ML14308A340
| ML14308A340 | |
| 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: ML14308A340 (13) | |
Text
HB Robinson / Shearon Harris Reload Design and Safety Analysis Methodology Report November 12, 2014
Duke Energy Attendees Julie Olivier (Manager, Nuclear Fleet Licensing)
J h D (GO R l t Aff i )
Josh Duc (GO Regulatory Affairs)
John Caves (HNP Regulatory Affairs)
Scott Connelly (RNP Regulatory Affairs)
Bob Harvey (Manager, PWR Methods)
Kenny Epperson (PWR Methods) 2
Outline
Background
Method Report Matrix Method Report Matrix Methodology Report Content S h d l Schedule Regulatory Process DPC-NE-2005 Appendices for Robinson and Harris Nuclear Plants 3
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Background===
Duke Energy performs the analyses of record for Oconee, McGuire, and Catawba, which includes reload physics design, core thermal hydraulic analysis, fuel mechanical analysis, and non-LOCA transient analysis y
y The computer codes and methods used are approved by NRC and are largely independent of those used by its fuel vendors The analysis methods (computer codes and analysis approach) are similar at all The analysis methods (computer codes and analysis approach) are similar at all nuclear stations (ONS/MNS/CNS)
Following the merger of Duke Energy and Progress Energy (DEP), it is our intention to perform the reload licensing analysis for the (DEP) PWR plants (Robinson and to perform the reload licensing analysis for the (DEP) PWR plants (Robinson and Harris)
To leverage the existing analysis experience, the analytic approach to be applied at RNP d HNP ill b i il t th t d t ONS/MNS/CNS RNP and HNP will be very similar to that used at ONS/MNS/CNS.
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Background===
Cost Savings Analysis costs are reduced Reload design team objectives are aligned with company goals (better management of Reload design team objectives are aligned with company goals (better management of analysis margins)
Flexibility to change fuel vendors Makes competitive fuel bids more effective since fuel target peaking/operating limits can be pre-defined Flexibility to adapt to scheduling changes Flexibility to adapt to scheduling changes Core redesigns at limited additional analysis costs Can provide timely and cost effective plant support for emergent issues p
y p
pp g
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Methods Report Matrix Proposed RNP/HNP MNS/CNS (Duke)
ONS (Duke)
Current RNP/HNP (AREVA)
Proposed RNP/HNP (Duke)
Physics Codes / Models DPC-NE-1005 CASMO-4/SIMULATE-3 DPC-NE-1006 CASMO-4/SIMULATE-3 EMF 96-029 CASMO-3/PRISM DPC-NE-1008 CASMO-5/SIMULATE-3 Physics Applications Power Distribution Monitoring DPC-NE-2011 NFS-1001 DPC-NE-1002 ANF-88-054 DPC-NE-2011 revision Physics Applications Reload Design DPC-NF-2010 NFS-1001 DPC-NE-1002 EMF-96-029 DPC-NF-2010 revision DPC-NE-3000 DPC-NE-3000 ANF-89-151 EMF-2310 DPC-NE-3008 NSSS Codes / Models DPC NE 3000 RETRAN-02 DPC NE 3000 RETRAN-3D ANF 89 151 EMF 2310 ANF-RELAP S-RELAP5 DPC NE 3008 RETRAN-3D Subchannel T/H Methods DPC-NE-3000 DPC-NE-2004 VIPRE-01 DPC-NE-3000 DPC-NE-2003 VIPRE-01 XN-75-21 XN-NF-82-21 XCOBRA-IIIC DPC-NE-3008 DPC-NE-2005 (Appendix)
VIPRE-01 SCD Methodology DPC-NE-2005 DPC-NE-2005 EMF-92-081 DPC-NE-2005 revision Transient Analysis DPC-NE-3001 DPC-NE-3002 SIMULATE-3K (REA)
DPC-NE-3005 SIMULATE-3K (REA)
EMF-2310 (SRP Non-LOCA Ch 15)
EMF 84-093 (SLB - Harris)
XN-NF-78-44 (REA) XTRAN-PWR DPC-NE-3009 SIMULATE-3K (REA) 6 Fuel Performance DPC-NE-2008 (TACO-3)
DPC-NE-2009 (PAD 4.0)
DPC-NE-2008 (TACO-3 and GDTACO)
EMF-92-116 (Mechanical Design)
XN-NF-81-58 and ANF-81-58 RODEX2 TBD
Report Content / Approach DPC-NE-1008 The report will consist of detailed comparisons of calculated key physics parameters with The report will consist of detailed comparisons of calculated key physics parameters with measurements obtained from several operating cycles of RNP and HNP and comparison against several critical experiments to quantify a pin uncertainty. These results are used to determine the acceptability of C5/S3 for calculation of physics parameters and to develop the 95/95 peaking t i t uncertainty.
Similar to DPC-NE-1005 CASMO-4 replaced by CASMO-5 No MOX applications or benchmark calculations Plans are to include benchmark calculations of cores containing IFBA/WABA fuel to address Plans are to include benchmark calculations of cores containing IFBA/WABA fuel to address the option of alternate fuel products 7
Report Content / Approach DPC-NE-2005 (revision presented later)
DPC-NF-2010 / DPC-NE-2011 DPC-NF-2010 The report describes the application of the reactor physics methods to determine reactivity and safety analysis inputs required to validate the Chapter 15 analyses safety analysis inputs required to validate the Chapter 15 analyses.
Minor changes / clarifications will be required DPC-NE-2011 DPC NE 2011 The report describes the methodology for determining the power dependent AFD limits and validation of the OP/T and OT/T setpoints Minor changes will be required and potential modification to Tech Spec monitoring Minor changes will be required and potential modification to Tech Spec monitoring 8
Report Content / Approach DPC-NE-3008 The report will contain a description of the RETRAN and VIPRE base models used to perform the Chapter 15 non LOCA safety analysis Validation of the RETRAN models will be benchmarked to Chapter 15 non-LOCA safety analysis. Validation of the RETRAN models will be benchmarked to several Chapter 15 reference calculations (AOR) for RNP and HNP. Focus of benchmark is on the overall system response and sequence of events. The events being considered are:
UFSAR 15.1.2 - Increase in Feedwater Flow (HNP)
UFSAR 15.2.3 - Turbine Trip (HNP)
UFSAR 15.2.7 - Loss of Normal Feedwater (RNP)
(
)
UFSAR 15.2.8 - Feedwater Line Break (HNP)
UFSAR 15.3.2 - Complete Loss of Forced Coolant Flow (HNP)
UFSAR 15 3 3 - RCP Locked Rotor (RNP)
UFSAR 15.3.3 RCP Locked Rotor (RNP)
UFSAR 15.4.2 - Uncontrolled RCCA Bank Withdrawal (RNP) 9
Report Content / Approach DPC-NE-3009 This report will describe the methodology for simulating the UFSAR Chapter 15 t
i t
d id t f RNP d HNP transients and accidents for RNP and HNP The report will include details of the computer codes and models, methods for calculating safety analysis physics parameters and setpoints, and detailed modeling assumptions for all of the non-LOCA transients and accidents This methodology will be used to reanalyze the RNP and HNP UFSAR transients and accidents in order to establish an up-to-date design basis, and to support advanced fuel assembly and core reload designs 10
Schedule Need:
Support the Reload Licensing Analysis for HNP Cycle 22 and RNP Cycle 32 Outage Dates/New Methods Implemented: H1EOC21 (4/18) R2EOC31 (9/18)
Outage Dates/New Methods Implemented: H1EOC21 (4/18), R2EOC31 (9/18)
Start of the Reload Analysis HNP ( December 2016)
RNP (Spring 2017)
Submittals:
DPC NE 2005 (December 2014/January 2015)
DPC-NE-2005 (December 2014/January 2015)
DPC-NE-1008 (March/April 2015)
DPC-NE-3008 (April/May 2015)
DPC-NF-2010, DPC-NE-2011, DPC-NE-3009 (December 2015) 11
Regulatory Process LAR submittals Methodology report Tech Spec 5.6.5 and 6.9.1.6 changes Tech Spec 5.6.5 and 6.9.1.6 changes COLR/Tech Spec changes as required UFSAR changes Implemented via 10 CFR 50.59 following methodology report approval with first in-house reload analysis Additional Work Scope Additional Work Scope Turbine Trip analysis to support Tech Spec change to safety valve tolerances Dose Analysis Ch t
6 A l
i Chapter 6 Analysis 12
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