IEEE 933-2013 REDLINE

Name: IEEE 933-2013 REDLINE
Brand: IEEE
Price: 325.51 USD

Superseded

View Superseded by

IEEE Guide for the Definition of Reliability Program Plans for Nuclear Generating Stations and Other Nuclear Facilities

Available format(s)

Hardcopy , PDF

Superseded date

04-22-2024

Language(s)

English

Published date

01-10-2014

Publisher

Institute of Electrical & Electronics Engineers

1 Overview
2 Normative references
3 Definitions, acronyms, and abbreviations
4 Program elements
5 Major programmatic resources
Annex A (informative) - Reliability program
        management
Annex B (informative) - Case study-Application
        of Excelsior Power Company's reliability
        program plan to service water pumps
Annex C (informative) - Sample RAM specification
        for replacement service water pumps
Annex D (informative) - Bibliography

This document provides guidelines for the definition of a reliability program at nuclear generating stations and other nuclear facilities.

Committee	Nuclear Power Engineering Committee
DocumentType	Standard
ISBN	978-0-7381-8750-1
Pages	65
PublisherName	Institute of Electrical & Electronics Engineers
Status	Superseded
SupersededBy	IEEE 933-2023
Supersedes	IEEE 933-1999

IEEE 577-2012	IEEE Standard Requirements for Reliability Analysis in the Design and Operation of Safety Systems for Nuclear Power Generating Stations
CFR 10(PTS0-199) : JAN 87	ENERGY - NUCLEAR REGULATORY COMMISSION
ANS 2.27 : 2008(R2016)	CRITERIA FOR INVESTIGATIONS OF NUCLEAR FACILITY SITES FOR SEISMIC HAZARD ASSESSMENTS
NFPA 805 : 2015	PERFORMANCE-BASED STANDARD FOR FIRE PROTECTION FOR LIGHT WATER REACTOR ELECTRIC GENERATING PLANTS
ASME OM : 2017	OPERATION AND MAINTENANCE OF NUCLEAR POWER PLANTS
IEEE 1205-2014	IEEE Guide for Assessing, Monitoring, and Mitigating Aging Effects on Electrical Equipment Used in Nuclear Power Generating Stations and Other Nuclear Facilities
ANS 2.29 : 2008(R2016)	PROBABILISTIC SEISMIC HAZARD ANALYSIS
IEEE 352-1987	IEEE Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Safety Systems
ASME RA-S : 2008	LEVEL 1/LARGE EARLY RELEASE FREQUENCY PROBABILISTIC RISK ASSESSMENT FOR NUCLEAR POWER PLANT APPLICATIONS