Published 1980 | Version v1
Book

IEEE standard for design qualification of safety systems equipment used in nuclear power generating stations

Creators

Description

This standard is written to serve as a general standard for qualification of all types of safety systems equipment, mechanical and instrumentation as well as electrical. It also establishes principles and procedures to be followed in preparing specific safety systems equipment standards. Guidance for qualifying specific safety systems equipment may be found in various specific equipment qualification standards that are now available or are being prepared. It is required that safety systems equipment in nuclear power generating stations meet or exceed its performance requirements throughout its installed life. This is accomplished by a disciplined program of design qualification and quality assurance of design, production, installation, maintenance and surveillance. This standard is for the design qualification section of the program only. Design qualification is intended to demonstrate the capability of the equipment design to perform its safety function(s) over the expected range of normal, abnormal, design basis event, post design basis event, and in-service test conditions. Inherent to design qualification is the requirement for demonstration, within limitations afforded by established technical state-of-the-art, that in-service aging throughout the qualified life established for the equipment will not degrade safety systems equipment from its original design condition to the point where it cannot perform its required safety function(s), upon demand. The above requirement reflects the primary role of design qualification to provide reasonable assurance that design- and age-related common failure modes will not occur during performance of safety function(s) under postulated service conditions

Additional details

Publishing Information

Publisher
The Institute of Electrical and Electronics Engineers, Inc.
Imprint Place
New York, NY
Imprint Pagination
14 p.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
15002053
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY;
Descriptors DEI
NUCLEAR POWER PLANTS; QUALITY ASSURANCE; REACTOR INSTRUMENTATION; SAFEGUARDS; SAFETY ENGINEERING; SPECIFICATIONS
Descriptors DEC
NUCLEAR FACILITIES; POWER PLANTS; THERMAL POWER PLANTS

Optional Information

Secondary number(s)
IEEE--627-1980.