ML110260450

Summary of January 26, 2011, Meeting Slides

ML110260450
Person / Time
Site:	Sequoyah
Issue date:	01/28/2011
From:	Office of Nuclear Reactor Regulation
To:
Lingam, S NRR/DORL 415-1564
Shared Package
ML110280330	List: ML110260392 ML110260450
References
Download: ML110260450 (15)

Text

Sequoyah Nuclear Plant, Unit 2 Sequoyah Nuclear Plant, Unit 2 Steam Generator Replacement Project Status and Licensing Plan 1

Licensing Plan January 26, 2011

Introduction Introduction

• Purpose

• Background

• Replacement Steam Generator (RSG) Design Features and Installation Overview

• Project Status 2

Project Status

• Licensing Plan

• Summary

Purpose Purpose

• Provide background information, RSG design and installation overview, and describe the overall licensing process that TVA will use

• Provide the NRC staff TVAs current project status and licensing plan for the Sequoyah Unit 2 (SQN 2)

Steam Generator (SG) replacement

• Describe the submittals that TVA expects to provide to the NRC 3

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Background===

Background

• The SQN 1 steam generators were replaced in 2003

• The Watts Bar Unit 1 (WBN 1) steam generators were replaced in 2006

• The contract for SQN 2 steam generator removal g

and installation was awarded in 2009 to the Steam Generating Team (SGT)

• The methodology for replacement is virtually the same as SQN 1 and WBN 1 4

Background (continued)

Background (continued)

• The SQN 2 replacement steam generators are like-for-like compared to the original steam generators in form, fit, and function (same as SQN 1)

• Shield Building, Steel Containment Vessel (SCV) and SG Compartment Modifications use the same methodology as SQN 1 5

RSG Design Features RSG Design Features

• Steam Generators were designed by Westinghouse, fabricated by Doosan, and SG tubes provided by Sandvik

- Same physical size as existing steam generators

- Increased tube surface area to provide additional 6

plugging margin

- Integral loose parts strainer provided for FW/AFW

- Reduced moisture content at steam nozzle exit

- Additional access hand holes for maintenance

- Snaplock Nozzle Dams provided for dose reduction

- Electro Polished Head Bowls for dose reduction

RSG Installation Overview RSG Installation Overview

• One Piece Replacement like SQN 1

• Major Activities Involve:

- Defuel Reactor

- Cut holes in Shield Building dome, SCV, and SG Compartment Roofs Remove existing SGs 7

- Remove existing SGs

- Install Replacement SGs

- Restore SG Compartments, RCS piping, SCV, and Shield Building dome

- Refuel Reactor

- Pressure Test to Demonstrate Restored Containment Integrity

Project Status Project Status

• The SQN 2 steam generators are to be replaced in the Cycle 18 (U2C18) Refueling Outage, scheduled to start October 21, 2012

• RSGs are on site (controlled storage)

• Engineering and planning for U2R17 work g

g p

g progressing on schedule

• Engineering, licensing, and installation planning for U2R18 progressing on schedule

• AREVA Accident Analyses review complete

- No new analysis required for the Unit 2 RSGs

- Currently reconciling existing calculations and analysis by mid summer 2011 8

Project Status (continued)

Project Status (continued)

• Safe Load Paths and Drop Analysis for Crane Components, Steam Generators, and Other Heavy Loads under Development

• Licensing Submittals being prepared 9

Licensing Plan Licensing Plan

• Steam Generator Component Replacement Performed via 10 CFR 50.59

• Design Changes Related to RSGs Performed via 10 CFR 50.59 10

Licensing Plan (continued)

Licensing Plan (continued)

• License Amendment Requests (LARs)

- LAR (UFSAR 3.8.3.4.8) to address the Code change used in restoration of the concrete roof of the steam generator compartments LAR (UFSAR 3 8 1) to use Bar Lock Mechanical 11

- LAR (UFSAR 3.8.1) to use Bar-Lock Mechanical Couplers instead of Cadwelds for Rebar Splicing during Shield Building Dome Restoration

- LAR to revise Steam Generator Inspections (TSTF-449)

Licensing Plan (continued)

Licensing Plan (continued)

• Relief Request

- Relief request to utilize a containment pressure test in lieu of a Containment Integrated Leak Rate Test for Post Modification Testing of restored Steel Containment Vessel

• One Time Use LARs

- One time use LAR (License Condition) for movement of loads over Essential Raw Cooling Water piping per GL 96-02

- One time use LAR for two 18 hatches in the shield building dome to allow pre-outage work in the annulus space during power 12

Licensing Plan (continued)

Licensing Plan (continued)

- Request for use of 18 hatches at power will facilitate pre-outage work in the annulus space

• Will use alternate source terms

• This is a one time change with defined times of use, limits on use, compensatory measures while in this condition, and defined expiration date p

13

Licensing Plan (continued)

Licensing Plan (continued)

• Submittal Schedule

- Relief Request for containment pressure test submitted December 22, 2010 - approval requested by October 1, 2012 One time use LAR for two 18 hatches to be submitted by 14

- One time use LAR for two 18 hatches to be submitted by May 1, 2011 - approval requested by July 1, 2012

- Three LARs to be submitted by May 1, 2011 - approval requested by October 1, 2012

- One time use LAR for movement of loads to be submitted by July 1, 2011 - approval requested by October 1, 2012

Summary Summary

• Implementing SQN/WBN Lessons Learned and Best Practices

• Based on SQN 1 Licensing/Design Basis similarities

• Plan is to provide at least 1 year NRC review time 15

• Plan is to provide at least 1 year NRC review time