Liquid Metal Fast Breeder Reactor Program. Volume III. Environmental Statement Page: 91 of 622
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Table 6A.1-5
RELEASES IN LIQUID EFFLUENTS DURING 1971 COMPARED WITH PROPOSED DESIGN OBJECTIVESaMixed Fission and Corrosion Products Tritium
Curies Concentration Curies Concentration
Facility Released (Ci/liter) Released (Ci/liter)
PWRs
Indian Point 81 220 725 1890
Yankee Rowe 0.0115 0.041 1685 5940
San Onofre 1.54 2.4 4570 7200
Conn. Yankee 5.88 1.3 5830 7800
Ginna 0.96 1.38 154 210
H. B. Robinson 0.736 11.5 118.3 1860
Point Beach 0.15 0.27 266 450
BWRs
Oyster Creek 12.1 11.3 21.5 78
Nine Mile Point 32.2 69 12.4 27
Dresden 1 6.15 21 8.7 30
Dresden 2 & 3 23.2 17 8.5 30
Humboldt Bay 1.84 11.4
Big Rock Point 3.46 34 10.3 60
Millstone 19.65 26 12.7 18
Monticello 0.014 0.054 0.59 24
aNumerical guides for liquid effluent design objectives in proposed Appendix I of 10 CFR Part 50 are: for radio-
active material except tritium, 5 curies annually and an average concentration of 20 picocuries/liter; and for
tritium, an average concentration of 5000 picocuries/liter.0 C
rn
a
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Liquid Metal Fast Breeder Reactor Program. Volume III. Environmental Statement, report, December 1, 1974; Washington, District of Columbia. (https://digital.library.unt.edu/ark:/67531/metadc1019855/m1/91/: accessed July 16, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.