ML041000440

3/25/2004 - Fort Calhoun, Meeting Handouts

ML041000440
Person / Time
Site:	Fort Calhoun
Issue date:	03/25/2004
From:	Gambhir S Omaha Public Power District
To:	Office of Nuclear Reactor Regulation
Wang A, NRR/DLPM, 415-1445
Shared Package
ML041050474	List: ML041000440 ML041050455
References
Download: ML041000440 (17)

Text

Fort Calhoun Station Steam Generators-Pressurizer-RV Head Replacement Projects Omaha Public Power District Presentation to the Nuclear Regulatory Commission March 25,2004 MOU 2CJ4 BE I

Introduction and Overview Sudesh Gambhir Division Manager - Nuclear Projects j4 HZE 2

1

I Meeting Agenda

• Introduction - Sudesh Gambhir

• Project Overview - Ron Short

• Component Design/Fabrication - Jay Cate

• Installation - Ron Bayer

• RRP/RRVH Installation - John Brandeau

• Licensing - Tom Matthews 03/M004 3FfP.

3 11X 2

Project Goals

• Nuclear safety/quality o First time quality in everything we do

• Industrial safety o No one injured

• Excellent communications

• Improved plant performance o Reliability 03r.doM4 Chug EL;G Power Uprate Plans

• Plans currently indefinitely deferred

• Replacement components sized for up to 17% power uprate 03MO04 6

3

Meeting Objectives and Projects Summary Ron Short Manager - NSSS Refurbishment Project 03-004

§ 7

Meeting Objectives

• Introduce project plans and team to NRC staff

• Provide overview of project responsibilities

• Provide overview of replacement component designs

• Provide summary of schedules

• Establish plans for additional meetings/

presentations 40;4

=SrZWL 4

Scope

• Replace Steam Generators - 2006 RFO

• Replace Pressurizer - 2006 RFO

• Replace Reactor Vessel Head - 2006 RFO

• Install Rapid Refueling Package o New Missile and Neutron Shields in 2005 RFO (Phase 1) o Remainder in 2006 RFO (Phase 2)

-e on520 E90Aff 9

I Vendors Involved

• RSGs o Mitsubishi Heavy Industries (MHI): Design, Fabrication, and Delivery o Framatome ANP (Areva):

Licensing/Safety Analysis o Bechtel: Installation

• RRVH o MHI: Design, Licensing, Fabrication, and Delivery (Westinghouse is Licensing subcontractor) o TBD: Installation

,t Mitsubishi

=-

=

- t-9 OWestinghouse OM2WW4 10 5

I Vendors Involved

• RPZR o MHI: Design, Licensing, Fabrication, and Delivery (Westinghouse is Design and Licensing subcontractor) o Bechtel: Installation

• RRP o Westinghouse: Phase 1 Design, Fabrication, and Installation o TBD: Phase 2 Design, Licensing, Fabrication, and Installation A, mitsubishi OWestinghouse

=5/2CO4 WWII 11 I

Schedule

• N-1 RFO: February 25 - April 21, 2005

• NSSS components delivery to FCS:

May 15,2006

• SGRO: September 8 - December 7, 2006 03,22004 12fi12 6

I Project Team

=522004 13 O25P2OO4 13 Component Design and Fabrication Jay Cate NSSS Component Lead 03/25d2004 14 7

NSSS Components - General

• Designed to ASME 1I1, 1989 edition, no addenda

• Power uprate capable

• Design and material enhancements MW2sn004 15 8

I Replacement Pressurizer (RPZR)

Fabrication/Design Features Safety Nozzle integrally Forged Nozzles All Forged She" Components

• Safe End Manway Added Heater Sleeve Repair Pads Larger Support Skirt Access Holes Safe End Improved Heater Sleeve Material Reduced Number of Heaters Surge Nozzle 032S004 17 I

Replacement RV Head (RRVH)

Fabrication/Design Features Flange eliminated CEDM Penetrations (redundant below Graytoc penetrations removed)

One Piece t

iz Forging UWt Lug Improvements Alloy 690 Penetration Weld - Alloy 690 Equivalent J-groove weld 03/2&2004 18 k1 9

NSSS Component Supplier Responsibilities

• Mitsubishi Heavy Industries contracted to supply RSGs,

• Design

+ Material procurement

• Component fabrication

• Delivery to Fort Calhoun (MHI)

RPZR, RRVH 03=2W4

.e-0i HERBM 19 Major Sub-suppliers of MHI

. RPZR Design -Westinghouse

• Heavy Forgings - Japan Steel Works

• RSG Tubing - Sumitomo Metals Industries

. Various other forging/material/services sub-suppliers - all accepted under MHI Quality Assurance Program 5/2WO4 20 10

Component Installation Ron Bayer NSSS Installation Manager O3/251204 21 Component Installation 2 Phase Approach

• Phase 1 o Perform engineering studies to determine optimum installation method o Identify risks and propose mitigation o Identify "first of a kind" evolutions for further action

• Phase 2 o Perform detailed installation engineering o Perform detailed planning 03d2512004 11 22 11

Component Installation

• Maintenance Rule evaluations as appropriate

• Containment Opening o Similar to other plants o Complex process due to the helical tendon design and number of tendons o Octagon opening allows removal of the fewest tendons

-=5r2Y04 23 Component Installation

• Inside Lift System (ILS) o Used for SG movements

• Double Runway System o Outside rails supports ILS o Inside rails used to transport

-l components out of and in to Containment 03125r2004 24

- W_ F; 12

I Closing Containment Opening

• Reinstall Containment Liner

• Reinstall Tendon Sheathing

• Reinstall Rebar

• Pour Concrete to Close Opening

• Retension Tendons

• Code pressure testing 03d252004E 25 I

RRP/RRVH Installation John Brandeau RRP/RRVH Installation Lead 03t25/2004 f,;pif 26 13

I RRP/RRVH Installation Before 200.5 Marve off00 MRAF 27 ThULI 27 RRP/RRVH Installation

• RRVH installed with rapid refueling enhancements o Retractable utility bridges, integral fans o Missile & neutron shield installation 2005 RFO o Concept similar to Seabrook, Wolf Creek, others

• RRVH largely assembled prior to 2006 RFO

• Limited laydown space in Containment o Difficult to reuse old components o Unique CEDM design (rack & pinion)

• OEM vendor (Westinghouse) as technical lead o325WOo4 F

28

/

I Licensing Approach Tom Matthews Projects Licensing Lead 031252004 29 Licensing Strategy

• Benchmarked with other licensees u 10 CFR 50.59 Evaluation approach for component replacements o Framatome-ANP (Areva), Westinghouse o Interface meetings

• Coordination with NRC o Frequent communications with NRC/NRR Project Manager o Schedule meetings with NRC o Allow time for licensing actions review

• Minor relief request(s) and TS changes anticipated 0-5/2004 30 15

License Amendment Requests

• Non-TS changes requiring NRC approval (per 50.59) have not been identified to date

• Technical Specifications Changes

• Table 1-1, Item 3 (Low Steam Generator Water Level RPS Trip Setpoint description) o 3.17 (SG tube inspection requirements)

• Waiver for 2006 outage

• Revised requirements for new SGs o 4.3.1 (RCS volume)

OT252004 epp31 Relief Requests

• ASME Section XI leak rate testing for Containment following restoration of opening o Type B local leak rate testing of liner plate welds vs.

Type A integrated leak rate testing of Containment Building o Precedents are North Anna and Surry RV Head replacements oaM2S2004 32 16

I Licensing Actions Schedule

• License Amendment Requests (TS changes) and any Code Relief Requests submitted to NRC for review no later than March 1, 2005

• NRC approvals by no later than July 1, 2006

• Individual vs. batch submittals 0,V2WW4 33 I

Conclusion

• Questions

• Plans for next meeting 03d25.2004 34 17