Root cause evaluation and repair of alloy 82/182 J-groove weld cracking of reactor vessel head penetrations at North Anna Unit 2

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

Volumn 437, Issue , 2002, Pages 179-186

  Bennetch, J I ^a   Modzelewski, G E ^a   Spain, L L ^a   Rao, G V ^a  

^a Dominion   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

WELD CRACKING;

BORON COMPOUNDS; FERRITE; LEAK DETECTION; NUCLEAR REACTORS; STEEL; WELDING;

CRACK INITIATION;

EID: 0036385284     PISSN: 0277027X     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1115/PVP2002-1189     Document Type: Conference Paper

References (10)

1. United States Nuclear Regulatory Commission (USNRC) Generic Letter (GL) 97-01, "Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations," dated April 1, 1997.
2. Robinson, M. R., Duke Power Company, "Oconee Unit 1 and Unit 3 Reactor Vessel Head Leakage. Cracking of RV Head Penetrations Due to Primary Water Stress Corrosion Cracking (PWSCC), presented at the April 12, 2001 NRC meeting with the Nuclear Energy Institute and the Electric Power Research Institute (EPRI) Materials Reliability Program Regarding Control Rod Drive Mechanism (CRDM) Nozzle Cracking Issues, Rockville, MD, April 12, 2001.
3. USNRC Informational Notice 2001-005, "Through-Wall Circumferential Cracking of Reactor Pressure Vessel Head Control Rod Drive Mechanism Penetration Nozzles at Oconee Nuclear Station, Unit 3", April 30, 2001.
4. USNRC Bulletin (BL) 2001-01, "Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles, dated August 3, 2001.
5. Rao, Gutti V. and Bennetch, J. "Metallurgical Investigation of Cracking of the Alloy 82/182 J-Groove Weld of the Reactor Vessel Head Penetration Joint at North Anna Unit 2 Station," Westinghouse report WCAP-15777, Jan. 2002.
6. B. A. Bishop, G. V. Rao, W. H. Bamford and S. L. Abbot "R V Closure Head Penetration Supplemental Assessment of NRC SER Issues" Westinghouse Report WCAP-14219, Rev. 1, October 1995.
7. "Crack Growth and Microstructrual Characterization of Alloy 600 PWR Vessel Head Penetration Materials," Electric Power Research Institute (EPRI) report TR-109136, December 1997.
8. "RV Closure Head Penetration Tube ID Weld Overlay Repair," Westinghouse Report WCAP-13998, Rev. 1, March 1994.
9. Attachment 1 to Donald C. Cook Nuclear Plant Unit 2, Additional Information Requested by USNRC BL 2001-01, AEP:NRC:2054, Docket Number 50-316, March 28, 2002, Westinghouse Report WDI-RVHP-002, "D.C. Cook 2 Reactor Vessel Head Penetration Inspection Final Report, March 20, 2002.
10. "Aging Management Review and Time Limited Aging Analysis for the North Anna Units 1 and 2 Reactor Pressure Vessels," WCAP-15268, Rev. 1, September 2001.