ML080800506

Licensee Meeting Handouts, 03/13/2008 Summary of Meeting with Eight Operating Nuclear Power Plant Licensees to Discuss Emerging Metallurgical Issues Certain Welds in Reactor Coolant System for Pressurized-Water Reactors

ML080800506
Person / Time
Site:	Palo Verde, Braidwood, Summer, Seabrook, Vogtle, Waterford, South Texas, Comanche Peak
Issue date:	03/13/2008
From:	NRC/NRR/ADES/DCI
To:
Markley, M T, NRR/DORL/LP4, 301-415-5723
Shared Package
ML080800024	List: ML080800029 ML080800506
References
Download: ML080800506 (1)

Text

Conclusions

• The indications on the pressurizer safety nozzle welds did not represent an immediate safety concern

• Encoded phased array examination results have determined that the indications are fabrication induced defects

• Indications are acceptable under original ASME construction code requirements and do not challenge structural integrity of the weld

• Results were confirmed by radiography

• The Advanced Finite Element Analysis remains valid. The examinations and analysis performed support continued plant operation until the scheduled inspections during the spring refueling outages.

• Two separate approaches - NDE and analytical - both reached the same conclusion: no safety concern exists