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ANS
ANS 58.9 : 2002(R2015)

ANS 58.9 : 2002(R2015)

Superseded

Superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

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superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

SINGLE FAILURE CRITERIA FOR LWR SAFETY-RELATED FLUID SYSTEMS

Superseded date

20-10-2022

Published date

12-01-2013

Publisher

American Nuclear Society

1 Scope
2 Definitions
3 Rules for application of the single failure
    criteria
4 Exemptions
5 Design requirements
6 Analysis requirements
7 References

Describes criteria for the designer which interpret the requirements of Title 10, Code of Federal Regulations, Part 50, 'Licensing of Production and Utilization Facilities,' Appendix A, 'General Design Criteria for Nuclear Power Plants,' with respect to design against single failures in safety-related Light Water Reactor (LWR) fluid systems. Means of treating both active and passive failures are addressed for safety-related fluid systems following various initiating events.

DocumentType
Standard
PublisherName
American Nuclear Society
Status
Superseded
SupersededBy

ANS 59.2 : 1985 NUCLEAR POWER PLANTS - HVAC SYSTEMS LOCATED OUTSIDE PRIMARY CONTAINMENT, SAFETY CRITERIA FOR,
ANS 58.2 : 1988 DESIGN BASIS FOR PROTECTION OF LIGHT WATER NUCLEAR POWER PLANTS AGAINST THE EFFECTS OF POSTULATED PIPE RUPTURE
ANS 54.1 : 1989 GENERAL SAFETY DESIGN CRITERIA FOR A LIQUID METAL REACTOR NUCLEAR POWER PLANT
ANS 56.10 : 82(R1987) NUCLEAR REACTORS - SUBCOMPARTMENT PRESSURE AND TEMPERATURE TRANSIENT ANALYSIS IN LIGHT WATER REACTORS
ANS 56.11 : 1998 DESIGN CRITERIA FOR PROTECTION AGAINST THE EFFECTS OF COMPARTMENT FLOODING IN LIGHT WATER REACTOR PLANTS
ANS 59.1 : 1986 COOLING WATER SYSTEMS FOR LIGHT WATER REACTORS, NUCLEAR SAFETY RELATED,
ANS 51.10 : 1991(R2008) AUXILIARY FEED-WATER SYSTEM FOR PRESSURIZED WATER REACTORS
IEEE 603-2009 REDLINE IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations
ANS 59.51 : 1997(R2015) FUEL OIL SYSTEMS FOR SAFETY-RELATED EMERGENCY DIESEL GENERATORS
ANS 58.6 : 1996(R2001) CRITERIA FOR REMOTE SHUTDOWN FOR LIGHT WATER REACTORS
ANS 58.11 : 1995(R2002) DESIGN CRITERIA FOR SAFE SHUTDOWN FOLLOWING SELECTED DESIGN BASIS EVENTS IN LIGHT WATER REACTORS
ANS 51.1 : 83(R1988) NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY PRESSURIZED WATER REACTOR PLANTS
ANS 52.1 : 83(R1988) NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY BOILING WATER REACTOR PLANTS
ANS 58.14 : 2011(R2017) SAFETY AND PRESSURE INTEGRITY CLASSIFICATION CRITERIA FOR LIGHT WATER REACTORS

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