IEEE 933-2013 REDLINE
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
View Superseded by
IEEE Guide for the Definition of Reliability Program Plans for Nuclear Generating Stations and Other Nuclear Facilities
Hardcopy , PDF
22-04-2024
English
10-01-2014
Important note : Users cannot be edited or removed once added to your Multi user PDF.
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Superseded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 | |
| Supersedes |
| 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 |
Access your standards online with a subscription
Features
-
Simple online access to standards, technical information and regulations.
-
Critical updates of standards and customisable alerts and notifications.
-
Multi-user online standards collection: secure, flexible and cost effective.