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 q A PDR
l 2.3 METEOROLOGICAL MODEL (Reference 7 and Section 2.3.5 of Reference 5) l 2.3.1 Atmospheric Dispersion l 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 (sector) and distance. (sec/m3) t
=lpF).032 dph % (38)
Nu jk x2 zk where 2.032 = (2/fr )b divided by the number of radians in a 22.5 0 sector (0.3927 radians).
i dp = plume depletion factor for all radionuclides 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.
gcF open 4cceain recicculch ma q, c ayycn a cc apm. n&ca h.6/wah n
-ra bl e 2 3 - 1.
Tr = 3.1416 b = maximum height of adjacent plant structure
(}
(55 meters).
2.3.1.2 Mixed-Mode Releases (X/Q) M
= the mixed-mode sector-averaged relative concentration for a given wind direction (sector) and distance (sec/m3)
=
(9J:f')r t _n1h " E 2.032vdp [k "* . jkIzk *
+hy exp(-h2 /2r2) zk (39) where dp = plume depletion factor for all radionuclides
(} 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.
= wind speed extrapolated to the effective Ujk 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 l
l
l 2.3.2 R71ative Dnposition 2.3.2.1 Ground-Level Releases O
= the ground-level sector-averaged relative (D/Q)G deposition at a given distance and for a given sector (1/m 2),
2.55 D q n k A {k Nx (42) where 2.55 = the inverse of the number of radians in a 22.5 0 sector ( 2 ff /16 ) -1..
Dg = deposition rate at a given distance, taken from Figure 2.3-6 for ground-level releases.
= the number of hours the wind is directed into, nk the sector of interest, during which time O stability category k exists.
N = the total number of hours of valid meteorological data.
RCF = opn herra,o (gc,kcgla Q [ac r. h la u t- 5(u :Fe Gr+- en a<e Ma;na (<n Ta b t e 2 3 -2.
9 O
2-80
l
- . 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 given sector (1/m 2),
= 2. '
((E) (D g ) + (1 - E) D,) (43) where ,( flC F)
Dg = relative deposition rate for the ground-level 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.
E = fraction of releases considered as ground- !
level.
Otl.er terms were defined in previous Subsections.
I l
l l
l O
2-81 l
l
s.
- A.5-L i
TABLE [.GPENTERRAINCORRECTIONFACTORf*
- 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 The factor is linearly use a factoe between 4 and 1.7.
interpolated based on actual distance.
Distances from 1.0 through 3.0 miles in all direction sectors
- 3. The factor is linearly use a factor between 1.7 and 1.4.
inurpolawa based on actuti af stanse.
- 4. Distances from 3.0 through 5.0 miles in all d{recion sectors use The factor is linearly a faster between 1.4 and 1.0, istances.
interpolated based on actual d .
O *From NUREG/CR-2919, X00D00: Computer Program for the Meteorotoff ael Evaluation of Routine Effluent Releases at Nuclear Power Stations, figure 3.1.
6 8
eD e , e
.2 -.13 A
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