Nuclear Regulatory Commission description

This report is a statistical description of pipe system failures. The characteristics of these failures have been derived from reports submitted by the utilities to the Nuclear Regulatory Commission. The bulk of the data is from Licensee Event Reports supplemented as necessary by plant outage and maintenance data. 

BENNETT, R.D., MILLER, W.O., WARRINER, J.B., MALONE, P.G. and MCANENY, C.C. (1984). Alternative Methods for Disposal of Low-Level Radioactive Wastes—Task 1 Description of Methods and Assessment Criteria, U.S. Nuclear Regulatory Commission Report NUREG/CR-3774, Volume 1 (National Technical Information Service, Springfield, Virginia). 

NUREG-0471, "Generic Task Problem Descriptions (Categories B, C, and D)", U. S. Nuclear Regulatory Commission, June 1978. 

This section contains the description of related engineering and analytical processes that are used generally in nuclear engineering related to the design and operation of nuclear processes. Chapters 19 and 20 describe the safety evaluations that are used for nuclear facilities. Chapter 19 introduces the risk assessment and safety analysis process that is used for nuclear reactors that are licensed in the United States by the Nuclear Regulatory Commission (NRC). This process has evolved from a relatively simple safety analysis used in the 1950s to a detailed risk assessment process that is used today. Chapter 20 describes the process used in the United States by the Department of Energy for safety analysis of its facilities. It is more prescriptive and less probability and risk based than the process used by the NRC. 

Methodological Description. Washington DC US Nuclear Regulatory Commission (USNRC). 

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