ML23254A056
| 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
2 Agenda
Introductions
GAIA LAR Review Status and Schedule Reload LAR Approval Requests Technical Basis Expected Attachments
3 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 Kohlroser Nuclear Safety Analysis Brian Vitiello Supervisor, Nuclear Core Design Brian Kinney Nuclear Core Design Rich Ridder Supervisor, Fuel Performance Assessment Dave van Schooneveld Fuel Performance Assessment Shayan Sinha Regulatory Affairs
4 GAIA LAR Review Status and Schedule 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.
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 Q4 2022 Q2 Q3 2023 2024 2025 Q1 Q2 Q3 Q4 Q1 Mar Q2 Q3 Q4 Q1 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 Apr May Jun Jul Aug
5 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
6 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
7 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-A Limitations 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
8 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
Discussion 9
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 Q4 2022 Q2 Q3 2023 2024 2025 Q1 Q2 Q3 Q4 Q1 Mar Q2 Q3 Q4 Q1 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 Apr May Jun Jul Aug
10 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
11 Acronyms AOR Analysis of Record CFR Code of Federal Regulations COLR Core Operating Limits Report DBLFPB Design Basis Limits for Fission Product Barriers DDL Deterministic Design Limit for Fission Product Barrier Fuel Barrier DE Dominion Energy DENC Dominion Energy Nuclear Connecticut DNB Departure from Nucleate Boiling FRM Framatome LAR License Amendment Request LB Large Break LOCA Loss of Coolant Accident
12 Acronyms MPS3 Millstone Power Station Unit 3 NRC Nuclear Regulatory Commission RG Regulatory Guide SB Small Break SDL Statistical Design Limit SE Safety Evaluation SFP Spent Fuel Pool T-M Thermal-Mechanical TS Technical Specifications WEC Westinghouse Electric Company