|
|
| Line 17: |
Line 17: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:Monticello License Amendment Request To Adopt Advanced Framatome Methods March 25, 2021 | | {{#Wiki_filter:}} |
| | |
| 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]
| |
| 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
| |
| * 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}}
| |
