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Docket Nos. 50-424/425 NSV 1919%
MEMORANDUM FOR:
Thomas M. Novak, Assistant Director for Licensing, DL FROM:
Daniel R. Muller, Assistant Director for Radiation Protection, DSI
SUBJECT:
METB INPUT FOR SUPPLEMENT TO THE DRAFT SER FOR V0GTLE, UNIT NOS. 1 AND 2 PLANT NAME: Vogtle Electric Generating Plant, Unit Nos. 1 and 2 LICENSING STAGE:
0L DOCKET NUMBER (S):
50-424/425 RESPONSIBLE BRANCH:
LBt4; M. Miller, LPM As requested in the August 24, 1984 memorandum from E. Adensam and discussed with M. Miller, enclosed is the Meteorology and Effluent Treatment Branch (METB) input for the supplement to the draft SER for Vogtle.
The input addresses Section 15.7.3, which was not included in the METB draft SER input submitted in our October 11, 1984 memorandum.
If there are any questions c.oncerning this submittal, please contact C. Nichols (x27634), Effluent Treatment Systems Section, NETB.
CW.u! s*gned by Dr.niel R. Mulley Daniel R. Muller, Assistant Director for Radiation Protection Division of Systems Integration
Enclosure:
As stated cc:
R. Bernero W. Gammill E. Adensam M. Miller G. Staley C. Willis WP,th:hols DISTRIBUTION:
Docket File 50-424 DocketFile50-425(w/oencl)
METB Docket Files METB Reading File ADRP Reading File FC :DSI:RP:METB :DSI:RP:METB :DSI:RP:METB :
DSI:RP
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METEOROLOGY AND EFFLUENT TREATMENT BRANCH INPUT FOR SUPPLEMENT TO THE SAFETY EVALUATION REPORT FOR V0GTLE ELECTRIC GENERATING PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-424/425 15.7.3 Postulated Radioactive Releases Due to Liquid-Containing Tank Failures The applicant's analysis of the failure of radioactive-liquid-waste tanks located outside the reactor containment that could result in releases of liquid containing radioactive materials to the environs is in FSAR Section 15.7.3.
The NRC staff has reviewed the applicant's analysis and conducted an independent evaluation of this accident, in accordance with SRP 15.7.3.
The principal criteria governing acceptance in the NRC staff review are (1) GDC 60, as it relates to the radioactive waste management systems designed to control releases of radioactive materials to the environment, Tanks and,(2) 10 CFR 20, as it relates to effluents to unrestricted areas.
and associated components containing radioactive liquids outside containment are considered acceptable, by the criteria of SRP 15.7.3, if failure does not result in radionuclide concentrations in excess of the limits in 10 CFR 20, Appendix B, Table II, Column 2, at the nearest potable water supply in an unrestricted area.
Vogtle, Unit Nos.1 and 2, has several radioactive liquid waste processing and storage tanks that are encompassed by the review conducted under 4
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SRP 15.7.3.-
The applicant's analysis postulated the spill of 112,000 gallons of radioactive materials because of failure of the recycle holdup tank.
The accidental releases are assumed to spill from the recycle holdup tank into the auxiliary building, and then to move through postulated cracks in j.
the auxiliary building directly to groundwater and flow toward the Savannah River..The nearest downgradient drinking water source i,s the Savannah River.
Using conservative groundwater parameters, the applicant's analysis concluded that the concentrations of any postulated acc dental release of radioactive effluents from the recycle holdup tank would not exceed 10 CFR 20 limits at the neorest surface water intake.
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The NRC staff's independent analysis ~(th.e hydrologic considerations of w;.ich appear in Section 2.4 above) showed that, with the realistic groundwater travel time of 338 years, all of the radionuclides from the
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Waste Evaporator Concentrate Holdup Tank (WECHT) would be less than the 10 CFR Part 20 requirements at the spring 2800 ft southeast of.the Unit No. 1 containment..Using an ultra conservative groundwater travel time of
.14.8 years, all of the radionuclides from the postulated failure of t'he WECHT, except Co-60, Cs-134 Cs-137, and Sr-90, would be less.than 10 CFR Part 20 requirements at the spring. The steff considered the effects of sorption on the.radionuclide travel time for the four critical nuclides and
, determined that they also would have concentrations at the spring that are 5
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3 small fractions of the 10 CFR Part 20 requirements. Moreover, the nearest j.
potable water supply in an unrestricted area is the Beauford/ Jasper County ir;take 112 river miles downstream.
Ignoring travel time and considering only the combined ground and river water dilution factor of about 140,000, all of the radionuclides from the WECHT postulated failure would have concentrations less than,the 10 CFR Part 20 requirement at the Beauford/ Jasper County intake. Thus, considering both the radioactive decay due to travel in the groundwater and the effects of dilution in the ground and surface water, the concentrations of radionuclides from the postulated tankfailurewouldnotexceedthe10CFRPart,23requirementsatthe nearest potable water supply in an unrestricted area.
The scope of the review included the calculation of radionuclide concentrations in the applicable failed components based upon the expected fuel failure rate for the plant and the effect of site hydrology for those systems that have not been provided with special design features to mitigate the cffects of failures.
Radionuclide concentrations at the nearest potable water supply were found to be acceptable. The basis for acceptance has been that the NRC staff's review shows that the postulated failure of a tank and its associated u
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components would not result in radionuclide concentrations in excess of the limits in 10 CFR 20, Appendix B, Table II, Column 2, at the water source noted above, when evaluated in accordance with SRP 15.7.3.
The applicant has met the requirements of GDC 60 with respect to the control of releases of radioactive materials to the environment by providing controls to reduce the potential impact of the failure of a radioactive liquid-containing tank and its associated components. Such a release will not result in concentrations exceeding the limits of 10 CFR 20, Appendix B, Table II, Column 2, in the unrestricted area.
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