ML090370455
| ML090370455 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 01/28/2009 |
| From: | Omaha Public Power District |
| To: | Office of Nuclear Reactor Regulation |
| Wilkins, L E, NRR/DORL/LPL4, 415-1377 | |
| Shared Package | |
| ML090370404 | List: |
| References | |
| TAC ME0592 | |
| Download: ML090370455 (17) | |
Text
Fort Calhoun Station Extended Power Uprate (EPU) Project January 28, 2009
Agenda Purpose Project Overview Plant Impact Pl t M difi ti
- Ron Short
- Bernie Van Sant B
i V
S t
Plant Modifications Licensing Approach PRA Risk Insights Summary Questions/Feedback
- Bernie Van Sant
- Bob Dulee
- Carmen Ovici
- Ron Short
Project Purpose Support the OPPD Integrated Resource Plan (IRP) for additional power supply by January 2013
Project Scope 17% Power Uprate - 1755 MWt Current License - 1500 MWt 75 MWe - Summer 79 MWe - Non-Summer 78 MWe Average
=
Background===
Combustion Engineering NSSS Initial operation - September 1973 License expires - August 2033 EPU studied several times Conceptual engineering is complete Detailed engineering/licensing in progress Large components replaced in 2005/2006
Project Schedule Project Initiation - April 2008 Design and licensing Engineering analyses/Licensing in progress Finalize modification scope - early 2009 Submit LAR to NRC - March 2011 2011 and 2012 Re-Fueling Outages (RFO)
Component modifications Uprated condition following 2012 RFO
Project Management Team
Vendor Support Team Fuel & Related Services - AREVA NP NSSS - Westinghouse Balance of Plant - Sargent & Lundy g
y Modification Packages - Sargent & Lundy Equipment - TBD Installation - TBD
Licensing Approach Benchmark Ginna and Waterford 3 License Amendment Request (LAR) prepared per Review Standard RS-001 EPU Project to compile LAR Independent review prior to submittal Expect frequent interface with NRC Member NEI EPU Working Group
PRA Risk Insights Initial EPU impact assessed Potential risk reduction items identified Power Operated Relief Valves (PORVs)
Atmospheric Dump Valves (ADVs)
Procedure enhancements
Plant Impact 3-pump operation (Main feedwater, Condensate)
Reactor coolant system at 2250 psi Increased fuel enrichment (4.95%)
Several modifications required
Activities Completed with EPU Considerations Replaced Steam Generators Replaced Pressurizer Replaced Low Pressure Turbines Replaced Main Condenser Replaced Main Transformer
2011 RFO Modifications New potable water and supplemental emergency feedwater storage tank Heater drain tank and valves Main feedwater regulation valve trim Main feedwater regulation valve trim Turbine cross around relief valves Safety injection pump room cooling Nuclear detector well cooling
2012 RFO Modifications High pressure turbine Main generator rewind Main steam safety valves (MS-291/292) y
(
)
Trippable Group N rods Isophase bus duct cooling Auxiliary feedwater pump and motor Transmission & Distribution No FCS switchyard modifications
Possible Component Modifications Replace Feedwater heaters (FW-14 A & B)
Switchgear room cooling I
h b
d t
Isophase bus duct Larger PORVs ADVs upstream of MSIVs
Project Summary Supports the OPPD Integrated Resource Plan (IRP) for additional power supply by January 2013 Vendor detailed Engineering & Licensing work underway LAR submittal in March 2011 NRC approval in March 2012
Questions/Feedback Questions/Feedback