ML041000440

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3/25/2004 - Fort Calhoun, Meeting Handouts
ML041000440
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
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:
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 HZEj4 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 11X 3FfP.

3 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 EL;G Chug $

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 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 ,t Mitsubishi Delivery o Framatome ANP (Areva): _. =-

- t- =

Licensing/Safety Analysis o Bechtel: Installation

  • RRVH o MHI: Design, Licensing, Fabrication, and Delivery 9 (Westinghouse is Licensing subcontractor) o TBD: Installation OWestinghouse OM2WW4 10 5

I Vendors Involved

  • RPZR o MHI: Design, Licensing, Fabrication, and Delivery A, mitsubishi (Westinghouse is Design and Licensing subcontractor) o Bechtel: Installation
  • RRP o Westinghouse: Phase 1 Design, Fabrication, and Installation o TBD: Phase 2 Design, OWestinghouse Licensing, Fabrication, and Installation

=5/2CO4 11 WWII 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
  • Design and material enhancements MW2sn004 15 8

I Replacement Pressurizer (RPZR)

Fabrication/Design Features Safety Nozzle

  • Safe End integrally Forged Nozzles -

Manway All Forged She" Components Improved Heater Sleeve Material Added Heater Sleeve Repair Pads Larger Support Skirt Access Holes Reduced Number of Heaters Safe End 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 UWtLug Forging Improvements Alloy 690 Penetration Weld - Alloy 690 Equivalent J-groove weld 03/2&2004 18

--- k1 9

NSSS Component Supplier Responsibilities

  • Mitsubishi Heavy Industries (MHI) contracted to supply RSGs, RPZR, RRVH
  • Design

+ Material procurement

  • Component fabrication
  • Delivery to Fort Calhoun 03=2W4

.e-0i 19 HERBM 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

-l supports ILS o Inside rails used to transport 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

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