Abstract

IEEE 1012 [1] describes the SDLC phase activities for software independent verification and validation (IV & V) for nuclear power plant in truly general and conceptual manner, which requires the upward and/or downward tailoring on its interpretation for practical IV & V. It contains crucial and encompassing check points and guidelines to analyze the design integrity, without addressing the formalized and the specific criteria for IV & V activities confirming the technical integrity. It is necessary to list up the inspection viewpoint via interpretation of the standard that is practical review points checking design consistency. For fruitful IV & V of Control Element Driving Mechanism Control System (CEDMCS) software for Yonggwang Nuclear Power Plant unit 3 & 4, the specific viewpoints and approach are necessary based on the guidelines of IEEE 1012 to enhance the system quality by considering the level of implementation of the theoretical and the practical IV & V. Additionally IV & V guideline of IEEE 1012 does not specifically provide the concrete measure considering the system characteristics of CEDMCS. This paper provides the seven (7) characteristic criteria for CEDMCS IV & V, and by applying these viewpoints, the design analysis such as function, performance, interface and exception, backward and forward requirement traceability analysis has been conducted. The requirement, design, implementation, and test phase were only considered for IV & V in this project. This article also provides the translation of code to map theoretical verification and validation into practical verification and validation. This paper emphasizes the necessity of the intensive design inspection and walkthrough for requirement phase to resolve the design faults because the IV & V of early phase of SDLC obviously contributes to find out most of critical design inconsistency. Especially for test phase IV & V, it is strongly recommended to prepare the test plan document which is going to be the basis for the test coverage selection and test strategy. This test plan document should be based on the critical characteristics of function and performance of CEDMCS. Also to guarantee the independency of V & V organization participating in this project, and to acquire the full package of design details for IV & V, the systematic approach and efforts with an aspect of management is highlighted among the participants.

Highlights

  • Due to the hardware aging and obsolescence, the upgrade of Control Element Driving Mechanism Control System (CEDMCS) for Yonggwang 3 & 4, and Ulchin 3 & 4 nuclear power plants was brought up as necessary

  • Yonggwang unit 3 & 4 and Ulchin unit 3 & 4 that is one of the Korea Standard Nuclear Plant (KSNP) are upgraded with new hardware where the CEDMCS software is running

  • Independent verification and validation has been conducted throughout the Software Development Life Cycle (SDLC)

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Summary

Introduction

Due to the hardware aging and obsolescence, the upgrade of CEDMCS for Yonggwang 3 & 4, and Ulchin 3 & 4 nuclear power plants was brought up as necessary. This approach is enhancing the reliability of the CEDMCS software system

Design Group
Identification of Critical Characteristics
Identification of the Interface
Cohesion and Coupling
Reliability of Function and Performance
Test Coverage
Statistical Distribution of Anomaly Data
High Level Design Error
The Test Preparation of CEDMCS
Conclusions
Full Text
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