Document: NUREG-0800
Document ID: 23331bab-fa00-40fd-8357-d8db908b4532
Document Type: srp
Title: GASEOUS WASTE MANAGEMENT SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0707/ML070710366.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.3
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at could affect the design basis of SSCs important to safety are reflected in the site characteristics, design parameters, or terms and conditions on the early site permit. IV. EVALUATION FINDINGS The reviewer verifies that the applicant has provided sufficient information and that the review and calculations (if applicable) support conclusions of the following type to be included in the staff's safety evaluation report. The reviewer also states the bases for those conclusions. 11.3-17 Revision 3 - March 2007 The staff concludes that the design of the GWMS (either as a permanently installed system or in combination with a mobile system) includes the necessary equipment to process and control releases of radioactive materials in gaseous effluents in accordance with GDC 3, 60, and 61 of Appendix A to 10 CFR Part 50 and 10 CFR 50.34a. The staff concludes that the design of the GWMS is acceptable and meets the requirements of 10 CFR Part 20, 10 CFR 20.1301 and 20.1302, 10 CFR 20.1301(e), and 10 CFR 20.1406; 10 CFR Part 50 and 10 CFR 50.34a; GDC 3, 60, and 61; and Appendix I to 10 CFR Part 50. This conclusion is based on the following: 1. The applicant has met the requirements of GDC 60 and 61 with respect to controlling releases of radioactive materials to the environment by assuring that the design of the GWMS includes the equipment and instruments necessary to detect and control the release of radioactive materials in gaseous effluents. 2. The applicant has met the requirements of Appendix I to 10 CFR Part 50 by meeting the as low as is reasonably achievable criterion as follows: A. Regarding Sections II.B and II.C of Appendix I, the staff has considered releases of radioactive material (noble gases, radioiodine, tritium, carbon-14, and particulates) in gaseous effluents for normal operation, including anticipated operational occurrences, based on expected amounts and concentrations of gaseous wastes over the life of the plant for each reactor on the site. The staff