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
CFR Part: 
CFR Title: 

Content:
apacity 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 operational limitations on the release of such effluents to the environment. 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. Acceptable holdup times are used in the source term calculations provided in NUREG-0016 and NUREG-0017. Meeting the requirements of GDC 60 provides reasonable 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 unrestricted areas exceeding the limits specified in 10 CFR Part 20. III. REVIEW PROCEDURES The reviewer will select material from the procedures described below, as may be appropriate for a particular case. These review procedures are based on the identified SRP acceptance criteria. For deviations from these acceptance criteria, the staff should review the applicant’s evaluation of how the proposed alternatives provide an acceptable method of complying with the relevant NRC requirements identified in Subsection II. 1. In the review of the mathematical models and parameters given in the SAR to calculate primary coolant concentrations, the reviewer compares parameters and calculations given in the SAR with the models and parameters given in ANSI/ANS 18.1-1999, NUREG-0016, or NUREG-0017. If the SAR includes models or parameters to estimate reactor coolant concentrations that differ from these reports, the parameters and calculations used should be substantiated. The preferred method of substantiation is by presentation of operating data from similar reactors. 2. The reviewer performs an independent