ML20207P384
| ML20207P384 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 01/05/1987 |
| From: | Bailey J GEORGIA POWER CO., SOUTHERN COMPANY SERVICES, INC. |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| GN-1291, NUDOCS 8701160089 | |
| Download: ML20207P384 (6) | |
Text
Georgia Fbwer Company Fbst Offica Box 282 Waynesboro, Georgia 30830 Telephone 404 554-9961 404 724-8114 Southern Company Services, Inc.
Fbst Office Box 2625 Birmingham, Alabama 35202 Telephone 205 8704011 VOgtle Project January 5, 1987-Director of Nuclear Reactor Regulation File:
X7BC35 Attention: Mr. B. J. Youngblood Log:
GN-1291 PWR Project Directorate #4 Division of PWR Licensing A U. S. Nuclear Regulatory Commission Washington, D.C.
20555
Reference:
Letter GN-1242, dated December 16, 1986 NRC DOCKET NUMBERS 50-424 AND 50-425 CONSTRUCTION PERMIT NUMBERS CPPR-108 AND CPPR-109 V0GTLE ELECTRIC GENERATING PLANT - UNITS 1 AND 2 0FFSITE DOSE CALCULATION MANUAL
Dear Mr. Denton:
In the referenced letter, Georgia Power Company committed to revising certain meteorological parameters with respect to default recirculation values and ground-level parameters.
In recent discussions _with your staff, Georgia Power Company was asked to provide marked-up pages of the ODCM with the proposed changes dealing with the above mentioned meteorological parameters. Attached please find those marked-up pages.
These changes will be incorporated in the next revision of the ODCM.
If your staff requires any additional information, do not hesitate to contact me.
Sincerely,
. h.
J. A. Bailey Project Licensing Manager JAB /ddd Attachments xc:
R. E. Conway NRC Regional Administrator R. A. Thomas NRC Resident Inspector J. E. Joiner, Esquire D. Feig
[000 B. W. Churchill, Esquire R. A. McManus M. A. Miller (2)
L. T. Gucwa fl B. Jones Vogtle Project File G. Bockhold, Jr.
rt701160089 870105 PDR ADOCK 05000424 A
PDR q
2.3 METEOROLOGICAL MODEL (Reference 7 and Section 2.3.5 of Reference 5) 2.3.1 Atmospheric Dispersion Atmospheric dispersion (long-term) may be calculated using the appropriate form of the sector-averaged straight line flow Gaussian model.
Gaseous releases are considered to be either ground-level or mixed-mode.
Considered as ground-level are releases from the turbine building (s) vents and the radwaste solidification building vent.
Releases from reactor building (s)
(plant) vent (s) are considered to be mixed-mode.
9 2.3.1.1 Ground-Level Releases (X/Q)g the ground-level sector-averaged relative
=
concentration for a given wind direction 3
(sector) and distance. (sec/m )
t
=lpF).032 dph Nu (38) x2 jk zk where (2/fr )b divided by the number of radians in a 2.032
=
0 22.5 sector (0.3927 radians).
i d
plume depletion factor for all radionuclides
=
p other than noble gasen a.t a distance x shown in Figure 2.3-2 for ground-level releases; for noble gases the depletion factor is unity.
If an undepleted relative
)
concentration is desired, the depletion f
factor is unity.
Only depletion by deposition is considered since depletion by decay would be of little significance at the distances considered.
4cceain recicculch m &c h.6/wah gcF open ma q, c ayycn a cc ap. n a n
-ra bl e 2 3 - 1.
Tr
=
3.1416
(}
maximum height of adjacent plant structure b
=
(55 meters).
2.3.1.2 Mixed-Mode Releases (X/Q) M the mixed-mode sector-averaged relative
=
concentration for a given wind direction 3
(sector) and distance (sec/m )
(9J:f')r _n1h E
t 2.032vdp [k "*
. jk zk I
=
+hy exp(-h /2r2)
(39) 2 zk where
(}
d plume depletion factor for all radionuclides
=
p other than noble gases at a distance x shown in Figures 2.3-3 through 2.3-5 for elevated releases; for noble gases the depletion factor is unity.
If an undepleted relative concentration is desired, the depletion factor is unity.
Only depletion by l
deposition is considered since depletion by decay would be of little significance at the distances considered.
Ujk wind speed extrapolated to the effective
=
release height; extrapolation is accomplished by raising the ratio of the two heights to the n power where n = 0.25, 0.33, and 0.5 for unstable, neutral, and stable conditions, respectively. (Reference 5,
()
Section 2.3.5).
i i
2-77
2.3.2 R71ative Dnposition Ground-Level Releases O
2.3.2.1 (D/Q)G the ground-level sector-averaged relative
=
deposition at a given distance and for a 2
given sector (1/m ),
2.55 D n
A {k q
k (42)
Nx where 2.55 =
the inverse of the number of radians in a 22.5 sector ( 2 ff /16 ) -1..
0 deposition rate at a given distance, taken D
=
g from Figure 2.3-6 for ground-level releases.
nk the number of hours the wind is directed into,
=
the sector of interest, during which time O
stability category k exists.
the total number of hours of valid N
=
meteorological data.
RCF =
herra,o (gc,kcgla Q [ac
- r. h la u opn t-5(u :Fe Gr+- en a<e Ma;na (<n Ta b t e 2 3 -2.
9 O
2-80
l 2.3.2.2=
Mixed-Modo Raincons (D/Q)M the mixed-mode sector-averaged relative
=
deposition at a given distance and for a 2
given sector (1/m ),
2.
((E) (D ) + (1 - E) D,)
(43)
=
g
, flC F)
(
where relative deposition rate for the ground-level D
=
g portion of mixed-mode releases from Figure 2.3-6.
D, relative' deposition rate for the elevated
=
portion of mixed-mode releases from Figures 2.3-7 through 2.3-9.
fraction of releases considered as ground-E
=
level.
Otl.er terms were defined in previous Subsections.
I l
l l
l O
2-81 l
l
s.
A.5-L TABLE [.GPENTERRAINCORRECTIONFACTORf*
i 1.
Distances of c through 1 miles in all alrection seuturs use a factor of 4.0.
2.
Distances from 1.0 through 2.0 miles in all direction sectors use a factoe between 4 and 1.7.
The factor is linearly interpolated based on actual distance.
Distances from 1.0 through 3.0 miles in all direction sectors 3.
use a factor between 1.7 and 1.4.
The factor is linearly inurpolawa based on actuti af stanse.
Distances from 3.0 through 5.0 miles in all d{recion sectors use 4.
The factor is linearly a faster between 1.4 and 1.0, istances.
interpolated based on actual d O
Computer Program for the Meteorotoff ael
- From NUREG/CR-2919, X00D00:
Evaluation of Routine Effluent Releases at Nuclear Power Stations, figure 3.1.
6 8
eD e
, e
.2 -.13 A
--