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Docket File 50-424 Docket File 50-425 (w/o enc AUG 011984 METB Docket Files METB Reading File CAWillis Docket Nos. 50-424/425 MEMORANDUM FOR:
Edward F. Branagan, Jr., Leader Radiological Impact Section, RAB FROM:
Charles A. Willis, Leader Effluent Treatment Systems Section, METB
SUBJECT:
REVISED LIQUID AND GASE0US SOURCE TERMS FOR V0GTLE ELECTRIC GENERATING PLANT, UNIT NOS. 1 AND 2 PLANT NAME: Vogtle Electric Generating Plant, Unit Nos.1 and 2 LICENSING STAGE: OL DOCKETNUMBER(S):
50-424/425 RESPONSIBLE BRANCH:
LB#4; M. Miller, PM REVIEW STATUS:
Continuing Gaseous and liquid effluent releases were reevaluated considering data on iodine species distributions, including particulate, in the volume reduction system. Adjustments were made in the iodine releases in liquid
. effluents and in iodine and all nuclides releases in particulate form in gaseous effluents from the radwaste solidification building vent.
Questions concerning the source terms should be addressed to C. Nichols (x27634), cognizant engineer assigned to this facility.
Originsi nisnad by&
Cryudo E tdicho\\S bf' Charles A. Willis, Leader Effluent Treatment Systems Section Meteorology and Effluent Treatment Branch
Enclosures:
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As stated cc:
D. Muller (w/oencis)
W. Gammill M. Miller J. Swift I. Spickler C. Nichols 2405 ogk m
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CALCULATED RELEASES OF RADI0 ACTIVE MATERIALS IN LIQUID EFFLUENTS FROM V0GTLE ELECTRIC GENERATING PLANT, UNIT N05. 1 AND 2
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Nuclide Ci/Yr/ Reactor Nuclide Ci/Yr/ Reactor Corrosion & Activation Products Fission Products (Cont'd)
Cr-51
.00016 Te-132
.00130 Mn-54
.00100 I-132
.01800 Fe-55
.00015 I-133
.05400 Fe-59
.00009 Cs-134
.03200 Co-58
.00550 I-135
.00730 Co-60
.00890 Cs-136
.00800 Zr-95
.00140 Cs-137
.03800 Nb-95
.00200 Ba-137m
.01300 Np-239
.00005 Ba-140
.00002 La-140
.00002 Fission Products Ce-144
.00520 All Others
.00006 Br-83
.00003 Rb-86
.00006 Total
.27000 Sr-89
.00003 (except tritium)
.00390 Tc-99m
.00330 Tritium release 610 i
Ru-103
.00014 Ru-106
.00240 Ag-110m
.00044 Te-127m
.00003 Te-127
.00003 Te-129m
.00012 Te-129
.00008 I-130
.00017 Te-131m
.00006 Te-131 *
.00001 I-131'
.10000 t
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Page 1 of 2 CALCULATED RELEASES OF RADIOACTIVE MATERIALS IN GASE0US EFFLUENTS FROM V0GTLE ELECTRIC GENERATING PLANT, UNIT NOS. 1 AND 2 Ci/Yr/ Reactor (All releases should be considered continuous except as noted)
Waste Gas Building Ventilation Air System Reactor Auxiliary Ejector Total Nuclide (PV)
(PV)
(PV)
Turbine Exhaust PV a
Kr-83m O.
3.0E+00 0.
O.
O.
3.0E+00
- Kr-85m O.
3.1E+01 2.0E+00 0.
1.0E+00 3.3E+01 Kr-85 2.5E+02 5.0E+00 0.
O.
O.
2.6E+02 Kr-87 0.
7.0E+00 1.0E+00 0.
O.
8.0E+00 Kr-88 0.
4.4E+01 4.0E+00 0.
- 3.0E+00 4.8E+01 Kr-89 0.
O.
O.
O.
O.
O.
Xe-131m 3.0E+00 1.3E+01 0.
O.
O.
1.6E+01 Xe-133m O.
6.4E+01 2.0E+00 0.
1.0E+00 6.6E+01 Xe-133 1.0E+00 3.4E+03 1.1E+02 0.
7.0E+01 3.5E+03 Xe-135m O.
O.
O.
O.
O.
O.
Xe-135 0.
1.3E+02 7.0E+00 0.
4.0E+00 1.4E+02 Xe-137 0.
O.
O.
O.
O.
O.
Xe-138 0.
1.0E+00 1.0E+00 0.
O.
2.0E+00 4
I-131 0.
1.8E-02 4.5E-03 1.3E-03 2.8E-02 2.3E-02 I-133 0.
2.1E-02 6.4E-03 1.4E-03 4.0E-02 2.7E-02 8.2E+02 H-3 b
C-14 8.0E+00 A-41 2.5E+01 PV = Plant Vent 0
aExponential notation; 3.0E+00 = 3x10,
bFor the determination of the "P" factor in C-14 dose calculations, 7 Ci/Yr/ Reactor should be attributed to an annual release duration of 400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br />, and 1 Ci/Yr/ Reactor should be attributed to continuous releases.
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Page 2 of 2 CALCULATED RELEASES OF RADI0 ACTIVE MATERIALS IN GASEOUS EFFLUENTS FROM V0GTLE ELECTRIC GENERATING PLANT, UNIT N05. 1 AND 2 Ci/Yr/ Reactor (All releases should be considered continuous except as noted)
Waste Gas Building Ventilation System Reactor Auxiliary Total Nuclide (PV)
(PV)
(PV)
PV 8
'4.5E-05 2.2E-04 1.8E-04 4.5E-04 Fe-59 1.5E-05 7.4E-05 6.0E-05 1.5E-04 Co-58 1.5E-04 7.4E-04 6.0E-04 1.5E-03 Co-60 7.0E-05 3.4E-04 2.7E-04 6.8E-04 Sr-89 3.3E-06 1.7E-05 1.3E-05 3.3E-05 Sr-90 6.0E-07 3.0E-06 2.4E-06 6.0E-06 Cs-134 4.5E-05 2.2E-04 1.8E-04 4.5E-04 Cs-137 7.5E-05 3.8E-04 3.0E-04 7.6E-04 Radwaste Solidification Radwaste Solidification Nuclide Building Vent Nuclide Building Vent H-3
_2.3E+02 Te-127 8.IE-06 Cr-51 4.3E-05 Te-129 2.1E-05 Mn-54 7.5E-06 Te-129m 3.2E-05 Fe-59 3.9E-05 Te-131 3.3E-06 Fe-58 2.3E-05 Te-131m 1.8E-05 Co-58 3.8E-04 Te-132 3.8E-04 Co-60 4.9E-05 I-130 1.3E-03 Br-83 9.0E-07 I-131 2.6E-01 Rb-86 7.2E-06 I-132 2.0E-02 l
Sr-89 8.3E-06 I-133 9.7E-02
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Sr-90 3.0E-07 I-134 1.5E-05 Y-90 1.0E-07 I-135 1.2E-02 Y-91 1.6E-06 Cs-134 2.4E-03 i
Y-91m 9.0E-07 Cs-236 1.0E-03 Zr-95 1.4E-06 Cs-137 1.8E-03 l
Nb-95 1.2E-06 Sa-137m 1.6E-03 t
Mo-99 1.1E-03 Ba-140 4.6E-06 Tc-99m 1.0E-03 La-140 4.4E-06 Ru-103 1.1E-06 Ce-141 1.6E-06 Ru-106 3.0E-07 Ce-143 3.0E-07 Rh-103m 1.1E-06 Ce-144 8.0E-07 Rh-106 3.0E-07 Pr-143 1.1E-06 Te-125 7.0E-07 Pr-144 8.0E-07 Te-127m 6.7E-06 Np-239 1.4E-05
' Exponential notation; 4.5E-05 = 4.5x10-5,
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