Document: NUREG-0800
Document ID: 723c7d66-7b0b-443a-af9b-ec3026461a0c
Document Type: srp
Title: - 12.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1130/ML113081427.pdf
Revision Date: 2023-06
Chapter: 12
Section ID: 12.3
CFR Part: 
CFR Title: 

Content:
ment during the licensing process. 13. 10 CFR 52.80(a), which requires that a COL FSAR contain the proposed inspections, tests, and analyses, including those applicable to emergency planning, that the licensee shall perform, and the acceptance criteria that are necessary and sufficient to provide reasonable assurance that, if the inspections, tests, and analyses are performed and the acceptance criteria met, the facility has been constructed and will operate in conformity with the combined license, the provisions of the AEA, and the NRC's regulations. SRP Acceptance Criteria Specific SRP acceptance criteria acceptable to meet the relevant requirements of the NRC’s regulations identified above are as follows for the review described in this SRP section. The SRP is not a substitute for the NRC’s regulations, and compliance with it is not required. However, an applicant is required to identify differences between the design features, analytical techniques, and procedural measures proposed for its facility and the SRP acceptance criteria and evaluate how the proposed alternatives to the SRP acceptance criteria provide acceptable methods of compliance with the NRC regulations. The following RGs, NUREGs, and industry standards provide information, recommendations, and guidance and in general describe a basis acceptable to the staff for implementing the requirements of the regulations identified above: 1. RG 1.32, as it relates to assumptions used in evaluating gaseous concentrations of radionuclides in containment and plant systems following a loss-of-coolant accident (LOCA) for boiling-water reactors (BWRs). 2. RG 1.42, as it relates to assumptions used in evaluating gaseous concentrations of radionuclides in containment and plant systems following an LOCA for pressurized-water reactors (PWRs). 3. RG 1.7, as it relates to methods for determining gaseous radionuclides in containment following an accident. 4. RG 1.52, as it relates to radiation protection