ML18088A012

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Framatome Fuel Pre-Submittal Slides (Non-Proprietary)
ML18088A012
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 04/05/2018
From: Siva Lingam
Plant Licensing Branch IV
To: Bement R
Arizona Public Service Co
Lingam S, 301-415-1564
References
Download: ML18088A012 (31)
v • d • e


Text

NRC Pre-Submittal Meeting Implementation of Framatome CE16HTP Fuel Palo Verde Units 1, 2, and 3 April 5, 2018

2 Overview Framatome Fuel Design Features Analytical and Licensing Changes Safety Limit 2.1.1 - DNBR and Peak Fuel Centerline Temperature Safety Limits Technical Specification 4.2.1 - Design Features Technical Specification 5.6.5.b - COLR Methodologies 10 CFR 50.12 Permanent Cladding Exemption Request Implementation Schedule Summary Discussion Topics

3 Thomas Weber - Acting Director, Regulatory Affairs, APS Michael Dilorenzo - Department Leader, Regulatory Affairs, APS Matthew Cox - Section Leader, Regulatory Affairs, APS Sean McCormack - Engineer III, Regulatory Affairs, APS Thomas Remick - Department Leader, Nuclear Fuel Management, APS David Ricks - Section Leader, Nuclear Fuel Management, APS David Medek - Consulting Engineer, Nuclear Fuel Management, APS Charles Karlson - Section Leader, Nuclear Fuel Management, APS Shawn Gill - Senior Engineer, Nuclear Fuel Management, APS Bradley Sutton - Senior Engineer, Nuclear Fuel Management, APS Jill Magnusson - Engineer III, Design Engineering, APS Greg Kessler - Project Manager, Framatome Rick Williamson - Contract Manager, Framatome Vick Nazareth - Director, Nuclear Fuel Technology, Structural Integrity Mark Drucker - Associate, Nuclear Fuel Technology, Structural Integrity Introduction of Personnel

4

  • Present planned license and methodology changes to implement the Framatome Advanced CE-16 High Thermal Performance (HTP') fuel design product (CE16HTP)

Purpose of Pre-Submittal Meeting

5

  • Communicate plan for submittal of Framatome CE16HTP fuel license amendment
  • Gain an understanding of NRC staff perspectives that need to be addressed proactively in the submittal
  • Discuss approval timeline for Framatome topical report currently under review by the NRC staff Desired Outcomes

6

  • APS is planning on using Framatome CE16HTP fuel in the Spring 2020 refueling of Unit 2 Estimated 100 CE16HTP fuel assemblies to be loaded into the reactor core Essentially the same design as that of the Framatome lead test assemblies (LTAs)
  • NRC approval is required for the Palo Verde methodology changes to address Framatome fuel

Background

7

  • Security of Supply Reliable fuel designs Multiple fuel vendors Geographically diverse manufacturing Commercial considerations Why Implement a New Fuel Design

8

  • Burnable absorber change (to gadolinia)
  • Cladding material change (to M5)
  • Grid design
  • Fuel assembly structure CE16STD refers to the Westinghouse standard fuel design CE16NGF refers to the recently approved Westinghouse Next Generation Fuel design Key Differences with CE16HTP (with respect to CE16STD and CE16NGF)

9 CE16HTP Fuel Assembly

10

  • Fuel Assembly Structure Upper tie plate design is the standard Framatome CE-type reconstitutable design Cage or skeleton design includes:
  • four (4) M5 MONOBLOC' corner guide tubes
  • one (1) M5 center guide tube / instrument tube
  • ten (10) M5 HTP' spacers
  • one (1) Alloy 718 HMP' spacer at the lowest spacer position Lower tie plate design is the FUELGUARD' structure CE16HTP Mechanical Design

11

  • Lead Assembly Program implemented in Unit 1 for three reload cycles beginning in 2008, completed in 2013
  • Lead Assemblies met all acceptance criteria based on post-irradiation examination CE16HTP Lead Assembly Program

12

  • Reload Methods addressed in the submittal Update NRC approved APS reload methods to address Framatome fuel Use of NRC approved Framatome Mechanical Design and LOCA methods Use of NRC approved Framatome COPERNIC methods for fuel behavior analysis (addresses Thermal Conductivity Degradation)

Builds on APS NGF submittal (ML16188A336)

Submittal Highlights

13

  • Update NRC approved reload methods to:

Add VIPRE-01 thermal-hydraulic code Add Framatome BHTP critical heat flux (CHF) correlation Add method for performing Framatome fuel behavior analysis (COPERNIC fuel performance code)

Add methods for performing Framatome Small and Large Break LOCA analyses Modify methods for performing CEA ejection analysis, DNB propagation, and statistical convolution for fuel failure to address Framatome fuel Reload Method Changes

14

  • Same approach as used for Next Generation Fuel (ML16188A336)

This ensures consistency between the TS 2.1.1.1 DNBR Safety Limit value and DNBR monitoring in the Control Rooms Analytical limit presented in TS Bases

  • Submittal to include discussion on use of BHTP CHF correlation and how to equate the analytical DNBR limit to the CE-1 DNBR Safety Limit DNBR Safety Limit

15

  • The DNBR analytical limit depends on fuel type For a CE16STD core the DNBR analytical limit is 1.34 using CE-1 or ABB-NV For a CE16NGF core the DNBR analytical limit is 1.25 using WSSV & ABB-NV For a CE16HTP core the DNBR analytical limit is 1.25 using BHTP
  • For a mixed core where multiple fuel types may be limiting, the more conservative DNBR analytical limit will be used in conjunction with the CHF correlation for each limiting fuel type DNBR Analytical Limit

16

  • Change to TS 2.1.1.2 Peak Fuel Centerline Temperature Safety Limit Retain existing limit for Westinghouse supplied fuel Add NRC approved limit for Framatome supplied fuel

[consistent with COPERNIC Topical Report BAW-10231(P)(A)]

Peak Fuel Centerline Temperature Safety Limit

17 Peak Fuel Centerline Temperature Safety Limit

18

  • TS 4.2.1 - Design Features of Fuel Assemblies Update to allow use of M5 clad Remove wording that requires an exemption for other cladding material to conform with NUREG-1432 Standard Technical Specifications TS 4.2.1 Changes

19 TS 4.2.1 Changes

20

Add VIPRE-01 Add Framatome methodologies applicable to CE16HTP fuel, including BHTP CHF correlation TS 5.6.5

21 Topical Reports Added to TS 5.6.5.b

22 Core Operating Limits Report Changes T.S.

Ref.

Title Report No.

Rev.

Date Suppl.

27 Realistic Large Break LOCA Methodology for Pressurized Water Reactors EMF-2103P-A 3

June 2016 N.A.

28 PWR Small Break LOCA Evaluation Model, S-RELAP5 Based EMF-2328(P)(A) 0 March 2001 N.A.

28 PWR Small Break LOCA Evaluation Model, S-RELAP5 Based EMF-2328(P)(A) 0 December 2016 1(P)(A) 29 COPERNIC Fuel Rod Design Computer Code BAW-10231P-A 1

January 2004 N.A.

30 BHTP DNB Correlation Applied with LYNXT BAW-10241(P)(A) 1 July 2005 N.A.

31 VIPRE-01: A Thermal-Hydraulic Analysis Code for Reactor Cores EPRI-NP-2511-CCM-A Mod 02 Rev 3 Volume 1-3 (August 1989), Volume 4 (April 1987), Volume 5 (September 1989)

N.A.

23 Palo Verde Reload Methodology Reload Specification Document Fuel Management Enrichment and U suppliers Core Physics Design Fuel Rod Behavior Analysis Core Thermal Hydraulic Analysis Fuel Assembly Mechanical Design Fuel Fabrication LOCA Analysis Non-LOCA Transient Analyses (non CEA Ejection)

COLSS & CPC Setpoints Analysis As-Built Data from Manufacturing New Fuel Batch TS Bases and COLR Changes (if needed)

COLSS & CPC Products Core Follow and At-Power Physics Low Power and Power Ascension Physics Testing Predictions CECOR Incore Libraries Core Data Book Vendor Scope PV & Vendor Interface PV Scope Method Impacted by Framatome Fuel Legend:

CEA Ejection

24

  • Fuel Mechanical Design
  • Nuclear Design
  • Fuel Rod Behavior (Performance)
  • Core Thermal Hydraulic Design
  • COLSS/CPCS Setpoints Technical Areas Reviewed in Submittal

25

  • LOCA analyses address the change in burnable absorber and clad material with CE16HTP introduction Framatome Realistic Large Break LOCA methodology Framatome Small Break LOCA methodology (Appendix K)

Thermal Conductivity Degradation (TCD) is addressed Long Term Cooling analyses not impacted by fuel change

26 Westinghouse Fuel Analysis Framatome CE16HTP Analysis LBLOCA Peak Clad Temperature (F) 2129.6 1752 Local Maximum Oxidation (%)

15.78 2.37 Core Wide Oxidation (%)

0.813 0.020 SBLOCA Peak Clad Temperature (F) 1678 1620 Local Maximum Oxidation (%)

4.5 2.96 Core Wide Oxidation (%)

< 0.33 0.006 LOCA Analysis

27

  • Radiological Consequence Analyses No change in power level or plant systems Accident analysis results expected to be maintained consistent with current input to the dose analyses Therefore, the UFSAR dose analyses would continue to remain applicable
  • Spent Fuel Pool (SFP) Criticality Analysis SFP criticality analysis remains bounding Framatome 16x16 fuel bounded by CE16NGF fuel design as modeled in the current SFP criticality analysis Impact on Other Analyses

28 March 2018 Manufacturing of long lead fuel components began April 2018 Pre-submittal meeting May 2018 NRC approval of Framatome topical June 2018 Submittal July 2018 NRC acceptance review complete Fall 2019 NRC Safety Evaluation with submittal approval, and approval of clad exemption request January 2020 Delivery of Framatome fuel begins Spring 2020 Refueling outage Implementation Schedule

29

  • Topical Report required to be approved prior to submittal ANP-10337P Revision 0, PWR Fuel Assembly Structural Response to Externally Applied Dynamic Excitations
  • APS requests a 12 to 15 month NRC review to support the implementation date Implementation Schedule (cont.)

30

  • Palo Verde is implementing a proven CE16HTP fuel design Excellent performance in previous LTA program Reload methods adjusted for CE16HTP fuel design Realistic Large Break LOCA analyses performed Addresses thermal conductivity degradation
  • Technical Specification Changes Reactor Core Safety Limits Fuel Design Information Core Operating Limits Report
  • Permanent Cladding Exemption
  • First use in Spring 2020 Summary

31 Questions?

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