Assessment of the leak tightness integrity of the steam generator tubes affected by ODSCC at the tube support plates
- AIB-Vincotte Nuclear, Brussels (Belgium)
An EPRI report gives a method for predicting a conservative value of the total primary-to-secondary leak rate which may occur during, a postulated steam generator depressurization accident such as a Main Steam Line Break (MSLB) in a steam generator with axial through-wall ODSCC at the TSP intersections. The Belgian utility defined an alternative method deviating somewhat from the EPRI method. When reviewing this proposed method, the Belgian safety authorities performed some calculations to investigate its conservatism. This led them to recommend some modifications to the EPRI method which should reduce its undue conservatism while maintaining the objective of conservatism in the offsite dose calculations.
- Research Organization:
- CH2M Hill, Gainesville, FL (United States); Argonne National Lab. (ANL), Argonne, IL (United States)
- OSTI ID:
- 467907
- Report Number(s):
- NUREG/CP-0154; ANL-96/14; NEA/CNRA/R-(96)1; CONF-9510423-; ON: TI97004312; TRN: 97:008373
- Resource Relation:
- Conference: CNRA/CSNI workshop on steam generator tube integrity in nuclear power plants, Oak Brook, IL (United States), 30 Oct - 2 Nov 1995; Other Information: PBD: Feb 1997; Related Information: Is Part Of Proceedings of the CNRA/CSNI workshop on steam generator tube integrity in nuclear power plants; Diercks, D.R. [Argonne National Lab., IL (United States)]; PB: 621 p.
- Country of Publication:
- United States
- Language:
- English
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