Document: NUREG-0800
Document ID: 39169f01-cad7-4157-8b41-e77433086afc
Document Type: srp
Title: SOURCE TERMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070607.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.1
CFR Part: 
CFR Title: 

Content:
erms. The assumptions used in the calculations that are based on the performance of modern equipment have a driving influence on the design parameters used for the radwaste management systems reviewed in SRP Section 11.2, "Liquid Waste Systems," and in Section 11.3, "Gaseous Waste Systems." Meeting the source term calculation requirements of SRP Section 11.1 provides assurance that the system designs reviewed in SRP Sections 11.2 and 11.3 will meet the effluent concentration limits in unrestricted areas specified in 10 CFR Part 20, the requirements and ALARA objectives of 10 CFR 50.34a as it relates to adequacy of 11.1-5 DRAFT Rev. 3 - April 1996 design information for radwaste management systems; General Design Criteria 60 and 61 of 10 CFR Part 50, Appendix A; and the public dose limitations of 10 CFR Part 50, Appendix I.14 2. Compliance with GDC 60 requires that the nuclear power unit design shall include suitable means to control the release of radioactive materials in gaseous and liquid effluents and to handle radioactive solid wastes produced during normal reactor operation, including anticipated operational occurrences. GDC 60 specifies that the radwaste processing systems provide for a holdup capacity sufficient to retain the radioactive waste, particularly where unfavorable site environmental conditions may impose unusual operational limitations on the release of the effluent. The holdup capacity also provides time to allow the shorter lived isotopes a chance to decay before they are further processed or released to the atmosphere. The holdup times are used in the source term calculations provided for in NUREG-0016 and NUREG-0017. Meeting the requirements of GDC 60 provides assurance that releases of radioactive materials during normal operation of the radwaste processing systems and during anticipated transients will not result in offsite radiation doses exceeding the limits specified in 10 CFR Part 50, Appendix I, and the effluent concentration limits in