Containment venting analysis for the Peach Bottom Atomic Power Station
Technical Report
·
OSTI ID:6660458
The extent to which containment venting is an effective means of preventing or mitigating the consequences of overpressurization during severe accidents was evaluated for the Peach Bottom Atomic Power Station Units 2 and 3 (boiling water reactors with Mark I containments). Detailed analyses were conducted on operator performance, equipment performance, and the physical phenomenology for three severe accident sequences currently identified as being important contributors to risk. The results indicate that containment venting can be effective in reducing risk for several classes of severe accidents but, based on procedures in draft form and equipment in place at the time of the analyses, has limited potential for further reducing the risk for severe accidents currently identified as being important contributors to the risk for Peach Bottom.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA); Battelle Columbus Div., OH (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 6660458
- Report Number(s):
- NUREG/CR-4696; EGG-2464; ON: TI87007118
- Country of Publication:
- United States
- Language:
- English
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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
BUILDINGS
BWR TYPE REACTORS
COMPUTER CALCULATIONS
CONTAINMENT
CONTAINMENT BUILDINGS
CONTAINMENT SYSTEMS
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
FAULT TREE ANALYSIS
FLUID MECHANICS
HYDRAULICS
MECHANICS
PEACH BOTTOM-2 REACTOR
PEACH BOTTOM-3 REACTOR
POWER REACTORS
PRESSURE RELEASE
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BUILDINGS
BWR TYPE REACTORS
COMPUTER CALCULATIONS
CONTAINMENT
CONTAINMENT BUILDINGS
CONTAINMENT SYSTEMS
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
FAULT TREE ANALYSIS
FLUID MECHANICS
HYDRAULICS
MECHANICS
PEACH BOTTOM-2 REACTOR
PEACH BOTTOM-3 REACTOR
POWER REACTORS
PRESSURE RELEASE
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
WATER COOLED REACTORS
WATER MODERATED REACTORS