Document: NUREG-0800
Document ID: a5f6fd7c-4062-40ac-b548-0ddba421091d
Document Type: srp
Title: ENVIRONMENTAL QUALIFICATION OF MECHANICAL AND ELECTRICAL
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0636/ML063600397.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.11
CFR Part: 
CFR Title: 

Content:
ects on mechanical and electrical equipment (such as electromatic relief valves in BWR steam systems) from pressure fluctuations and vibration caused by acoustic resonances and hydrodynamic forces. B. SRP 3.9.6 includes functional design and qualification of pumps, valves, and dynamic restraints at a nuclear power plant. The review includes the potential impact of adverse environmental conditions on active mechanical and electrical equipment. For example, electric motors might produce less torque under high temperature conditions than under ambient conditions, which could impact their capability to operate their individual pumps or valves. C. The design bases for protection of mechanical and electrical equipment against natural phenomena and external events, are reviewed under appropriate sections of SRP Chapter 3 (e.g., 3.3.1, 3.3.2, 3.4.1, 3.5.1.1, 3.5.1.4, 3.5.1.5, and 3.5.2). SRP Section 3.10 includes seismic and dynamic qualification of mechanical and electrical equipment. 11. Review of the adequacy of equipment functional performance during and after being exposed to the environmental conditions resulting from the release of hydrogen generated by the equivalent of a 100% fuel-clad metal-water reaction, as stated in 10 CFR 50.44(c), is performed under SRP Section 6.2.5. 12. For COL reviews of operational programs, the review of the applicant’s implementation plan is performed under SRP Section 13.4, “Operational Programs.” The specific acceptance criteria and review procedures are contained in the referenced SRP sections. II. ACCEPTANCE CRITERIA Requirements Acceptance criteria are based on meeting the relevant requirements of the following Commission regulations: 1. 10 CFR 50.49, "Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants." 2. 10 CFR 50.67, ?Accident Source Term.” 3. 10 CFR Part 50, Appendix A, General Design Criterion (GDC) 1, "Quality Standards and Records." 4. GDC 2, "Design Bases for Protection