Document: NUREG-0800
Document ID: 4625ce02-1344-45f7-86eb-10700f6610b2
Document Type: srp
Title: APPLICABLE CODE CASES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0700/ML070040004.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.2.1.2
CFR Part: 
CFR Title: 

Content:
ions, 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 Atomic Energy Act, 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. To meet the requirements of General Design Criterion 1 and 10 CFR 50.55a, the following regulatory guides are used: 1. Regulatory Guide 1.84, "Design and Fabrication Code Case Acceptability, ASME Section III, Division 1." This guide lists those Section III, Division 1, ASME Code Cases oriented to design, fabrication, materials, and testing, which are acceptable to the staff for implementation in the licensing of nuclear power plants. 2. Regulatory Guide 1.147, "Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1." This guide lists those Section XI ASME Code Cases which are acceptable to the staff for use in the inservice inspection of components and their supports, as described in the first paragraph of subsection I, of this SRP. 3. Regulatory Guide 1.192, "Operation and Maintenance Code Case Acceptability, ASME OM Code." This guide lists ASME OM Code Cases oriented to operation and maintenance for nuclear power plant components which are acceptable to the staff for implementation in the licensing of nuclear power plants. Code Cases pertaining to ASME Code Section III, Division 2, as well as