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:
on Assemblies for Nuclear Power Plants,” endorses IEEE Std 572, “IEEE Standard for Qualification of Class 1E Connection Assemblies for Nuclear Power Generating Stations.” These documents contain guidance acceptable to the staff for the environmental qualification of Class 1E connection assemblies, and should be used in conjunction with NUREG-0588 and RG 1.89, as appropriate, for evaluating the environmental qualification of Class 1E connection assemblies. 3.11 -13 Draft Revision 4 – December 2017 13. RG 1.158, “Qualification of Safety-Related Lead Storage Batteries for Nuclear Power Plants,” endorses IEEE Std 535, “IEEE Standard for Qualification of Class 1E Lead Storage Batteries for Nuclear Power Generating Stations.” These documents contain guidance acceptable to the staff for the environmental qualification of Class 1E lead storage batteries, and should be used in conjunction with NUREG-0588 and RG 1.89, as appropriate, for evaluating the environmental qualification of lead storage batteries. 14. RG 1.180, “Guidelines for Evaluating Electromagnetic and Radio-Frequency Interference in Safety-Related Instrumentation and Control Systems,” provides guidance acceptable to the staff for determining electromagnetic compatibility for I&C equipment during service. These criteria, as supplemented by those of RG 1.89, should be used to evaluate the environmental design and qualification of safety-related I&C equipment. New digital systems and new advanced analog systems may require susceptibility testing for electromagnetic interference/radio-frequency interference (EMI/RFI) and power surges, if the environments are significant to the equipment being qualified. The functional descriptions of I&C equipment are provided in SRP Chapter 7. 15. RG 1.183, “Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors,” provides guidance acceptable to the staff for determining the radiation dose and dose rate for