ML25105A210
| ML25105A210 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 04/24/2025 |
| From: | Southern Nuclear Company |
| To: | John Lamb NRC/NRR/DORL/LPL2-1 |
| References | |
| EPID L-2025-LRM-0040 | |
| Download: ML25105A210 (1) | |
Text
Vogtle Electric Generating Plant Units 3 and 4 License Amendment Request Revise Technical Specifications for Spent Fuel Storage Racks Maximum U-235 Enrichment Pre-submittal Meeting: April 24, 2025
Agenda
- Background
- Change
- Justification
- Schedule
BACKGROUND LAR to Revise TS 4.3.1.1 and Figure 3.7.12-1 TS 4.3.1.1 4.0 DESIGN FEATURES 4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:
- Subsection 9.1.2, Spent Fuel Storage
- Subsection 9.1.2.3, Safety Evaluation methodology used in the spent fuel pool criticality analysis is provided in APP-GW-GLR-029 (ML110670298) 3
BACKGROUND LAR to Revise TS 4.3.1.1 and Figure 3.7.12-1 TS 3.7.12, Spent Fuel Pool Storage Figure 3.7.12-1, Minimum Fuel Assembly Burnup Versus Initial Enrichment for Region 2 Spent Fuel Cells 4
BACKGROUND FYI - New Fuel Storage Criticality Requirements TS 4.3.1.2 SNC LAR Supplement 4.0 DESIGN FEATURES 4.3 Fuel Storage 4.3.1 Criticality 4.3.1.2 The new fuel storage racks are designed and shall be maintained with:
- a. Fuel assemblies having a maximum U-235 enrichment of 5.0 weight percent; UFSAR Subsection 9.1.1, New Fuel Storage Subsection 9.1.1.3, Safety Evaluation methodology used in the new fuel pool criticality analysis is provided in APP-GW-GLR-030 (ML061520157) 5
CHANGE LAR to Revise TS 4.3.3.1 4.0 DESIGN FEATURES 4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:
- a. Fuel assemblies having a maximum U-235 enrichment of 4.95 weight percent; CHANGE TO READ
- a. Fuel assemblies having a maximum nominal U-235 enrichment of 4.95 weight percent; 6
CHANGE Revised Figure 3.7.12-1 TS 3.7.12, Spent Fuel Pool Storage Figure 3.7.12-1, Minimum Fuel Assembly Burnup Versus Initial Nominal Enrichment for Region 2 Spent Fuel Cells 7
CHANGE FYI - Associatd Bases Revisions Bases for TS 3.7.12, Spent Fuel Pool Storage BACKGROUND The high density spent fuel storage racks are divided into two separate and distinct regions and include locations for storage of defective fuel as shown in Figure 4.3-1.
Region 1, with a maximum of 243 storage locations and the Defective Fuel Cells, with 5 storage locations are designed and analyzed (Ref. 2) to accommodate new fuel assemblies that are within the with a maximum nominal enrichment identified in TS 4.3.1.1.of 4.95 weight percent U-235, or spent fuel assemblies regardless of the combination of initial enrichment and burnup. Region 2, with a maximum of 641 storage locations is designed and analyzed (Ref. 2) to accommodate spent fuel assemblies in all locations which comply with the combination of initial nominal enrichment and burnup specified in LCO Figure 3.7.12-1, Minimum Fuel Assembly Burnup Versus Initial Nominal Enrichment for Region 2 Spent Fuel Cells. To allow for burnup uncertainty, which the Region 2 loading curve of LCO Figure 3.7.12-1 does not include, the fuel assembly burnup from the reactor records shall be conservatively reduced.
8
CHANGE Change is consistent with:
Westinghouse STS NUREG-1431 Vogtle Units 1 and 2
~ 25 other Westinghouse Units Vogtle Units 3 and 4 spent fuel rack criticality analysis is limiting
[
]a,c
[
]a,c (spent fuel rack analysis complies with 10 CFR 50.68 requirements)
Vogtle Units 3 and 4 new fuel rack criticality TS
[
]a,c
[
]a,c (new fuel rack analysis complies with 10 CFR 50.68 requirements) 9
JUSTIFICATION Supporting Analysis - APP-GW-GLR-029 Spent Fuel Storage Racks Criticality Analysis
[
]a,c
[
]a,c REGULATION - 10 CFR 50.68, Criticality accident requirements (b)(7) The maximum nominal U-235 enrichment of the fresh fuel assemblies is limited to five (5.0) percent by weight.
Request is consistent with the safety analysis, the Westinghouse ITS NUREG, and the majority of Westinghouse plants, and the request complies with the regulatory limits.
10
SCHEDULE SUBMITTAL planned by May 1, 2025 Need ~ September 19, 2025, for ordering fuel for Unit 3 cycle 3 REQUEST approval by September 18, 2025 11