Document: NUREG-0800
Document ID: 9bcad4cd-a055-4dc1-9315-db9d703e6f6f
Document Type: srp
Title: ENVIRONMENTAL QUALIFICATION OF MECHANICAL AND ELECTRICAL
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1634/ML16343A167.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.11
CFR Part: 
CFR Title: 

Content:
uctuations and vibration caused by acoustic resonances and hydrodynamic forces. B. SRP Section 3.9.6, “Functional Design, Qualification, and Inservice Testing Programs for Pumps, Valves, and Dynamic Restraints,” 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,electrical, and I&C equipment against natural phenomena and external events are reviewed under appropriate sections of SRP Chapter 3 (e.g., Sections 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, “Seismic and Dynamic Qualification of Mechanical and Electrical Equipment,” includes seismic and dynamic qualification of mechanical, electrical, and I&C equipment. 8. 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 100percent fuel-clad metal-water reaction, as stated in 10 CFR 50.44(c)(5), is performed under SRP Section 6.2.5. 9. For COL reviews of operational programs, the review of the applicant’s implementation plan is performed under SRP Section 13.4, “Operational Program Implementation.” 10. Review of the types of radiation and the radiation environment used to determine the total dose expected during normal operation over the installed life of the equipment, and the radiation environment associated with the most severe design basis accident, consistent with 10 CFR 50.49(e)(4), and identifying the kinds and quantities of radioactive materials expected to be produced in the operation, consistent