ML21082A470
| 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
Discuss proposed License Amendment Request (LAR) for the Monticello Nuclear Generating Plant (MNGP) to adopt Framatome advanced fuel analysis methods.
Purpose 3
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
Background
4
- 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
Background
5
- 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 LAR Licensing Approach 6
- 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 LAR Licensing Approach 7
- 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 Apply Approved Methodologies 8
- 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]
Apply Approved Methodologies 9
- 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 Apply Approved Methodologies 10
- 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 Methodologies Discussion 11
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 Methodologies Discussion 12
- 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)
Methodologies Discussion 13
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 Methodologies Discussion 14
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 Methodologies Discussion 15
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 Methodologies Discussion 16
- 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 LAR Content Overview 17
- 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)
LAR Content Overview 18
- 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 TS Changes - RPS 19
- 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 TS Changes - COLR 20
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]
TS Changes - COLR 21
- 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 TS Changes - COLR 22
- 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 TS Changes - COLR 23
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 Summary 24