Document: NRC Regulatory Guide
Document ID: e16da529-b6b4-4fdf-bc3f-7490180363f3
Document Type: regulatory_guide
Title: Environmental Qualification of Certain Electric Equipment Important to Safety for Nuclear Power Plants (Rev. 2)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2018/ML20183A423.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.89
CFR Part: 
CFR Title: 

Content:
ting Licenses as of May 23, 1980, will be evaluated by the staff against the DOR guidelines. In accordance with the statement of considerations for 10 CFR 50.49, Category I requirements of NUREG-0588, which supplement the recommendations of and apply to equipment qualified in accordance with IEEE Std. 323- 1974, “IEEE Standard for Qualifying Class IE Equipment for Nuclear Power Generating Stations” (Ref. 9), apply to nuclear power plants for which the construction permit safety evaluation report was issued after July 1, 1974. Category II requirements, which supplement the recommendations of and apply to equipment qualified in accordance with IEEE Std. 323-1971, “IEEE Trial-Use Standard: General Guide for Qualifying Class I Electric Equipment for Nuclear Power Generating Stations” (Ref. 10), apply to nuclear power plants for which the construction permit safety evaluation report was issued prior to July 1, 1974. For plants whose Safety Evaluation Reports for construction permits were issued since July 1, 1974, the Commission has used RG 1.89. • RG 1.97, “Criteria for Accident Monitoring Instrumentation for Nuclear Power Plants,” describes a method that is acceptable to the staff of the NRC for use in complying with the agency’s regulations with respect to satisfying criteria for accident monitoring instrumentation in nuclear power plants (Ref. 11). DG-1361, Page 4 • RG 1.164, “Dedication of Commercial-Grade Items for Use in Nuclear Power Plants,” describes methods that the staff of the NRC considers acceptable in meeting regulatory requirements for dedication of commercial-grade items and services used in nuclear power plants (Ref. 12). • RG 1.183, “Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors” (Ref. 13), provides guidance to licensees of operating power reactors on acceptable applications of alternative source terms (ASTs); the scope, nature, and documentation of associated analyses