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ANS 58.8 : 1994(R2017)

Superseded

Superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

View Superseded by
superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

TIME RESPONSE DESIGN CRITERIA FOR SAFETY-RELATED OPERATOR ACTIONS

Available format(s)

Hardcopy , PDF

Superseded date

08-21-2023

Language(s)

English

Published date

01-12-2013

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Superseded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

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ANS 56.11 : 1998 DESIGN CRITERIA FOR PROTECTION AGAINST THE EFFECTS OF COMPARTMENT FLOODING IN LIGHT WATER REACTOR PLANTS
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ANS 56.2 : 84(R1989) NUCLEAR POWER PLANTS - CONTAINMENT ISOLATION PROVISIONS FOR FLUID SYSTEMS AFTER A LOCA
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ANS 58.14 : 2011(R2017) SAFETY AND PRESSURE INTEGRITY CLASSIFICATION CRITERIA FOR LIGHT WATER REACTORS
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ANS 51.1 : 83(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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