ML14050A400
| ML14050A400 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 02/20/2014 |
| From: | Region 3 Administrator |
| To: | |
| References | |
| Download: ML14050A400 (8) | |
Text
02/19/2014 1
NRC Public Webinar Davis Besse Steam Generator Replacement Inspection February 20, 2014 1
Welcome Darrell Roberts Deputy Regional Administrator NRC Region III 2
02/19/2014 2
Introductions - NRC Jamnes Cameron, Chief, Projects Branch 6, RIII (Moderator)
David Hills, Chief, Engineering Branch 1, RIII Atif Shaikh, Senior Reactor Inspector, Division of Reactor Safety, RIII (Presenter)
James Neurauter, Senior Reactor Inspector, Division of Reactor Safety, RIII 3
Meeting Agenda Overview of once through steam generators (OTSGs)
Overview of NRC steam generator replacement inspection objectives and activities
Question and Answer (Q&A) session Closing Remarks 4
02/19/2014 3
OTSGs - Overview 5
OTSGs - Overview 6
Replacement OTSGS are each 75 feet tall and 13 feet in diameter
Replacement OTSG Weight
= 465 Tons (Dry)
Replacement OTSG tubes are made from thermally treated Alloy-690 material providing increased corrosion resistance
02/19/2014 4
7 Davis Besse SG
Inspection began December 2013 and will not complete until after plant start up from outage
NRC will inspect various pre-outage and outage activities
Specialists from NRC regional office will supplement the two resident inspectors
Opening will be made in Shield Building and Containment
Background
8
02/19/2014 5
Inspection Objectives Verify that:
Engineering evaluations and design changes are in conformance with facility license, codes, regulations Removal and replacement activities maintain nuclear and radiological safety in accordance with Federal regulations and industry codes &
standards Post-installation test program implementation is in compliance with applicable codes and regulations 9
Major Inspection Activities Design and Planning Engineering evaluations, design changes, modifications, and operating experience evaluation Steam Generator lifting and rigging Radiation Protection program: controls, planning, and preparations Security considerations - affected barriers 10
02/19/2014 6
Major Inspection Activities 11 Steam Generator Removal / Replacement Cutting, welding / non-destructive examinations Lifting / rigging activities Containment opening Radiation protection controls implementation Post-installation Testing Testing program and implementation Shield Building Opening 12 Steam Generator replacement opening is completely encompassed by the 2011 Reactor Pressure Vessel Head replacement opening New opening was cut through new concrete poured in 2012
02/19/2014 7
13 Shield Building Opening 14 Questions?
02/19/2014 8
Meeting Closure Darrell Roberts Deputy Regional Administrator NRC Region III 15 Meeting Contacts For Follow-up Questions - Contact the NRC Region III Office of Public Affairs:
Viktoria Mitlyng / Prema Chandrathil Tel: (630) 829-9500 Email: OPA3@nrc.gov 16