Technical Basis Document for at-Power Significance Determination Process (SDP) Notebooks.

Azarm, M. A. ; Smanta, P. K. ; Martinez-Guridi, G. ; Higgins, J.

Brookhaven National Laboratory

关键词: Manuals;    Recommendations;    22 General Studies Of Nuclear Reactors;    Us Nrc;    Risk Assessment;   

RP-ID  :  BNL--72341-2004
RP-ID  :  AC02-98CH10886
RP-ID  :  15007854

美国|英语

来源: UNT Digital Library

【 摘 要 】

To support the assessment of inspection findings as part of the risk-informed inspection in the United States Nuclear Regulatory Commission's (USNRC's) Reactor Oversight Process (ROP), risk inspection notebooks, also called significance determination process (SDP) notebooks, have been developed for each of the operating plants in the United States. These notebooks serve as a tool for assessing risk significance of inspection findings along with providing an engineering understanding of the significance. Plant-specific notebooks are developed to capture plant-specific features, characteristics, and analyses that influence the risk profile of the plant. At the same time, the notebooks follow a consistent set of assumptions and guidelines to assure consistent treatment of inspection findings across the plants. To achieve these objectives, notebooks are designed to provide specific information that are unique both in the manner in which the information is provided and in the way the screening risk assessment is carried out using the information provided. The unique features of the SDP notebooks, the approaches used to present the information for assessment of inspection findings, the assumptions used in consistent modeling across different plants with due credit to plant-specific features and analyses form the technical basis of the SDP notebooks. In this document, the unique features and the technical basis for the notebooks are presented. The types of information that are included and the reasoning/basis for including that information are discussed. The rules and basis for developing the worksheets that are used by the inspectors in the assessment of inspection findings are presented. The approach to modeling plants' responses to different initiating events and specific assumptions/considerations used for each of the reactor types are also discussed.