Document: NUREG-0800
Document ID: 9f9f8fe1-9b66-460c-b928-6d1644a23c4c
Document Type: srp
Title: RADIATION PROTECTION - INSPECTIONS, TESTS, ANALYSES, AND
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550022.pdf
Revision Date: 2023-06
Chapter: 14
Section ID: 14.3.8
CFR Part: 
CFR Title: 

Content:
icense, the provisions of the Atomic Energy Act, and the NRC's regulations. 14.3.8-4 March 2007 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. 1. The reviewer should primarily use the applicable rules and regulations, general design criteria, regulatory guides, unresolved safety issues, and generic safety issues in the review of Tier 1 to determine the safety significance of SSCs with respect to the radiation protection for occupational workers and the general public they provide. Other sources include the SRP and applicable U.S. Nuclear Regulatory Commission (NRC) generic correspondence. The reviewer should use the guidance in Appendix C to SRP Section 14.3 as an aid for ensuring the comprehensiveness and consistency of this review. 2. Radiation Protection: The reviewer should ensure that Tier 1 identifies and describes, commensurate with their safety significance, those SSCs that provide radiation shielding, confinement or containment of radioactivity, ventilation of airborne contamination, or radiation (or radioactivity concentration) monitoring for normal operations and during accidents. Tier 1 identifies and describes the measures that need to be employed during first-of-a-kind engineering to ensure that final design details (i.e., materials and component selection, equipment placement, and pipe routing) are consistent with the radiation protection commitments (including the