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
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Content:
new program. The reviewer states the bases for those conclusions, as listed below: 1. The staff concludes that sufficient information has been provided by the applicant so that the requirements of 10 CFR 50.34 and 10 CFR 50.34a have been met. The reviewer responsible for review of effectiveness of radwaste systems will provide a summary statement on the acceptability of radioactive source terms used as design parameters for the waste management systems under SER Section 11.2 and SER Section 11.3. 2. The staff concludes that the liquid and gaseous source terms are acceptable and that their use in calculating doses associated with liquid and gaseous effluents will meet the regulatory requirements under 10 CFR Part 20 for effluent concentration and dose limits for members of the public, and 10 CFR Part 50, Appendix I design objectives and ALARA provisions. The review includes the bases of the source terms for both the design basis and normal operations and AOOs. The staff confirms that the source terms were developed using the guidance provided in RG 1.112; NUREG-0016, NUREG-0017, or ANSI/ANS 18.1-1999; and that specific adjustments were made in consideration of the specific design and operating features of the proposed reactor design. The staff confirms that the applicant has provided sufficient information in justifying changes in the use of input parameters for the reactor design. 3. The staff concludes that the liquid and gaseous source terms are acceptable and that their use in calculating doses associated with accident conditions will meet the regulatory requirement of GDC 61. Meeting GDC 61 provides the means to determine the amounts of radioactive materials contained in RWMS and assess the radiological impacts during postulated accidents. The staff determined that the applicant used the method and guidance described in SRP Sections 2.4.13, SRP 11.2 using BTP 11-5, SRP 11.3 using BTP 11-6, and the analysis of RG 1.143 in assigning the safety classifications of