ML20212E003
| ML20212E003 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 12/10/1986 |
| From: | Rolonda Jackson, Mckay J MIDDLE SOUTH UTILITIES, INC. |
| To: | |
| Shared Package | |
| ML20212D758 | List: |
| References | |
| PROC-861210, NUDOCS 8703040251 | |
| Download: ML20212E003 (13) | |
Text
.
ATTACHMENT VI I
OFFSITE DOSE CALCULATION MANUAL REVISION N0. 10 d
r a
4
- k.
y s
-1.
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0FFSITE DOSE CALCULATION MANUAL GRAND GULF NUCLEAR STATION i.
GRAND GULF, UNIT 1 Rev. 10 - 12/86 J200DCM86092903 l
r:
s Revision No. 10 Date 12/86 GRAND GULF NUCLEAR STATION OFFSITE DOSE CALCULATION MANUAL
^
~
SAFETY RELATED EVALUATION APPLICABILITY SAFETY EVALUATION ENVIRONMENTAL EVALUATION
[X] APPLICABLE (X] APPLICABLE
[ ] NOT APPLICABLE
( ] NOT APPLICABLE
\\
\\a-\\-%
Reviewed / Approved:
k Supervisor, E onmental Services /Date
~
0
/ 2-A - 8 C d
Reviewed / Approved:
a Supervisor, Radiological services /Date DEC 0 01986 Reviewed / Approved:
Manager,Radiologcal&EnvironmentalServices/Date
- 2W[
/d"Y-/h Reviewed / Approved:
(
iTEctot, Nuglear Supp/ Jate
, I.jelj JYk
[j -
I Reviewed / Approved:
Chafrman, Plant ($sfetyfeviewCommit' tie /Date v
l 1
l GRAND GULF, UNIT 1 Rev. 10 - 12/86 i
J200DCM86092903 l
A ODCM LIST OF EFFECTIVE PAGES PAGE REV.
PAGE REV.
NO.
No._
NO.
NO.
i 10 2.0-22 1
11 2
2.0-23 10 iii 8
2.0-24 10 iv 8
2.0-25 0
6 2.0-26 10 v
vi 2
2.0-27 3
vii 10 2.0-28 5
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3.0-9 3
2.0-8 6
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2.0-9 6
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2.0-10 5
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2.0-11 1
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2.0-19 1
2.0-20 1
2.0-21 2
GRAND GULF, UNIT 1 Rev. 10 - 12/86 vii
'J200DCM86092903
f = the waste tank effluent flow setpoint as measured at the radiation monitor location, in volume per unit time, but in the same units as F, below.
i F = the dilution water flow setpoint as measured prior to the release point, in volume per unit time.
At Grand Gulf Unit 1, the available dilution water flow (F) should be constant for a given release, and the waste tank flow (f)
)
and monitor setpoint (c) are set to meet the condition of equation 1 for a given effluent concentration, C.
The method by which this is accomplished is as follows:
Step 1)
The isotopic concentration for a waste tank to be released is
[
obtained from the sum of the measured concentrations as deter,
mined by the analysis required in the RETS Table 4.11.1.1.1-1:
= IC
+C
+ IC
+C
+C (2) 10 i
gg a
ss t
f i
where:
10 the sum of concentrations C of each measured IC
=
88 8
gamma emitter observed by gamma-ray spectroscopy of the waste sample.
10 C,
the concentration C, of gross alpha emitters in
=
liquid waste as measured in the monthly composite sample.
10 the measured concentrations of Sr-89 and Sr-90 in IC,
=
liquid waste as observed in the quarterly composite sample.
GRAND GlU, UNIT 1 Rev. 10 - 12/86 J200DCM86092903 1.0-2
i the measured concentration of H-3 in liquid waste as C
=
g determined from analysis of the monthly composite sample.
the concentration of Fe-55 in liquid waste as 10 C
=
f measured in the quarterly composite sample.
The C, term will be. included in the analysis of each waste tank batch to be released; terms for alpha, strontiums, lo tritium and iron may be included if analysis of reactor water has shown the presence of these isotopes.
The measured radionuclide concentrations are.used to calculate Step 2) a Dilution Factor, D.F., which is the ratio of total dilution flow rate to waste tank effluent flow rate required to aspure that the limiting concentration of 20CFR20, Appendix B, Table II, Column 2 are met at the point of discharge.
C
.D.F. = [I
} x S. F.
MPC.
i 1-C C
C C
C
- I b, +
C, + I NC, + NC + MPC ] x S. F.
(3) 10 s
t g
Where:
C,C,,C,,C and C ; measured concentrations as g
f C
=
g g
and C will be defined in Step 1.
Terms C,, C,,
Cg f
included in the calculation,as appropriate.
10 and W C are limiting concentra-WC,WC,,WC,,WCg f
=
g g
tions of the appropriate radionuclide from 10CFR20, For dissolved or Appendix B, Table II, Column 2.
entrained noble gases, the concentration shall be limited to 2.0E-4 pCi/ml total activity.
Rev. 10 - 12/86 GRAND GUII, UNIT 1 1.0-3 J200DCM86092903
4
.y.
i Thus, if instrumentation indicates the dilution flow rate falls G
below' the assumed flow rate of 90 percent of the actual dilution Q
flow,.or if the easte tank effluent flow rate exceeds 90 percent j
3 of the calculated maximum waste tank effluent flow rate, the
'f I
release is terminated (manually or automatically).
Step 5)
The radioactivity monitor setpoint may now be specified based on 4
the values of IC, F, and f which were specified to provide la g
i compliance with the limits of 10CFR20, Appendix B, Table II, Column 2.
The monitor resporse is primarily.to gamma radiation; 1
1 therefore,theactualsetpointisbasedongC. The setpoint i
concent ation, C, is determined as follows:
I d
C, gC (pCi/ml)
(7)
=
a where f, is the actual (or maximum expected) waste tank effluent The value of C, (pCi/ml) is used to determine the flow rate.
monitor setpoint (CPM) from a calibration curve similar to Figure 10 i
1.0-1.
NOTE:
The setpoint c ins a factor of conservatism, even if the calculated maximum waste tank flow rate is attainable, since the calculated rate contains the safety factor margin, waste tank effluent flow rate margin, and the d,ilution flow rate margin.
In practice, the actual waste tank effluent flow rate normally is many times less than the calculated tank flow rate, thus providing an additional conservatism during release.
GRAND GULF, UNIT 1 Rev. 10 - 12/86 J200DCM86092903 1.0-5 6
f i
l Figure 1.0-1 Extmple Calibration Curve for Liquid Effluent Monitor 10 10-2
.._g...
/
._s+..
-I f-
.= ::.-.. -
/
c
..u
,. 2-.L. r a i --.== -,..,,-. : -
1 1 - s
- C..j ut-lpi-i-t4 C9E%5=';-i-i~i-I} -- ----- ~=:. ~~/
, 55.:=.
".j : t-.4 - j i 3r ".-.
10-3 Z-Ti
-I.'.) f,- i'i 0 --
'%'2 :'* I j_]d [JI - y N - M*Q t:
-l-3-N~P '
- -.;.--.Y. -
- '-- ~
c
-- ~
'~~- -
r e
-i e
.. w --
v.
. s
. s s
--,-;t.
-a
/..
ri.:A-2='--
- i-
. - t..1
. r: It i 1._ _=..p
%-..n 1
. - n:r. s
~
.' rn.-
y f _ w_ r, _
I
~
1 __
s~*
1
.u_
.. g n.=
. n.. r2-7.r i -
.f_,;-g _,:,.
..._n-
-s i-W. 6 --9_t is *.u.;-.-- F.->mK - A.sy--- -=w.
-._:t :af. ', :y~._ :n
-- u-
-e e
.:2
\\
a 2+.. -. Le. a :,.. e ei=--J
- 4 e + 1,.i t >e--t --r :-pw
. -a,s._ y.
.r
_2_a _... i..
.a--
.I-m := -
- -- - ~ :.:
---a,x;-t..w g5 -@ "
C
~":"'W
=
- r
_2 2
10-4--
,.,, -.n, g
-_--,-o
.,,-,--+._r_
w ;
m_- 3 x.
= _, _.w.s
_. _ xw. x_.. _- - -
o
, _. _._==,r.>
2
. = _ i. r.-.n-:s-4;-,
_....-y
_.cm
__._=1,.
u
- -a.=-;, a :,-,..,
-w,e~+-<
a _..,---a_-
s u-
.. i v. inn,,-
r--
,m#
m m.-~.
'-l 3-,_.
.sm
. w-.y,.mu 1.. _ m m - :2 c m_:
,f-_.-
um_. g e-e-. &, -.
m y;t -. -
--d r-C,_3.,.._ _.
.-K f_-- --
.nir#_'_~=L:!r _-i_TSn :.W-=MfgS '-.'.= Li i r.;3Eg.'
. =. - _
n._
--.e.
. :=.3- -
u I.8
~~~
- 10-5 C.
-n-8
,_,,.. = <
4.__,-
,a m.
. _,_f _ :. __., %,,-r m : s. _.. :._ m m,_,__..0__~m,,.2_...
u
^
2'MT E-t *:-[
d ~ 1' s.y -:4ra s. :. __,
!.= 01.~d'- 1..si-g {_3 i
- ___-_-__ z gi l. - t
.. _ y".fri..
- / _'-,- t.+-r - ss,.. a m2. - _.,-v :
u n--
,v..
._3_-
.... u- -3.-
w.-/.
-u.
o e=:u-
.U
=-
=r=+ =.. _. =t -Ma- _.! _ A..==". _ r :=.-:.:i - 12 =.
=~=m w-+ :c.+-M-. '.; = = -
~~
=
L a
_--==.:-._..
._ ~:. -
- - M- =. - -
- =.=~
z
^_a_
-. =. -... -
~ ~
10-6..._
s.
o u
i-r
..,e s_- t
~
' I II G
'm---
_- _ i. -
s n -~T_1 Um---
- 1 E2 M
- _;/
r I_
m.-_
e..
=-
.=s
- ' -- D 'C.L;} ' 7" ~f '_-t 1 ^ 'iitv ?=-Z-.hnn =%
b.H.-st' =i-"~..'..
Mf.-j--/ j _ ~ M.- % 1 ~
.s
=: ~==r---. -,.-+ m A m-
=c =-k-yha-a
, s_-n_
.T _-L w
_.. - = ~ -
~
r= a==- r-U
+. - kna:- -~.,
-s w +-.
... : m,m c_ :
-m
- 1. s.
now ~-i, 1
. _ ~
U m\\r:m mgmq _ y j g.=.
_5 _ y.
.,.. y.
. -.y sw t. xse
__,_, y mm pu m.1v.-
.-_..=_9.,.. -
- v__~,,;m w, s.=.= =u :
. m r z-w-wn.-
.. = -.w
=
s1.mw w n-c.'.
..v
_u.___,=.==%._ _ _y
. p-m.__.,_
=._.-
.4--
__m.=_,,_
_m.
_m 10 7 m
1v--.y R 1
-b---
a
__L:s
_._;,=____-n-2.:
m..
=
10-E 1
2 3
10' 10 100 5
10 10 10 Count Rate (Counts per Minute)
Grand Gulf, Unit 1 1.0-6 Rev. 10 -
12/86 1
J
s 4
TABLE 2.2-3 CONTROLLING RECEPTORS, LOCATIONS, AND PATHWAYS
. Origin (for Distance.
25ector" (Neters)
- Miles Pathway Ane Group info only) it.
(A) N.
.148f 0.92-Vegetation-Adult _
garden 10
-(B)'NNE 1207 0.75 Vegetation
-Teenager garden
.(C) NE-1062 0.66 Vegetation
-Teenager garden 10 (D) ENE 4300 2.69 Inha1/ Gad Plane Child residence (E) E 982 0.61 Inha1/ Gad Plane Adult residence W!
(F) ESE 7000 4.38 Inha1/ God Plane Adult
-residence i.t-(G) SE 3100 1.94 Inha1/ God Plane Child residence 10 i
residence j
(H) SSE 1800 1.13 Inha1/Gnd Plane Adult
-(3)S 805-0.50 Vegetation Child hypothetical
- 10 (K) SSW 3734 2.33 Vegetation Child garden
{
I (L)'SW 1432 0.90 Inha1/Gnd Plane Adult residence I
(M) WSW 8047 5.00
'9w/ Milk Infant hypothetical j
(N) W 8047 5.00 Cow / Milk Infant hypothetical 10 (P) WNW 7680 4.80 Vegetation Child garden 8047 5.00 Cow / Milk Infant hypothetical (Q) NW.
(R) NNW 1207 0.75 Vegetation Child hypothetical
- 10 Tchle based on 1986 Land Use Census These locations represent MP&L gardens located inside the site boundary.
- Distances shown are actual mileage in each sector.
GRAND GULF, UNIT 1 Rev. 10 - 12/86 2.0-23 J200DCM86092903 t
f-2.3 Meteorological Model 2.3.1
.The atmospheric dispersion for gaseous releases may be calculated using a ground level, wake-split form of the.
straight line flow model.
C 3
X/Q =
atmospheric dispersion (sec/m )'
2.03 6 k
~~
ru I
- Where, distance (a) from release point to location of r
=
interest t
plume depletion factor at distance r from 6
=
i Figure 2.3-1 I*
wind speed at ground level ~(m/sec) a
=
p I
open terrain recirculation factor at distance r,
(
k
=
from page 2.0-34 a + b )\\ or 4 30 j
2 the lesser of (c I
=
f H
a
- Where, 10 vertical standard deviation (m) of the plume at c
=
distance r for ground level releases under the stability category indicated by T, from Figure 2.3-2.
temperature differential with vertical separation i
=
(*K/100m) height of the reactor building = 53.3m.
b
=
GRAND GULF, UNIT 1 Rev. 10 - 12/86 2.0-24 J200DCM86092903
(.
p.
TABLE 2.3-1 fi.
ATMOSPHERIC DISPERSION PARAMETERS
- FOR TECHNICAL SPECIFICATIONS 4.11.2.1.1, 4.11.2.2, 4.11.2.3. 4.11.2.5.1 I'
SECTOR
- MILES XJ Df_g (A) N 0.92 1.333 x 10-8 5.485'x lo-o (B) NNE 0.75 1.129 x 10-s 5.298 x 10-'
l' (C) NE 0.66 9.373 x 10-7 5.821 x 10-8 j
h (D) ENE 2.69 7.358 x 10-s 4.341 x 10-20 (E) E 0.61 8.618 x 10-7 5.135 x 10-8 (F) ESE 4.38 3.206 x 10-s 1.824 x 10-10 (G) SE 1.94 2.628 x 10-7
.1.474 x 10-8 (H) SSE 1.13 7.347 x 10-7 3.587 x 10-8 (J) S 0.50 4.057 x 10-s 1.408 x lo-a (K) SSW 2.33 4.022 x 10-7 8.232 x 10-10 10 (L) SW 0.90 2.653 x 10-8 4.463 x 10-8 i
(M) WSW 5.00 3.931 x 10-7 3.177 x 10-10 (N) W 5.00 4.259 x 10-7 3.716 x 10-10 (P) WNW 4.80 3.164 x 10-7 3.739 x 10-10 10 (Q) NW 5.00 1.584 x 10-7 2.733 x 10-10
(
(R) NNW 0.75 2.199 x 10-s 7.650 x 10-8 l
Reference:
Grand Gulf Nuclear Station, Final Environmental Report, Table 6.1.26, 6.1.28, 6.1.29 and ODCM Table 2.2-3.
Distances shown are actual miles in each sector.
In those cases where X/Q and D/Q were not available from FER Table 6.1.26, they were taken from FER Tables 6.1.28 and 6.1.29 using the closest distance interval to the plant.
GRAND G'JLF, UNIT 1 J200DCM86092903 2.0-26 Rev. 10 - 12/86 i-
2.6 Annual Dose Commitment For the purpose of implementing Technical Specification 3.11.4, the
. annual (calendar year) dose or dose commitment to any MEMBER OF THE i
PUBLIC will be calculated by summing the following doses for the i
1 calendar year:
Direct radiation dose Liquid effluent dose (DTau)
Noble gas dose (D, D )
p Particulate dose (D )
p These calculations are required only if the liquid or gaseous effluents exceed twice the limits of Technical Specifications 3.11.1.2.a 3.11.1.2.b, 3.11.2.2.a, 3.11.2.2.b, 3.11.2.3.a, or, 3.11.2.3.b.
2.6.1 Direct Radiation Dose Measurement Technical Specification 3.11.4 requires the determination of cumulative dose contributions to a MEMBER OF THE PUBLIC from direct radiation from the reactor units and from radwaste storage tanks. This requirement is applicable only under conditions set forth in Specification 3.11.4 Action a.
This determination is made by the utilization of direct radiation measur,ements from indicator thermoluminescent dosimeters (TLDs) located near the 10 GGNS property line in each of the 16 meteorological sectors.
GRAND GULF, UNIT 1 J200DCM86092903 2.0-36 Rev. 10 - 12/86 i
5' &
8 b
k >T@//
////p
/g$'#,
/
IMAGE EVALUATION f[+4 k//77 N
TEST TARGET (MT-3) 4 p,,
'%/,
1.0
'd BM M l 9 El
[.!E EM i,i 4
I23 llM 11 4
150mm 4
6" 4 y
/!b L
+4 Vp
- %*V'Q h
4ie-
T Measurements from these TLDs represent the direct
{:
radiation generated by the facility plus normal r
background radiation. The locations are identified in j
Table 3.0-3 by the following TLD numbers:
M-16 M-22 M-41 M-86 10 M-18 M-25 M-42 M-92 M-19 M-27 M-44 M-93 M-21 M-28 M-45 M-94 4
Control TLDs are also utilized to differentiate between background radiation and direct radiation from the facility. The following seven TLDs are designated as controls based on the criterion that they are located 4
ten miles or greater from the facility. Exact locations are identified in Table 3.0-3.
M-06 M-12 M-14 M-39 M-11 M-13 M-33 The difference between the averaged quarterly radiation measurements of the indicator TLDs and the control TLDs 10 represents the direct radiation dose to a MEMBER OF THE PUBLIC from the operating facility.
l GRAND GULF, UNIT 1 J200DCM86092903 2.0-37 Rev. 10 - 12/86
. - -.