ML17200C780

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Duke Energy Pre-submittal Meeting Presentation, August 3, 2017, Harris and Robinson License Amendment Request to Support the Transition to Duke Non-LOCA Analysis Methods, MF9824, MF9825
ML17200C780
Person / Time
Site: Harris, Robinson  Duke Energy icon.png
Issue date: 07/19/2017
From: Bortz D, Harvey R
Duke Energy Progress
To:
Division of Operating Reactor Licensing
Barillas M DORL/LPL2-2 301-415-6256
References
CAC MF9824, CAC MF9825
Download: ML17200C780 (32)
v • d • e


Text

Shearon Harris / H. B. Robinson License Amendment Request to Support the Transition to Duke Non-LOCA Analysis Methods Presenters:

David Bortz Robert Harvey Duke/NRC Pre-submittal Meeting August 3, 2017 Duke Energy - PWR Methods Duke / NRC Meeting

Objective

  • Brief the NRC on the proposed submittal and review schedule
  • Obtain feedback on schedule Duke Energy - PWR Methods Duke / NRC Meeting 2

Presentation Outline

  • Methodology Report Status
  • Licensing Approach

- Power Distribution TS Changes

- Shutdown Margin TS Changes (Harris Only)

- Relocation of TS Parameters to the COLR

- COPERNIC

- BOC MTC TS Revision (Robinson Only)

  • Conclusion Duke Energy - PWR Methods Duke / NRC Meeting 3

Methodology Report Status Duke Energy - PWR Methods Duke / NRC Meeting 4 MNS/CNS ONS Proposed RNP/HNP Submittal Date Physics Codes / Models DPC-NE-1005 CASMO-4/SIMULATE-3 DPC-NE-1006 CASMO-4/SIMULATE-3 DPC-NE-1008 CASMO-5/SIMULATE-3 August 19, 2015 Approved May 18, 2017 Physics Applications Power Distribution Monitoring DPC-NE-2011 NFS-1001 DPC-NE-1002 DPC-NE-2011 revision February 3, 2016++

Resubmitted May 4, 2016 Approved May 18, 2017 Physics Applications Reload Design DPC-NF-2010 NFS-1001 DPC-NE-1002 DPC-NF-2010 revision February 3, 2016++

Resubmitted May 4, 2016 Approved May 18, 2017 NSSS Codes / Models DPC-NE-3000 RETRAN-02 DPC-NE-3000 RETRAN-3D DPC-NE-3008 RETRAN-3D November 19, 2015 RAI Response: Nov. 10, 2016 Subchannel T/H Methods DPC-NE-3000 DPC-NE-2004 VIPRE-01 DPC-NE-3000 DPC-NE-2003 VIPRE-01 DPC-NE-3008 DPC-NE-2005 VIPRE-01 November 19, 2015 RAI Response: Nov. 10, 2016 SCD Methodology DPC-NE-2005 DPC-NE-2005 DPC-NE-2005 revision March 5, 2015 Approved March 8, 2016 Transient Analysis DPC-NE-3001 DPC-NE-3002 SIMULATE-3K (REA)

DPC-NE-3005 SIMULATE-3K (REA)

DPC-NE-3009 SIMULATE-3K (REA)

October 3, 2016 Fuel Performance DPC-NE-2008 (TACO-3)

DPC-NE-2009 (PAD 4.0)

DPC-NE-2008 (TACO-3 and GDTACO)

N/A - TS changes only COPERNIC-2 August/September 2017

++ Withdrawn April 7, 2016

Licensing Approach

  • Extend previously NRC-approved McGuire/Catawba and fuel vendor methodologies to Harris and Robinson
  • Power distribution TS changes are based on those implemented at McGuire and Catawba
  • TS parameters relocated are consistent with those relocated for McGuire and Catawba
  • Adopt COPERNIC fuel rod performance methodology (approved for Oconee)

Duke Energy - PWR Methods Duke / NRC Meeting 5

Licensing Approach contd

  • BOC MTC TS Change implemented to improve analysis margins at 50% rated thermal power

- Implemented via 10 CFR 50.59 following methodology report approval coincident with first in-house reload Duke Energy - PWR Methods Duke / NRC Meeting 6

Schedule

  • Support the reload licensing analysis for Harris Unit 1 Cycle 23 and Robinson Unit 2 Cycle 33

- H1EOC22 (10/19)

- R2EOC33 (9/20)

  • Reload Analyses Start:

- HNP (Spring 2018)

- RNP (Early 2019)

  • NRC approval requested for (December 2018)
  • Implementation prior to the startup of H1C23 and R2C34 Duke Energy - PWR Methods Duke / NRC Meeting 7

Power Distribution TS Changes

  • Required to implement the power distribution surveillance methodology described in DPC-NE-2011-P-A
  • McGuire and Catawba specifications used as a template
  • Affected Specifications

- TS 3.2.1 (TS 3.2.2) Heat Flux Hot Channel Factor - FQ

- TS 3.2.2 (TS 3.2.3) Nuclear Enthalpy Rise Hot Channel Factor -

FH

- TS 3.2.3 (TS 3.2.1 ) Axial Flux Difference (AFD)

- TS 3.2.4 (TS 3.2.4) Quadrant Power Tilt Ratio (QPTR)

Duke Energy - PWR Methods Duke / NRC Meeting 8

DPC-NE-2011-P Overview

  • Develops Axial Flux Difference (AFD) and Rod Insertion limits (RILs) to preserve the initial condition power peaking assumptions for LOCA and LOF DNB
  • Confirms the acceptability of the f(I) portion of the OTDT and OPDT trip functions for over-power Condition II transients

- OPDT and OTDT trip functions protect against centerline fuel melt and DNB.

  • Develops core Monitoring Factors for Tech Spec FQ and FH power distribution surveillances Duke Energy - PWR Methods Duke / NRC Meeting 9

Maneuvering Analysis Process Duke Energy - PWR Methods Duke / NRC Meeting 10

DPC-NE-2011-PA Overview Monitoring Factors

  • Similar to the Westinghouse W(Z) factors in that they are used to quantify peaking factor margin in the transient condition at the AFD limits
  • 3-D factors functionalized against burnup and power
  • Cycle-specific
  • Specified in the COLR Duke Energy - PWR Methods Duke / NRC Meeting 11

Typical Axial Flux Difference Limits Duke Energy - PWR Methods Duke / NRC Meeting 12 0

10 20 30 40 50 60 70 80 90 100 110

-40

-30

-20

-10 0

10 20 30 40 Power Level (%)

Axial Flux Difference (%)

Acceptable Unacceptable Operation Unacceptable Operation Unrestricted Operation (< 50% RTP)

TS AFD Limits TS AFD Limits Typical SS Operational Band

Heat Flux Hot Channel Factor FQ Surveillance

  • Three checks are performed

- Steady State FQ: confirmation of the current state of the core

- Transient (or operational) FQ: Confirmation that the LOCA limits would not be exceeded under operational transient conditions

- RPS FQ: Confirmation that CFM limits would not be exceeded in the event of an over-power Condition II transient Duke Energy - PWR Methods Duke / NRC Meeting 13

FQ Steady State

  • FQ M x, y, z FQ RTP P

K(Z) for P > 0.5

where, FQ M(x, y, z) = measured FQ FQ RTP= the LOCA limit at rated thermal power (RTP) specified in the Core Operating Limits Report (COLR). Augmented by K(BU) if necessary.

K(BU) = normalized FQ as a function of burnup P = relative thermal power K(Z) = normalized FQ as a function of core height P = 0.5 for all powers < 50% RTP Duke Energy - PWR Methods Duke / NRC Meeting 14

FQ Operational Surveillance

  • FQ M(x, y, z) FQ D x, y, z MQ(x, y, z)
where, FQ M(x, y, z) = measured FQ FQ D(x, y, z) = design FQ MQ x, y, z = LOCA margin available at core location x,y,z Duke Energy - PWR Methods Duke / NRC Meeting 15

Centerline Fuel Melt Surveillance

  • FQ M(x, y, z) FQ D x, y, z MC(x, y, z)
where, FQ M(x, y, z) = measured FQ FQ D(x, y, z) = design FQ MC x, y, z = CFM margin available at core location x,y,z Duke Energy - PWR Methods Duke / NRC Meeting 16

Measured FQ Exceeding Op Surveillance Limit

  • With FQ exceeding its Operational limit:

- Reduce the operational AFD limits and/or core power

- When AFD adjustments alone are insufficient to recapture the desired margin, reduce the core power level

  • This is a change from the MNS/CNS specifications
  • Compensatory actions address concerns raised in NSAL 09-05

- Power level adjustments are accompanied with RPS trip setpoint adjustments to maintain appropriate margin to the trip limit Duke Energy - PWR Methods Duke / NRC Meeting 17

Measured FQ Exceeding RPS Surveillance Limit

  • With FQ exceeding its RPS limit:

- Reduce the OPDT f2(I) breakpoints

- Alternate options include:

  • Reducing the OTDT trip setpoint (K1)
  • Reducing the OTDT f1(I) breakpoints

- Alternate options may be required for Harris prior to installation of the f2(I) trip reset function Duke Energy - PWR Methods Duke / NRC Meeting 18

Nuclear Enthalpy Rise Hot Channel Factor - FH

  • Two checks are performed

- Steady State FH: confirmation of the current state of the core

- Transient (or operational) FH: Confirmation that the LOF DNBR limits would not be exceeded under operational transient conditions Duke Energy - PWR Methods Duke / NRC Meeting 19

FH Steady State

  • FH M x, y MARP x, y 1.0 +

1 RRH (1.0 P)

where, FH M x, y = Measured value of FH P = relative thermal power RRH = the thermal power reduction required to compensate for each 1% that the measured radial peak exceeds its limit MARP(x,y) = Maximum Allowed Radial Peak for the limiting DNB transient. Function of axial peak and elevation z.

Duke Energy - PWR Methods Duke / NRC Meeting 20

FH Operational Surveillance

  • FH M x, y UMR [FH D

x, y MH x, y ]

where, FH M x, y = Measured FH UMR = Radial uncertainty factor FH D

x, y = Design radial power, FH MH x, y = DNB margin remaining in location x,y in the calculated transient power distributions Duke Energy - PWR Methods Duke / NRC Meeting 21

Measured FH Exceeding Steady State or Surveillance Limit

  • With FH exceeding its limits

- Reduce thermal power by > RRH for each percent FH exceeds its limit

- Reduce power range and OTDT setpoints

- Verify FH within limits Duke Energy - PWR Methods Duke / NRC Meeting 22

AFD Changes Duke Energy - PWR Methods Duke / NRC Meeting 23

  • Replace PDC-3 methodology with the DPC-NE-2011-P-A methodology
  • Replace CAOC and sliding barn limits with AFD versus power envelope

QPTR Changes

  • The QPTR reference value at which a thermal power reduction is calculated is changed from 1.0 to 1.02
  • Peaking factors are increased by an amount corresponding to a 2% quadrant power tilt prior to comparison against LOCA, DNB and centerline fuel melt limits Duke Energy - PWR Methods Duke / NRC Meeting 24

SDM Definition Change (Harris Only)

  • The change allows an exception to the highest reactivity worth stuck control rod allowance if there are two independent means of confirming that all control rods are fully inserted
  • Definition change is consistent with the definition of SDM in NUREG-1431
  • With any rod cluster assembly not capable of being fully inserted, the reactivity worth of the stuck control rod must be accounted for in the determination of SDM
  • Soluble boron requirements to maintain SDM with and without the stuck rod assumption are controlled by plant procedures Duke Energy - PWR Methods Duke / NRC Meeting 25

Benefits of SDM Definition Change

  • Potentially decreases the amount of boron addition required following a reactor trip or shutdown
  • Reduces the amount of water and acid processing leading up to, and following a subsequent reactor startup following shutdown
  • Allows commencement of a reactor cooldown earlier Duke Energy - PWR Methods Duke / NRC Meeting 26

Tech Spec Parameter Relocation-Harris

  • Parameters relocated are consistent with those contained in the McGuire and Catawba COLRs
  • MODE 1 and 2 SDM limit

- TS 3.1.1.1 - Shutdown Margin - MODES 1 and 2

- TS 3.1.2.5 - Borated Water Source - Shutdown

- TS 3.1.2.6 - Borated Water Source - Operating

- TS 3.5.1 Emergency Core Cooling Systems, Accumulators

- TS 3.5.4 - Emergency Core Cooling Systems, Refueling Water Storage Tank Duke Energy - PWR Methods Duke / NRC Meeting 27

Tech Spec Parameter Relocation-Robinson

- TS 3.5.1 - Emergency Core Cooling Systems, Accumulators

- TS 3.5.4 - Emergency Core Cooling Systems, Refueling Water Storage Tank (RWST)

Duke Energy - PWR Methods Duke / NRC Meeting 28

COPERNIC

  • Current fuel rod mechanical analyses are performed by AREVA with RODEX2
  • Transition to COPERNIC is proposed to address TCD concerns
  • Analysis method is described in BAW-10231P-A
  • The proposed amendments would add the COPERNIC fuel performance code to TS 6.9.1.6 (Harris) and TS 5.6.5 (Robinson)

- BAW-10231P-A to the approved COLR lists

  • Self perform based on the guidance from generic letter 83-11
  • COPERNIC has been approved for fuel rod mechanical analyses at Oconee (May 11, 2017)

Duke Energy - PWR Methods Duke / NRC Meeting 29

Proposed Robinson BOC MTC TS Change Duke Energy - PWR Methods Duke / NRC Meeting 30

  • More restrictive at power levels below 50% RTP
  • Slightly less restrictive between 50% and 70% RTP
  • Unchanged between 70%

and 100% RTP 0

1 2

3 4

5 6

0 10 20 30 40 50 60 70 80 90 100 MTC (PCM/°F)

Rated Thermal Power (%)

Current MTC Limit Proposed MTC Limit

BOC MTC TS Change (Robinson Only)

  • Current specification is restrictive at 50% RTP
  • Proposed change is being pursued to increase design flexibility
  • Current UFSAR analyses supports both the current and proposed MTC limits
  • Future Duke analyses will be performed at the proposed limits Duke Energy - PWR Methods Duke / NRC Meeting 31

Conclusion

  • Changes made to support Duke reload analysis methodology
  • Fleet consistency was a priority
  • Power distribution Tech Spec revisions are based on previously approved methods (DPC-NE-2011-P-A) and specifications approved for McGuire and Catawba
  • Parameters relocated to the COLR are consistent with those contained in McGuire and Catawba COLRs
  • Implementation of COPERNIC is consistent with vendor guidance
  • Robinson BOC MTC Tech Spec change is driven by low margins associated with core designs using in-house methods Duke Energy - PWR Methods Duke / NRC Meeting 32
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