Document: NUREG-0800
Document ID: faf774de-7226-41f8-ba11-7cf612907af6
Document Type: srp
Title: GASEOUS WASTE MANAGEMENT SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1306/ML13065A119.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.3
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Content:
�� August 2014 A. Regarding Sections II.B and II.C of Appendix I, the staff has considered releases of radioactive material in gaseous effluents for normal operation, including AOOs, based on expected amounts and concentrations of gaseous wastes over the life of the plant for each reactor on the site. The staff has determined that the proposed GWMS is capable of maintaining releases of radioactive materials in gaseous effluents such that the calculated individual doses in an unrestricted area from all pathways of exposure are less than 0.05 mSv (5 mrem) to the total body or 0.15 mSv (15 mrem) to the skin and less than 0.15 mSv (15 mrem) to any organ from releases of radioiodines, tritium, carbon-14, and radioactive materials in particulate form. B. The staff has determined that the calculated air doses from gaseous effluents at any location near ground level that could be occupied by individuals in unrestricted areas will be less than 0.01 cGy (10 millirads) for gamma radiation and 0.02 cGy (20 millirads) for beta radiation. C. Regarding the ALARA provisions of Section II.D of Appendix I, the staff has considered the potential effectiveness of augmenting the proposed GWMS using reasonably demonstrated technology, and determined that further gaseous effluent treatment will not effect reductions in cumulative population doses within an 80-km (50-mile) radius of the reactor, and the proposed GWMS complies with the cost-benefit ratio of Section II.D of Appendix I. 3. The applicant has met the requirements of 10 CFR 20.1301 and 10 CFR 20.1302, as the staff has considered the potential consequences resulting from reactor operation with design basis fuel defect, TS limits for dose equivalent halogens and noble gases, and core inventories of fission products inventory PWRs. For BWRs, the offgas noble gas release rate should be determined assuming 30-minute decay within the offgas system. The design basis fuel defect level for PWRs and noble gases release rate for BWRs were