Assessment of severe accident prevention and mitigation features: BWR, Mark II containment design
Technical Report
·
OSTI ID:6845752
Plant features and operator actions, which have been found to be important in either preventing or mitigating severe accidents in BWRs with Mark II containments (BWR Mark II's) have been identified. These features and actions were developed from insights derived from reviews of in-depth risk assessments performed specifically for the Limerick and Shoreham plants and from other relevant studies. Accident sequences that dominate the core-damage frequency and those accident sequences that are of potentially high consequence were identified. Vulnerabilities of the BWR Mark II to severe-accident containment loads were also noted. In addition, those features of a BWR Mark II, which are important for preventing core damage and are available for mitigating fission-product release to the environment were also identified. This report is issued to provide focus to an analyst examining an individual plant. This report calls attention to plant features and operator actions and provides a list of deterministic attributes for assessing those features and actions found to be helpful in reducing the overall risk for Mark II plants. Thus, the guidance is offered as a resource in examining the subject plant to determine if the same, or similar, plant features and operator actions will be of value in reducing overall plant risk. This report is intended to serve solely as guidance.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (USA). Div. of Reactor and Plant Systems; Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 6845752
- Report Number(s):
- NUREG/CR-4920-Vol.2; BNL-NUREG-52070-Vol.2; ON: TI88014806
- Country of Publication:
- United States
- Language:
- English
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22 GENERAL STUDIES OF NUCLEAR REACTORS
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ACCIDENTS
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CONTAINMENT SYSTEMS
DESIGN
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REACTOR CORE DISRUPTION
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210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BWR TYPE REACTORS
CONTAINMENT
CONTAINMENT SYSTEMS
DESIGN
ENGINEERED SAFETY SYSTEMS
MITIGATION
PERFORMANCE
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTORS
RISK ASSESSMENT
WATER COOLED REACTORS
WATER MODERATED REACTORS