ANS 58.8-1994(R2017)
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
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TIME RESPONSE DESIGN CRITERIA FOR SAFETY-RELATED OPERATOR ACTIONS
Hardcopy , PDF
21-08-2023
English
12-01-2013
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1 Introduction
1.1 Scope
1.2 Purpose
1.3 Assumptions
2 Definitions
3 General requirements
3.1 Safety-related operator actions
3.2 Safety-related operator actions outside the
control room
3.3 Instrumentation
4 Calculation of operator related time intervals
4.1 TI diagnosis
4.2 TI operator
4.3 Application requirements
5 Exceptions
5.1 Use of performance data
5.2 Impact of criteria on plant safety
6 References
Figure 1 Definition of discrete time points
2 Definition of time intervals
3 Example event analyses
Table 1 Minimum TI diagnosis for each PC
2 TI operator sub-intervals for each PC & for actions
to be taken outside the control room
Appendix
Bases for timing requirements
Describes time response design criteria for safety-related operator actions to be used in the design of light water reactor nuclear power plants. This standard specifies time requirements that are to be met to receive credit in the safety analysis for operator actions that initiate or control safety-related functions.
| DocumentType |
Standard
|
| Pages |
28
|
| PublisherName |
American Nuclear Society
|
| Status |
Superseded
|
| SupersededBy | |
| Supersedes |
| 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 |
| I.S. EN 61839:2014 | NUCLEAR POWER PLANTS - DESIGN OF CONTROL ROOMS - FUNCTIONAL ANALYSIS AND ASSIGNMENT |
| BS IEC 61839 : 2000 | NUCLEAR POWER PLANTS - DESIGN OF CONTROL ROOMS - FUNCTIONAL ANALYSIS AND ASSIGNMENT |
| ANS 59.1-1986 | COOLING WATER SYSTEMS FOR LIGHT WATER REACTORS, NUCLEAR SAFETY RELATED, |
| ANS 56.2-1984(R1989) | NUCLEAR POWER PLANTS - CONTAINMENT ISOLATION PROVISIONS FOR FLUID SYSTEMS AFTER A LOCA |
| BS EN 61839:2014 | Nuclear power plants. Design of control rooms. Functional analysis and assignment |
| IEEE 1023-2004 REDLINE | IEEE Recommended Practice for the Application of Human Factors Engineering to Systems, Equipment, and Facilities of Nuclear Power Generating Stations and Other Nuclear Facilities |
| EN 61839:2014 | Nuclear power plants - Design of control rooms - Functional analysis and assignment |
| ANS 51.1-1983(R1988) | NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY PRESSURIZED WATER REACTOR PLANTS |
| IEEE 279-1971 | IEEE Standard: Criteria for Protection Systems for Nuclear Power Generating Stations |
| ANS 3.1-2014 | SELECTION, QUALIFICATION, AND TRAINING OF PERSONNEL FOR NUCLEAR POWER PLANTS |
| ANS 52.1-83(R1988) | NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY BOILING WATER REACTOR PLANTS |
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