Containment-emergency-sump performance. Technical findings related to Unresolved Safety Issue A-43. [PWR]
This report summarizes key technical findings related to the Unresolved Safety Issue A-43, Containment Emergency Sump Performance, and provides recommendations for resolution of attendant safety issues. The key safety questions relate to: (a) effects of insulation debris on sump performance; (b) sump hydraulic performance as determined by design features, submergence, and plant induced effects, and (c) recirculation pump performance wherein air and/or particulate ingestion can occur. The technical findings presented in this report provide information relevant to the design and performance evaluation of the containment emergency sump.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (USA). Office of Nuclear Reactor Regulation
- Sponsoring Organization:
- U.S. Nuclear Regulatory Commission (NRC)
- OSTI ID:
- 6210299
- Report Number(s):
- NUREG-0897; ON: DE83901719
- Country of Publication:
- United States
- Language:
- English
Similar Records
Containment Emergency Sump Performance. Technical findings related to Unresolved Safety Issue A-43. Revision 1
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Technical Report
·
Tue Oct 01 00:00:00 EDT 1985
·
OSTI ID:6330602
Methodology for evaluation of insulation-debris effects. Containment emergency sump performance-unresolved safety issue A-43
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Wed Sep 01 00:00:00 EDT 1982
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OSTI ID:6733320
Containment-emergency-sump studies to investigate Unresolved Safety Issue A-43. [PWR; BWR]
Conference
·
Thu Dec 31 23:00:00 EST 1981
·
OSTI ID:5092762
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
CONTAINMENT
CONTAINMENT SYSTEMS
COOLING SYSTEMS
ECCS
ENERGY SYSTEMS
ENGINEERED SAFETY SYSTEMS
FLOW BLOCKAGE
FLOW RATE
FLUID MECHANICS
HYDRAULICS
LOSS OF COOLANT
MECHANICS
PERFORMANCE
PRESSURE GRADIENTS
PUMPS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
RHR SYSTEMS
SAFETY
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
CONTAINMENT
CONTAINMENT SYSTEMS
COOLING SYSTEMS
ECCS
ENERGY SYSTEMS
ENGINEERED SAFETY SYSTEMS
FLOW BLOCKAGE
FLOW RATE
FLUID MECHANICS
HYDRAULICS
LOSS OF COOLANT
MECHANICS
PERFORMANCE
PRESSURE GRADIENTS
PUMPS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
RHR SYSTEMS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS