Document: NUREG-0800
Document ID: 14a7348a-8b3c-404a-bddd-d0b57465bf85
Document Type: srp
Title: COMPLIANCE WITH AMERICAN SOCIETY OF MECHANICAL ENGINEERS CODE
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1422/ML14227A623.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.2.1.1
CFR Part: 
CFR Title: 

Content:
REQUIREMENTS INTHE CODES AND STANDARDS RULE, 10 CFR 50.55a REVIEW RESPONSIBILITIES Primary - Organization responsible for mechanical engineering reviews Secondary - Organization responsible for materials engineering reviews I. AREAS OF REVIEW This Standard Review Plan (SRP) section is used to verify whether acceptable codes and standards (and their edition and addenda) required by Title 10 of the Code of Federal Regulations (10 CFR) 50.55a, “Codes and Standards,” are identified for component construction1. This SRP section addresses compliance with the requirements related to the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (BPV Code) and Operation and Maintenance of Nuclear Power Plants (OM Code). The review under this section is coordinated closely with the review described in SRP Section 3.2.2, “System Quality Group Classification.” More detailed review of conformance with ASME BPV Code requirements for the component code class (e.g., component welds verified to meet requirements applicable for the Code Class), is addressed in other SRP sections. The applicant’s framework for compliance with 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. 5.2.1.1-2 Draft Revision 4 - August 2015 10 CFR 50.55a requirements for application of codes and standards during the inservice phase of the component life is also reviewed in other SRP sections (e.g., 3.9.6, 5.2.4, and 6.6). In addition to providing requirements related to the ASME BPV Code and OM Code, 10 CFR 50.55a also describes requirements for instrumentation and control in reactor protection and safety systems. Specifically, Institute of Electrical and Electronics Engineers (IEEE) Standards IEEE-279, “Criteria for Protection Systems for Nuclear Power Generating Stations,” and IEEE-603, “Criteria for