ML16014A110
"Draft Meeting" is not in the list (Request, Draft Request, Supplement, Acceptance Review, Meeting, Withholding Request, Withholding Request Acceptance, RAI, Draft RAI, Draft Response to RAI, ...) of allowed values for the "Project stage" property.
| ML16014A110 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 01/20/2016 |
| From: | Arizona Public Service Co |
| To: | Office of Nuclear Reactor Regulation |
| Watford M, NRR/DORL/LPLIV-1 | |
| References | |
| CAC MF7214, CAC MF7215, CAC MF7216 | |
| Download: ML16014A110 (19) | |
Text
NRC Pre-Submittal Meeting Next Generation Fuel Palo Verde Units 1, 2, and 3 January 20, 2016
Introduction of Personnel Thomas Weber - Department Leader, Regulatory Affairs, APS Michael Dilorenzo - Section Leader, Regulatory Affairs, APS Matthew Cox - Sr. Licensing Consultant, APS Brian Blackmore - Acting Director, Nuclear Engineering, APS Robert Hicks - Sr. Engineer, Transient Analysis, APS Cory Schingeck - Operations Manager, APS Doug Weaver - VP, Nuclear Regulatory Affairs, Westinghouse Thomas Zalewski - Project Manager, Westinghouse Max OCain - Overall Program Manager, Westinghouse Jeff Brown - Consulting Engineer, Westinghouse Vick Nazareth - Director, Nuclear Fuel Technology, Anatech 2
Agenda
- Overview
- Fuel Design Features
- Analytical and Licensing Changes
- Summary 3
Purpose
- Present planned license changes to implement the Westinghouse Next Generation Fuel product
- New improved fuel design (CE_16x16_NGF) 1
- Consistent with precedents for other Combustion Engineering (CE) digital protection plants (ML080840015, (3/26/2008) &
ML080880014, (4/15/2008))
1: CE_16x16_NGF is Next Generation Fuel design, referred to as CE16NGF through the presentation 4
Why Change Fuel Design
- Palo Verde Nuclear Generating Station (PVNGS) is the last domestic station using CE16STD fuel
- CE16NGF fuel design contains advanced features to enhance fuel reliability, fuel cycle economics and thermal performance 5
Typical CE16NGF Assembly 6
Design Changes with CE16NGF
- Burnable absorber change (Erbia to ZrB2)
- Fuel rod dimensional changes
- Rod outer diameter
- Clad thickness
- Spacer Grid changes
- New I-spring grid design
- Addition of mixing vane grids
- Addition of intermediate flow mixing grids 7
NGF Lead Assembly Program
- Temporary Optimized ZIRLO TM exemption approved for Lead Assembly Program (ML101900254, August 2010)
CE16NGF Design Change Licensing Topics
- CE16NGF design previously approved in WCAP 16500-P-A (Rev. 0 and Supplement 1)
- Supplement 2 is currently in NRC review
- Three design changes to spacer grids
- Addresses IN 2012-09, Irradiation Effects on Fuel Assembly Spacer Grid Crush Strength 9
Reload Method Changes Update NRC approved reload methods to:
- Add VIPRE thermal-hydraulic code
- Add Departure from Nucleate Boiling Ratio (DNBR) correlations (ABB-NV, WSSV, WLOP)
- Modify method of determining the Core Protection Calculator System (CPCS) and Core Operating Limit Supervisory System (COLSS) penalties
- Add the use of the approved CENTS code for flow coast down simulation in support of CENPD-183-A 10
DNBR Limit Implementation Plan
- No change to Technical Specification (TS) 2.1.1.1 DNBR safety limit
- Consistent with WCAP-16500-P-A, Supplement 1, CPCS DNBR correlation not being changed
- This ensures the consistency between the Technical Specification value and DNBR monitoring in the control room License amendment request to include discussion on use of WSSV and ABB-NV DNBR correlations and how to equate the analytical DNBR limit to CE-1 DNBR Limit 11
DNBR Limits for CE16NGF Cores Analytical TS/CPCS Core Fuel Types Correlation(s)
Limit Limit Current CE16STD CE-1 1.34 1.34 1st transition majority CE16STD WSSV & ABB-NV 1.34 1.34 2nd transition majority CE16NGF WSSV & ABB-NV 1.25 1.34 Full Core CE16NGF WSSV 1.25 1.34
- No change to TS 2.1.1.1 DNBR safety limit 12
Loss Of Coolant Accident (LOCA)
LOCA analyses address the change in burnable absorber and clad material with CE16NGF introduction
- Current PVNGS Appendix K LOCA methodology (CE 1999 Large Break LOCA and S2M Small Break LOCA) is utilized
- Long Term Cooling (LTC) calculation revised to address issues associated with CENPD-254-P (ML053220569)
- Thermal Conductivity Degradation (TCD) is addressed through use of the conservative FATES3B fuel performance code and Appendix K LOCA methodology The CE16NGF design utilizes Optimized ZIRLO TM cladding which will be documented in a permanent exemption request per 10 CFR 50.12 13
Technical Specification Changes
- TS 5.6.5b - Core Operating Limits Report (COLR) methodologies - update to incorporate CE16NGF, VIPRE code, and DNBR correlations 14
Topical Reports Being Added to T.S.
5.6.5b WCAP-16500-P-A, CE 16x16 Next Generation Fuel Core Reference Report WCAP-16523-P-A, Westinghouse Correlations WSSV and WSSV-T for Predicting Critical Heat Flux in Rod Bundles with Side-Supported Mixing Vanes EPRI-NP-2511-CCM, VIPRE-01: A Thermal-Hydraulic Analysis Code for Reactor Cores WCAP-14565-P-A, VIPRE-01 Modeling and Qualification for Pressurized Water Reactor Non-LOCA Thermal-Hydraulic Safety Analysis CENPD-387-P-A, ABB Critical Heat Flux Correlations for PWR Fuel WCAP-16072-P-A, Implementation of Zirconium Diboride Burnable Absorber Coatings in CE Nuclear Power Fuel Assembly Designs Consistent with the current TS 5.6.5b, the COLR will contain the complete identification for each of the Technical Specification referenced topical reports 15
Technical Areas Reviewed Mechanical Design Core Design Fuel Performance Core Thermal Hydraulic Design Fuel Rod Corrosion Non-LOCA Transient Analysis Emergency Core Cooling System (ECCS) Performance Analyses Containment Response Radiological Source Term Radiological Accident Core Reload Setpoints RCS Structural RCS Design, Systems, and Components Reactor Vessel Fluence and Brittle Fracture Pressure Temperature Limits 16
Implementation Schedule NRC approval of WCAP-16500-P-A, Supplement 2, required prior to submittal PVNGS planning transition to CE16NGF design with Unit 2, 21st refueling (Fall of 2018)
- Fuel order date June 2016 PVNGS would like to request an 18 month NRC review time to the support the implementation date Other item - Spent Fuel Pool Criticality License Amendment Request (LAR) 17
Summary
- PVNGS transitioning to a proven fuel design for CE16NGF fuel
- Reload methods adjusted for CE16NGF fuel design
- LOCA analyses support CE16NGF fuel design
- WCAP-16500 Supplement 2
- Technical Specification DNBR Limit
- COLR methodologies
- Spent Fuel Pool Criticality LAR
- 18 month NRC review time 18
We SAFELY and efficiently generate electricity for the long term 19