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| {{#Wiki_filter:Pre-Submittal Meeting for Palo Verde Unit 1, 2, and 3 Updated Spent Fuel Pool Criticality AnalysisMay 11, 2015 Purpose*Present and discuss planned licensing changeschanges-Update spent fuel pool (SFP) criticality analysis-Add neutron absorbing inserts to SFP racks2 Objectives*Updated criticality analysis will-Provide basis for replacing non-conservative Technical Specification (TS) caused by missed poweruprateimpactpower uprate impact-Include Next Generation Fuel (NGF) *Account for reactivity effects of integral fuel burnable absorber (IFBA)Maintainfullcoreoffloadcapability-Maintain full core offload capability3 Borated Aluminum Inserts*Additional reactivity hold down is planned tomeet10CFR5068andmaintainfullto meet 10 CFR 50.68 and maintain full core offload capabilityThlhdliiittld-Thermal hydraulic, seismic, structural, and pool cooling calculations will be updated as needed-Add a coupon surveillance program to monitor material performance4 TS Changes*TS 3.7.17 -Spent Fuel Assembly Storage -Incorporate new burnup and enrichment curves-Display information with the polynomial explicitly stated-Include diagrams of approved arrays5 TS Changes*TS 3.7.15 -Fuel Storage Pool Boron-Currently 2150 ppm-May increase in response to accident conditions analysis6 TS Changes*TS 4.3 -Fuel Storage-Incorporate new arrays-Update boron concentration-Reduce radially averaged enrichment from 4.8 wt% to 4.65 wt%7 New TS*5.5.21 -Spent Fuel Storage Rack Neutron AbsorberMonitoringprogramAbsorber Monitoring program -Will consider upcoming NRC Generic Letter "MonitoringofNeutronAbsorbingMaterialsinMonitoring of Neutron-Absorbing Materials in Spent Fuel Pools"RecentDresdenOE-Recent Dresden OE-License extension-Plant decommissioning8 Implementation *Prior to NGF implementation in each unit*Considering installing inserts under 10CFR505910 CFR 50.59Cidiliditif*Considering a license condition for a specified period of time to transition betweenTSbetween TS9 Methodology*Based onISG201001"StaffGuidanceRegardingthe-ISG-2010-01, "Staff Guidance Regarding the Nuclear Criticality Safety Analysis for Spent Fuel Pools"-NEI 12-16, "Guidance for Performing Criticality Analyses of Fuel Storage at Light-Water ReactorPowerPlants"Revision1Reactor Power Plants, Revision 1-EPRI Depletion Benchmark Reports-Multiple NUREGsp10 Recent Licensing Actions*Methodology similar to:-ComanchePeak-Comanche Peak-Prairie Island-Turkey Point*Insert material similar to:-LaSallePhBtt-Peach Bottom-Quad Cities*Criticalitycodeusagesimilarto:Criticality code usage similar to:-Millstone 211 ISG Item 1 -Fuel Assembly Selection*Palo Verde will demonstrate that variations indesignareadequatelyaccountedforinin design are adequately accounted for in a single, limiting, fuel assembly designCEStddFl-CE Standard Fuel-CE Value Added Pellet-Westinghouse NGF (8 LUAs)-AREVAAdvancedCE-16HTP(8LTAs)AREVA Advanced CE16 HTP (8 LTAs)12 ISG Item 2 -Depletion Analysis *Depletion parameters will impact the isotopicinventoryofburnedfuelisotopic inventory of burned fuel*Major depletion inputs-Fuel type-Axial burnup -Moderator temperature-Reactor powerSolubleboron-Soluble boron-Burnable absorbers13 ISG Item 2.a -Depletion Uncertainty*The EPRI methodology will be used to demonstratethe5%depletionuncertaintydemonstrate the 5% depletion uncertainty is conservative for Palo Verde*Fission product uncertainty explicitly considered14 ISG Item 2.b -Reactor Parameters*Limiting axial moderator temperature profiles derivedpastpresentandanticipatedprofilesderived past, present, and anticipated profiles-Same methodology employed at Comanche Peakgypy*Analysis performed at 4070 MWth*Licensee controls include verification of radial diibidTldpower distribution and T-cold15 ISG Item 2.c -Burnable Absorbers*Palo Verde has used the following integral burnable absorbers-B4C rods in CE STD Fuel-Erbia in CE STD Fuel and Value Added Pellet-IntegralFuelBurnableAbsorber(IFBA)inNGFIntegral Fuel Burnable Absorber (IFBA) in NGF -Gadolinia in AREVA Fuel *AnalysiswillnotcreditErbiaBCorGadolinia*Analysis will not credit Erbia, B4C, or Gadolinia*NGF fuel modeled with IFBA in all 236 pins for depletion analysis onlypyy-Pool model assumes no burnable absorbers16 ISG Item 2.d -Rodded Operation*Palo Verde does not operate with control rodsinsertedrods inserted-Guide tube wear program*End of cycle check will ensure that fuel assembliesexperiencedaninsignificantassemblies experienced an insignificant amount of rodded operation at hot full powerp17 ISG Item 3 -Criticality Analysis*SCALE 6.1.2 will be used in the analysis-KENO V.a solves the eigenvalue (keff) problem in 3D using the Monte Carlo method-238 Group ENDF/B-VII will be used as the library-Millstone LAR used SCALE 6.0 with the KENO V.a module and 238 Group ENDF/B-VII library18 ISG Item 3.a -Axial Burnup Profile*Bounding axial burnup profiles selected frompastpresentandanticipatedfrom past, present, and anticipated profilesClifilitlildhk-Cycle specific licensee controls include checks on cutback regions (blanket), fuel design, and moderator temperature-Same methodology used at Comanche Peak and Prairie Island19 ISG Item 3.b -Rack Model*Dimensions and tolerance of racks are traceabletodesigndocumentstraceable to design documentsBoratedaluminuminsertB10areal*Borated aluminum insert B-10 areal density conservatively modeled at quantitylessthanminimumcertifiedarealquantity less than minimum certified areal density20 ISG Item 3.c -Interfaces*All interfaces are evaluated and all interfacesareanacceptable2x2arrayinterfaces are an acceptable 2x2 array-Palo Verde has only one rack design-No gaps modeled between rack modules21 ISG Item 3.d -Normal Conditions*Analysis demonstrates that keff 0.95 at lessthantheTSrequiredboronless than the TS required boron concentration for:Fuelmovement-Fuel movement-Fuel inspection and reconstitutionForeignObjectSearchandRetrieval-Foreign Object Search and Retrieval-Limiting normal condition to initiate accident identifiedidentified22 ISG Item 3.e -Accident Conditions*Analysis demonstrates that keff 0.95 at lessthantheTSrequiredboronless than the TS required boron concentration forMisloadedordroppedsinglefreshfuel-Misloaded or dropped single fresh fuel assembly into, outside of, or on top of spent fuel racks-Multiple misloaded fuel assemblies-Loss of SFP cooling-Seismic events23 ISG Item 3.e (contd.)*Limiting dilution event reduces pool boron from2150ppmto1900ppmfrom 2150 ppm to 1900 ppm TRMrequiresboronconcentrationtobe*TRM requires boron concentration to be maintained at 4000 ppm24 ISG Item 4 -Code Validation*Will perform criticality code validation in accordancewithNUREG/CR-6698accordance with NUREG/CR-6698-Data carefully considered to identify trends consistentwithNUREG1475consistent with NUREG-1475-HTC experiments will be included*Fission products will be explicitly accounted for-No lumped fission products will be used25 Palo Verde Arrays*6 arrays will be analyzed*Palo Verde expects to submit between 3 and6ofthefollowingarraysforapprovaland 6 of the following arrays for approvalFildiifltid*Final designs specify location and orientation of borated aluminum inserts26 Palo Verde Arrays*Infinite array of 2 fresh fuel assemblies (Fr)withtwoblockedlocationsandno(Fr) with two blocked locations and no inserts27 Palo Verde Arrays*Infinite array of 2 fresh fuel assemblies (Fr)withtwotrashcans(TC)andtwo(Fr) with two trash cans (TC) and two inserts28 Palo Verde Arrays*Infinite array of 3 low reactivity fuel assemblies(Lo)and1high(Hi)reactivityassemblies (Lo) and 1 high (Hi) reactivity fuel assembly with 2 inserts29 Palo Verde Arrays*Infinite array of 2 high reactivity fuel assemblies(Hi)andonelowreactivityfuelassemblies (Hi) and one low reactivity fuel assembly (Lo) with one blocked cell and oneinsertone insert30 Palo Verde Arrays*Infinite array of 4 low reactivity fuel assemblies(Lo)withoneinsertassemblies (Lo) with one insert31 Palo Verde Arrays*Infinite array of 4 depleted fuel assemblies (De)withnoinserts(De) with no inserts32 Margin Maintenance*Palo Verde will monitor the margin identifiedintheanalysisidentified in the analysis*CyclespecificchecksofkeyinputCycle specific checks of key input parameters*0.005 k additional margin reserved by Palo VerdeBurnupandenrichmentcurveswillbefor-Burnup and enrichment curves will be for keff= 0.9933 Conclusion*Palo Verde is proposing an acceptable methodology for performing SFP criticality gypgyanalysisllldbdl*Permanently installed borated aluminum inserts will be credited in the analysis*Submit LAR by Nov 2015*Request NRC approval in 18 -24 months34}} | | {{#Wiki_filter:Pre-Submittal Meeting for Palo Verde Unit 1, 2, and 3 Updated Spent Fuel Pool Criticality AnalysisMay 11, 2015 Purpose*Present and discuss planned licensing changeschanges-Update spent fuel pool (SFP) criticality analysis |
| | -Add neutron absorbing inserts to SFP racks 2 |
| | Objectives |
| | *Updated criticality analysis will |
| | -Provide basis for replacing non-conservative Technical Specification (TS) caused by missed poweruprateimpact power uprate impact-Include Next Generation Fuel (NGF) |
| | *Account for reactivity effects of integral fuel burnable absorber (IFBA)Maintainfullcoreoffloadcapability |
| | -Maintain full core offload capability 3 |
| | Borated Aluminum Inserts |
| | *Additional reactivity hold down is planned tomeet10CFR5068andmaintainfull to meet 10 CFR 50.68 and maintain full core offload capabilityThlhdliiittld |
| | -Thermal hydraulic, seismic, structural, and pool cooling calculations will be updated as |
| | |
| | needed-Add a coupon surveillance program to monitor material performance 4 |
| | TS Changes |
| | *TS 3.7.17 -Spent Fuel Assembly Storage |
| | -Incorporate new burnup and enrichment curves-Display information with the polynomial explicitly stated |
| | -Include diagrams of approved arrays 5 |
| | TS Changes |
| | *TS 3.7.15 -Fuel Storage Pool Boron |
| | -Currently 2150 ppm |
| | -May increase in response to accident conditions analysis 6 |
| | TS Changes |
| | *TS 4.3 -Fuel Storage |
| | -Incorporate new arrays |
| | -Update boron concentration |
| | -Reduce radially averaged enrichment from 4.8 wt% to 4.65 wt% |
| | 7 New TS*5.5.21 -Spent Fuel Storage Rack Neutron AbsorberMonitoringprogram Absorber Monitoring program -Will consider upcoming NRC Generic Letter "MonitoringofNeutronAbsorbingMaterialsin Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools" RecentDresdenOE |
| | -Recent Dresden OE-License extension |
| | -Plant decommissioning 8 |
| | Implementation |
| | *Prior to NGF implementation in each unit |
| | *Considering installing inserts under 10CFR5059 10 CFR 50.59Cidiliditif |
| | *Considering a license con dition for a specified period of time to transition betweenTS between TS9 Methodology |
| | *Based onISG201001"StaffGuidanceRegardingthe |
| | -ISG-2010-01, "Staff Guidance Regarding the Nuclear Criticality Safety Analysis for Spent Fuel Pools" |
| | -NEI 12-16, "Guidance for Performing Criticality Analyses of Fuel Storage at Light-Water ReactorPowerPlants "Revision1Reactor Power Plants, Revision 1-EPRI Depletion Benchmark Reports |
| | -Multiple NUREGs p10 Recent Licensing Actions |
| | *Methodology similar to: |
| | -ComanchePeak |
| | -Comanche Peak-Prairie Island |
| | -Turkey Point |
| | *Insert material similar to: |
| | -LaSallePhBtt-Peach Bottom-Quad Cities |
| | *Criticalitycode usagesimilarto: |
| | Criticality code usage similar to:-Millstone 2 11 ISG Item 1 -Fuel Assembly Selection |
| | *Palo Verde will demonstrate that variations indesignareadequatelyaccountedforin in design are adequately accounted for in a single, limiting, fuel assembly designCEStddFl-CE Standard Fuel-CE Value Added Pellet |
| | -Westinghouse NGF (8 LUAs) |
| | -AREVAAdvancedCE |
| | -16HTP(8LTAs)AREVA Advanced CE16 HTP (8 LTAs)12 ISG Item 2 -Depletion Analysis |
| | *Depletion parameters will impact the isotopicinventoryofburnedfuel isotopic inventory of burned fuel*Major depletion inputs |
| | -Fuel type |
| | -Axial burnup |
| | -Moderator temperature |
| | -Reactor powerSolubleboron |
| | -Soluble boron-Burnable absorbers 13 ISG Item 2.a -Depletion Uncertainty |
| | *The EPRI methodology will be used to demonstratethe5%depletionuncertaintydemonstrate the 5% depletion uncertainty is conservative for Palo Verde |
| | *Fission product uncertainty explicitly considered 14 ISG Item 2.b -Reactor Parameters |
| | *Limiting axial moderator temperature profiles derivedpastpresentandanticipatedprofilesderived past, present, and anticipated profiles-Same methodolo gy employed at Comanche Peakgypy*Analysis performed at 4070 MWth |
| | *Licensee controls include verification of radial diibidTldpower distribution and T-cold15 ISG Item 2.c -Burnable Absorbers |
| | *Palo Verde has used the following integral burnable absorbers |
| | -B4C rods in CE STD Fuel |
| | -Erbia in CE STD Fuel and Value Added Pellet |
| | -IntegralFuelBurnableAbsorber(IFBA)inNGFIntegral Fuel Burnable Absorber (IFBA) in NGF -Gadolinia in AREVA Fuel |
| | *AnalysiswillnotcreditErbiaBCorGadolinia |
| | *Analysis will not credit Erbia, B4C, or Gadolinia |
| | *NGF fuel modeled with IFBA in all 236 pins for depletion anal ysis onlypyy-Pool model assumes no burnable absorbers 16 ISG Item 2.d -Rodded Operation |
| | *Palo Verde does not operate with control rodsinsertedrods inserted-Guide tube wear program |
| | *End of cycle check will ensure that fuel assembliesexperiencedaninsignificant assemblies experienced an insignificant amount of rodded operation at hot full powerp17 ISG Item 3 -Criticality Analysis |
| | *SCALE 6.1.2 will be used in the analysis |
| | -KENO V.a solves the eigenvalue (k eff) problem in 3D using the Monte Carlo method |
| | -238 Group ENDF/B-VII will be used as the library-Millstone LAR used SCALE 6.0 with the KENO V.a module and 238 Group ENDF/B-VII library 18 ISG Item 3.a -Axial Burnup Profile |
| | *Bounding axial burnup profiles selected frompastpresentandanticipated from past, present, and anticipated profilesClifilitlildhk |
| | -Cycle specific licensee con trols include checks on cutback regions (blanket), fuel design, and moderator temperature |
| | -Same methodology used at Comanche Peak and Prairie Island 19 ISG Item 3.b -Rack Model |
| | *Dimensions and tolerance of racks are traceabletodesigndocumentstraceable to design documentsBoratedaluminuminsertB10areal*Borated aluminum insert B-10 areal density conservatively modeled at quantitylessthanminimumcertifiedareal quantity less than minimum certified areal density20 ISG Item 3.c -Interfaces |
| | *All interfaces are evaluated and all interfacesareanacceptable2x2array interfaces are an acceptable 2x2 array-Palo Verde has only one rack design |
| | -No gaps modeled between rack modules 21 ISG Item 3.d -Normal Conditions |
| | *Analysis demonstrates that k eff 0.95 at lessthantheTSrequiredboron less than the TS required boron concentration for:Fuelmovement |
| | -Fuel movement-Fuel inspection and reconstitutionForeignObjectSearchandRetrieval |
| | -Foreign Object Search and Retrieval |
| | -Limiting normal condition to initiate accident identified identified 22 ISG Item 3.e -Accident Conditions |
| | *Analysis demonstrates that k eff 0.95 at lessthantheTSrequiredboron less than the TS required boron concentration forMisloadedordroppedsinglefreshfuel |
| | -Misloaded or dropped single fresh fuel assembly into, outside of, or on top of spent fuel racks |
| | -Multiple misloaded fuel assemblies |
| | -Loss of SFP cooling |
| | -Seismic events 23 ISG Item 3.e (contd.) |
| | *Limiting dilution event reduces pool boron from2150ppmto1900ppm from 2150 ppm to 1900 ppm TRMrequiresboronconcentrationtobe |
| | *TRM requires boron concentration to be maintained at 4000 ppm 24 ISG Item 4 -Code Validation |
| | *Will perform criticality code validation in accordancewithNUREG/CR |
| | -6698accordance with NUREG/CR-6698-Data carefully considered to identify trends consistentwithNUREG 1475consistent with NUREG-1475-HTC experiments will be included |
| | *Fission products will be explicitly accounted for |
| | -No lumped fission products will be used 25 Palo Verde Arrays |
| | *6 arrays will be analyzed |
| | *Palo Verde expects to submit between 3 and6ofthefollowingarraysforapproval and 6 of the following arrays for approvalFildiifltid |
| | *Final designs specify location and orientation of borated aluminum inserts 26 Palo Verde Arrays |
| | *Infinite array of 2 fresh fuel assemblies (Fr)withtwoblockedlocationsandno (Fr) with two blocked locations and no inserts27 Palo Verde Arrays |
| | *Infinite array of 2 fresh fuel assemblies (Fr)withtwotrashcans(TC)andtwo (Fr) with two trash cans (TC) and two inserts28 Palo Verde Arrays |
| | *Infinite array of 3 low reactivity fuel assemblies(Lo)and1high(Hi)reactivity assemblies (Lo) and 1 high (Hi) reactivity fuel assembly with 2 inserts29 Palo Verde Arrays |
| | *Infinite array of 2 high reactivity fuel assemblies(Hi)andonelowreactivityfuel assemblies (Hi) and one low reactivity fuel assembly (Lo) with one blocked cell and oneinsert one insert30 Palo Verde Arrays |
| | *Infinite array of 4 low reactivity fuel assemblies(Lo)withoneinsert assemblies (Lo) with one insert31 Palo Verde Arrays |
| | *Infinite array of 4 depleted fuel assemblies (De)withnoinserts (De) with no inserts32 Margin Maintenance |
| | *Palo Verde will monitor the margin identifiedintheanalysis identified in the analysis*CyclespecificchecksofkeyinputCycle specific checks of key input parameters |
| | *0.005 k additional margin reserved by Palo VerdeBurnupandenrichmentcurveswillbefor |
| | -Burnup and enrichment curves will be for keff= 0.9933 Conclusion |
| | *Palo Verde is proposing an acceptable methodolo gy for performing SFP criticalit y gypgyanalysisllldbdl*Permanent ly installed borated aluminum inserts will be credited in the analysis |
| | *Submit LAR by Nov 2015 |
| | *Request NRC approval in 18 -24 months 34}} |
Letter Sequence Request |
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MONTHYEARML15134A3592015-05-11011 May 2015
5/11/2015, Meeting Slide Regarding Pre-Submittal Meeting for Palo Verde Unit 1, 2, and 3 Updated Spent Fuel Pool Criticality Analysis
Project stage: Request
ML15286A0282015-10-23023 October 2015
Summary of Presubmittal Meeting with Arizona Public Service Company to Discuss Revised Methodology for Spent Fuel Pool Criticality Analysis and Associated Technical Specification Changes for Palo Verde, Units 1, 2, and 3 (CAC MF6600-MF6602)
Project stage: Meeting
2015-10-23
[Table View] |
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Category:Meeting Briefing Package/Handouts
MONTHYEARML24038A1742024-02-0707 February 2024
Pre-submittal Meeting Slides
ML24019A1512024-01-22022 January 2024
Slides - Modification of Browns Ferry Technical Specifications to Eliminate LCO 3.3.2.1 Actions C.2.1.1 and C.2.1.2 for Rod Worth
ML24003A8532024-01-0303 January 2024
January 4, 2024 Presubmittal Meeting Presentation-Risk Informed Process for Evaluations (RIPE) License Amendment Request for Safety Injection Tank (SIT) LCO (EPID: L?2023?LRM-0108)
ML23240A3232023-08-31031 August 2023
APS Presentation Slides for Pre-Submittal Meeting on 8/31/23, Alloy-600 Management Program Plan
ML23192A0102023-07-11011 July 2023
NRC RIPE 7-11-23 Public Meeting Presentation Slides
ML23144A0252023-05-25025 May 2023
APS Presentation Slides for Pre-Submittal Meeting on 5/25/23, Przr Surge Line
ML23093A0252023-04-30030 April 2023
April 5, 2023, Presubmittal Meeting Presentation - Containment Temperature and Safety Injection Tank Volume Requirements LAR
ML23090A1392023-04-0404 April 2023
April 4, 2023 Presubmittal Meeting Presentation - LAR to Adopt TSTF-266, Eliminate the Remote Shutdown System Table of Instrumentation and Controls (EPID: L?2023?LRM-0017)
ML23055B0572023-03-0101 March 2023
March 1, 2023 Presubmittal Meeting Presentation - Request for Use of Mururoa V4F1 and MTH2 Supplied Air Suits (EPID: L?2023?LRM-0012)
ML22096A0052022-04-0606 April 2022
TSTF-487 LAR Pre-submittal Public Meeting Presentation Slides
ML22025A0012022-01-25025 January 2022
1/25/22 Pre-submittal Meeting Presentation Slides for RR-69 to Extend Containment Tendon Inspection by Three Months Beyond 2/8/22
ML21342A0502021-12-0808 December 2021
TSTF-567 LAR Pre-submittal Public Meeting Presentation Slides
ML21320A1032021-11-17017 November 2021
RIPE Exemption 11-17-21 Pre-submittal Public Meeting Presentation Slides
ML21194A2502021-08-10010 August 2021
RIC 2021 - Ai EPRI-Artificial Intelligence and Development at EPRI
ML21131A0132021-05-13013 May 2021
License Transfer from Pnm to SRP, 5-13-21 Pre-submittal Public Meeting Presentation Slides
ML21025A0032021-01-26026 January 2021
Risk-Informed Process for Evaluations (RIPE) - NEI Public Meeting Presentation Slides
ML21025A0042021-01-25025 January 2021
Risk-Informed Process for Evaluations (RIPE) - NRC Public Meeting Presentation Slides
ML20171A2352020-06-24024 June 2020
Inservice Testing - Supplemental Position Indication Relief Request - NRC Pre-Application Meeting - June 24, 2020
ML19192A0972019-07-11011 July 2019
License Amendment Request for Emergency Plan, July 11, 2019
ML18299A0722018-09-26026 September 2018
Ionizing Radiation Factsheet-Veterans - Information for Veterans and Their Families
ML17320A1932017-11-15015 November 2017
NRC Public Meeting, Treatment of Mitigating Strategies in Risk Informed Decision Making
ML17003A0332016-12-29029 December 2016
Enclosure 2 - APS Meeting Slides
ML16357A6872016-12-20020 December 2016
One-Time License Amendment Request Unit 3 Train B Diesel Generator
ML17003A0862016-11-0303 November 2016
Enclosure 2 Slides Regulatory Audit Report for November 2-3, 2016
ML16253A4112016-09-0707 September 2016
Palo Verde Nuclear Generating Station Generic Letter 2004-02 - September 7, 2016
ML16083A4722016-03-24024 March 2016
NRC Subsequent Pre-Submittal Meeting Next Generation Fuel - Palo Verde, Units 1, 2, and 3
ML16014A1102016-01-20020 January 2016
Draft APS Slides for January 20, 2015, Public Meeting with APS Regarding Upcoming Next Generation Fuel License Amendment Request for Palo Verde, Units 1, 2, and 3
ML15244B2632015-08-27027 August 2015
Slides for Public Meeting with Arizona Public Service Company to Discuss License Amendment Request for Palo Verde Regarding Revised Methodology for Spent Fuel Pool Criticality Analysis
ML15236A1342015-08-26026 August 2015
Presentation Slides for Public Meeting with Arizona Public Service Generic Letter 2004-02 for Palo Verde Nuclear Generating Station, Units 1, 2, and 3
ML15159B2972015-06-0909 June 2015
Near-Term Task Force Recommendation 2.1 (R2.1) Seismic Hazard Evaluation - Arizona Public Service, Palo Verde Nuclear Generating Station Public Meeting - June 9, 2015
ML15156B3312015-06-0909 June 2015
Public Meeting Slides on R2.1 Seismic Hazard Re-Evaluation
ML15156B3522015-06-0404 June 2015
Draft Slides for Public Meeting with Arizona Public Service Company Ongoing Resolution of Generic Letter 2004-02 for Palo Verde Nuclear Generating Station, Units 1, 2, and 3
ML15134A3592015-05-11011 May 2015
5/11/2015, Meeting Slide Regarding Pre-Submittal Meeting for Palo Verde Unit 1, 2, and 3 Updated Spent Fuel Pool Criticality Analysis
ML15126A2072015-05-11011 May 2015
Presentation Slides for Prelicensing Meeting with Arizon Public Service Company to Discuss License Amendment Request for Palo Verde, Units 1, 2, and 3,
ML15103A2882015-04-0909 April 2015
Presentation on Potential Relief Request About Pressure Boundary Leakage on Reactor Coolant Pump 2A Pipe Nozzle
ML15070A2522015-02-18018 February 2015
Pre-Submittal Public Meeting Final Slides on Risk-Informed Completion Times.
ML15042A4152015-02-11011 February 2015
Pre-Submittal Public Meeting Draft Slides on Risk- Informed Completion Times
ML14184B4112014-06-11011 June 2014
Nrc/Nei/Utility MTG 6/11/14
ML14149A5092014-04-23023 April 2014
4/23/14 Meeting Slide for Palo Verde Nuclear Generating Station, Units 1, 2, and 3 Re. Sig Tube Inspection
ML14098A1832014-04-0202 April 2014
4/2/2014 Meeting Slide for Bottom-Mounted Instrument (Bmi) Relief Request 52 Pre-Submittal Meeting
ML13309A7202013-11-0505 November 2013
Meeting Presentation for November 5, 2013 Public Meeting Regarding Incorporation of NEI 11-04 Into the QA Program at Palo Verde Nuclear Generating Station, Units 1, 2, and 3
ML13308B3322013-11-0404 November 2013
Meeting Presentation for November 4, 2013 Public Meeting Regarding Bmi Leakage
ML13308C3402013-11-0404 November 2013
SG Unit 3 Telephone Call
ML13025A2832013-01-29029 January 2013
NRC Comments on Draft Integrated Plans, Palo Verde
ML12311A0492012-09-18018 September 2012
Part 26 Public Meeting NEI Presentation Slides
ML12243A4352012-08-30030 August 2012
8/30/2012 Meeting RR 48 - Phased Array Ultrasonic Examination in Lieu of Radiography
ML12243A4382012-08-30030 August 2012
8/30/2012 Meeting - RR 48 UT Vs Rt Discussion
ML12243A4472012-08-30030 August 2012
8/30/2012 Meeting - RR 48 UT in Lieu of Rt for Nuclear Power Plant Applications
ML12157A2722012-06-11011 June 2012
5/31/2012 Summary of Telephone Conference with Licensees Regarding Near Term Task Force Recommendation 2.1 Seismic Reevaluations - Diablo Canyon, 1 and 2, San Onofre, Units 2 and 3, Columbia Generating Station, and Palo Verde, Units 1, 2, a
ML11188A0722011-07-0606 July 2011
NRC Meeting with NEI and Licensees June 28, 2011 Workshop Engineering Approach Rev F
2024-02-07
[Table view]
Category:Slides and Viewgraphs
MONTHYEARML24038A1742024-02-0707 February 2024
Pre-submittal Meeting Slides
ML24019A1512024-01-22022 January 2024
Slides - Modification of Browns Ferry Technical Specifications to Eliminate LCO 3.3.2.1 Actions C.2.1.1 and C.2.1.2 for Rod Worth
ML24003A8532024-01-0303 January 2024
January 4, 2024 Presubmittal Meeting Presentation-Risk Informed Process for Evaluations (RIPE) License Amendment Request for Safety Injection Tank (SIT) LCO (EPID: L?2023?LRM-0108)
ML23296A0162023-10-20020 October 2023
October 20, 2023 Presubmittal Meeting Presentation - 1R24 Pressurizer Nozzle Repair - RR-70 (EPID: L?2023?LLR-0057)
ML23240A3232023-08-31031 August 2023
APS Presentation Slides for Pre-Submittal Meeting on 8/31/23, Alloy-600 Management Program Plan
ML23192A0102023-07-11011 July 2023
NRC RIPE 7-11-23 Public Meeting Presentation Slides
ML23144A0252023-05-25025 May 2023
APS Presentation Slides for Pre-Submittal Meeting on 5/25/23, Przr Surge Line
ML23093A0252023-04-30030 April 2023
April 5, 2023, Presubmittal Meeting Presentation - Containment Temperature and Safety Injection Tank Volume Requirements LAR
ML23055B0572023-03-0101 March 2023
March 1, 2023 Presubmittal Meeting Presentation - Request for Use of Mururoa V4F1 and MTH2 Supplied Air Suits (EPID: L?2023?LRM-0012)
ML22312A5952022-11-0808 November 2022
Independent Spent Fuel Storage Installation, Submittal of Annual Financial Reports 2021
ML22299A1812022-10-26026 October 2022
Presubmittal Meeting Presentation - License Amendment Request - Adoption of TSTF-107-A Separate Control Rods That Are Untrippable Versus Inoperable and Change to TS 3.1.5 Condition B (EPID: L?2021?LRM-0081)
ML22096A0052022-04-0606 April 2022
TSTF-487 LAR Pre-submittal Public Meeting Presentation Slides
ML22025A0012022-01-25025 January 2022
1/25/22 Pre-submittal Meeting Presentation Slides for RR-69 to Extend Containment Tendon Inspection by Three Months Beyond 2/8/22
ML21342A0502021-12-0808 December 2021
TSTF-567 LAR Pre-submittal Public Meeting Presentation Slides
ML21320A1032021-11-17017 November 2021
RIPE Exemption 11-17-21 Pre-submittal Public Meeting Presentation Slides
ML21278B0912021-10-0606 October 2021
Presubmittal Meeting with Arizona Public Service Company Regarding Relief Request No. 68 for Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (EPID L-2021-LRM-0104) (Slides)
ML21243A5432021-09-0101 September 2021
Request for Partial Exemption from 10 CFR 50.62(c)(1) Risk-Informed Process for Evaluations (RIPE)
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Pre-Submittal Meeting for Palo Verde Unit 1, 2, and 3 Updated Spent Fuel Pool Criticality AnalysisMay 11, 2015 Purpose*Present and discuss planned licensing changeschanges-Update spent fuel pool (SFP) criticality analysis
-Add neutron absorbing inserts to SFP racks 2
Objectives
- Updated criticality analysis will
-Provide basis for replacing non-conservative Technical Specification (TS) caused by missed poweruprateimpact power uprate impact-Include Next Generation Fuel (NGF)
- Account for reactivity effects of integral fuel burnable absorber (IFBA)Maintainfullcoreoffloadcapability
-Maintain full core offload capability 3
Borated Aluminum Inserts
- Additional reactivity hold down is planned tomeet10CFR5068andmaintainfull to meet 10 CFR 50.68 and maintain full core offload capabilityThlhdliiittld
-Thermal hydraulic, seismic, structural, and pool cooling calculations will be updated as
needed-Add a coupon surveillance program to monitor material performance 4
TS Changes
- TS 3.7.17 -Spent Fuel Assembly Storage
-Incorporate new burnup and enrichment curves-Display information with the polynomial explicitly stated
-Include diagrams of approved arrays 5
TS Changes
- TS 3.7.15 -Fuel Storage Pool Boron
-Currently 2150 ppm
-May increase in response to accident conditions analysis 6
TS Changes
-Incorporate new arrays
-Update boron concentration
-Reduce radially averaged enrichment from 4.8 wt% to 4.65 wt%
7 New TS*5.5.21 -Spent Fuel Storage Rack Neutron AbsorberMonitoringprogram Absorber Monitoring program -Will consider upcoming NRC Generic Letter "MonitoringofNeutronAbsorbingMaterialsin Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools" RecentDresdenOE
-Recent Dresden OE-License extension
-Plant decommissioning 8
Implementation
- Prior to NGF implementation in each unit
- Considering installing inserts under 10CFR5059 10 CFR 50.59Cidiliditif
- Considering a license con dition for a specified period of time to transition betweenTS between TS9 Methodology
- Based onISG201001"StaffGuidanceRegardingthe
-ISG-2010-01, "Staff Guidance Regarding the Nuclear Criticality Safety Analysis for Spent Fuel Pools"
-NEI 12-16, "Guidance for Performing Criticality Analyses of Fuel Storage at Light-Water ReactorPowerPlants "Revision1Reactor Power Plants, Revision 1-EPRI Depletion Benchmark Reports
-Multiple NUREGs p10 Recent Licensing Actions
-ComanchePeak
-Comanche Peak-Prairie Island
-Turkey Point
- Insert material similar to:
-LaSallePhBtt-Peach Bottom-Quad Cities
- Criticalitycode usagesimilarto:
Criticality code usage similar to:-Millstone 2 11 ISG Item 1 -Fuel Assembly Selection
- Palo Verde will demonstrate that variations indesignareadequatelyaccountedforin in design are adequately accounted for in a single, limiting, fuel assembly designCEStddFl-CE Standard Fuel-CE Value Added Pellet
-Westinghouse NGF (8 LUAs)
-AREVAAdvancedCE
-16HTP(8LTAs)AREVA Advanced CE16 HTP (8 LTAs)12 ISG Item 2 -Depletion Analysis
- Depletion parameters will impact the isotopicinventoryofburnedfuel isotopic inventory of burned fuel*Major depletion inputs
-Fuel type
-Axial burnup
-Moderator temperature
-Reactor powerSolubleboron
-Soluble boron-Burnable absorbers 13 ISG Item 2.a -Depletion Uncertainty
- The EPRI methodology will be used to demonstratethe5%depletionuncertaintydemonstrate the 5% depletion uncertainty is conservative for Palo Verde
- Fission product uncertainty explicitly considered 14 ISG Item 2.b -Reactor Parameters
- Limiting axial moderator temperature profiles derivedpastpresentandanticipatedprofilesderived past, present, and anticipated profiles-Same methodolo gy employed at Comanche Peakgypy*Analysis performed at 4070 MWth
- Licensee controls include verification of radial diibidTldpower distribution and T-cold15 ISG Item 2.c -Burnable Absorbers
- Palo Verde has used the following integral burnable absorbers
-B4C rods in CE STD Fuel
-Erbia in CE STD Fuel and Value Added Pellet
-IntegralFuelBurnableAbsorber(IFBA)inNGFIntegral Fuel Burnable Absorber (IFBA) in NGF -Gadolinia in AREVA Fuel
- AnalysiswillnotcreditErbiaBCorGadolinia
- Analysis will not credit Erbia, B4C, or Gadolinia
- NGF fuel modeled with IFBA in all 236 pins for depletion anal ysis onlypyy-Pool model assumes no burnable absorbers 16 ISG Item 2.d -Rodded Operation
- End of cycle check will ensure that fuel assembliesexperiencedaninsignificant assemblies experienced an insignificant amount of rodded operation at hot full powerp17 ISG Item 3 -Criticality Analysis
- SCALE 6.1.2 will be used in the analysis
-KENO V.a solves the eigenvalue (k eff) problem in 3D using the Monte Carlo method
-238 Group ENDF/B-VII will be used as the library-Millstone LAR used SCALE 6.0 with the KENO V.a module and 238 Group ENDF/B-VII library 18 ISG Item 3.a -Axial Burnup Profile
- Bounding axial burnup profiles selected frompastpresentandanticipated from past, present, and anticipated profilesClifilitlildhk
-Cycle specific licensee con trols include checks on cutback regions (blanket), fuel design, and moderator temperature
-Same methodology used at Comanche Peak and Prairie Island 19 ISG Item 3.b -Rack Model
- Dimensions and tolerance of racks are traceabletodesigndocumentstraceable to design documentsBoratedaluminuminsertB10areal*Borated aluminum insert B-10 areal density conservatively modeled at quantitylessthanminimumcertifiedareal quantity less than minimum certified areal density20 ISG Item 3.c -Interfaces
- All interfaces are evaluated and all interfacesareanacceptable2x2array interfaces are an acceptable 2x2 array-Palo Verde has only one rack design
-No gaps modeled between rack modules 21 ISG Item 3.d -Normal Conditions
- Analysis demonstrates that k eff 0.95 at lessthantheTSrequiredboron less than the TS required boron concentration for:Fuelmovement
-Fuel movement-Fuel inspection and reconstitutionForeignObjectSearchandRetrieval
-Foreign Object Search and Retrieval
-Limiting normal condition to initiate accident identified identified 22 ISG Item 3.e -Accident Conditions
- Analysis demonstrates that k eff 0.95 at lessthantheTSrequiredboron less than the TS required boron concentration forMisloadedordroppedsinglefreshfuel
-Misloaded or dropped single fresh fuel assembly into, outside of, or on top of spent fuel racks
-Multiple misloaded fuel assemblies
-Loss of SFP cooling
-Seismic events 23 ISG Item 3.e (contd.)
- Limiting dilution event reduces pool boron from2150ppmto1900ppm from 2150 ppm to 1900 ppm TRMrequiresboronconcentrationtobe
- TRM requires boron concentration to be maintained at 4000 ppm 24 ISG Item 4 -Code Validation
- Will perform criticality code validation in accordancewithNUREG/CR
-6698accordance with NUREG/CR-6698-Data carefully considered to identify trends consistentwithNUREG 1475consistent with NUREG-1475-HTC experiments will be included
- Fission products will be explicitly accounted for
-No lumped fission products will be used 25 Palo Verde Arrays
- 6 arrays will be analyzed
- Palo Verde expects to submit between 3 and6ofthefollowingarraysforapproval and 6 of the following arrays for approvalFildiifltid
- Final designs specify location and orientation of borated aluminum inserts 26 Palo Verde Arrays
- Infinite array of 2 fresh fuel assemblies (Fr)withtwoblockedlocationsandno (Fr) with two blocked locations and no inserts27 Palo Verde Arrays
- Infinite array of 2 fresh fuel assemblies (Fr)withtwotrashcans(TC)andtwo (Fr) with two trash cans (TC) and two inserts28 Palo Verde Arrays
- Infinite array of 3 low reactivity fuel assemblies(Lo)and1high(Hi)reactivity assemblies (Lo) and 1 high (Hi) reactivity fuel assembly with 2 inserts29 Palo Verde Arrays
- Infinite array of 2 high reactivity fuel assemblies(Hi)andonelowreactivityfuel assemblies (Hi) and one low reactivity fuel assembly (Lo) with one blocked cell and oneinsert one insert30 Palo Verde Arrays
- Infinite array of 4 low reactivity fuel assemblies(Lo)withoneinsert assemblies (Lo) with one insert31 Palo Verde Arrays
- Infinite array of 4 depleted fuel assemblies (De)withnoinserts (De) with no inserts32 Margin Maintenance
- Palo Verde will monitor the margin identifiedintheanalysis identified in the analysis*CyclespecificchecksofkeyinputCycle specific checks of key input parameters
- 0.005 k additional margin reserved by Palo VerdeBurnupandenrichmentcurveswillbefor
-Burnup and enrichment curves will be for keff= 0.9933 Conclusion
- Palo Verde is proposing an acceptable methodolo gy for performing SFP criticalit y gypgyanalysisllldbdl*Permanent ly installed borated aluminum inserts will be credited in the analysis
- Request NRC approval in 18 -24 months 34
