Validation of Sizewell ``B`` ultrasonic inspections -- Messages for performance demonstration
- AEA Technology, Warrington (United Kingdom)
At the time that the decisions leading to the construction of the Sizewell ``B`` plant were being made, public concern over the potential hazards of nuclear power was increasing. This concern was heightened by the accident at USA`s Three Mile Island plant. The result of this and public pressure was that an extensive public inquiry was held in addition to the UK`s normal licensing process. Part of the evidence to the inquiry supporting the safety case relied upon the ability of ultrasonic inspections to demonstrate that the Reactor Pressure Vessel (RPV) and other key components were free from defects that could threaten structural integrity. Evidence from a variety of trials designed to investigate the performance capability of ultrasonic inspection revealed that although ultrasonic inspection had the potential to satisfy this requirement its performance in practice was heavily dependent upon the details of application. It was therefore generally recognized that some form of inspection validation was required to provide assurance that the equipment, procedures and operators to be employed were adequate for purpose. The concept of inspection validation was therefore included in the safety case for the licensing of Sizewell ``B``. The UK validation trials covering the ultrasonic inspections of the Sizewell ``B`` PWR Reactor Pressure Vessel are now nearing completion. This paper summarizes the results of the RPV validations and considers some of the implications for ASME 11 Appendix 8 the US code covering performance demonstration.
- OSTI ID:
- 72580
- Report Number(s):
- CONF-931061--; ISBN 0-87170-506-0
- Country of Publication:
- United States
- Language:
- English
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