Document: NUREG-0800
Document ID: a55c61ec-57c4-4f3d-b403-d27c8f7c6427
Document Type: srp
Title: SOURCE TERMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0707/ML070790010.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.1
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Content:
quid and gaseous effluents (Section II.D of Appendix I). Conformance with Section II.D of Appendix I demonstrates that the plant design includes all items of established modern technology for reducing the cumulative population dose due to releases of radioactive materials from the reactor to ALARA levels of Appendix I. The calculations using the Gaseous and Liquid Effluent (GALE) Computer Code and the source term parameters given in NUREG-0016 and NUREG-0017 for BWRs and PWRs, respectively, take into account modern technology and the availability of equipment based on that technology to reduce the liquid and gaseous waste management system source terms. 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 criteria of SRP Section 11.1 provides reasonable 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 they relate to the adequacy of design information for radwaste management systems; GDC 60 and 61 of 10 CFR Part 50, Appendix A; and the public dose limitations of 10 CFR Part 50, Appendix I. 11.1-6 Revision 3 - March 2007 2. GDC 60 requires, in part, that the nuclear power unit design shall include means to control suitably the release of radioactive materials in gaseous and liquid effluents produced during normal reactor operation, including anticipated operational occurrences. GDC 60 specifies that sufficient holdup capacity shall be provided for retention of gaseous and liquid effluents containing radioactive materials, particularly where unfavorable site environmental conditions can be expected to impose unusual