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{{#Wiki_filter:Pre-Submittal Meeting for Reload License Amendment Request to Implement Framatome 17x17 GAIA Fuel at Millstone Power Station Unit 3 | {{#Wiki_filter:Pre-Submittal Meeting for Reload License Amendment Request to Implement Framatome 17x17 GAIA Fuel at Millstone Power Station Unit 3 | ||
Agenda | September 13, 2023 | ||
1 Agenda | |||
* Introductions | * Introductions | ||
* GAIA LAR Review Status and Schedule | *GAIA LAR Review Status and Schedule | ||
* Reload LAR | *Reload LAR | ||
* Approval Requests | * Approval Requests | ||
* Technical Basis | * Technical Basis | ||
* Expected Attachments 2 | * Expected Attachments | ||
2 GAIA Project Team | |||
* Chris Clemens Supervisor, Fuel Procurement Engineering | |||
*Dan Smith Fuel Procurement Project Manager | |||
*Scott Luchau Supervisor, Nuclear Safety Analysis | |||
*Brian Mount Nuclear Safety Analysis | |||
*Ruxandra Bobolea Nuclear Safety Analysis | |||
*Emily Tomlinson Nuclear Safety Analysis | |||
*William KohlroserNuclear Safety Analysis | |||
*Brian Vitiello Supervisor, Nuclear Core Design | |||
*Brian Kinney Nuclear Core Design | |||
*Rich Ridder Supervisor, Fuel Performance Assessment | |||
*Dave van SchooneveldFuel Performance Assessment | |||
*Shayan Sinha Regulatory Affairs | |||
3 GAIA LAR Review Status and Schedule | |||
2022 2023 2024 2025 Q4 Q1 Q2 Q3 Q4 Q1 Q2 Q3 Q4 Q1 Q2 Q3 OctNovDec JanFebMar AprMayJun JulAugSep OctNovDec JanFebMar AprMayJun JulAugSep OctNovDec JanFebMar AprMay JunJulAug M3C22 Operation | |||
SFP Criticality Supplement NRC Review [12M Review Requested] | |||
ORFEO DDL NRC Review [12M Review Requested] | ORFEO DDL NRC Review [12M Review Requested] | ||
T-M Design LAR NRC Review [12M Review Requested] | T-M Design LAR NRC Review [12M Review Requested] | ||
SB/LB LOCA LAR NRC Review [12M Review Requested] | SB/LB LOCA LAR NRC Review [12M Review Requested] | ||
M3C23 Operation Reload LAR NRC Review [12M Review Requested] | |||
GAIA Fuel Batch Fabrication M3C24 Operation DENC desired to spread out NRC review, provide focused topic area submittals, and minimize the potential for overlapping linked submittals (DOM-NAF-2 App. F and Reload LAR). | M3C23 Operation | ||
Reload LAR NRC Review [12M Review Requested] | |||
GAIA Fuel Batch Fabrication | |||
M3C24 Operation DENC desired to spread out NRC review, provide focused topic area submittals, and minimize the potential for overlapping linked submittals (DOM-NAF-2 App. F and Reload LAR). | |||
Based on current review schedule DOM-NAF-2 SE will not be issued prior to Reload LAR submittal. | Based on current review schedule DOM-NAF-2 SE will not be issued prior to Reload LAR submittal. | ||
GAIA Reload LAR LAR Content - Approval Requests | 4 GAIA Reload LAR | ||
LAR Content -Approval Requests 1)TS Change to add DE Fleet Report DOM-NAF-2, App. F to the TS 6.9.1.6.b COLR list of methodologies 2)TS Change to add ORFEO-GAIA DDL (1.13) to TS 2.1.1.1 Reactor Core Safety Limit 3)TS Change to the P-8 setpoint in Table 2.2-1 Reactor Trip System Instrumentation Trip Setpoints | |||
* Conservative reduction from current 50% to 35% | * Conservative reduction from current 50% to 35% | ||
4)DBLFPBs associated with the implementation of the FRM AREA method (ANP-10338-P-A) and DE Fleet Report VEP-NE-2-A | |||
GAIA Reload LAR LAR Content - Technical Basis | 5 GAIA Reload LAR | ||
LAR Content -Technical Basis 1)Addition of DOM-NAF-2, App. F to the COLR list | |||
* Reliant on pending approval of DOM-NAF-2, App. F (RAI responses currently in NRC review) | * Reliant on pending approval of DOM-NAF-2, App. F (RAI responses currently in NRC review) | ||
* Discussion of the development of the ORFEO-GAIA SDL (1.26) and ORFEO-NMGRID SDL (1.31) for MPS3 with GAIA fuel in accordance with NRC-approved VEP-NE-2 topical | * Discussion of the development of the ORFEO-GAIA SDL (1.26) and ORFEO-NMGRID SDL (1.31) for MPS3 with GAIA fuel in accordance with NRC-approved VEP-NE-2 topical 2)Addition of ORFEO-GAIA DDL (1.13) to TS 2.1.1.1 Safety Limit | ||
* Reliant on pending approval of DOM-NAF-2, App. F (RAI responses currently in NRC review) 3)Revision of P-8 setpoint to 35% | |||
* Reliant on pending approval of DOM-NAF-2, App. F (RAI responses currently in NRC review) | * Results in an earlier trip than current setpoint | ||
* Results in an earlier trip than current setpoint 6 | 6 GAIA Reload LAR | ||
LAR Content -Technical Basis (continued) 4)Approval of AREA DBLFPBs (analysis available for audit) | |||
* Compliance with RG 1.236 acceptance criteria (criteria met) | * Compliance with RG 1.236 acceptance criteria (criteria met) | ||
* Compliance with ANP-10338-P- | * Compliance with ANP-10338-P-ALimitations and Conditions | ||
* Qualitative assessment for maintaining WEC Overpressure Analysis (WCAP-7588) as the AOR | * Qualitative assessment for maintaining WEC Overpressure Analysis (WCAP-7588) as the AOR 5)Additional analyses/results | ||
* Statement that limited setpoint changes (e.g., k terms for OTT/OPT) are required for implementation of GAIA and will be implemented in accordance with 10 CFR 50.59 | * Statement that limited setpoint changes (e.g., k terms for OTT/OPT) are required for implementation of GAIA and will be implemented in accordance with 10 CFR 50.59 | ||
* Mixed core DNB penalty developed for transition core effects | * Mixed core DNB penalty developed for transition core effects | ||
GAIA Reload LAR LAR Content - Expected Attachments | 7 GAIA Reload LAR | ||
LAR Content -Expected Attachments 1)Discussion of changes and technical basis, excluding SDL development 2)SDL development 3)Proposed TS pages (Mark-ups) 4)FRM affidavit supporting a request for withholding proprietary information | |||
* Inclusion dependent on in-process proprietary review | |||
* Inclusion dependent on in-process proprietary review 8 | 8 Discussion | ||
2022 2023 2024 2025 Q4 Q1 Q2 Q3 Q4 Q1 Q2 Q3 Q4 Q1 Q2 Q3 Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug M3C22 Operation | |||
SFP Criticality Supplement NRC Review [12M Review Requested] | |||
ORFEO DDL NRC Review [12M Review Requested] | ORFEO DDL NRC Review [12M Review Requested] | ||
T-M Design LAR NRC Review [12M Review Requested] | T-M Design LAR NRC Review [12M Review Requested] | ||
SB/LB LOCA LAR NRC Review [12M Review Requested] | SB/LB LOCA LAR NRC Review [12M Review Requested] | ||
References | M3C23 Operation | ||
Reload LAR NRC Review [12M Review Requested] | |||
GAIA Fuel Batch Fabrication | |||
M3C24 Operation | |||
9 References | |||
* DE Topical Report, DOM-NAF-2-P-A, Revision 0.4, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code, September 2022 | * DE Topical Report, DOM-NAF-2-P-A, Revision 0.4, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code, September 2022 | ||
[ML21320A007] | [ML21320A007] | ||
* Appendix F, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code, Pending NRC review [ML22353A620] | * Appendix F, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code, Pending NRC review [ML22353A620] | ||
* DE Topical Report, VEP-NE-2-A, Revision 0, Statistical DNBR Evaluation Methodology, June 1987 [ML101330527] | * DE Topical Report, VEP-NE-2-A, Revision 0, Statistical DNBR Evaluation Methodology, June 1987 [ML101330527] | ||
* FRM Topical Report, ANP-10338P-A, Revision 0, AREA' - ARCADIA Rod Ejection Accident, December 2017 [ML18059A782] | * FRM Topical Report, ANP-10338P-A, Revision 0, AREA ' -ARCADIA Rod Ejection Accident, December 2017 [ML18059A782] | ||
* WEC Topical Report, WCAP-7588, Revision 1-A, An Evaluation of the Rod Ejection Accident in Westinghouse Pressurized Water Reactors Using Spatial Kinetics Methods, January 1975 10 | * WEC Topical Report, WCAP-7588, Revision 1-A, An Evaluation of the Rod Ejection Accident in Westinghouse Pressurized Water Reactors Using Spatial Kinetics Methods, January 1975 | ||
10 Acronyms | |||
AORAnalysis of Record CFRCode of Federal Regulations COLRCore Operating Limits Report DBLFPB Design Basis Limits for Fission Product Barriers DDLDeterministic Design Limit for Fission Product Barrier Fuel Barrier DE Dominion Energy DENCDominion Energy Nuclear Connecticut DNBDeparture from Nucleate Boiling FRMFramatome LARLicense Amendment Request LB Large Break LOCALoss of Coolant Accident | |||
11 Acronyms | |||
MPS3Millstone Power Station Unit 3 NRCNuclear Regulatory Commission RG Regulatory Guide SB Small Break SDLStatistical Design Limit SE Safety Evaluation SFPSpent Fuel Pool T-MThermal-Mechanical TS Technical Specifications WECWestinghouse Electric Company | |||
12}} | |||
Revision as of 12:12, 13 November 2024
| ML23254A056 | |
| Person / Time | |
|---|---|
| Site: | Millstone |
| Issue date: | 09/13/2023 |
| From: | Dominion Energy Nuclear Connecticut |
| To: | NRC/NRR/DORL/LPL1 |
| References | |
| EPID L-2023-LRM-0068 | |
| Download: ML23254A056 (1) | |
Text
Pre-Submittal Meeting for Reload License Amendment Request to Implement Framatome 17x17 GAIA Fuel at Millstone Power Station Unit 3
September 13, 2023
1 Agenda
- Introductions
- GAIA LAR Review Status and Schedule
- Reload LAR
- Approval Requests
- Technical Basis
- Expected Attachments
2 GAIA Project Team
- Chris Clemens Supervisor, Fuel Procurement Engineering
- Dan Smith Fuel Procurement Project Manager
- Scott Luchau Supervisor, Nuclear Safety Analysis
- Brian Mount Nuclear Safety Analysis
- Ruxandra Bobolea Nuclear Safety Analysis
- Emily Tomlinson Nuclear Safety Analysis
- William KohlroserNuclear Safety Analysis
- Brian Vitiello Supervisor, Nuclear Core Design
- Brian Kinney Nuclear Core Design
- Rich Ridder Supervisor, Fuel Performance Assessment
- Dave van SchooneveldFuel Performance Assessment
- Shayan Sinha Regulatory Affairs
3 GAIA LAR Review Status and Schedule
2022 2023 2024 2025 Q4 Q1 Q2 Q3 Q4 Q1 Q2 Q3 Q4 Q1 Q2 Q3 OctNovDec JanFebMar AprMayJun JulAugSep OctNovDec JanFebMar AprMayJun JulAugSep OctNovDec JanFebMar AprMay JunJulAug M3C22 Operation
SFP Criticality Supplement NRC Review [12M Review Requested]
ORFEO DDL NRC Review [12M Review Requested]
T-M Design LAR NRC Review [12M Review Requested]
SB/LB LOCA LAR NRC Review [12M Review Requested]
M3C23 Operation
Reload LAR NRC Review [12M Review Requested]
GAIA Fuel Batch Fabrication
M3C24 Operation DENC desired to spread out NRC review, provide focused topic area submittals, and minimize the potential for overlapping linked submittals (DOM-NAF-2 App. F and Reload LAR).
Based on current review schedule DOM-NAF-2 SE will not be issued prior to Reload LAR submittal.
4 GAIA Reload LAR
LAR Content -Approval Requests 1)TS Change to add DE Fleet Report DOM-NAF-2, App. F to the TS 6.9.1.6.b COLR list of methodologies 2)TS Change to add ORFEO-GAIA DDL (1.13) to TS 2.1.1.1 Reactor Core Safety Limit 3)TS Change to the P-8 setpoint in Table 2.2-1 Reactor Trip System Instrumentation Trip Setpoints
- Conservative reduction from current 50% to 35%
4)DBLFPBs associated with the implementation of the FRM AREA method (ANP-10338-P-A) and DE Fleet Report VEP-NE-2-A
5 GAIA Reload LAR
LAR Content -Technical Basis 1)Addition of DOM-NAF-2, App. F to the COLR list
- Reliant on pending approval of DOM-NAF-2, App. F (RAI responses currently in NRC review)
- Discussion of the development of the ORFEO-GAIA SDL (1.26) and ORFEO-NMGRID SDL (1.31) for MPS3 with GAIA fuel in accordance with NRC-approved VEP-NE-2 topical 2)Addition of ORFEO-GAIA DDL (1.13) to TS 2.1.1.1 Safety Limit
- Reliant on pending approval of DOM-NAF-2, App. F (RAI responses currently in NRC review) 3)Revision of P-8 setpoint to 35%
- Results in an earlier trip than current setpoint
6 GAIA Reload LAR
LAR Content -Technical Basis (continued) 4)Approval of AREA DBLFPBs (analysis available for audit)
- Compliance with RG 1.236 acceptance criteria (criteria met)
- Compliance with ANP-10338-P-ALimitations and Conditions
- Qualitative assessment for maintaining WEC Overpressure Analysis (WCAP-7588) as the AOR 5)Additional analyses/results
- Statement that limited setpoint changes (e.g., k terms for OTT/OPT) are required for implementation of GAIA and will be implemented in accordance with 10 CFR 50.59
- Mixed core DNB penalty developed for transition core effects
7 GAIA Reload LAR
LAR Content -Expected Attachments 1)Discussion of changes and technical basis, excluding SDL development 2)SDL development 3)Proposed TS pages (Mark-ups) 4)FRM affidavit supporting a request for withholding proprietary information
- Inclusion dependent on in-process proprietary review
8 Discussion
2022 2023 2024 2025 Q4 Q1 Q2 Q3 Q4 Q1 Q2 Q3 Q4 Q1 Q2 Q3 Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Jan Feb Mar Apr May Jun Jul Aug M3C22 Operation
SFP Criticality Supplement NRC Review [12M Review Requested]
ORFEO DDL NRC Review [12M Review Requested]
T-M Design LAR NRC Review [12M Review Requested]
SB/LB LOCA LAR NRC Review [12M Review Requested]
M3C23 Operation
Reload LAR NRC Review [12M Review Requested]
GAIA Fuel Batch Fabrication
M3C24 Operation
9 References
- DE Topical Report, DOM-NAF-2-P-A, Revision 0.4, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code, September 2022
[ML21320A007]
- Appendix F, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code, Pending NRC review [ML22353A620]
- DE Topical Report, VEP-NE-2-A, Revision 0, Statistical DNBR Evaluation Methodology, June 1987 [ML101330527]
- FRM Topical Report, ANP-10338P-A, Revision 0, AREA ' -ARCADIA Rod Ejection Accident, December 2017 [ML18059A782]
- WEC Topical Report, WCAP-7588, Revision 1-A, An Evaluation of the Rod Ejection Accident in Westinghouse Pressurized Water Reactors Using Spatial Kinetics Methods, January 1975
10 Acronyms
AORAnalysis of Record CFRCode of Federal Regulations COLRCore Operating Limits Report DBLFPB Design Basis Limits for Fission Product Barriers DDLDeterministic Design Limit for Fission Product Barrier Fuel Barrier DE Dominion Energy DENCDominion Energy Nuclear Connecticut DNBDeparture from Nucleate Boiling FRMFramatome LARLicense Amendment Request LB Large Break LOCALoss of Coolant Accident
11 Acronyms
MPS3Millstone Power Station Unit 3 NRCNuclear Regulatory Commission RG Regulatory Guide SB Small Break SDLStatistical Design Limit SE Safety Evaluation SFPSpent Fuel Pool T-MThermal-Mechanical TS Technical Specifications WECWestinghouse Electric Company
12