Document: NUREG-0800
Document ID: 63521156-eb6b-472c-9560-1e85462dc1be
Document Type: srp
Title: ENVIRONMENTAL QUALIFICATION OF MECHANICAL AND ELECTRICAL
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070288.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.11
CFR Part: 
CFR Title: 

Content:
uide. f. IEEE Std 535, "IEEE Standard for Qualification of Class 1E Lead Storage Batteries for Nuclear Power Generating Stations" (Reference 11), (endorsed by Regulatory Guide 1.158, "Qualification of Safety-Related Lead Storage Batteries for Nuclear Power Plants"), contains guidance acceptable to the staff for environmental qualification of Class 1E lead storage batteries. Therefore, this document as it relates to environmental qualification should be used in conjunction with NUREG-0588 and Regulatory Guide 1.89, as appropriate, for evaluating the environmental qualification of this equipment.96 g. The effects of the chemicals should be addressed for the equipment qualification. The concentration of chemicals used for qualification should be equivalent to or more severe than that resulting from the most limiting mode of plant operation (e.g., containment spray, emergency core cooling system ECCS initiation, or 97 recirculation phase). If the chemical composition of the chemical spray can be affected by equipment malfunctions, the most severe chemical environment that results from a single failure in the spray system should be assumed. If only demineralized water spray is used, then the effect of the demineralized water spray should be included in the equipment qualification. h. Radiation dose and dose rate used to determine the radiation environment for qualification of electrical and mechanical equipment shall be based on an NRC 98 staff-approved source term and methodology as discussed in NUREG-0588 and 3.11-9 DRAFT Rev. 3 - April 1996 supplemented by Section II.B.2 of NUREG-0737 and NUREG-0718, or NUREG-1465, "Accident Source Terms for Light-Water Nuclear Power Plants." The radiation environment shall be based on the integrated effects of 99 the normally expected radiation environment over the equipment's installed life, plus that associated with the most severe design basis event during or following which the equipment is required to remain functional. Effects