Izvestia Vysshikh Uchebnykh Zawedeniy. Yadernaya Energetika

The peer-reviewed scientific and technology journal. ISSN: 0204-3327

Results of a preoperational inspection at unit №1 of Novovoronezh NPP II

10/02/2017 2017 - #03 Nuclear power plants

Urazov O.V.

DOI: https://doi.org/10.26583/npe.2017.3.13

UDC: 621.311.25

A preoperational inspection for the state of the parent metal and welded joints in components and pipelines at unit № 1 of Novovoronezh NPP II is discussed. Peculiarities involved in the inspection of the reactor vessel welded joints facing the anticorrosive plating and the steam generator heatexchange tubes using innovative test systems and techniques are considered.

To inspect the reactor vessel, «Computational and Engineering Case Study RTO-KR-UZA-15-[1] was developed specifically, based on which the VVER-1200 reactor vessel welded joints were inspected, using a manual ultrasonic technique, through the anticorrosive plating.

A technology [2], developed by JSC «Center for Eddy-Current Testing «Politest» and by the Scientific and Technical Center for Emergency Engineering Operations at Nuclear Power Plants, a branch of JSC «Concern Rosenergoatom», and used for the first time at a Russian NPPs at the stage of preoperational incoming inspection for the state of the parent metal and welded joints in components and pipelines at unit № 1 of Novovoronezh NPP II using «Politest-PG», an innovative system for the automated eddy-current testingof the steam generator heat-exchange tubes at nuclear power plants with VVER reactors, was used to inspect the heat-exchange tubes in all of the steam generators. As a result of the test, the steam generator tubes were found to have discontinuities with the maximum depth of up to 10% of the nominal wall thickness which is tolerable. The inspection results have confirmed the unit to be fit for commercial operation.


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preoperational inspection ultrasonic testing ultrasonic testing technology eddy-current testing reactor vessel steam generator