Individual plant examination program: Perspectives on reactor safety and plant performance. Part 6, appendices A, B, and C

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This report provides perspectives gained by reviewing 75 Individual Plant Examination (IPE) submittals pertaining to 108 nuclear power plant units. IPEs are probabilistic analyses that estimate the core damage frequency (CDF) and containment performance for accidents initiated by internal events (including internal flooding, but excluding internal fire). The U.S. Nuclear Regulatory Commission (NRC), Office of Nuclear Regulatory Research, reviewed the WE submittals with the objective of gaining perspectives in three major areas: (1) improvements made to individual plants as a result of their IPEs and the collective results of the IPE program, (2) plant-specific design and operational features and modeling ... continued below

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47 p.

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Creator: Unknown. December 1, 1997.

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  • U.S. Nuclear Regulatory Commission
    Publisher Info: Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Technology
    Place of Publication: Washington D.C.

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Description

This report provides perspectives gained by reviewing 75 Individual Plant Examination (IPE) submittals pertaining to 108 nuclear power plant units. IPEs are probabilistic analyses that estimate the core damage frequency (CDF) and containment performance for accidents initiated by internal events (including internal flooding, but excluding internal fire). The U.S. Nuclear Regulatory Commission (NRC), Office of Nuclear Regulatory Research, reviewed the WE submittals with the objective of gaining perspectives in three major areas: (1) improvements made to individual plants as a result of their IPEs and the collective results of the IPE program, (2) plant-specific design and operational features and modeling assumptions that significantly affect the estimates of CDF and containment performance, and (3) strengths and weaknesses of the models and methods used in the IPEs. These perspectives are gained by assessing the core damage and containment performance results, including overall CDF, accident sequences, dominant contributions to component failure and human error, and containment failure modes. In particular, these results are assessed in relation to the design and operational characteristics of the various reactor and containment types, and by comparing the IPEs to probabilistic risk assessment characteristics. Methods, data, boundary conditions, and assumptions used in the IPEs are considered in understanding the differences and similarities observed among the various types of plants.

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47 p.

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INIS; OSTI as TI98002677

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  • Other Information: PBD: Dec 1997

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  • Other: TI98002677
  • Report No.: NUREG--1560-Vol.3
  • DOI: 10.2172/576992 | External Link
  • Office of Scientific & Technical Information Report Number: 576992
  • Archival Resource Key: ark:/67531/metadc692660

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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  • December 1, 1997

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  • Aug. 14, 2015, 8:43 a.m.

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  • April 22, 2016, 6:36 p.m.

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Individual plant examination program: Perspectives on reactor safety and plant performance. Part 6, appendices A, B, and C, report, December 1, 1997; Washington D.C.. (digital.library.unt.edu/ark:/67531/metadc692660/: accessed October 22, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.