Containment Venting Analysis for the Shoreham Nuclear Power Station
- EG and G Idaho, Inc., Idaho Falls, ID (United States)
An evaluation of the Shoreham Mark 2 containment was performed to identify the effects of containment venting on the core melt frequency, containment failure mode, and offsite consequences. The analysis was based on the Long Island Lighting Company's updated 1988 probabilistic risk assessment of the Shoreham plant with the proposed supplemental containment system (SCS). The SCS is a filtered containment vent system based on the Swedish Filtra system installed at the Barseback Nuclear Power Station in southern Sweden. The following three different containment venting strategies were examined for their effects on plant risk: venting using the proposed Filtra system; venting using the existing equipment at Shoreham; and no venting. In addition, the consequences of containment venting were examined in conjunction with two sets of assumptions about the effects of a harsh reactor building environment, produced by containment failure or venting through the existing containment and reactor building heating, ventilating, and air conditioning systems, on the equipment located there. Specifically, the analyses studied the consequences when a harsh reactor building environment is assumed to have either no adverse effect on equipment or to fail all equipment.
- Research Organization:
- US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Office of Nuclear Regulatory Research; EG and G Idaho, Inc., Idaho Falls, ID (United States)
- Sponsoring Organization:
- USNRC; USDOE
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 5890518
- Report Number(s):
- NUREG/CR--5654; EGG--2632; ON: TI91010630
- Country of Publication:
- United States
- Language:
- English
Similar Records
An analysis of containment venting as a severe accident mitigation strategy for the BWR Mark II containment
The filtered venting system under construction at barseback
An overview of BWR Mark-I containment venting risk implications
Conference
·
Sat Mar 31 23:00:00 EST 1990
· IEEE Transactions on Nuclear Science (Institute of Electrical and Electronics Engineers); (USA)
·
OSTI ID:6892424
The filtered venting system under construction at barseback
Journal Article
·
Thu Aug 01 00:00:00 EDT 1985
· Nucl. Technol.; (United States)
·
OSTI ID:6309422
An overview of BWR Mark-I containment venting risk implications
Technical Report
·
Mon Oct 31 23:00:00 EST 1988
·
OSTI ID:5431287
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AEROSOLS
AIR CONDITIONING
AIR FILTERS
ATWS
BARSEBAECK-1 REACTOR
BWR TYPE REACTORS
CLEANING
COLLOIDS
CONTAINERS
CONTAINMENT
CONTAINMENT SYSTEMS
CONTROL ROD DRIVES
COOLING SYSTEMS
CORE SPRAY SYSTEMS
CORIUM
DAMAGE
DECONTAMINATION
DISPERSIONS
ECCS
ELEMENTS
EMERGENCY PLANS
ENERGY SYSTEMS
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
EQUIPMENT
EUROPE
FAILURE MODE ANALYSIS
FILTERS
HIGH PRESSURE COOLANT INJECTION
HYDROGEN
LOSS OF COOLANT
MELTDOWN
MITIGATION
NONMETALS
POLLUTION CONTROL EQUIPMENT
POWER REACTORS
PRESSURE SUPPRESSION
PRESSURE VESSELS
PRESSURIZATION
PROBABILITY
RCIC SYSTEMS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORE DISRUPTION
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
RHR SYSTEMS
RISK ASSESSMENT
SAFETY
SCANDINAVIA
SHOREHAM REACTOR
SOLS
SWEDEN
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL REACTORS
VENTILATION SYSTEMS
VENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WESTERN EUROPE
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AEROSOLS
AIR CONDITIONING
AIR FILTERS
ATWS
BARSEBAECK-1 REACTOR
BWR TYPE REACTORS
CLEANING
COLLOIDS
CONTAINERS
CONTAINMENT
CONTAINMENT SYSTEMS
CONTROL ROD DRIVES
COOLING SYSTEMS
CORE SPRAY SYSTEMS
CORIUM
DAMAGE
DECONTAMINATION
DISPERSIONS
ECCS
ELEMENTS
EMERGENCY PLANS
ENERGY SYSTEMS
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
EQUIPMENT
EUROPE
FAILURE MODE ANALYSIS
FILTERS
HIGH PRESSURE COOLANT INJECTION
HYDROGEN
LOSS OF COOLANT
MELTDOWN
MITIGATION
NONMETALS
POLLUTION CONTROL EQUIPMENT
POWER REACTORS
PRESSURE SUPPRESSION
PRESSURE VESSELS
PRESSURIZATION
PROBABILITY
RCIC SYSTEMS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORE DISRUPTION
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
RHR SYSTEMS
RISK ASSESSMENT
SAFETY
SCANDINAVIA
SHOREHAM REACTOR
SOLS
SWEDEN
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL REACTORS
VENTILATION SYSTEMS
VENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WESTERN EUROPE