ML21082A470

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Xcel Presentation for Monticello Pre-Application Public Meeting to Adopt Advanced Framatome Methods
ML21082A470
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 03/25/2021
From:
Xcel Energy
To: Robert Kuntz
NRC/NRR/DORL/LPL3
Kuntz R
References
Download: ML21082A470 (25)
v • d • e


Text

Monticello License Amendment Request To Adopt Advanced Framatome Methods March 25, 2021

Agenda

  • Purpose
  • Background
  • LAR Licensing Approach
  • Apply Approved Methodologies
  • Methodologies Discussion
  • LAR Content Overview
  • TS Changes
  • Summary 2

Purpose Discuss proposed License Amendment Request (LAR) for the Monticello Nuclear Generating Plant (MNGP) to adopt Framatome advanced fuel analysis methods.

3

Background

  • Xcel Energy intends to transition to the Framatome ATRIUM 11 fuel design (Cycle 32, spring 2023)
  • Advanced Framatome methods are needed to support ATRIUM 11 fuel deployment 4

Background

  • ATRIUM 10XM fuel operated at MNGP since 2017
  • ATRIUM 11 fuel provides following benefits:
  • 11x11 array reduces Linear Heat Generation Rate (LHGR) - improving safety margin
  • Improved debris protection features (fuel failure risk reduction)
  • Improved fuel channel performance
  • Improved economics 5

LAR Licensing Approach

  • Core Operating Limits Report (COLR) Technical Specifications (TS) revised to include advanced methods
  • Best Estimate Enhanced Option III (BEO-III) methodology to be utilized for stability protection
  • Demonstrate new methods application with an equilibrium cycle Monticello ATRIUM 11 core 6

LAR Licensing Approach

  • Xcel Energy can provide implementation cycle reports post-LAR approval for information
  • Fuel Cycle Design Report
  • Nuclear Fuel Design Report
  • Fuel Rod Thermal and Mechanical Report
  • Reload Safety Analysis Report
  • Safety Limit MCPR Report 7

Apply Approved Methodologies

  • All advanced Framatome methodologies used will have NRC approval (BEO-III topical report approval near)
  • NRC approved generic reports:
  • ANP-10332P-A, AURORA-B: An Evaluation Model for Boiling Water Reactors; Application to Loss of Coolant Accident Scenarios, Revision 0, March 2019
  • ANP-10333P-A, AURORA-B: An Evaluation Model for Boiling Water Reactors; Application to Control Rod Drop Accident (CRDA),

Revision 0, March 2018

  • ANP-10300P-A, AURORA-B: An Evaluation Model for Boiling Water Reactors; Application to Transient and Accident Scenarios, Revision 1, January 2018 8

Apply Approved Methodologies

  • NRC approved generic reports (continued):
  • ANP-10335P-A, ACE/ATRIUM 11 Critical Power Correlation, Revision 0, May 2018
  • ANP-10340P-A, Incorporation of Chromia-Doped Fuel Properties in AREVA Approved Methods, Revision 0, May 2018
  • ANP-10346P-A, ATWS-I Analysis Methodology for BWRs Using RAMONA5-FA, Revision 0, January 2020
  • ANP-10344P, Framatome Best-estimate Enhanced Option Ill Methodology, Revision 0, [est. April 30, 2021]

9

Apply Approved Methodologies

  • NRC approved generic reports (continued):
  • BAW-10247PA, Revision 0, Supplement 1P-A, Revision 0, Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors Supplement 1: Qualification of RODEX4 for Recrystallized Ziracaloy-2 Cladding, April 2017
  • BAW-10247P-A, Supplement 2P-A, Revision 0, Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors Supplement 2: Mechanical Methods, August 2018 10

Methodologies Discussion

  • New Monticello Long Term Stability Solution consisting of the Framatome Best-estimate Enhanced Option Ill Methodology (ANP-10344P)
  • BEO-III utilizes a best-estimate plus uncertainty analysis approach over the entire event to ensure margin to the SLMCPR at the time of the SCRAM
  • Will allow for single loop operation (SLO) outside the EFW region
  • No changes to plant NUMAC hardware 11

Methodologies Discussion

  • NRC approved AURORA-B CRDA method (ANP-10333P-A) topical report methodology applied on a cycle-specific basis
  • Demonstration analysis based on ATRIUM-11 equilibrium core
  • AURORA-B, CRDA NRC SE, Section 3.0 addressed reactivity insertion accident (RIA) criteria and need to evaluate to verify no changes beyond clarification associated with DG-1327

Methodologies Discussion

  • Current licensing basis release for a CRDA event remains bounding
  • Confirmatory dose consequence evaluation considers the steady state release and the transient release criteria
  • Steady state release fractions based on RG 1.183, Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors, (July 2000)
  • Transient release fraction from Draft Guide-1327, Pressurized Water Reactor Control Rod Ejection and Boiling Water Reactor Control Rod Drop Accidents, Revision 1 (July 2019) 13

Methodologies Discussion

  • NRC approved AURORA-B transient method utilized for HPCI:
  • ANP-10300P-A, AURORA-B: An Evaluation Model for Boiling Water Reactors; Application to Transient and Accident Scenarios, Revision 1, January 2018
  • Limitation and Condition 12 of the topical requires plant specific review of the method used to determine the mixing in the lower plenum during an inadvertent HPCI event
  • Inadvertent HPCI will be analyzed for Monticello
  • Will utilize the same method as used for Susquehanna
  • This method will be defined in the Methods Applicability report 14

Methodologies Discussion

  • Section 6.2.8 of the topical contains a sensitivity study on time step size with the following conclusion
  • Based on the sensitivity, time step sizes larger than 0.0050 sec are acceptable as long as the impact is conservative for the analysis.
  • This is proposed to be amended to
  • Based on the sensitivity, time step sizes larger than 0.0050 sec are acceptable as long as the impact is negligible or conservative for the analysis
  • This allows for small negligible fluctuations in the temporally converged solution
  • Justification will be identical to that provided for Susquehanna and will be included in the Methods Applicability report 15

Methodologies Discussion

  • NRC approved generic ATWS-I methodology (ANP-10346P-A) to be applied
  • ATRIUM 10XM for Monticello used a plant-specific AISHA/

SINANO methodology

  • Predecessor to the current generic RAMONA5-FA ATWS-I
  • Contain many simplifications which were compensated by additional conservatisms in the methodology
  • RAMONA5-FA generic ATWS-I methodology simulates full event
  • Removes the additional conservatisms from the AISHA/SINANO methodology
  • Peak Cladding Temperature expected to be considerably lower 16

LAR Content Overview

  • Reports submitted with LAR based on Monticello equilibrium cycle ATRIUM 11 fuel design
  • Assembly Mechanical Design reports
  • Methods Applicability Document
  • Thermal Hydraulic Design Report
  • BWR Licensing Methodology Compendium 17

LAR Content Overview

  • Reports submitted with LAR based upon Monticello equilibrium cycle ATRIUM 11 fuel design
  • ATRIUM 11 ATWSi Analysis Report
  • AURORA-B Limiting Transient Analysis Uncertainty Demonstration

TS Changes - RPS

  • Remove the Extended Flow Window Stability (EFW) - High trip (Function 2.g) in Table 3.3.1.1-1 and remove the references to the function in the ACTIONS
  • Remove Condition J to reduce Thermal Power to below MELLLA boundary defined in the COLR from the ACTIONS
  • Specification 5.6.3 - COLR, Item a.6 - Remove reference to the COLR for Function 2.g EFW setpoints 19

TS Changes - COLR

  • Specification 5.6.5 COLR additions
  • ANP-10332P-A, AURORA-B: An Evaluation Model for Boiling Water Reactors; Application to Loss of Coolant Accident Scenarios, Revision 0, March 2019
  • ANP-10333P-A, AURORA-B: An Evaluation Model for Boiling Water Reactors; Application to Control Rod Drop Accident (CRDA), Revision 0, March 2018
  • ANP-10300P-A, AURORA-B: An Evaluation Model for Boiling Water Reactors; Application to Transient and Accident Scenarios, Revision 1, January 2018 20

TS Changes - COLR

  • ANP-10335P-A, ACE/ATRIUM 11 Critical Power Correlation, Revision 0, May 2018
  • ANP-10346P-A, ATWS-I Analysis Methodology for BWRs Using RAMONA5-FA, Revision 0, January 2020
  • ANP-10344P, Framatome Best-estimate Enhanced Option Ill Methodology, Revision 0, [est. April 30, 2021]

21

TS Changes - COLR

  • Add Framatome Thermal-Mechanical methodologies:
  • ANP-10340P-A, Revision 0, Incorporation of Chromia-Doped Fuel Properties in AREVA Approved Methods, May 2018
  • BAW-10247PA, Revision 0, Supplement 1P-A, Revision 0, Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors Supplement 1: Qualification of RODEX4 for Recrystallized Ziracaloy-2 Cladding, April 2017
  • BAW-10247P-A, Supplement 2P-A, Revision 0, Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors Supplement 2: Mechanical Methods, August 2018 22

TS Changes - COLR

  • Remove superseded licensing methodologies and evaluations:
  • XN-NF-84-105(P)(A) Volume 1, and Volume 1 Supplements 1 and 2, XCOBRA-T: A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis, February 1987
  • ANF-913(P)(A) Volume 1 Revision 1, and Volume 1 Supplements 2, 3, and 4, COTRANSA2: A Computer Program for Boiling Water Reactor Transient Analyses, August 1990
  • Engineering Evaluation EC 25987, Calculation Framework for the Extended Flow Window Stability (EFWS) Setpoints, as docketed in Xcel Energy letter to NRC L-MT-15-065, dated September 29, 2015 23

Summary

  • Advanced Framatome methods have been previously approved for other licensees
  • BEO-III expected to be approved by the targeted date for LAR submittal - so all advanced methods topical reports utilized will have received prior NRC approval
  • Projected date for LAR submittal - July 2021
  • Requested for the spring 2023 refueling outage 24
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