
Units are arenVyr per uCip'for the food and ground plane pathways.
for h-3 and the inhalation pr.thway and mrenVyr per uCi/sec per m l
l.
Table 3-4. Infant Dose Factors l.
l:
3-24 Rev. 8 lf y
- i i
i
?
x: q.
1 FNP-0-M-012
' Gaseous Effluents i
g f(]7
~ 3.5 1&STE CAS S'IURAGE TANK
.q he radioactivity contained in the; watte gas dccay tanks will be j
monitored regularly to. ensure that-- it is below ' the ' Tech. Spec.=
.e limit of 70,500 Curies per tank.
I me storage limit for each tank may be verified by sampling and analysis or by use of R-13.
Sample anhlysis'results for nuclides
_other than Xe-133 will be converted to an equivalent Xe-133 level by normalizing with the ratio of the MPC value for that nuclide to-the MPC value for Xe-133.
3.6 CUMULATIVE DOSE CALCULATIONS '
Two,. methods of calculating cunulative doses can be employed.
These are designated. " Method A" and " Method B" below.
Method A uses real-time input of hourly averages of meterological data, and
' Method' B uses average highest value of X/Q and DM for all releases.
Method B is the
" annual average" method described in NUREG-0133.
Method A or B may be selected at the discretion of the licensee.
3.6.1 Dose Calculations From Noble Gas Releases y}
I.
Method At Real Time Meteorological Input he 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:
_During any time period, for ganna radiation:
j D,y, = 1.14 x 10 I, M, E otj (XM )3,,-Q,3, (3.26) 3 During any time period, for beta radiation:
i D,,, = 1~.14 x 10 I, H, E ot, (X/Q)3,, Q,3y (3.27) 3 where:
L 1.14 x 10-* = = 1 / 8760 hours0.101 days <br />2.433 hours <br />0.0145 weeks <br />0.00333 months <br /> / year L
(
V 3-25 Rev. 8
[
,r_.
'-\\l
g x
@f FNP-0-M-011 7, c
+
.*V' MNNM M ORING M TIONS
.y m PANY SAMPLING IDCATIONS SAMPLE-
' (,, '
. AND/t)R SAMPLE IDI!NTIFICATION -
(W-0.8)-
.RI -'1201 (WNW-0.8)
RI; -1301 (NW1.1) l (telW-0.9 ) '_
RI - 1401-RI - 1501' (N-0.8)
RI'- 1601 Control Stations:
Blakely, GA, (NE-15)
RB - 0215 Y
Neals' Landing, FL (SSE-18)
RB~- 1311 Haleburg, AL (N-12)
RB - 1612 Comma:nity Stations:
-(NNE-4)
.RC - 0104 (NF-4).
RC - 0204~
(ENE-4)
RC - 0304
_(E-5)
RC - 0405
-(ESE-5)
RC - 0505 (SE-5)
RC - 0605 l_
(SSE-3)
RC - 0703 e
(S-5)
PC - 0805 (SSW-4).
RC - 0904
'(q (SW-1.2)
RC - 1001
'i
'j (SW-5)
RC -'1005 (WSW-4)
RC - 1104-(WSW-8)
RC - 1108 l-(W-4)
RC - 1204 i
(NNW-4).
RC
.1304 (NW-4)
-RC - 1404 (NNK-4)
RC - 1504 (N-5)-
RC - 1605
,i
- 3. ' WATERBORNE Indicator Stations.
i a.
Surface Great Southern Paper WRI Intake Structure (River Mile-40)
I Control Station:
Andrews Lock & Dam o
Upper Pier (River Mile-47)
WRB l
b.
Ground Indicator Station:
Great Southern Paper WGI - 07 i
'Co. Well (SSE-4)-
Control Station:
Mr. Whatley (SW-1.2)
WGB - 10 i.
~
Table 5-1. Radiological Environmental Monitoring Locations (con't)
JNV) m.t 5-3 Rev. 8 a
,L g
r :3_:
.