ML14050A400

NRC Presentation for Davis-Besse Steam Generator Replacement Webinar

ML14050A400
Person / Time
Site:	Davis Besse
Issue date:	02/20/2014
From:	Region 3 Administrator
To:
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Download: ML14050A400 (8)

Text

02/19/2014 NRC Public Webinar Davis Besse Steam Generator Replacement Inspection February 20, 2014 1

Welcome Darrell Roberts Deputy Regional Administrator NRC Region III 2

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02/19/2014 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

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02/19/2014 OTSGs - Overview 5

OTSGs - Overview 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 6

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02/19/2014 Davis Besse SG 7

Background

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 8

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02/19/2014 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 5

02/19/2014 Major Inspection Activities 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 11 Shield Building Opening 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 12 6

02/19/2014 Shield Building Opening 13 Questions?

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02/19/2014 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 8