摘要 :
Volume 2, Part 1, Appendices A-C contains a description of the codes and input/output files used to perform the LaSalle Level II /III Probabilistic Risk Assessment. A chart showing the process flow is presented and the relationshi...
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Volume 2, Part 1, Appendices A-C contains a description of the codes and input/output files used to perform the LaSalle Level II /III Probabilistic Risk Assessment. A chart showing the process flow is presented and the relationship between the codes and the needed input and output data is discussed. Code listings for codes not documented elsewhere and complete or sample listings of the input and output files are also presented.
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摘要 :
Volume 2, Part 2, Appendices D-G contains a description of the codes and input/output files used to perform the LaSalle Level II /III Probabilistic Risk Assessment. A chart showing the process flow is presented and the relationshi...
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Volume 2, Part 2, Appendices D-G contains a description of the codes and input/output files used to perform the LaSalle Level II /III Probabilistic Risk Assessment. A chart showing the process flow is presented and the relationship between the codes and the needed input and output data is discussed. Code listings for codes not documented elsewhere and complete or sample listings of the input and output files are also presented.
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摘要 :
A Level III Probabilistic Risk Assessment (PRA) has been performed for LaSalle Unit 2 under the Risk Methods Integration and Evaluation Program (RMIEP) and the Phenomenology and Risk Uncertainty Evaluation Program (PRUEP). The rep...
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A Level III Probabilistic Risk Assessment (PRA) has been performed for LaSalle Unit 2 under the Risk Methods Integration and Evaluation Program (RMIEP) and the Phenomenology and Risk Uncertainty Evaluation Program (PRUEP). The report documents the phenomenological calculations and sources of uncertainty in the calculations performed with MELCOR in support of the Level II portion of the PRA. These calculations are an integral part of the Level II analysis since they provide quantitative input to the Accident Progression Event Tree (APET) and Source Term Model (LASSOR). However, the uncertainty associated with the code results must be considered in the use of the results. The MELCOR calculations performed include four integrated calculations: (1) a high-pressure short-term station blackout, (2) a low-pressure short-term station blackout, (3) an intermediate-term station blackout, and (4) a long-term station blackout. Several sensitivity studies investigating the effect of variations in containment failure size and location, as well as hydrogen ignition concentration are also documented.
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The volume presents the methodology and results of the internal event accident sequence analysis of the LaSalle Unit II nuclear power plant performed as part of the Level III Probabilistic Risk Assessment being performed by Sandia...
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The volume presents the methodology and results of the internal event accident sequence analysis of the LaSalle Unit II nuclear power plant performed as part of the Level III Probabilistic Risk Assessment being performed by Sandia National Laboratories for the Nuclear Regulatory Commission. The total internal core damage frequency has a mean value of 4.41E-05/R-yr. with a 5th percentile of 2.05E-6/R-yr., a median value of 1.64E-05/R-yr., and a 95th percentile of 1.39E-04/R-yr. The dominant sequences involve a loss of off-site power (LOSP), immediate or delayed failure of on-site AC power resulting in station-blackout, and failure of the reactor core isolation cooling system (RCIC). The events most important to risk reduction are: frequency of LOSP, non-recovery of offsite power within one hour, diesel generator (DG) cooling water pump common mode failure, and non-recoverable isolation of RCIC during station blackouts. The events most important to risk increase are: failure of various AC power circuit breakers resulting in partial loss of onsite AC power, failure to scram, and DG cooling water common mode failure. The dominant contributors to uncertainty are: control circuit failure rates, relay coil failure to energize, energized relay coils failing deenergized, frequency of LOSP, and DG failure to start.
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The project scope consists of the following major tasks: 1. Review of the current methodologies for characterizing tornado wind hazards. 2. Development of an updated windhornado characterization methodology based on probabilistic ...
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The project scope consists of the following major tasks: 1. Review of the current methodologies for characterizing tornado wind hazards. 2. Development of an updated windhornado characterization methodology based on probabilistic hazard assessment techniques. 3. Development of a computer program implementing the updated methodology. 4. Performing trial applications of the methodology to several DOE sites. 5. Formation of a Tornado Wind Hazard Expert Panel. This panel would assist in the review of current methods, identify tools and techniques to be incorporated in the updated hazard characterization methodology, be a resource for the development and interpretation of relevant historical tornado data and review the methodology developed. 6. Organizing three tornado wind hazard workshops to discuss the technical issues associated with the development of a probabilistic tornado wind hazard model.
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This NUREG is the tutorial for the Integrated Reliability and Risk Analysis System (IRRAS) Version 4.0, a state-of-the-art, microcomputer-based probabilistic risk assessment (PRA) model development and analysis tool to address key...
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This NUREG is the tutorial for the Integrated Reliability and Risk Analysis System (IRRAS) Version 4.0, a state-of-the-art, microcomputer-based probabilistic risk assessment (PRA) model development and analysis tool to address key nuclear plant safety issues. IRRAS is an integrated software tool that gives the user the ability to create and analyze fault trees and accident sequences using a microcomputer. In this tutorial, a series of lessons is provided that guides the user through basic steps common to most analyses performed with IRRAS. The tutorial is divided into two major sections: basic and additional features. The basic section contains lessons that lead the student through development of a very simple problem in IRRAS, highlighting the program's most basic features. The additional features section contains lessons that expand on basic features of IRRAS 4.0.
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