A time-dependent human reliability analysis for a PWR (Pressurized Water Reactor) at shutdown
Conference
·
OSTI ID:6370790
Pressurized Water Reactors (PWRs) in the USA have experience numerous loss of residual heat removal (RHR) events during reactor shutdown and cooled down conditions. Of particular significance is the loss of the RHR system due to the inadvertent closure of the RHR suction valves on the lowering of the water level in the reactor vessel during required partially drained reactor coolant system (RCS) operations. Brookhaven National Laboratory (BNL) performed an assessment of the core damage frequency (CDF) due to loss of RHR events in an outage. The loss of RHR followed by failure of the operators to respond was found to be the dominant contributor to core damage. The objective of this paper is to present the human reliability model used to assess the associated human error probabilities (HEPs). The model includes determination of the time available for operator action as a function of the time after shutdown, partitioning of the time into a diagnosis phase and a recovery action phase, and assessment of the HEPs. The HEPs were then integrated into the loss of cooling event trees for CDF quantification. 7 refs.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 6370790
- Report Number(s):
- BNL-NUREG-41399; CONF-890405-3; ON: DE88013679
- Country of Publication:
- United States
- Language:
- English
Similar Records
Improved reliability of residual heat removal capability in pressurized water reactors
An estimation of core damage frequency of a pressurized water reactor during midloop operation due to loss of residual heat removal
Analysis of loss of off-site power with a PWR at shutdown
Conference
·
Wed Dec 31 23:00:00 EST 1986
·
OSTI ID:6174637
An estimation of core damage frequency of a pressurized water reactor during midloop operation due to loss of residual heat removal
Journal Article
·
Sat Jul 01 00:00:00 EDT 1995
· Nuclear Technology
·
OSTI ID:89647
Analysis of loss of off-site power with a PWR at shutdown
Conference
·
Wed Dec 31 23:00:00 EST 1986
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6897942
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COOLING SYSTEMS
DAMAGE
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HUMAN FACTORS
HYDRAULICS
LOSS OF COOLANT
MECHANICS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR SAFETY
REACTOR SHUTDOWN
REACTORS
RELIABILITY
SAFETY
SHUTDOWNS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COOLING SYSTEMS
DAMAGE
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HUMAN FACTORS
HYDRAULICS
LOSS OF COOLANT
MECHANICS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR SAFETY
REACTOR SHUTDOWN
REACTORS
RELIABILITY
SAFETY
SHUTDOWNS
WATER COOLED REACTORS
WATER MODERATED REACTORS