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Anon., 1996d. Salem-1 steam generator replete with potential new crack type. Nucleonics Week 37(22), 5.
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Anon., 1996e. ComEd disputes Braidwood tube pull with NRC as more Byron flaws found. Nucleonics Week 37(17), 4.
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Nucleonics Week
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Nucleonics Week
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CMP was to purchase power from PECO-owned Maine Yankee
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Fournel, J.C., 1993. A statistical insight in the suspected relations between PWSCC in R.T.Z. and IGASCC on TSP's. Paper 3. EPRI Workshop on Steam Generator Secondary Side IGA/SCC, October 14-15, 1993, Minneapolis.
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Hundley, F.D., 1993. Examination of Farley Unit-1 hot leg steam generator tube. EPRI Workshop on Steam Generator Secondary Side IGA/SCC, Minneapolis, October 14-15, 1993.
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G.J. Theus, & J.R. Weeks. Warrendale, PA: The Metallurgical Society
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NUREG/CR-5117. U.S. Nuclear Regulatory Commission, Washington, DC, May
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Doel 4: Secondary side corrosion mechanisms and effects of phosphate injection. Paper A3
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Laire C., Stubbe J., Pierson E. Doel 4: secondary side corrosion mechanisms and effects of phosphate injection. Paper A3. Proc. IAEA Specialists Meeting on Steam Generator Problems and Replacement, Madrid, Spain, December 13-16, 1993. 1994;International Atomic Energy Agency, Vienna.
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R.E. Gold, & E.P. Simonen. Warrendale, PA: The Minerals, Metals, and Materials Society
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Electric Power Research Institute, Palo Alto, CA, May
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Alloy 600 primary water SCC: A user's (Belgian Electricity Board) point of view
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Arlie, France, April 6-9, 1993
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Secondary side corrosion at Doel 4 - mechanisms and effects of phosphate injection
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Hideout return in EDF units
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Minneapolis, October 14-15, 1993
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Stutzmann, A., Nordmann, F., 1993. Hideout return in EDF units. EPRI Workshop on Steam Generator Secondary Side IGA/SCC, Minneapolis, October 14-15, 1993.
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Potential Failure of Westinghouse Steam Generator Tube Mechanical Plugs
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U.S. Nuclear Regulatory Commission, 1989a. Potential Failure of Westinghouse Steam Generator Tube Mechanical Plugs, NRC Information Notice 89-33. U.S. Nuclear Regulatory Commission, Washington, DC, March 23.
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U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission, Washington, DC, May 15
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Potential for Stress Corrosion Cracking in Steam Generator Tube Plugs Supplied by Babcock and Wilcox
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U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission, Washington, DC, September 8
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U.S. Nuclear Regulatory Commission, 1989c. Potential for Stress Corrosion Cracking in Steam Generator Tube Plugs Supplied by Babcock and Wilcox, NRC Information Notice 89-65. U.S. Nuclear Regulatory Commission, Washington, DC, September 8.
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U.S. Nuclear Regulatory Commission, 1990 U.S. Nuclear Regulatory Commission, Washington, DC, November 14
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U.S. Nuclear Regulatory Commission, 1990. Failure of Westinghouse Steam Generator Tube Mechanical Plugs, NRC Bulletin 89-01, Supplement 1.U.S. Nuclear Regulatory Commission, Washington, DC, November 14.
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U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission, Washington, DC, June 28
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U.S. Nuclear Regulatory Commission, 1991a. Failure of Westinghouse Steam Generator Tube Mechanical Plugs, NRC Bulletin 89-01, Supplement 2.U.S. Nuclear Regulatory Commission, Washington, DC, June 28.
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49
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0342715372
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Recent Incidents Involving Rapid Increases in Primary-to-Secondary Leak Rate
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U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission, Washington, DC, July 5
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U.S. Nuclear Regulatory Commission, 1991b. Recent Incidents Involving Rapid Increases in Primary-to-Secondary Leak Rate, NRC Information Notice 91-43.U.S. Nuclear Regulatory Commission, Washington, DC, July 5.
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50
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Operation with Steam Generator Tubes Seriously Degraded
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U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission, Washington, DC, December 7
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U.S. Nuclear Regulatory Commission, 1992. Operation with Steam Generator Tubes Seriously Degraded, NRC Information Notice 92-80.U.S. Nuclear Regulatory Commission, Washington, DC, December 7.
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51
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85031535124
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Unanticipated Crack in a Particular Heat of Alloy 600 Used for Westinghouse Mechanical Plugs for Steam Generator Tubes
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U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission, Washington, DC, December 22
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U.S. Nuclear Regulatory Commission, 1994a. Unanticipated Crack in a Particular Heat of Alloy 600 Used for Westinghouse Mechanical Plugs for Steam Generator Tubes, NRC Information Notice 94-87. U.S. Nuclear Regulatory Commission, Washington, DC, December 22.
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Potential Failure of Steam Generator Tubes with Kinetically Welded Sleeves
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U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission, Washington, DC, January 19
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U.S. Nuclear Regulatory Commission, 1994b. Potential Failure of Steam Generator Tubes with Kinetically Welded Sleeves, NRC Information Notice 94-05. U.S. Nuclear Regulatory Commission, Washington, DC, January 19.
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53
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U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission, Washington, DC, August 30
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U.S. Nuclear Regulatory Commission, 1994d. Operational Experience on Steam Generator Tube Leaks and Tube Ruptures, NRC Information Notice 94-62.U.S. Nuclear Regulatory Commission, Washington, DC, August 30.
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U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission, Washington, DC, December 23
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U.S. Nuclear Regulatory Commission, 1994e. Inservice Inspection Deficiencies Result in Severely Degraded Steam Generator Tubes, NRC Information Notice 94-88.U.S. Nuclear Regulatory Commission, Washington, DC, December 23.
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55
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U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission, Washington, DC, April 28
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U.S. Nuclear Regulatory Commission, 1995a. Circumferential Cracking of Steam Generator Tubes, NRC Generic Letter 95-03.U.S. Nuclear Regulatory Commission, Washington, DC, April 28.
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Supplemental Information to Generic Letter 95-03, 'Circumferential Cracking of Steam Generator Tubes'
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U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission, Washington, DC, September 20
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U.S. Nuclear Regulatory Commission, 1995b. Supplemental Information to Generic Letter 95-03, 'Circumferential Cracking of Steam Generator Tubes', NRC Generic Letter 95-40.U.S. Nuclear Regulatory Commission, Washington, DC, September 20.
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U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission, Washington, DC, June 21
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U.S. Nuclear Regulatory Commission, 1996. Results of Steam Generator Tube Examinations, NRC Information Notice 96-38.U.S. Nuclear Regulatory Commission, Washington, DC, June 21.
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85031528478
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B&W Once-Through Steam Generator Tube Inspection Findings
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U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission, Washington, DC, July 10
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U.S. Nuclear Regulatory Commission, 1997a. B&W Once-Through Steam Generator Tube Inspection Findings, NRC Information Notice 97-49. U.S. Nuclear Regulatory Commission, Washington, DC, July 10.
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U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission, Washington, DC, May 19
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U.S. Nuclear Regulatory Commission, 1997b. Degradation in Small-Radius U-Bend Regions of Steam Generator Tubes, NRC Information Notice 97-26. U.S. Nuclear Regulatory Commission, Washington, DC, May 19.
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