Improved reliability of residual heat removal capability in pressurized water reactors
Conference
·
OSTI ID:6174637
The work presented in this paper was performed by Brookhaven National Laboratory (BNL) in supporting Nuclear Regulatory Commission's (NRC) effort towards the resolution of Generic Issue 99 ''Reactor Coolant System (RCS)/Residual Heat Removal (RHR) Suction Line Interlocks on Pressurized Water Reactors (PWRs).'' Operational experience of US PWRs indicates that numerous loss of RHR events have occurred during plant shutdown. Of particular significance is the loss of RHR suction due to the inadvertent closure of the RHR suction/isolation valves or an excess lowering of the water level in the reactor vessel. In the absence of prompt mitigative action by the operator, the core may become uncovered. Various design/operational changes have been proposed. The objective of this paper is to estimate the improvement in the RHR reliability and the risk reduction potential provided by those proposed RHR design/operational changes. The benefits of those changes are expressed in terms of the reduction in the frequency of loss-of-cooling events and the frequency of core damage.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 6174637
- Report Number(s):
- BNL-NUREG-39975; CONF-870820-5; ON: DE87012873
- Country of Publication:
- United States
- Language:
- English
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·
Thu Dec 31 23:00:00 EST 1987
·
OSTI ID:6370790
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· Nuclear Technology; (United States)
·
OSTI ID:6934100
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
AFTER-HEAT REMOVAL
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
HEAT TRANSFER
LOSS OF COOLANT
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SHUTDOWN
REACTORS
RELIABILITY
REMOVAL
RHR SYSTEMS
RISK ASSESSMENT
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
AFTER-HEAT REMOVAL
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
HEAT TRANSFER
LOSS OF COOLANT
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SHUTDOWN
REACTORS
RELIABILITY
REMOVAL
RHR SYSTEMS
RISK ASSESSMENT
SHUTDOWNS
WATER COOLED REACTORS
WATER MODERATED REACTORS