The degradation of Unit 4 SG tubing by IGA/SCC has recently limited both the operating period and end of life predictions for Unit 4 since restart in late 2003. SG4 has experienced the most significant damage with substantial increases in both initiation and growth rates from 2005 through the spring of 2007. A detailed review of the occurrence of circumferential OD IGA/SCC at the RTZ in the HL TTS region of Bruce 4 steam generator tubes has led a conclusion that it is probable that the IGA/SCC has been the result of attack by partially reduced sulfur species such as tetrathionates and thiosulfates during periods of low temperature exposure. It is believed that attack of this type has most likely occurred during startup evolutions following outages as the result the development of aggressive reduced sulfur species in the TTS region during periods when the boilers were fully drained for maintenance activities. The modification of outage practices to limit secondary side oxygen ingress in the spring of 2007 has arrested the degradation and has had significant affects on the allowable operating interval and end of life predictions for the entire unit.
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17th International Conference on Nuclear Engineering
July 12–16, 2009
Brussels, Belgium
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4351-2
PROCEEDINGS PAPER
FFS Issues for Steam Generator Tube (Top of Tubesheet) Intergranular Attack/Stress Corrosion Cracking
David Durance,
David Durance
Bruce Power, Toronto, ON, Canada
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John Roberts,
John Roberts
CANTECH Associates Ltd., Toronto, ON, Canada
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Jeff Gorman
Jeff Gorman
Dominion Engineering, VA
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David Durance
Bruce Power, Toronto, ON, Canada
Ken Sedman
Bruce Power, Toronto, ON, Canada
John Roberts
CANTECH Associates Ltd., Toronto, ON, Canada
Jeff Gorman
Dominion Engineering, VA
Paper No:
ICONE17-75599, pp. 583-588; 6 pages
Published Online:
February 25, 2010
Citation
Durance, D, Sedman, K, Roberts, J, & Gorman, J. "FFS Issues for Steam Generator Tube (Top of Tubesheet) Intergranular Attack/Stress Corrosion Cracking." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems. Brussels, Belgium. July 12–16, 2009. pp. 583-588. ASME. https://doi.org/10.1115/ICONE17-75599
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