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| {{#Wiki_filter:}} | | {{#Wiki_filter:Surry Power Station New Fuel Storage and Spent Fuel Pool Criticality Analysis Proposed License Amendment Request NRC Pre-Submittal Meeting May 13, 2021 |
| | |
| | Agenda |
| | * Current Surry SFP Configuration |
| | * Proposed Changes |
| | * Analysis Methods |
| | * Conservatism |
| | * Conclusion/Timeline |
| | * Criticality Analysis Checklist 2 |
| | |
| | Current Spent Fuel Pool Configuration |
| | * One rack design, 2 regions |
| | - Maximum fuel enrichment: 4.3 wt. % U-235 |
| | - Racks have a large cell pitch (14 inch pitch) |
| | - No neutron absorber material |
| | - Region 1 |
| | * 4-out-of-4 pattern with burnup credit |
| | * Susceptible to cask drop accident |
| | - Region 2 |
| | * 4-out-of-4 pattern with no burnup credit 3 |
| | |
| | Current Spent Fuel Pool Configuration Cask Loading Area 4 |
| | |
| | Current Spent Fuel Pool Configuration |
| | * SFP boron concentration 2300 ppm |
| | - Technical Specification limit |
| | - Boron credited only for accident conditions (No dilution accident analysis. keff 0.95 with unborated water) 5 |
| | |
| | Proposed SFP Changes and Goals |
| | * Increase maximum enrichment to 5.00wt% |
| | * Update analysis |
| | - Includes items identified in Reg Guide 1.240 (NEI 12-16) |
| | - Brings analysis and codes in-house |
| | * Add soluble boron credit for normal and accident conditions |
| | - keff 1.00 when flooded with unborated water |
| | - Introduces boron dilution analysis |
| | - Maintains SFP Tech Spec minimum soluble boron (2300 ppm) |
| | * Add gadolinium burnable absorber into the Licensing Basis |
| | - Added to code benchmarking analysis and explicitly modeled in depletion |
| | * Increase identified analysis margin |
| | - NRC and Dominion Energy margin partitioned 6 |
| | |
| | Proposed SFP Changes and Goals |
| | * Maintain the 2 region configuration |
| | - Region 1: 4 out of 4 with updated burnup curve |
| | - Region 2: 4 out of 4 without burnup curve Cask Loading Cask LoadingArea Area 7 |
| | |
| | Current New Fuel Storage Area Configuration |
| | * Maximum fuel enrichment: 4.3 wt. % U-235 |
| | * No empty cells required or burnable absorber credited 8 |
| | |
| | Proposed New Fuel Storage Area Changes and Goals |
| | * Two storage configuration options |
| | - All cells used when all fuel is enriched to 4.35wt% |
| | - Required empty cells when any fuel is enriched to |
| | >4.35wt% (3-out-of-4 storage geometry) |
| | * Update analysis |
| | - Includes items identified in Reg Guide 1.240 (NEI 12-16) |
| | - Same computer codes as SFP analysis |
| | * Increase identified analysis margin |
| | - NRC and Dominion Energy margin partitioned 9 |
| | |
| | Proposed New Fuel Storage Area Changes and Goals |
| | * 3 out of 4 Configuration (X locations are required to be empty) 10 10 |
| | |
| | Analysis Methods |
| | * SCALE 6.2.3 with ENDF/B-VII 238 group cross section data |
| | - KENO-V.a criticality calculation |
| | - TRITON / T5-depl (KENO-V.a) fuel depletion |
| | - ORIGAMI fuel decay |
| | - New code benchmarking analyses |
| | * NUREG/CR-6698 used for criticality code analysis |
| | * EPRI Benchmark and Utilization Reports used for depletion code analysis |
| | * Consistent with RG 1.240 (NEI 12-16) 11 |
| | |
| | Analysis Methods |
| | * Boron dilution analysis |
| | - Supports incorporation of soluble boron credit |
| | - Identifies water sources, flow rates and volumes |
| | - Calculates dilution times |
| | - Discusses means of detection and mitigation |
| | - Starting and ending soluble boron conservatively bounded by criticality analysis boron |
| | * Boron required for normal storage 350 ppm |
| | * Technical Specification boron 2300 ppm 12 |
| | |
| | Cask Drop Accident |
| | * Cask Drop Accident |
| | - No wall between the cask loading area and fuel racks |
| | - Assumes cask is dropped and tips over. |
| | - Mechanical analysis shows two rows of 6x6 rack modules will be damaged. |
| | - The current Analysis of Record: |
| | * CSA conservatively assumes 3 rows of rack modules are damaged |
| | * CSA assumes racks are deformed to optimum pitch |
| | - New CSA additionally assumes Cask Loading Area fuel pins are deformed to optimum pitch 13 |
| | |
| | Cask Drop Accident Dropped cask deforms racks and assemblies to optimum rack and pin pitch 14 |
| | |
| | Cask Drop Accident Dropped cask deforms racks and assemblies to optimum rack and pin pitch 15 |
| | |
| | Misload Accidents |
| | * Single and multiple misload accidents are NOT analyzed because they are bounded |
| | - Region 2 allows storage of fresh assemblies with the maximum allowed enrichment in every cell. |
| | * There cannot be a Region 2 misload since no credit is taken for burnup, fuel storage geometry, reduced enrichment, etc. |
| | - A Region 1 misload would be equivalent to Region 2. |
| | * The only difference between the two regions is that Region 1 (i) is susceptible to the cask drop accident and (ii) credits burnup |
| | * The cask drop accident and the misload accident are independent events |
| | * A misload of fresh fuel would be equivalent to Region 2 16 |
| | |
| | Conservatism |
| | * Conservative modeling (e.g. no axial blanket credit, no decay credit) |
| | * NRC administrative margin of 0.01 K reserved to account for minor methodology issues and uncertainties |
| | * Identify Dominion retained margin to allow for future fuel changes and/or methodology issues 17 |
| | |
| | Conclusion / Timeline |
| | * Surry SFP and new fuel rack criticality analysis License Amendment Request |
| | - Increase maximum allowable enrichment |
| | - Include gadolinium into our Licensing Basis |
| | - Add soluble boron credit |
| | - Update methods with RG 1.240 |
| | - Bring computer codes and method in house |
| | - Increase identified margin |
| | * Major milestones: |
| | - Submit LAR to NRC Q3 2021 |
| | - Receive SER Q4 2022 |
| | - Implement new TS Q1 2023 18 |
| | |
| | Criticality Analysis Checklist |
| | * See attached completed checklist |
| | * Includes placeholders for analysis Scope, Methods, and Details |
| | * Some items not included or not applicable |
| | - Justification or explanation provided 19}} |
Letter Sequence Meeting |
---|
|
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance
- Supplement
|
MONTHYEARLR-N20-0010, License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures from the Design and Licensing Basis Based on Leak-Before-Break Methodology2020-04-24024 April 2020 License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures from the Design and Licensing Basis Based on Leak-Before-Break Methodology Project stage: Request ML20296A6232020-10-22022 October 2020 Request for NRC Approval to Apply Leak-Before-Break Methodology to Reactor Coolant System Branch Piping Project stage: Request ML20302A2012020-10-22022 October 2020 NRR E-mail Capture - Surry Power Station, Units 1 and 2 - Acceptance Review (L-2020-LLA-0219) Project stage: Acceptance Review ML20338A5422020-12-0303 December 2020 Proposed License Amendment Request, Update of the Loss of Coolant Accident Alternate Source Term Dose Analysis Project stage: Request ML20346A1032020-12-11011 December 2020 NRR E-mail Capture - Surry Power Station, Units 1 and 2 LBB LAR - Acceptance Review (L-2020-LLA-0255) Project stage: Acceptance Review ML20364A0172020-12-28028 December 2020 NRR E-mail Capture - Surry Power Station, Units 1 and 2 AST LAR - Acceptance Review (L-2020-LLA-0258) Project stage: Acceptance Review ML21084A2732021-03-24024 March 2021 License Amendment Request - Application of Leak-Before-Break Methodology to Reactor Coolant System Branch Piping - Response to Request for Additional Information and Clarification Project stage: Response to RAI ML21127A1362021-05-13013 May 2021 May 13, 2021 NRC Pre-Submittal Meeting - Surry Power Station New Fuel Storage and Spent Fuel Pool Criticality Analysis Proposed License Amendment Request Project stage: Meeting ML21133A4212021-05-13013 May 2021 Response to NRC Request for Additional Information Regarding Proposed License Amendment Request Update of LOCA Alternative Source Term Dose Analysis Project stage: Response to RAI ML21270A0232021-07-0707 July 2021 State of Virginia Notification of Pending Amendment Issuance Ref: Surry Power Station, Units 1 and 2 - Request to Revise Technical Specifications 2.1.A.1.b Project stage: Other ML21175A1852021-08-20020 August 2021 Issuance of Amendment Nos. 304 and 304 Leak-Before-Break for Pressurizer Surge, Residual Heat Removal, Safety Injection Accumulator, Reactor Coolant System Bypass and Safety Injection Lines Project stage: Approval ML21272A0622021-09-28028 September 2021 NRR E-mail Capture - (External_Sender) Surry Fuel Melt Safety Limit (SL) LAR Question Project stage: Other ML21277A0652021-09-30030 September 2021 Proposed License Amendment Request Removal of Refueling Water Chemical Addition Tank and Replacement of Containment Sump Buffer Project stage: Request ML21286A7372021-10-13013 October 2021 Additional Element Included in the Implementation Plan for the Surry Fuel Melt Safety Limit (SL) LAR Project stage: Request ML21292A3022021-10-19019 October 2021 Response to Question on License Amendment Request to Revise Reactor Core Safety Limit Project stage: Request ML21294A3382021-10-21021 October 2021 Proposed Amendment to Relocate Unit Staff Qualification Requirements from Technical Specifications to Nuclear Facility Quality . Project stage: Request ML21188A1742021-10-26026 October 2021 Issuance of Amendment Nos. 305 and 305 Revised Reactor Core Safety Limit to Reflect Topical Report WCAP-177642-P-A, Revision 1 Project stage: Approval ML21307A4302021-11-0909 November 2021 Supplemental Information Needed for Acceptance of Requested Licensing Action Surry Post LOCA Buffer Change Project stage: Acceptance Review ML21253A0632021-11-19019 November 2021 Issuance of Amendment Nos. 306 and 306 to Update of the Loss of Coolant Accident Alternate Source Term Dose Analysis Project stage: Approval ML21326A1502021-11-22022 November 2021 NRR E-mail Capture - Acceptance Review for Relocation of Unit Staff Requirements to the QAPD LAR (L-2021-LLA-0195) Project stage: Acceptance Review ML21334A1692021-11-29029 November 2021 Proposed License Amendment Request Removal of Refueling Water Chemical Additional Tank and Replacement of Containment Buffer Supplemental Information Project stage: Supplement ML21340A1642021-12-0606 December 2021 Acceptance of Requested Licensing Action Amendment Project stage: Acceptance Review ML22004A2872022-01-14014 January 2022 Technical Specification Section 3.4.A.4 Change of Post Loss-of-Coolant Accident Chemical Buffer Audit Plan Project stage: Other ML22077A0542022-03-18018 March 2022 Change in Engineering Hours Estimate Surry Ph Buffer LAR Acceptance Project stage: Approval ML22089A0092022-04-13013 April 2022 Regulatory Audit Summary Related to the License Amendment Request to Change Loss-Of-Coolant Accident Chemical Buffer Project stage: Other ML22153A1352022-06-0202 June 2022 Proposed License Amendment Request (LAR) - Removal of Refueling Water Chemical Addition Tank and Replacement of Containment Sump Buffer - Response to Request for Additional Information Project stage: Response to RAI ML22164A9252022-06-13013 June 2022 Page Substitutions to ADAMS Accession Number ML21294A338 Project stage: Request ML22164A8532022-06-13013 June 2022 Proposed License Amendment Request Removal of Refueling Water Chemical Addition Tank and Replacement of Containment Sump Buffer - Response to Request for Confirmation Project stage: Request ML22095A1072022-07-11011 July 2022 Issuance of Amendment Nos. 120, 344, & 284, 293 & 276, & 307 & 307 to Relocate Requirements to the QAPD Project stage: Approval ML22193A2952022-08-26026 August 2022 Issuance of Amendment Nos. 308 and 308 License Amendment Request for Removal of the Refueling Water Chemical Addition Tank and Containment Sump, Ph Buffer Change and Safety Evaluation Project stage: Approval ML22250A6672022-10-12012 October 2022 Correction to Issuance of Amendment Nos. 304 (EPID L-2020-LLA-0255), 305 (EPID L-2020-LLA-0219) 306 (EPID L-2020-LLA-0258), 307 (EPID L-2021-LLA-0195) and 308 Project stage: Approval 2021-12-06
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[Table view] |
Text
Surry Power Station New Fuel Storage and Spent Fuel Pool Criticality Analysis Proposed License Amendment Request NRC Pre-Submittal Meeting May 13, 2021
Agenda
- Current Surry SFP Configuration
- Criticality Analysis Checklist 2
Current Spent Fuel Pool Configuration
- One rack design, 2 regions
- Maximum fuel enrichment: 4.3 wt. % U-235
- Racks have a large cell pitch (14 inch pitch)
- No neutron absorber material
- Region 1
- 4-out-of-4 pattern with burnup credit
- Susceptible to cask drop accident
- Region 2
- 4-out-of-4 pattern with no burnup credit 3
Current Spent Fuel Pool Configuration Cask Loading Area 4
Current Spent Fuel Pool Configuration
- Technical Specification limit
- Boron credited only for accident conditions (No dilution accident analysis. keff 0.95 with unborated water) 5
Proposed SFP Changes and Goals
- Increase maximum enrichment to 5.00wt%
- Includes items identified in Reg Guide 1.240 (NEI 12-16)
- Brings analysis and codes in-house
- Add soluble boron credit for normal and accident conditions
- keff 1.00 when flooded with unborated water
- Introduces boron dilution analysis
- Maintains SFP Tech Spec minimum soluble boron (2300 ppm)
- Add gadolinium burnable absorber into the Licensing Basis
- Added to code benchmarking analysis and explicitly modeled in depletion
- Increase identified analysis margin
- NRC and Dominion Energy margin partitioned 6
Proposed SFP Changes and Goals
- Maintain the 2 region configuration
- Region 1: 4 out of 4 with updated burnup curve
- Region 2: 4 out of 4 without burnup curve Cask Loading Cask LoadingArea Area 7
Current New Fuel Storage Area Configuration
- Maximum fuel enrichment: 4.3 wt. % U-235
- No empty cells required or burnable absorber credited 8
Proposed New Fuel Storage Area Changes and Goals
- Two storage configuration options
- All cells used when all fuel is enriched to 4.35wt%
- Required empty cells when any fuel is enriched to
>4.35wt% (3-out-of-4 storage geometry)
- Includes items identified in Reg Guide 1.240 (NEI 12-16)
- Same computer codes as SFP analysis
- Increase identified analysis margin
- NRC and Dominion Energy margin partitioned 9
Proposed New Fuel Storage Area Changes and Goals
- 3 out of 4 Configuration (X locations are required to be empty) 10 10
Analysis Methods
- SCALE 6.2.3 with ENDF/B-VII 238 group cross section data
- KENO-V.a criticality calculation
- TRITON / T5-depl (KENO-V.a) fuel depletion
- ORIGAMI fuel decay
- New code benchmarking analyses
- EPRI Benchmark and Utilization Reports used for depletion code analysis
Analysis Methods
- Supports incorporation of soluble boron credit
- Identifies water sources, flow rates and volumes
- Calculates dilution times
- Discusses means of detection and mitigation
- Starting and ending soluble boron conservatively bounded by criticality analysis boron
- Boron required for normal storage 350 ppm
- Technical Specification boron 2300 ppm 12
Cask Drop Accident
- No wall between the cask loading area and fuel racks
- Assumes cask is dropped and tips over.
- Mechanical analysis shows two rows of 6x6 rack modules will be damaged.
- The current Analysis of Record:
- CSA conservatively assumes 3 rows of rack modules are damaged
- CSA assumes racks are deformed to optimum pitch
- New CSA additionally assumes Cask Loading Area fuel pins are deformed to optimum pitch 13
Cask Drop Accident Dropped cask deforms racks and assemblies to optimum rack and pin pitch 14
Cask Drop Accident Dropped cask deforms racks and assemblies to optimum rack and pin pitch 15
Misload Accidents
- Single and multiple misload accidents are NOT analyzed because they are bounded
- Region 2 allows storage of fresh assemblies with the maximum allowed enrichment in every cell.
- There cannot be a Region 2 misload since no credit is taken for burnup, fuel storage geometry, reduced enrichment, etc.
- A Region 1 misload would be equivalent to Region 2.
- The only difference between the two regions is that Region 1 (i) is susceptible to the cask drop accident and (ii) credits burnup
- The cask drop accident and the misload accident are independent events
- A misload of fresh fuel would be equivalent to Region 2 16
Conservatism
- Conservative modeling (e.g. no axial blanket credit, no decay credit)
- NRC administrative margin of 0.01 K reserved to account for minor methodology issues and uncertainties
- Identify Dominion retained margin to allow for future fuel changes and/or methodology issues 17
Conclusion / Timeline
- Surry SFP and new fuel rack criticality analysis License Amendment Request
- Increase maximum allowable enrichment
- Include gadolinium into our Licensing Basis
- Add soluble boron credit
- Update methods with RG 1.240
- Bring computer codes and method in house
- Increase identified margin
- Submit LAR to NRC Q3 2021
- Receive SER Q4 2022
- Implement new TS Q1 2023 18
Criticality Analysis Checklist
- See attached completed checklist
- Includes placeholders for analysis Scope, Methods, and Details
- Some items not included or not applicable
- Justification or explanation provided 19