ML20214G578
| ML20214G578 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 05/03/1972 |
| From: | Miner S US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Clark R US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| CON-WNP-0127, CON-WNP-127 NUDOCS 8605220295 | |
| Download: ML20214G578 (3) | |
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1972 To Files smU Robert A. Claat, Chief, Boiling Mater Rosatore Branch No. 3, Division of Rosetor Licensing 6 TO WPSB FtR SOERCE W N Er GAK RIDGE A rough evaluation of the VFFSS Weste Ons System Design by tha Effluent Systes Branch indicates there any be a factor of 2 to 3 difference in the decay tiens between the WPAS design and the ABC evaluation. The site doses were not estimated. The differenees were discussed with the applicant but he is not prepared at the present time to present the data on which he based his design.
Therefore, his answers to the waste gas source tera questions of May 1, 1972 will reflect his design basis wheroes the Oak Ridge source tones will be based on our design model.
If durias the safety review of the Waste Oss System the amicu-lated boundary doses are above Appendix I Wrfes will either have to provide experimental data to substantiate their design or change their waste gas system. If either of these approaches are required the radiosotive gas source teras for the environmental report will not reflect design conditions and will require recal-i culation. This could result in a schedule delay.
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A. 01 ark, Chief, Boiling Water Benetore Bmash Bo. 3, vision of Reneter Meeneing i
p to MR 3033 W GM Er eg arman A taiok and mush evaluation of the WWES unste Gas Areten design by the Effluent S em Brsnch indicates there may be a factor of 2 to 3 difference in he decay times attributable to the 07 charcoal delay beds be ween the WPSB design and the ABC evaluation.
The site doses were not stimated. The differsooes were discussed with the applicant but be a not prepared at the present time to present the data on which beoed his design. Therefore, his s
answers to the waste saa sour teru question of May 1, 1972 will reflect his design basis who the Oak Ridge souros terms will be based on our design model.
If during the safety review of the to Oas Bretes the boundary doses are calculated to be above ix I requirements WWGS will either have to provide experimenta data to substantiate their design or change their waste gas system.
f either of these approaches are required the radioactive gas source for the environmental report will not reflect design conditions will require recal-culation. This could result in a schedule de Distribution:
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%n e MAY 3 1972 To Filen Rcbert A. Clark, Chief, Rolling Water Reactcra Eranch fic, 3,'l(p La~I-TIUiU :
Divicion of Reuctor Licenaing QUESTIO:;S TO WPPSS FOR SOURCE TERM CALCULATIO!;S BY OAK RIDGE A rcugh evaluatica cf the WPPSS Waste Gac System Design by the Effluent Syctem Franch indicates there may be a factor of 2 to 3 difference in the decay timeu between the WPPSS design and the AEC evaluation. The site doses were r.ct estimated. The differences were diccusael with the applicant but he is not prepared at the preaent time to precent the data en which he based his design.
Therefore, his annvers to the vaste gas ccurce term questions of May 1, l'G2 vill reflect his design tasic whereas the Oak Ridge uoarce ter=> vill be bocel en our design model.
If dari r t hc aarety review of the Wast e Gas System the calcu-lated boundary dcaec are atcve Appendix I WPPSS will either have to trovide experitental data to cuoatantiate their design or change their vaste gas cyatem. If either of these approaches are requirei the ralicactive cas cource terms for the envircnmental report will not reflect design conditiens and will require recal-culatlen. Tnia coaltl recult in a achelule delay.
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^3 Sydney Miner Ecilinc Water Reactora branch No. 3 Divisien of Reactor Licencing I'