Document: NUREG-0800
Document ID: fabdf65c-d299-4b3a-a971-ae5b21a97177
Document Type: srp
Title: RADIATION SOURCES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1315/ML13151A413.pdf
Revision Date: 2023-06
Chapter: 12
Section ID: 12.2
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as it relates to ensuring that information necessary to demonstrate how operating experience insights have been incorporated into the plant design. 1 For 10 CFR Part 50 applicants not listed in 10 CFR 50.34(f), the provisions of 10 CFR 50.34(f) will be made a requirement during the licensing process. 12.2-7 Revision 4 – September 2013 13. 10 CFR 50.34(b)(3), 10 CFR 52.47(a)(5), 10 CFR 52.79(a)(3) and 10 CFR 52.157(e) as they relate to identifying the kinds and quantities of radioactive materials expected to be produced in the operation and the means for controlling and limiting radioactive radiation exposures within the limits set forth in 10 CFR Part 20 of this chapter. SRP Acceptance Criteria Specific SRP acceptance criteria acceptable to meet the relevant requirements of the NRC regulations identified above are as follows for the review described in this SRP section. The SRP is not a substitute for the NRC 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 regulatory guides, standards, and NUREGs provide information, recommendations, and guidance and in general describe a basis acceptable to the staff for implementing the requirements of 10 CFR 50.34(b)(3), 10 CFR 52.47(a)(5), 10 CFR 52.79(a)(3) and 10 CFR 52.157(e), 10 CFR 20.1201, 10 CFR 20.1202, 10 CFR 20.1203, 10 CFR 20.1204, 10 CFR 20.1206, 10 CFR 20.1207, 10 CFR 20.1301, 10 CFR 20.1406, 40 CFR Part 190, 10 CFR 20.1801 and 10 CFR 50.49. 1. Regulatory Guide (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, for boiling-water reactors (BWRs). 2. RG