EPRI 2000 Session: Pressure Vessel and Primary Circuit Inspection
Inspection and Repair of Reactor Vessel Internals Bolting
J. Pfefferle, Wisconsin Electric Power Company; M. Saporito, Rochester Gas & Electric; M. G. Hacker, G. M. Mignogna, Framatome Technologies Inc.
ABSTRACT
The inspection and removal of reactor internals baffle former bolts at Point Beach Unit 2 in 1998 and 1999 and at Ginna in 1999 confirmed that these components are susceptible to cracking due the effects of plant aging. The cracking mechanism is believed to be primarily Irradiation Assisted Stress Corrosion Cracking (IASCC). A Framatome Technologies, Inc. and Master-Lee team performed the inspection and replacement activities for Wisconsin Electric Power Company and Rochester Gas & Electric; with significant new data being obtained through the non-destructive and destructive examinations. This data is being utilized nationally and internationally to access the significance of this degradation mechanism. This report summarizes the results of the Point Beach Unit 2 and Ginna ultrasonic testing and the Point Beach Unit 2 destructive tensile testing campaigns. More complete results have been recently published by EPRI (TR-114779), and are also included in a unique CD-ROM available from EPRI which allows rapid viewing of results through a graphical interface.
Publication Source: 2nd International Conference on NDE in Relation to Structural Integrity for Nuclear and Pressurized Components, May 24-26, 2000, New Orleans, Louisiana USA. Publisher: EPRI - [Homepage]
