ML14308A347

Meeting Slide Regarding DPC-NE-2005 Appendices for Robinson and Harris Nuclear Plants

ML14308A347
Person / Time
Site:	Robinson, Harris
Issue date:	11/12/2014
From:	Duke Energy Progress
To:	Plant Licensing Branch II
Barillas M DORL/LPL2-2 301-415-2760
References
Download: ML14308A347 (13)

Text

DPC NE 2005 Appendices for DPC-NE-2005 Appendices for Robinson and Harris Nuclear Plants November 12, 2014 NRC Offices NRC Offices Duke Energy - PWR Methods

Outline Outline Outline Outline

• Background

• Background

• Review of Previous Appendix Submittals

• Outline of new Appendices

• Preliminary Statistical Core Design (SCD)

• Preliminary Statistical Core Design (SCD)

Results for Harris and Robinson

• Summary Duke Energy - PWR Methods 2

DPC DPC-NE NE-2005 Background 2005 Background DPC DPC NE NE 2005 Background 2005 Background Duke developed a Statistical Core Design (SCD) methodology for DNBR analyses in PWRs Approach for calculating the Statistical Design Limit (SDL) is similar to other approved methods (SDL) is similar to other approved methods Key difference is a thermal-hydraulic computer code, VIPRE-01, is used directly to calculate the coefficient of f

ll d

variation for all state points and cases Methodology was submitted in September 1992 and approved in February 1995 approved in February 1995 Topical structure based on the methodology (main body of report) with separate Appendices for each plant li i

application Duke Energy - PWR Methods 3

DPC DPC-NE NE-2005 Background 2005 Background - Continued Continued DPC DPC NE NE 2005 Background 2005 Background Continued Continued Process was also defined in the Methodology section for gy submitting new Appendices to address:

Different plants N

f l d i

New fuel designs New Critical Heat Flux (CHF) correlations New Appendix format to include:

1.

Identification of plant, fuel type, CHF correlation 2

Description of model 2.

Description of model 3.

List of key parameters, uncertainties and distributions 4.

List of State points analyzed 5.

The Statistical Design Limit (SDL) licensed for the application Duke Energy - PWR Methods 4

DPC DPC-NE NE-2005 Appendices 2005 Appendices DPC DPC NE NE 2005 Appendices 2005 Appendices Original report contained two appendices for Original report contained two appendices for then current Duke plants:

• Appendix A

• Appendix A

- Oconee Nuclear Station

- Mark-B10 fuel BWC CHF correlation

- BWC CHF correlation

• Appendix B

- McGuire and Catawba Nuclear Stations

- Mark-BW17 fuel

- BWCMV CHF correlation

- BWCMV CHF correlation Duke Energy - PWR Methods 5

DPC DPC-NE NE-2005 Appendices 2005 Appendices - Continued Continued DPC DPC NE NE 2005 Appendices 2005 Appendices Continued Continued Subsequent Appendices were submitted for CHF q

pp correlation changes and fuel transitions:

• Appendix C b

l

- McGuire and Catawba Nuclear Stations

- Mark-BW17 fuel

- BWU-Z CHF correlation Submitted April 1996, approved November 1996 Submitted April 1996, approved November 1996

• Appendix D

- Oconee Nuclear Station

- Mark-B11 fuel

- BWU-Z CHF correlation Submitted April 1997, approved November 1998 Duke Energy - PWR Methods 6

DPC DPC-NE NE-2005 Appendices 2005 Appendices - Continued Continued DPC DPC NE NE 2005 Appendices 2005 Appendices Continued Continued

• Appendix E

- McGuire and Catawba Nuclear Stations McGuire and Catawba Nuclear Stations

- Advanced Mark-BW and Mark-BW/MOX1 fuel

- BWU-Z/MSM CHF correlation Submitted September 2001, approved September 2002

• Appendix F

- Oconee Nuclear Station

- Mark-B HTP fuel

- BHTP CHF correlation BHTP CHF correlation Submitted September 2007, approved September 2008

• Appendix G

- McGuire and Catawba Nuclear Stations

- McGuire and Catawba Nuclear Stations

- RFA fuel

- WRB-2M CHF correlation Submitted via DPC-NE-2009 in July 1998, approved December 2002.

Included in DPC-NE-2005 in December 2008 Included in DPC-NE-2005 in December 2008.

Duke Energy - PWR Methods 7

New SCD Appendices for DPC New SCD Appendices for DPC-NE NE-2005 2005 New SCD Appendices for DPC New SCD Appendices for DPC NE NE 2005 2005 To date, submittals have been for the same plants o date, sub tta s a e bee o t e sa e p a ts as the Rev 0 with difference fuel designs or CHF correlations M

h d i i f PWR i i ll li d

• Method is generic for any PWR as originally licensed New submittal will be for two new additional plants Separate Appendix for Robinson (H) and Harris (I) Nuclear

- Separate Appendix for Robinson (H) and Harris (I) Nuclear Plants

- VIPRE-01 model structure the same as existing approved 14 h l

d l (DPC NE 3000) i h f

l 14 channel model (DPC-NE-3000) with necessary fuel geometry updates

• Two fuel designs, Advanced W 15x15 HTP @ RNP and Advanced W 17 17 HTP @ HNP W 17x17 HTP @ HNP Duke Energy - PWR Methods 8

RNP 14 Channel Model RNP 14 Channel Model 9

Duke Energy - PWR Methods

HNP 14 Channel Model HNP 14 Channel Model 10 Duke Energy - PWR Methods

New SCD Appendices for DPC New SCD Appendices for DPC--NE NE--2005 2005 --

C i

d C

i d

Continued Continued New submittal changes also include:

New submittal changes also include:

- HTP CHF correlation

• Used for both fuel designs

• Data validation in VIPRE-01 code demonstrated

- Plant specific parameter uncertainties Format of new appendices same as the last chronologically submitted, Appendix F

- Sections as defined in Methodology main body

- No Transition or Mixed Core section since no fuel design transition occurring transition occurring Duke Energy - PWR Methods 11

Preliminary DNB Statistical Core Design (SCD)

Preliminary DNB Statistical Core Design (SCD)

R l

f R bi d H i

R l

f R bi d H i

Results for Robinson and Harris Results for Robinson and Harris Calculations applying the Duke methodology with the Calculations applying the Duke methodology with the indicated models completed

- Specific Plant uncertainties and state points applied

- Results anticipated to be similar to Oconee Appendix F

• Similar fuel design Preliminary SDL results for both Robinson and Harris plants as expected Plant SDL Appendix Oconee 1.34 F

Robinson 1 35 H

Robinson 1.35 H

Harris 1.34 I

Duke Energy - PWR Methods 12

Summary Summary Summary Summary Duke Energy Thermal-Hydraulic Statistical Core Design Duke Energy Thermal Hydraulic Statistical Core Design Methodology as per DPC-NE-2005 has been applied to the Robinson and Harris Nuclear Plants

• Methodology applied as described in report Main Body for each plant Required Duke SCD Appendices completed as Appendix H (Robinson) and Appendix I (Harris)

-Statistical Design Limit (SDL) calculated for each plant based on resident fuel design, plant uncertainties

-Submittal planned for December 2014

-Submittal planned for December 2014 Duke Energy - PWR Methods 13