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Additional info for Ageing of Nucl. Powerplant Compnts. - BWR Pressure Vessel Internals (IAEA TECDOC-1471)
In both units the power is upgraded from original 660 to 840 MWe. The licensing of upgrading included the updating of safety analysis of systems including RPVIs in accordance with current code requirements. 5. Requirements in Switzerland In Switzerland there are two BWR units. One plant, a GE BWR-4 type, was taken into operation in 1971, the other, a GE BWR-6 type plant, is operating since 1984. Regulatory guidelines are provided by the HSK, the Swiss Federal Nuclear Inspectorate. Generally, requirements for design and analysis are in accordance with ASME III.
3] which prescribes in-service inspection requirements, including inspection and evaluation of defects. Reactor internals design fabrication and installation are covered by rules given in Section III of the ASME Boiler and Pressure Vessel Code, Subsection NG, Core Support Structures. Core support structures are those structures or parts of structures, which are designed to provide direct support or restraint of the core, within the reactor pressure vessel. Before Subsection NG was published, Subsection NB of the ASME Code was used as a guideline for the development of vendor-specific internals system design criteria.
Factors of stress corrosion cracking. 2. Influence of environment In the BWR environment, two major parameters influence IGSCC aggressiveness. These are water conductivity and electrochemical corrosion potential (ECP). The benefits with respect to preventing IGSCC are attained when both water conductivity and ECP are controlled. Crevices significantly increase the probability for SCC due to the highly aggressive local environment that may form within the crevice. , nozzle safe ends, shroud head bolts, access hole covers).