Essential information required for an engineering and probabilistic assessment of a reactor protection system
Conference
·
· IEEE Trans. Nucl. Sci.; (United States)
OSTI ID:7175360
The main objective of this paper is to establish the essential information that is needed so that an adequate engineering and probabilistic assessment of the Reactor Protection System (RPS) can be carried out. This required information takes the form of questions that the assessor needs to ask of the system to aid his analysis. The SCRAM function of the RPS is used as an example. For simplicity and ease the RPS is divided up into its three main functional subsystems namely: 1) The Parameters, Permissives and Interlocks; 2) The Safety Logic; 3) The Relay Actuation and Control Rod Actuation. This paper includes questions related to the above listed subsystems, and satisfactory answers should be obtained from the Plant Safety Analysis Report, Plant Scpeificiations and Analyses. Conclusions reached should indicate that information is adequate to: a) demonstrate design intent; b) demonstrate how the system functions; and c) undertake a meaningful engineering and probabilistic assessment.
- Research Organization:
- Bechtel Western Power Co., CA (US)
- OSTI ID:
- 7175360
- Report Number(s):
- CONF-871006-
- Conference Information:
- Journal Name: IEEE Trans. Nucl. Sci.; (United States) Journal Volume: 35:1
- 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
99 GENERAL AND MISCELLANEOUS
990220 -- Computers
Computerized Models
& Computer Programs-- (1987-1989)
COMPUTERIZED CONTROL SYSTEMS
CONTROL SYSTEMS
DOCUMENT TYPES
ENGINEERED SAFETY SYSTEMS
EQUIPMENT PROTECTION DEVICES
MAN-MACHINE SYSTEMS
OPERATION
PERFORMANCE
REACTOR CONTROL SYSTEMS
REACTOR INSTRUMENTATION
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTOR SHUTDOWN
RECOMMENDATIONS
REVIEWS
SAFETY
SCRAM
SHUTDOWNS
220400 -- Nuclear Reactor Technology-- Control Systems
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990220 -- Computers
Computerized Models
& Computer Programs-- (1987-1989)
COMPUTERIZED CONTROL SYSTEMS
CONTROL SYSTEMS
DOCUMENT TYPES
ENGINEERED SAFETY SYSTEMS
EQUIPMENT PROTECTION DEVICES
MAN-MACHINE SYSTEMS
OPERATION
PERFORMANCE
REACTOR CONTROL SYSTEMS
REACTOR INSTRUMENTATION
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTOR SHUTDOWN
RECOMMENDATIONS
REVIEWS
SAFETY
SCRAM
SHUTDOWNS