Categorization of PWR accident sequences and guidelines for fault trees: seismic initiators
This study developed a set of dominant accident sequences that could be applied generically to domestic commercial PWRs as a standardized basis for a probabilistic seismic risk assessment. This was accomplished by ranking the Zion 1 accident sequences. The pertinent PWR safety systems were compared on a plant-by-plant basis to determine the applicability of the dominant accident sequences of Zion 1 to other PWR plants. The functional event trees were developed to describe the system functions that must work or not work in order for a certain accident sequence to happen, one for pipe breaks and one for transients.
- Research Organization:
- Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
- DOE Contract Number:
- W-7405-ENG-48
- OSTI ID:
- 6513598
- Report Number(s):
- UCID-20211; ON: DE85001587
- Country of Publication:
- United States
- Language:
- English
Similar Records
Seismic qualification of equipment by means of probabilistic risk assessment. [PWR]
Methods for review and evaluation of emergency-procedure guidelines. Volume II. Applications to Westinghouse plants. [PWR]
Probability of pipe fracture in the primary coolant loop of a PWR plant. Volume 1. Summary, Load Combination Program. Project I final report
Conference
·
Fri Jan 01 00:00:00 EST 1982
·
OSTI ID:6513598
Methods for review and evaluation of emergency-procedure guidelines. Volume II. Applications to Westinghouse plants. [PWR]
Technical Report
·
Tue Mar 01 00:00:00 EST 1983
·
OSTI ID:6513598
Probability of pipe fracture in the primary coolant loop of a PWR plant. Volume 1. Summary, Load Combination Program. Project I final report
Technical Report
·
Mon Jun 01 00:00:00 EDT 1981
·
OSTI ID:6513598
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
ZION-1 REACTOR
CLASSIFICATION
COMPARATIVE EVALUATIONS
ECCS
FEEDWATER
LOSS OF COOLANT
SEISMIC EFFECTS
STEAM GENERATORS
ACCIDENTS
BOILERS
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
HYDROGEN COMPOUNDS
OXYGEN COMPOUNDS
POWER REACTORS
REACTOR PROTECTION SYSTEMS
REACTORS
THERMAL REACTORS
VAPOR GENERATORS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
ZION-1 REACTOR
CLASSIFICATION
COMPARATIVE EVALUATIONS
ECCS
FEEDWATER
LOSS OF COOLANT
SEISMIC EFFECTS
STEAM GENERATORS
ACCIDENTS
BOILERS
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
HYDROGEN COMPOUNDS
OXYGEN COMPOUNDS
POWER REACTORS
REACTOR PROTECTION SYSTEMS
REACTORS
THERMAL REACTORS
VAPOR GENERATORS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled