Document: NUREG-0800
Document ID: 36b6a414-c2ba-46ab-ae85-e214a0f457fa
Document Type: srp
Title: COOLANT SOURCE TERMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1502/ML15029A022.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.1
CFR Part: 
CFR Title: 

Content:
s reviewed in SRP Section 11.2 and SRP Section 11.3. If either code is modified to model specific design features, the modifications should be described in sufficient detail that they can be reviewed. If an alternate calculation model is proposed by the applicant, it should be described in sufficient detail, and the bases of all parameters used in the model should be described to allow the staff to conduct an independent evaluation. Meeting the coolant 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 (Appendix B, Table 2, Columns 1 and 2, and Note 4) and the 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 numerical criteria of 10 CFR Part 50, Appendix I. 2. GDC 60 requires, in part, that the nuclear power unit design include the means to control releases of radioactive materials in gaseous and liquid effluents produced during normal reactor operation and AOOs. GDC 60 requires that sufficient holdup capacity be provided for the retention of gaseous and liquid effluents containing radioactive materials, particularly where unfavorable site environmental conditions can be expected to impose unusual operational limitations upon the release of effluents to the environment. The holdup capacity also provides time to allow shorter-lived radionuclides to decay before they are further processed or released to the environment. Acceptable holdup times, applied in source term calculations, are provided in NUREG-0016, NUREG-0017, or ANSI/ANS 18.1-1999. Meeting the requirements of GDC 60 provides reasonable assurance that releases of radioactive materials, during normal operation and AOOs of radwaste processing systems, will not result in offsite radiation doses exceeding the