ML22336A026

From kanterella
Jump to navigation Jump to search

December 7 2022 24-Month Fuel Cycle Public Meeting Licensee Slides
ML22336A026
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 12/07/2022
From:
Florida Power & Light Co
To:
NRC/NRR/DORL/LPL2-2
References
EPID L-2022-LRM-0096
Download: ML22336A026 (1)


Text

Turkey Point Units 3 and 4 License Amendment Requests for Transition to 24-Month Fuel Cycles December 7, 2022 Non-proprietary information suitable for public disclosure

FPL Project Team Steve Catron Kenneth Mack Jarrett Mack Emilio Fuentes Patrick Hahn Philip Tiemann Rob Regan Director Licensing & Reg. Compliance Manager Fleet Licensing Principal Engineer, Licensing Director Fuel Engineering Manager Fuel Engineering Principal Engineer, Fuel Project Engineer, Fuel Westinghouse Project Support

Meeting Agenda Objectives Licensing Actions Methodology & Approach ADOPT' AXIOM FSLOCA' Non-LOCA Rod Ejection and RG 1.236 Spent Fuel Pool Criticality Project Status Proposed Schedule Questions ADOPT, AXIOM, and FSLOCA are trademarks or registered trademarks of Westinghouse Electric Company LLC, its affiliates and/or its subsidiaries in the United States of America and may be registered in other countries throughout the world. All rights reserved. Unauthorized use is strictly prohibited.

Non-proprietary information suitable for public disclosure

Provide overview of FPLs plan to transition Turkey Point Units 3 & 4 to 24-Month Fuel Cycles

- Scope and content

- Schedule Obtain NRC feedback

- LAR Content

- Approval schedule Objectives Non-proprietary information suitable for public disclosure

WCAP-16996-P-A Revision 1 Realistic LOCA Evaluation Methodology Applied to the Full Spectrum of Break Sizes

- Amendment 296, 289 - May 2022 (ML22028A064)

Requirements of Generic Letter 91-04

- Surveillance Frequency Control Program per TSTF-425 Amendments 263, 258 - July 2015 (ML15166A320)

- Containment Leak Rate Test Frequency Extension per NEI 94-01, Rev 3A Amendments 295, 288 - May 2021 (ML21119A355)

- Revised Frequencies for Steam Generator Tube Inspections per TSTF-577 Submitted with Improved Standard Technical Specifications transition LAR (ML22089A195)

Completed Licensing Actions Non-proprietary information suitable for public disclosure

Spent Fuel Pool Criticality License Amendment Request

- Incorporates fuel management changes

- Updated to fully comply with latest guidance 24-Month Fuel Cycle License Amendment Request

- Fuel design change technical justifications

- NSSS and BOP analyses updates

- Instrument drift (per GL 91-04)

- Tech Spec, Bases, TRM and COLR markups Exemption Request for AXIOM Fuel Cladding Proposed Licensing Actions Non-proprietary information suitable for public disclosure

Methodology & Approach ADOPT Fuel Introduction Reason for change:

- Improved fuel cycle economics due to 2% density increase WCAP-18482-P approved ADOPT fuel in November 2022 Licensed for use in all PWR reactor designs

- Compatible with NRC-approved zirconium based cladding materials, including AXIOM

- Existing NRC-approved analytical methods and models are appropriate for ADOPT fuel designs

- Will comply with the limitation and condition by utilizing 3D rod ejection and RG 1.236 Non-proprietary information suitable for public disclosure

Methodology & Approach AXIOM Fuel Cladding Introduction Reason for change:

- Improved corrosion resistance and reduced hydrogen pickup

- Reduced cladding creep and growth WCAP-18546-P was submitted in March 2021

- Applicable to all current PWR fuel designs

- New models and methods developed as necessary for some of the properties different from existing cladding

- Existing NRC-approved safety analysis methods are compatible with AXIOM

- Compatible with conventional and ADOPT fuel pellets The ACRS Material, Metallurgy, and Reactor Fuel Subcommittee reviewed and recommended approval of the AXIOM topical report on October 4, 2022 Non-proprietary information suitable for public disclosure AXIOM Cladding requires an exemption from 10 CFR 50.46

Methodology & Approach AXIOM Cladding Topical Report Addressed 10 CFR 50.46c Research Findings Non-proprietary information suitable for public disclosure Peak cladding temperature - 10 CFR 50.46 (b)(1)

Maximum cladding oxidation - 10 CFR 50.46 (b)(2)

Maximum hydrogen generation - 10 CFR 50.46 (b)(3)

Coolable Geometry - 10 CFR 50.46 (b)(4)

Long-term cooling - 10 CFR 50.46 (b)(5)

Peak cladding temperature - 10 CFR 50.46c (g)(1)(i)

Cladding embrittlement - 10 CFR 50.46c (g)(1)(ii)

Breakaway oxidation - 10 CFR 50.46c (g)(1)(iii)

Maximum hydrogen generation - 10 CFR 50.46c (g)(1)(iv)

Long-term cooling - 10 CFR 50.46c (g)(1)(v)

Implicitly demonstrated by meeting fuel performance criteria and accounting for changes in core geometry during postulated accident Current acceptance criteria AXIOM cladding fuel performance criteria Content of AXIOM cladding topical report established applicable fuel performance criteria

Methodology & Approach FSLOCA Re-analysis Reasons for re-analysis:

- AXIOM topical reports Limitations and Conditions

- Cycle length

- Blanket design

- Burnable poison

- Power shape libraries and burnup dependent peaking factor limits

- ADOPT fuel pellets WCAP-16996-P-A Revision 1

- Approved for Turkey Point, May 2022

- Amendment 296, 289 (ML22028A064)

Non-proprietary information suitable for public disclosure The re-analysis will be subject to reporting pursuant to 10 CFR 50.46 (a)(3)(ii)

Methodology & Approach Non-LOCA Re-analysis Technical evaluations for UFSAR Chapter 14 Non-LOCA analyses

- No changes to analysis models or methods, except Rod Ejection

- Changes addressed via updated analysis inputs Increased cycle length Fuel design changes Steam generator tube plugging limit increase The majority of Non-LOCA events are being reanalyzed Non-proprietary information suitable for public disclosure

Methodology & Approach Rod Ejection - Approved Codes and Methods Uses 3D core kinetics NRC approved methodology

- WCAP-15806-P-A, Westinghouse Control Rod Ejection Accident Analysis Methodology Using Multi-Dimensional Kinetics Similar approach as for AP1000 PWR Core Reference Report

- WCAP-17524-P-A, AP1000 Core Reference Report

- This used the interim limits described in NUREG-0800, Rev. 3 Uses AXIOM limit for rod ejection and models

- WCAP-18546-P, Westinghouse AXIOM Cladding for Use in Pressure Water Reactor Fuel AP1000 is a registered trademark of Westinghouse Electric Company LLC, its affiliates and/or its subsidiaries in the United States of America and may be registered in other countries throughout the world. All rights reserved. Unauthorized use is strictly prohibited.

Non-proprietary information suitable for public disclosure

Methodology & Approach Rod Ejection and RG 1.236 Compliance Transient Fission Gas Release Model

- Based on limiting enthalpy rise calculations High Temperature Cladding Failure Limit

- Based on limiting rod internal pressure PAD5 calculations PCMI Failure Criterion

- Based on limiting PAD5 corrosion calculations Other Limits from RG 1.236

- DNBR failure for non-prompt critical initiated events

- Burnup dependent fuel melt failure criterion This analysis will confirm AST dose analysis inputs Coolability limits on fuel melt and peak enthalpy will be met Peak reactor coolant pressure < ASME Service Limit C Non-proprietary information suitable for public disclosure

Methodology & Approach Spent Fuel Pool Criticality Analysis Current Analysis of Record was implemented ~10 years ago The updated analysis will:

- Incorporate fuel management changes as a result of 24-month cycles Burnable absorbers Soluble boron during depletion Axial profiles Other important fuel design inputs (e.g., fuel density)

- Include updated methodology NEI-12-16, Revision 4 as endorsed by RG 1.240 Non-proprietary information suitable for public disclosure

Project Kickoff November 2021 Safety analysis impact assessments are ongoing

- Methodical review of all plant systems and safety analyses

- Update analyses as-needed Preliminary Analysis Impacts / Results

- Fluences and source terms found to be bounded

- Radiological dose not expected to be impacted

- Reanalyzed Containment analysis Main Steam Line Break (MSLB)

Large Break LOCA (LBLOCA)

Project Status Non-proprietary information suitable for public disclosure

Proposed Schedule Non-proprietary information suitable for public disclosure Submit SFP Criticality LAR June 2023 Submit 24-Month Fuel Cycle LAR (with attached AXIOM Exemption Request)

August 2023 Requested Approval for SFP Criticality LAR July 2024 Requested Approval for 24-Month Fuel Cycle LAR September 2024 24-Month Fuel Cycle Implementation for Unit 4 Spring 2025 24-Month Fuel Cycle Implementation for Unit 3 Spring 2026

Questions?

Non-proprietary information suitable for public disclosure