ML093140162
| ML093140162 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun |
| Issue date: | 11/05/2009 |
| From: | Omaha Public Power District |
| To: | Office of Nuclear Reactor Regulation |
| Wilkins, L E, NRR/DORL/LPL4, 415-1377 | |
| References | |
| TAC ME2488 | |
| Download: ML093140162 (19) | |
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- Ron Short
- Bob Dulee
- Carmen Ovici
- Brian Jelke
- Bill Hansher
Introductions
EPU Project Manager EPU NSSSjLicensing Manager EPU NSSSjLicensing Supervisor Sargent & Lundy EPU PM FCS Licensing Supervisor
Agenda
- Project Overview - Ron Short
- Methodology Change that May Require Separate NRC Approval-Brian Jelke
- Changes to be Included in EPU License Amendment Request - Bob Dulee
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Project Overview
- 17% EPU: 1500 MWt to 1755 MWt 80 MWe
- Engineering & Licensing work in progress
- AREVAJ S&L and WEe
- Submit LAR to NRC: March 31, 2011
- Plant Modifications: 2011/2012 RFOs
- Implement EPU: Post-2012 RFO
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Spent Fuel Pool Cooling
- Cu rrent Licensing Basis
- Holtec analysis
- In accordance with NRC Branch Technical Position
- EPU Analysis
- GOTHIC Software
- In accordance with NRC Branch Technical Position
- Separate NRC Submittal?
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Realistic Large Break LOCA (RLBLOCA) Methodology
- Current Methodology: EMF-2103 Rev. 0
- EPU Methodology: EMF-2103 Rev. 0 + NRC Transition Changes
Post-LOCA Long Term Core Cooling
- Current Methodology: Westinghouse Post LOCA LTCC Analysis Methodology
Post-LOCA Long Term Core Cooling
- Additional Issues to be Addressed per NRC Request
- RV Head Mixing Volume
- Pressure Drop Between the Core and the Break
- Boric Acid Solubility Limit
- Decay Heat Multiplier of 1.2 at all times
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Spent Fuel Pool Criticality
- Current Licensing Basis: ~ 4.5 wt % U235
- EPU Licensing Basis: ~ 5.0 wt % U235
- Not needed until 2012 RFO
- Issues with Recent Submittals
Containment Accident Pressure
- Current Licensing Basis Credits Containment Accident Pressure (CAP)
- Maximum current credit is 'V 4 feet
- Preliminary EPU Conditions
- Increase in overpressure credit to 'V 11 feet
- Overpressure credit less than 25% of total
Radiological Consequences Analysis
- Alternate Source Term (AST) implemented in 2001
Radiological Consequences Analysis
- LOCA and Control Rod Ejection Accident (CREA): In accordance with RG 1.183, Rev. 0
- Non-LOCA analyses: In accordance with RG 1.183, Rev. 0, but gap fractions from NUREG/CR 5009
Alternate PTS RuIe
- FCS License Expires August 2033
- Current PTS Rule Acceptable Through 2033
- EPU Impact
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