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U.S. Department of Energy
Office of Scientific and Technical Information

Steam generator operating experience: Update for 1984-1986

Technical Report ·
OSTI ID:7014047

This report summarizes operational events and degradation mechanisms affecting pressurized water reactor steam generator integrity, provides updated inspection results reported in 1984, 1985, and 1986, and highlights both prevalent problem areas and advances in improved equipment test practices, preventive measures, repair techniques, and replacement procedures. It describes equipment design features of the three major suppliers and discusses 68 plants in detail. Steam generator degradation mechanisms include intergranular stress corrosion cracking, primary water stress corrosion cracking, pitting, intergranular attack, and vibration wear that effects tube integrity and causes leakage. Plugging, sleeving heat treatment, peening, chemical cleaning, and steam generator replacements are described and regulatory instruments and inspection guidelines for nondestructive evaluations and girth weld cracking are discusses. The report concludes that although degradation mechanisms are generally understood, the elimination of unscheduled plant shutdowns and costly repairs resulting from leaking tubes has not been achieved. Highlights of steam generator research and unresolved safety issues are discussed. 21 refs., 8 tabs.

Research Organization:
Nuclear Regulatory Commission, Washington, DC (USA). Div. of Engineering and System Technology; Science Applications International Corp., McLean, VA (USA)
OSTI ID:
7014047
Report Number(s):
NUREG/CR-5150; SAIC-87/3014; ON: TI88012785
Country of Publication:
United States
Language:
English