Revision to criteria for safety-related operator actions
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:5977315
- General Electric Co., San Jose, CA (United States)
The criteria contained in Time Response Design Criteria for Safety-Related Operator Actions ANS58.8-1984 established simple timing requirements to be used in the preliminary design process for determining whether the nuclear-safety systems that mitigate the consequences of design basis events may be initiated by (a) use of operator action or (b) automatic protection systems. The time response criteria given in this standard include conservative time margins, time delay, and other restrictions to provide an adequate nuclear safety margin for the purposes of system and plant design and nuclear safety evaluations. At present the Working Group for Operator Action is revising the Standard to encompass industry data available since original publication. The US Nuclear Regulatory Commission has taken great interest in this revision because they hope to use the revised standard as a basis for resolving the unresolved safety issue of safety-related operator actions. The Working Group for Operator Action has reviewed additional industry data available since the publication of the first version of this standard. The purpose of this review was to determine whether the data validated the time tests of the standard, or whether they indicated that either the time tests or the philosophical basis of the standard needed revision.
- OSTI ID:
- 5977315
- Report Number(s):
- CONF-910603--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 63
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400 -- Nuclear Reactor Technology-- Control Systems
220900* -- Nuclear Reactor Technology-- Reactor Safety
DESIGN
EDUCATION
ENGINEERED SAFETY SYSTEMS
ENGINEERING
EPRI
FUNCTIONS
HUMAN FACTORS
HUMAN FACTORS ENGINEERING
IMPLEMENTATION
NATIONAL ORGANIZATIONS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PERSONNEL
POWER PLANTS
REACTOR OPERATORS
REACTOR SAFETY
RELIABILITY
RESEARCH PROGRAMS
RESPONSE FUNCTIONS
SAFETY
TESTING
THERMAL POWER PLANTS
TIME DELAY
TRAINING
US NRC
US ORGANIZATIONS
VALIDATION
220400 -- Nuclear Reactor Technology-- Control Systems
220900* -- Nuclear Reactor Technology-- Reactor Safety
DESIGN
EDUCATION
ENGINEERED SAFETY SYSTEMS
ENGINEERING
EPRI
FUNCTIONS
HUMAN FACTORS
HUMAN FACTORS ENGINEERING
IMPLEMENTATION
NATIONAL ORGANIZATIONS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PERSONNEL
POWER PLANTS
REACTOR OPERATORS
REACTOR SAFETY
RELIABILITY
RESEARCH PROGRAMS
RESPONSE FUNCTIONS
SAFETY
TESTING
THERMAL POWER PLANTS
TIME DELAY
TRAINING
US NRC
US ORGANIZATIONS
VALIDATION