ML21082A470

Xcel Presentation for Monticello Pre-Application Public Meeting to Adopt Advanced Framatome Methods

ML21082A470
Person / Time
Site:	Monticello
Issue date:	03/25/2021
From:	Xcel Energy
To:	Robert Kuntz NRC/NRR/DORL/LPL3
Kuntz R
References
Download: ML21082A470 (25)

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

• Reactor Protection System TS revised to reflect BEO-III

• 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]

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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

• Monticello is not licensed for reduced feedwater heating or feedwater heater operation out-of-service (FWHOOS)

• 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

• Regulatory Guide (RG) 1.236, Pressurized-Water Reactor Control Rod Ejection and Boiling-Water Reactor Control Rod Drop Accidents, later issued - and to address hydrogen pick-up model

• Multiplier on approved Framatome hydrogen model will be used to address hydrogen in oxide layer per RG 1.236, Item 2.3.4.2 12

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

• LOCA / MAPLHGR 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

• AURORA-B Application for the Control Rod Drop Accident (CRDA) 18

TS Changes - RPS

• Specification 3.3.1.1 - Reactor Protection System (RPS) TS Changes

• 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

• Add Framatome licensing methodologies:

• 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

• Add Framatome licensing methodologies:

• 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