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UNITED STATES
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'4435 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 GASEOUS SOURCE TERMS FOR V0GTLE ELECTRIC GENERATING PLANT, UNIT NOS. 1 AND 2 PLANT NAME: Vogtle Electric Generating Plant, Unit Nos. I and 2 LICENSING STAGE: OL DOCKET NUMBER (S):
50-424/425 RESPONSIBLE BRANCH: LB#4; M. Miller, PM REVIEW STATUS:
Continuing Gaseous effluent releases were reevaluated incorporating updated assumptions concerning inputs to the volume reduction system and DFs for the volume Adjustments were made in iodine and all nuclides releases reduction system.
in particulate form in gaseous effluents from the radwaste solidification building vent.
See enclosure.
Questions concerning the source terms should be addressed to C. Nichols (x27634), cognizant engineer assigned to this facility.
lush &
Charles A. Willis, Leader Effluent Treatment Systems Section Meteorology and Effluent Treatment Branch
Enclosures:
As stated cc:
D. Muller (w/o encis)
W. Gammill M. Miller J. Swift I. Spickler C. Nichols 8601030160 B51127 PDR FOIA
'BELLB4-663 PDR N
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Table 0-1 (continued)
I i
Radwaste I
Radwaste solidification
/
solidification i,
Nuclide l
building vent Nuclide building vent H-3
/
2.3+02 Te-127 8.1: 05
- 4. 5 6' A f Cr-51
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4--3E-05 2 i g - o Y Te-129 ME:45
- f. 6 E -O V Mn-54 7-5E-06 3 9 6-07 Te-129m 34E C-6 1 7 f -# V Fe-59 3-9E- 05 /. x G -0 9 Te-131 3.-3E-3
' 8 6 -h V Fe-58 l
2.3E-05 Te-131m W5 2.,) f - OV Co-58
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3-eE-e+- 2.o f - e 3 Te-132 3 cE ^'
3./ 6-A l Co-60 4.4E--05 2 6 t? -b %
I-130
'r-5 "3-2.tE-O4 8r-83 4 5 f-04 S.05-42 C N7 I-131
- 2. :: 51 3,1 F- 0 2-Rb-86 7.2E-09 I, (, f - O ')
I-132 2 ^: 22 i, o l' -d 2,
~
Sr-89 S--SE-96 Y.3t-W I-133
N 2 2 Ya 6 -0 '2-
~
,'.u i.s's-L7 4U C 'O 3.-C-E-7 f.3F-06 I-134 W5 y-go
- 1. c+-s-7 2.2 E-9 7 I-135 1.2E-02 f.9 E 'O 1
-->S r-9 0 Y-91 6E-06 s. 0 E -O f Cs-134 2.4 E-3 4/2:~:-4.3 Y-9.4E=.0 7 3 7 6 -Of Cs-136 1.6E-03
. 3 L- - c.3 m
Si d '., l r 91m 95 1-E-46 7.y 6-v6 Cs-137 1.36-43 3.Gf-03 Nb-95 1-GE-06 6 1c-A-Ba-137m 1 -5E-03
- 3. M -D 3
~
Mo-99 1-E47 4.IE-93 Ba-140 ME--36 2. 7 t" - A),
Tc-99m 14J43
- f. P E - v3 La-140 4.-tf~t6 1,at,-Sp Ru-103 14,'.
E ;. E - 6 Ce-141 1--6E46 h le h,
o s
Ru-106 34EJ
/. M - N-Ce-1;3 34-E =47 v.I6-06 Rh-103nt le;; 0; f.i-i-;'6-Ce-144 S -GE--97 Y. / 'l - ^'~
Rh-106 3-eE-07 I. 3 t? -0 4.
Pr-143 1
06
?. 0 E -26 Te-125 7.0E-07 P r-144 S -4EW Y ' E 6 Tty [Te-127m 6246-06 7..ff-0.f Np-239 1.4E-05 f.,36-tp Total Kr and Xe. 4200Ci Total Iodine and particulates (excluding H-3 and C-14), 0.53 Ci "All releases should be. considered continuous.
- Plant vent.
0 3.0E+00 = 3x10
- Exponential notation:
TFor the C-14 dose releases, 7 Ci/yr/ reactor is attributed to an annual release duration of 700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br />, and 1 Ci/yr/ reactor is attributed to continuous releases.
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