Experience with detection and disposition of PWSCC flaws in PWR pressurizer & reactor coolant system loop alloy 600 penetrations

American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP

Volumn 335, Issue , 1996, Pages 5-8

  Boggs, R Scott ^a   Joseph, Mark W ^a   Hall, John F ^b  

^a Florida Power & Light Company   (United States)

^b ABB INC   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

INSPECTION; LEAK DETECTION; NICKEL ALLOYS; NUCLEAR POWER PLANTS; REPAIR; STANDARDIZATION; STRESS CORROSION CRACKING;

NICKEL ALLOY 600; PRIMARY WATER STRESS CORROSION CRACKING (PWSCC);

PRESSURIZED WATER REACTORS;

EID: 4243180632     PISSN: 0277027X     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Article

References (4)

1. CEOG Report CE NPSD-690-P, "Evaluation of Pressurizer Penetrations and Evaluation of Corrosion After Unidentified Leakage Develops", 1992.
2. CEOG Report CEN-393-P, "Evaluation of Pressurizer Heater Sleeve Susceptibility to PWSCC", 1989.
3. McIlree, A. R., and Gorman, J. A., "Predictive Modeling for Cracking in Explosive Transitions", EPRI Workshop Feb. 22, 23, 1990 - Unpublished
4. Woodman, B., Bamford, W., Begley, J., "1111A Review of PWSCC Models as Applied to Alloy 600 Vessel Penetrations", Proceedings: 1994 EPRI Workshop on PWSCC of Alloy 600 in PWR's - EPRI Report TR-105406, pp. E9-1 / E9-13.