ML20207P390
| ML20207P390 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 01/08/1987 |
| From: | Bailey J SOUTHERN COMPANY SERVICES, INC. |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| GN-1301, NUDOCS 8701160094 | |
| Download: ML20207P390 (10) | |
Text
.
Southem Company Sennces, Inc.
Poet Offee Box 282 t~aynesboro. Georgia 30830 Telephone 404 7221543 404 7224943 Vogtle Project January 8, 1987 Director of Nuclear Reactor Regulation File: X7BC35 Attention: Mr. B. J. Youngblood Log:
GN-1301 PWR Project Directorate #4 Division of PWR Licensing A U.S. Nuclear Regulatory Commission Washington, D.C.
20555
References:
Letter GN-1242, dated December 16, 1986 Letter GN-1291, dated January 5, 1987 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 (0DCM)
Dear Mr. Denton:
In the first referenced letter, Georgia Power Company committed to utilizing default recirculation values for determination of dispersion and deposition factors and also to using ground-level release parameters for plant vent releases in the east and east-northeast sectors.
In recent discussions with your staff, your staff requested the marked-up pages that will incorporate these commitments in the next revision of the ODCM.
Attached please find those marked-up pages.
The information in this letter supercedes the information of the second referenced letter.
If your staff requires any additional information, do not hesitate to contact me.
Sincerely, k.
J. A. Bailey Project Licensing Manager MSH:rbs Attachments xc:
R. E. Conway NRC Regional Administrator R. A. Thomas NRC Resident Inspector J. E. Joiner, Esquire D. Feig e
B. W. Churchill, Esquire R. A. McManus l
ct M. A. Miller (2)
L. T. Gucwa po B. Jones Vogtle Project File Li gI G. Bockhold, Jr.
~
B701160094 870108 PDR ADOCK 0500 4
A
8.
Estimating Acquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I, U. S. NRC Regulatory Guide 1.113, Rev.1 (April 1977).
9.
Vogtle Nuclear Plant, Units 1 and 2, Waste Water Effluent Discharge Structure Plume Analysis; Georgia Power Company; April 1981.
10.
Direct communications with Water Resources Division; U.S.
Geological Survey; U. S. Department of Interior; February 1985.
11.
Water Resources Data, Georgia, Water Year 1983; U. S.
Geological Survey, Water - Data Report GA-83-1; W. R.
Stoke III, T. W. Hale, J. L. Pearman, and G.
R. Buell; June 1,d4.
I i
12.
Vogtle Electric Generating Plant Land Use Survey - 1986; 2
j Georgia Power Company; April 1986.
13.
Letter to Georgia Power Company from Pickard Lowe, and 2
Garrick, Inc. ; Washington, D.C. ; October 30, 1986.
December I&
14.
Kahn, Bernd, et. al; " Bioaccumulation of P-32 in Bluegill 2
and Catfish"; NUREG/CR-3981 (February 1985).
l (5-Sagendecf, e t. ali " xoQ.paQ : con p ter Pc, can hr S e biete.colgical tTValwation of Sowh o e E luenf kele.arer at Nucl<ar Po we r %Es ons " j tJVMG (SepVambarIR8.2) l
1-SECTION 2 GASEOUS EFFLUENTS At Plant Vogtle there are five potential points where radioactivity is released to the atmosphere in gaseous discharges.
These five potential release points are:
Unit 1 plant vent; Unit 2 plant vent; Unit 1 and Unit 2 turbine building vents, which are not normal release pathways until a primary to 2
I secondary leak exists; and the radwaste solidification building vent.
The turbine building vent serves as the discharge point for the condenser air ejector and steam packing exhauster-system.
The fuel handling building is common to both units however ventilation from this area is through the Unit 1 plant vent.
Certain components of the Gaseous Waste Processing System are shared between the' two units and releases from this system are through th'e Unit 1 plant vent.
Containment building release 5 are through the respective plant vents.
Gaseous releases from the turbine building vents and the radwaste solidification building vent are considered to be ground-level releases.
Gaseous releases from the plant vents are considered to be mixed-mode releases as determined by the wake-split model.
All five release points are considered to be continuous leases.
In the absence of confirmed primary to l
secondary' le k (s), the turbine building vents are not release Points.
(gee fqg7g ;n g4,cp,,n,2, g2) l Gaseous effluent monitor setpoints are required only
~
for noble gas monitors serving the five release points.
Methodology for calculating noble gas monitor setpoints is presented in Subsection 2.1.
Although setpoint calculations are not required for radioiodine and particulate monitors, the methodology for assuring the potential organ dose rates due to radioiodines, tritium, and particulates in gaseous releases from the nite do not exceed the limits of Technica1' Specification 3.ll.2.1(b) is presented in the NOTE in Subsection 2.2.1.2.
2-1 r
-v
where I
Li skin dose factor due to beta emissions from
=
3 radionuclide 1 (ares /yr per uCi/m ) from Table 2.1-1.
mrem skin dose per arad air dose.
I 1.1
=
i air dose factor due to gamma emissions from M
=
3 radionuclide 1 (arad/yr per uCi/m ) from Table 2.1-1.
2.1.2 Unit 1 Plant Vent and Unit 2 Plant Vent Monitors:
RE12442C (Unit 1) and RE12442C (Unit 2)
Gaseous releases from the plant vent (s) are regarded as mixed-mode releases in that under certain conditions of vent exit velocity and meteorological conditions, the plume will behave as' an elevated release.
Under other conditions of vent exit velocity and meteorological conditions, the plume will behave as a ground-level release.
Using the wake-split model, dispersion values have been calculated utilizing expected annual average conditions. ( 3cc A/DTE belod).
l l
However, since setpoints for plant vent monitors must be established to ensure that the limits of Technical Specification 3.11.2.1.a will not be exceeded at any point in 2
time, the ground level dispersion value used in Subsection 2.1.1 is also used in'the calculation of setpoints for plant vent monitors.
NOTE: DekLt cec n(culde on Valwe s are "S h eed S
fe+erm.nahon d &qe rca on and clqosdion &c+o rg &c calc u l 4c n of the N-s i te < fh e t E a r eo as Aluents-3 Crcowad -level re lease parame +ers are use d for plaat denf eclearer m the ca.s.f and carf -,uc% e as t sec tues ( rech in wk c h We eco hng +a ssrc are lo ca4ed) +
a c csu nt for a-ny f ofen6 cJ c,,, r, n g +~e g_,wa ke.c ffe cts.
l I
.g,--.
_,,mm_,-_-.m.,.-.y.,,-_,.y.~,.,-......w..,_-.._.4._,
2.2 GASEOUS EFFLUENT DOSE RATE AND DOSE CALCUIATIONS 2.2.1 Dose Rates at or beyond Site Boundary i
2.2.1.1 Dose Rates Due to Noble Gases For the purpose of implementing Technical Specification
- 3. ll. 2. l(a), the dose rate in areas at or beyond the site boundary due to noble gases shall be calculated as follows:
t total body dose rate at time of release D
=
(arem/yr)
I (O
!OI Kg (Qg,) na I14) 2 G
i lg ng M
D
= skin dose rate at time of release (arem/yr) s
+
(27Q I i+
g g
M i} I im nm (X/Q)G ng (Lg + l.lM ) (Qg)
(15) 2 Where ng is the number of simultaneous ground-level l
vent releases and nm is the number of simultaneous 2
mixed-mode vent releases.
Other terms were defined Previously in Subsection 2.1.
l The dose rate limits are sita limits at any point in time; therefore, dose rates are summed over all gaseous releases occurring simultaneously.
For Plant Vogtle, Unit 1 turbine-building vent, Unit 2 turbine building vent, and radwaste solidification luilding vent are ground-level releases.
Unit 1 plant vent and Unit 2 plant vent are mixed-mode releases.
However, since the limits of Technical Specification 3.11.2.1 apply at any point in time, ground-level dispersion values are 2
used in lieu of mixed-mode values as discussed in Subsection 2.1.2. ( Se e tJO T E m 46recf on 2.(.2),
2-17
Pgo = K' (BR) DF (17) go and where 6
K' constant of unit conversion, 10 pci/uCi
=
breathing rate for child age group; 3700 BR
=
3 m /yr from Table 2.2-10 DFio =
inhalation pathway dose factor for child age group for organ o and radionuclide i, from Table 2.2-2)
NOTE:
In order to assure that potential dose rates (pre-release) to an organ due to I-131, I-133, tritium, and particulates in simultaneous gaseous releases from the site do not exceed 1500 aren/yr as specified in Technical Specification 3.ll.2.'. (b),
the potential organ dose rate D must be limited o
as follows:
D 1 (AG) (SF) 1500 mrea/yr (18) o where AG and SF are assigned the same values as were used in Subsection 2.1 for the gaseous discharge pathway under consideration.
To further ensure that dose rate limits were I
not exceeded (post-release), dose rates from simultaneous releases should be summed, as shown in equation (16) above.
2.2.2 Air Doses and Doses to a Member of the Public at or beyond the Site Boundarv i
(See dote m kbse c& 1 I 1) 2-19
_ _ _. _, _.. _. ~ _ _. _ _...... _. _.. _ _..
1 2.3 METEOROLOGICAL MODEL 13,15 (Reference 7[andSection2.3.5ofReference5) t 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 radweste solidificatMn building vent.
Releases from reactor building (s)
(plant) vent (s) are considered to be mixed-mode. (fee PJOTE m hbrec6 on 2. I.2).
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
[
"ik 2.032 d
=
9 p jk Nujk
- Izk (RL F) where (2/rr)b divided by the number of radians in a 2.032
=
0 22.5 sector (0.3927 radians).
1 d
plume depletion factor for all radionuclides
=
p other than noble gases at 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 factor is unity.
Only depletion by deposition is considered since depletion by decay would be of little significance at the distances considered.
ofen 4ercaon ce c n ecal a.S on $a c hor. Va lun h,oe RCF
=
S pe c ks c 2-75 dt Na n ces are vbhNu n e ck hro m Ps ce 5 2-S lle[e (4 nc e 'E -
3.1416 Tr
=
b
~
maximum height of adjacent plant structure
=
(55 meters).
2.3.1.2 Mixed-Mode Releases (X/Q) M the mixed-mode sector-averaged relative
=
concentration for a given wind direction 3
(sector) and distance (sec/m )
(REF)
{ Edh E
I Y
2.032 dp jk "*."jk zk I
=
1 ff exp(-h /2r2)
(39) 2
+[jkzk 2k where plume depletion factor for all radionuclides d
=
p other than noble gases at a distance x shown in Figures 2.3-3 through 2.3-5 for elevated releases; for noble gases the depletion factor is unity.
If an undepleted relative concentration is desired, the depletion factor is unity.
Only depletion by l
deposition is considered since depletion by decay would be of little significance at the l
distan(*s considered.
I Ujk wind sg i extrapolated to the effective
=
release right; extrapolation is accompi und by raising the ratio of the two i
1 I
heights to the n power where n = 0.25, 0.33, and 0.5 for unstable, neutral, and stable conditions, respectively. (Reference 5, l
Section 2.3.5).
l l
l 2-77 l'.__. _. _ _. _.. _, _ _. _. - _... _ _ _,. _. _.. _. _.,. _
2.3.2 Relativo D0 position HLt NOTC in % 6rech n Ll.2h 2.3.2.1 Ground-Level Releases (D/Q)G the ground-level sector-averaged relative
=
deposition at a given distance and for a 2
given sector (1/m ),
2.55 D n
f{k q
k (42)
Nx where 2.55 =
the inverse of the number of radians in a 22.5 sector (2ff/16)~1 0
deposition rate at a given distance, taken D
=
g from Figure 2.3-6 for ground-level releases.
nk the number of hours the wind is directed into,
=
the sector of interest, during which time stability category k exists.
the total number of hours of valid N
=
meteorological data.
fura in rec t realah$ on Schr.\\lalwe5 RCF
=
a en or spe c:Fic dMance a re An,nad from F; pre 3.2 of Reftreus (5.
J 2-80
2.3.2.2 Mixrd-Mods R71conon (D/Q)M the mixed-mode sector-averaged relative j
=
deposition at a given distance and for a given sector (1/m ),
2 i
- 2. 5 4((E) (D ) + (1 - E) D,)
(43)
=
9 (VCF) 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.
Other terms were defined in previous Subsections.
)
2-81
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