Document: NUREG-0800
Document ID: a6fb41ee-7d52-4c71-82e1-7bc60ac6087a
Document Type: srp
Title: APPLICABLE CODE CASES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1608/ML16088A219.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.2.1.2
CFR Part: 
CFR Title: 

Content:
REVIEW RESPONSIBILITIES Primary - Organization responsible for mechanical engineering reviews Secondary - Organization responsible for component integrity reviews I. AREAS OF REVIEW This Standard Review Plan (SRP) section is used to verify whether acceptable American Society of Mechanical Engineers (ASME) Code Cases are identified for component construction1. Acceptable Code Cases for construction of nuclear power plants are identified in Regulatory Guide (RG) 1.84, “Design and Fabrication Code Case Acceptability, ASME Section III”; RG 1.147, “Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1”; and RG 1.192, “Operation and Maintenance Code Case Acceptability, ASME OM Code,” which are incorporated by reference into Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a, “Codes and Standards”. These Code Cases provide generally acceptable alternatives to the requirements of the ASME Boiler and Pressure Vessel Code (BPV Code) and Operation and Maintenance of Nuclear Power Plants (OM Code), as modified by conditions in the associated regulatory guides. The specific areas of review are as follows: 1 Constructed, as used herein, is an all inclusive term comprising material certification, design, fabrication, examination, testing, inspection, and certification required in the manufacture and installation of components. Revision 4 – December 2016 1. ASME Code Cases contain alternatives to the requirements in the ASME BPV Code and ASME OM Code for the design, fabrication, manufacturing, construction, installation, testing, examination, and inspection of nuclear power plant components within the scope of these codes. The NRC staff review of an application under 10 CFR Part 50, “Domestic Licensing of Production and Utilization Facilities,” or 10 CFR Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants,” will determine the acceptability of ASME Code Cases specified in the applicant’s