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

Steam generator operating experience, update for 1989--1990

Technical Report ·
OSTI ID:10108021

This report summarizes operational events and degradation mechanisms affecting pressurized water reactor steam generator integrity. It provides: results of 1989 and 1990 steam generator inspections; highlights prevalent problem areas; improvements that have been made in nondestructive testing methods; preventive measures; repair techniques; and replacement procedures. It describes the equipment of the three (3) major suppliers and discusses recent examinations of 76 plants. Major areas of concern are the steam generator degradation mechanisms that affect tube integrity or cause tube leakage and tube failure. These include; (1) intergranular attack (IGA); (2) intergranular stress corrosion cracking (IGSCC); (3) primary water stress corrosion cracking (PWSCC); (4) pitting; and (5) vibrational wear and fatigue. Also discussed are plugging, sleeving, heat treatment, peening, chemical cleaning, and steam generator replacements. The current status of regulatory instruments and inspection guidelines for ensuring the steam generator integrity, is discussed with the highlights of steam generator research. New potential safety issues such as circumferential cracking and tube plug cracking are also discussed.

Research Organization:
Nuclear Regulatory Commission, Washington, DC (United States). Div. of Engineering Technology; Viking Systems International, Inc., Pittsburgh, PA (United States)
Sponsoring Organization:
Nuclear Regulatory Commission, Washington, DC (United States)
OSTI ID:
10108021
Report Number(s):
NUREG/CR--5796; ON: TI92004287
Country of Publication:
United States
Language:
English