|
|
| (One intermediate revision by the same user not shown) |
| Line 12: |
Line 12: |
| | document type = Meeting Briefing Package/Handouts, Slides and Viewgraphs | | | document type = Meeting Briefing Package/Handouts, Slides and Viewgraphs |
| | page count = 20 | | | page count = 20 |
| | | project = |
| | | stage = Meeting |
| }} | | }} |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:Fuel Transition License Amendment Request Pre-Submittal Update Meeting Exelon Generation Company, LLC Dresden and Quad Cities Stations May 19, 2014 Meeting Agenda Objectives Background Licensing Approach August 27, 2013 Pre-Submittal Meeting Summary Technical Topics Schedule Summary Discussion 1 Meeting Objectives Describe the transition process from Westinghouse to AREVA fuel supply Communicate transition plan Address technical topics associated with the proposed transition Discuss licensing activities and schedule Obtain NRC/Exelon alignment on LAR content Obtain NRC input on the transition plan 2 Background Dresden Nuclear Power Station (DNPS) and Quad Cities Nuclear Power Station (QCNPS) are both General Electric BWR/3 reactors with Mark I containments Current power levels DNPS Units 2 and 3 2957 MWt QCNPS Units 1 and 2 2957 MWt Renewed Operating License expires DNPS Unit 2 12/22/2029 DNPS Unit 3 01/12/2031 QCNPS Units 1 and 2 12/14/2032 DNPS and QCNPS fuel transition project began in December 2012 when AREVA was awarded a contract for fuel beginning in 2016 April 2013 through present AREVA has been collecting and evaluating plant data needed for fuel transition In June 2013 fuel transition LAR planning activities began 3 Background AREVA ATRIUM 10XM Fuel Key Features 10x10 lattice 91 fuel rod locations 3 X 3 Square internal water channel 12 part length rods 9 grid spacers Debris filter lower tie plate 178 kgU Extensive operating experience 4 Licensing Approach Exelon will be asking for NRC review of the inclusion of AREVA approved generic methodologies as applicable to support licensing analyses and associated DNPS and QCNPS TS changes in support of the transition to AREVA ATRIUM 10XM fuel Current licensing basis will be retained for events not impacted by the change in fuel design Exelon will also be requesting a revision to the ATWS RPT steam dome pressure setpoint help mitigate (lower) the peak reactor vessel pressure following an ATWS event during the short term phase of the event reducing the setpoint provides additional margin by reducing the ATWS peak pressure without adversely impacting plant operation analysis performed using approved AREVA methodologies 5 Licensing Approach Revise TS and COLR to incorporate AREVA fuel analysis methods and setpoint changes as necessary Proposed TS changes will be provided with LAR TS 3.3.4.1, Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation, Surveillance Requirement (SR) 3.3.4.1.4.b, Reactor Vessel Steam Dome Pressure-High , revised to reflect new setpoint TS 5.6.5, Core Operating Limits Report (COLR), changed to add AREVA analytical methods and remove any legacy methodologies that are no longer applicable Applicable TS bases will be revised as necessary Individual COLRs will be revised as part of the reload process 6 Licensing Approach LAR will provide AREVA proprietary reports for QCNPS Mechanical Design Report Fuel Rod Design Report Thermal-Hydraulic Design Report Fuel Cycle Design Report Reload Safety Analysis Report LOCA Break Spectrum Analysis Report LOCA-ECCS Analysis MAPLHGR Limit Report AREVA will generate these reports for both DNPS and QCNPS, however, the LAR will only include the reports for QCNPS since the application of the methodologies is the same for both stations The reports for DNPS will be available prior to the first load of AREVA ATRIUM 10XM fuel at DNPS LAR will provide listing of current BWR Approved Topical Reports for DNPS and QCNPS that are still applicable 7 Licensing Approach Representative QCNPS Unit 2 Cycle Analysis Report will be provided to the NRC in support of their review of the LAR This representative Cycle Analysis Report is intended to support the LAR review for DNPS Units 2 and 3 and QCNPS Units 1 and 2 Purpose of representative analyses is to demonstrate the applicability of AREVA methodology to DNPS and QCNPS at current operating conditions The basis for ensuring that the analyses provided will be representative for both plants is that the plants are the same in many aspects (power, flow, core size, etc.) Approach supports the applicability of the LAR review for DNPS Units 2 and 3 and QCNPS Units 1 and 2 8 August 27, 2013 Pre-Submittal Meeting Summary Key Points Discussed Exelon will utilize an established transition process followed by industry One License Amendment Request will be submitted for both DNPS and QCNPS Follow-up Issues Raised During Meeting Finalize approach on channel bow, verify it will be submitted as part of the LAR as a plant specific method, and come back with a proposed solution later as to how this needs to be addressed (i.e., license condition or SE summary) Channel Bow evaluation will be performed using approved methodologies The approach and results of the evaluation will be discussed in the LAR for plant specific application This discussion is intended to support NRC review and resolution in the subsequent safety evaluation 9 August 27, 2013 Pre-Submittal Meeting Summary Follow-up Issues Raised During Meeting (continued) Finalize approach to completing the Spent Fuel Pool (SFP) Criticality Safety Analysis (CSA) for DNPS and QCNPS (i.e., analysis for only one station and implementation under 50.59 at the other) and include as topic in future pre-submittal meetings A separate LAR will be submitted to address SFP CSA for DNPS Units 2 and 3 only (submittal scheduled for August 2014) QCNPS Units 1 and 2 criticality changes will be completed under 10 CFR 50.59 using the QCNPS rack insert application currently under review as a basis DNPS SFP CSA analysis will follow the same methodology used in the QCNPS rack insert application currently under review Status and schedule for release of the draft and final Standard Review Plan (SRP) revision for reactivity insertion accidents Use of 230 cal/gram as the appropriate upper limit for coolability LAR approach to be used depends on schedule for issuance of the revised SRP 10 August 27, 2013 Pre-Submittal Meeting Summary Follow-up Issues Raised During Meeting (continued) Address any maneuvering restrictions associated with the new fuel and how those restrictions account for current Westinghouse fuel Both Westinghouse fuel and ATRIUM 10XM fuel utilize barrier cladding There will be no changes to Westinghouse maneuvering restrictions Exelon intends to apply Westinghouse and AREVA specific fuel conditioning rules to Westinghouse and AREVA fuel respectively AREVA Critical Power Evaluator (ACE) Approved LTR uses an integrated peaking factor based on the local fuel rod peaking factors that could lead to non-conservative CPR predictions Generic ACE supplement review completed by NRC and SE issued on March 31, 2014 Generic supplement will be used for DNPS and QCNPS fuel transition LAR submittal, Exelon specific ACE supplement will not be required 11 AREVA Technical Topics Application of Critical Power Correlation to Co-Resident Fuel Application of EMF-2245(P)(A) Application of Siemens Power -Resident Fuel Indirect method used in the QCNPS and DNPS application A best estimate process is used to develop additive constants over the range of applicability Balanced approach to develop additive constants over the entire range of applicability Evaluate results over ranges in inlet enthalpy, pressure and mass flux ECPR is the major figure of merit Application of the process to OPTIMA2 fuel results in a significant trend at low mass fluxes using the AREVA correlation Conservative approach is applied at low mass fluxes to ensure appropriate CPR results for design, licensing and monitoring The conservative approach will be discussed in the LAR for plant specific application 12 AREVA Technical Topics Crud and Corrosion Aspects of Current Water Chemistry Programs The current coolant chemistry program and the addition of On-Line-Nobel-Chemistry (OLNC) may lead to elevated liftoff (crud and oxide) Increased uncertainty in liftoff conditions AREVA is taking a proactive approach to evaluate liftoff conditions, define a Bounding Administrative Liftoff and assess the potential consequences on fuel related licensing analyses Treatment of higher than normal liftoff is not explicitly described in all approved topical reports The evaluation process is described here for plant specific application Utilize plant specific data from QCNPS and Plant A to establish a liftoff baseline Plant A selected as a comparative reference based on similar feedwater chemistry, OLNC program, fuel rod performance, etc. Data includes reactor coolant and feedwater chemistry, liftoff measurements, fuel rod power history, etc. 13 AREVA considers all available data to make judgments for a specific plant to support the license basis AREVA Technical Topics Crud and Corrosion Aspects of Current Water Chemistry Programs Bounding Administrative Liftoff values are defined by applying conservative adjustments to the liftoff baseline Conservative adjustments account for effects of OLNC and operational variations Bounding Administrative Liftoff must be defined for the limiting core location (Peak Liftoff) and an average fuel rod (Rod Average Liftoff) Peak Liftoff is needed to assess fuel rod analysis criteria Rod Average Liftoff is needed to assess the impact on other events/accidents Potential impact on fuel related licensing analysis Fuel rod analysis Fast transients Neutronic safety analysis Steady-State operation and slow transients Stability LOCA Mechanical Design 14 AREVA has an on-going surveillance program at Plant A to assess the impact of OLNC AREVA Technical Topics Crud and Corrosion Aspects of Current Water Chemistry Programs Preliminary evaluation results Fuel rod analysis criteria are satisfied Delta-CPR for fast transients is expected to increase by approximately 0.02 Explicitly incorporating a Bounding Administrative Liftoff in licensing analyses mitigates the risk of not establishing appropriate operating limits or exceeding established licensing limits The technique applied for fast transient evaluation and the evaluation results are consistent with the technique applied for an operability assessment performed in 2009 to address elevated liftoff Administrative penalties were applied to the MCPR operating limit Treatment of higher than normal liftoff using Bounding Administrative Liftoff will be discussed in the LAR for plant specific application 15 Bounding Administrative Liftoff will be accounted for in all fast transient analyses until data becomes available that demonstrates liftoff conditions are within normal expectations. | | {{#Wiki_filter:Fuel Transition License Amendment Request Pre-Submittal Update Meeting Exelon Generation Company, LLC Dresden and Quad Cities Stations May 19, 2014 |
| Fuel Transition LAR Schedule Fuel Transition (Consistent with August 27, 2013 Meeting) LAR Submittal: February 2015 Amendment Need Date: March 2016 QCNPS Unit 2 implementation: March 2016 DNPS Unit 3 implementation: November 2016 QCNPS Unit 1 implementation: March 2017 DNPS Unit 2 implementation: November 2017 16 Fuel Transition LAR Schedule Concurrent Reviews Spent Fuel Pool (SFP) Criticality Safety Analysis (CSA) LAR SFP CSA for ATRIUM 10XM will follow the same methodology used in the QCNPS rack insert application currently under review QCNPS SFP CSA for ATRIUM 10XM will be completed under 10 CFR 50.59 DNPS SFP CSA for ATRIUM 10XM will be submitted as a LAR (SFP CSA LAR) Submittal scheduled for August 2014 Fuel Transition LAR does not depend on NRC approval of SFP CSA LAR SFP CSA LAR does not depend on NRC approval of Fuel Transition LAR Alternative Source Term (AST) If accident dose increases by more than 10% as a result of fuel transition, AST analysis will require revision and results will be included in the fuel transition LAR 17 Summary Exelon transitioning to AREVA ATRIUM 10XM fuel Established transition process followed by industry will be used NRC-approved methodologies will be used for the transition analyses Exelon will be asking for NRC review of the inclusion of AREVA approved generic methodologies as applicable to support licensing analyses and associated DNPS and QCNPS TS changes in support of the transition to AREVA ATRIUM 10XM fuel One license amendment request will address both DNPS and QCNPS LAR submittal will include QCNPS reports to support the NRC review of the LAR for DNPS and QCNPS Representative QCNPS Unit 2 Cycle Analysis Report will be provided to the NRC in support of their review of the DNPS and QCNPS LAR Exelon and AREVA are identifying and addressing technical issues to support 18 DNPS/QCNPS Fuel Transition DISCUSSION 19}} | | |
| | Meeting Agenda |
| | * Objectives |
| | * Background |
| | * Licensing Approach |
| | * August 27, 2013 Pre-Submittal Meeting Summary |
| | * Technical Topics |
| | * Schedule |
| | * Summary |
| | * Discussion 1 |
| | |
| | Meeting Objectives |
| | * Describe the transition process from Westinghouse to AREVA fuel supply |
| | * Communicate transition plan |
| | * Address technical topics associated with the proposed transition |
| | * Discuss licensing activities and schedule |
| | * Obtain NRC/Exelon alignment on LAR content |
| | * Obtain NRC input on the transition plan 2 |
| | |
| | === |
| | Background=== |
| | * Dresden Nuclear Power Station (DNPS) and Quad Cities Nuclear Power Station (QCNPS) are both General Electric BWR/3 reactors with Mark I containments |
| | * Current power levels |
| | - DNPS Units 2 and 3 - 2957 MWt |
| | - QCNPS Units 1 and 2 - 2957 MWt |
| | * Renewed Operating License expires |
| | - DNPS Unit 2 - 12/22/2029 |
| | - DNPS Unit 3 - 01/12/2031 |
| | - QCNPS Units 1 and 2 - 12/14/2032 |
| | * DNPS and QCNPS fuel transition project began in December 2012 when AREVA was awarded a contract for fuel beginning in 2016 |
| | * April 2013 through present AREVA has been collecting and evaluating plant data needed for fuel transition |
| | * In June 2013 fuel transition LAR planning activities began 3 |
| | |
| | === |
| | Background=== |
| | AREVA ATRIUM 10XM Fuel - Key Features |
| | * 10x10 lattice - 91 fuel rod locations |
| | * 3 X 3 Square internal water channel |
| | * 12 part length rods |
| | * 9 grid spacers |
| | * Debris filter lower tie plate |
| | * 178 kgU |
| | * Extensive operating experience 4 |
| | |
| | Licensing Approach |
| | * Exelon will be asking for NRC review of the inclusion of AREVA approved generic methodologies as applicable to support licensing analyses and associated DNPS and QCNPS TS changes in support of the transition to AREVA ATRIUM 10XM fuel |
| | * Current licensing basis will be retained for events not impacted by the change in fuel design |
| | * Exelon will also be requesting a revision to the ATWS RPT steam dome pressure setpoint |
| | - help mitigate (lower) the peak reactor vessel pressure following an ATWS event during the short term phase of the event |
| | - reducing the setpoint provides additional margin by reducing the ATWS peak pressure without adversely impacting plant operation |
| | - analysis performed using approved AREVA methodologies 5 |
| | |
| | Licensing Approach Revise TS and COLR to incorporate AREVA fuel analysis methods and setpoint changes as necessary |
| | * Proposed TS changes will be provided with LAR |
| | - TS 3.3.4.1, Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation, Surveillance Requirement (SR) 3.3.4.1.4.b, Reactor Vessel Steam Dome Pressure-High , revised to reflect new setpoint |
| | - TS 5.6.5, Core Operating Limits Report (COLR), changed to add AREVA analytical methods and remove any legacy methodologies that are no longer applicable |
| | - Applicable TS bases will be revised as necessary |
| | * Individual COLRs will be revised as part of the reload process 6 |
| | |
| | Licensing Approach |
| | * LAR will provide AREVA proprietary reports for QCNPS |
| | - Mechanical Design Report |
| | - Fuel Rod Design Report |
| | - Thermal-Hydraulic Design Report |
| | - Fuel Cycle Design Report |
| | - Reload Safety Analysis Report |
| | - LOCA Break Spectrum Analysis Report |
| | - LOCA-ECCS Analysis MAPLHGR Limit Report |
| | * AREVA will generate these reports for both DNPS and QCNPS, however, the LAR will only include the reports for QCNPS since the application of the methodologies is the same for both stations |
| | * The reports for DNPS will be available prior to the first load of AREVA ATRIUM 10XM fuel at DNPS |
| | * LAR will provide listing of current BWR Approved Topical Reports for DNPS and QCNPS that are still applicable 7 |
| | |
| | Licensing Approach |
| | * Representative QCNPS Unit 2 Cycle Analysis Report will be provided to the NRC in support of their review of the LAR |
| | - This representative Cycle Analysis Report is intended to support the LAR review for DNPS Units 2 and 3 and QCNPS Units 1 and 2 |
| | * Purpose of representative analyses is to demonstrate the applicability of AREVA methodology to DNPS and QCNPS at current operating conditions |
| | * The basis for ensuring that the analyses provided will be representative for both plants is that the plants are the same in many aspects (power, flow, core size, etc.) |
| | * Approach supports the applicability of the LAR review for DNPS Units 2 and 3 and QCNPS Units 1 and 2 8 |
| | |
| | August 27, 2013 Pre-Submittal Meeting Summary |
| | * Key Points Discussed |
| | - Exelon will utilize an established transition process followed by industry |
| | - One License Amendment Request will be submitted for both DNPS and QCNPS |
| | * Follow-up Issues Raised During Meeting |
| | - Finalize approach on channel bow, verify it will be submitted as part of the LAR as a plant specific method, and come back with a proposed solution later as to how this needs to be addressed (i.e., license condition or SE summary) |
| | * Channel Bow evaluation will be performed using approved methodologies |
| | * The approach and results of the evaluation will be discussed in the LAR for plant specific application |
| | * This discussion is intended to support NRC review and resolution in the subsequent safety evaluation 9 |
| | |
| | August 27, 2013 Pre-Submittal Meeting Summary |
| | * Follow-up Issues Raised During Meeting (continued) |
| | - Finalize approach to completing the Spent Fuel Pool (SFP) Criticality Safety Analysis (CSA) for DNPS and QCNPS (i.e., analysis for only one station and implementation under 50.59 at the other) and include as topic in future pre-submittal meetings |
| | * A separate LAR will be submitted to address SFP CSA for DNPS Units 2 and 3 only (submittal scheduled for August 2014) |
| | * QCNPS Units 1 and 2 criticality changes will be completed under 10 CFR 50.59 using the QCNPS rack insert application currently under review as a basis |
| | * DNPS SFP CSA analysis will follow the same methodology used in the QCNPS rack insert application currently under review |
| | - Status and schedule for release of the draft and final Standard Review Plan (SRP) revision for reactivity insertion accidents |
| | * Use of 230 cal/gram as the appropriate upper limit for coolability |
| | * LAR approach to be used depends on schedule for issuance of the revised SRP 10 |
| | |
| | August 27, 2013 Pre-Submittal Meeting Summary |
| | * Follow-up Issues Raised During Meeting (continued) |
| | - Address any maneuvering restrictions associated with the new fuel and how those restrictions account for current Westinghouse fuel |
| | * Both Westinghouse fuel and ATRIUM 10XM fuel utilize barrier cladding |
| | * There will be no changes to Westinghouse maneuvering restrictions |
| | * Exelon intends to apply Westinghouse and AREVA specific fuel conditioning rules to Westinghouse and AREVA fuel respectively |
| | - AREVA Critical Power Evaluator (ACE) |
| | * Approved LTR uses an integrated peaking factor based on the local fuel rod peaking factors that could lead to non-conservative CPR predictions |
| | * Generic ACE supplement review completed by NRC and SE issued on March 31, 2014 |
| | * Generic supplement will be used for DNPS and QCNPS fuel transition LAR submittal, Exelon specific ACE supplement will not be required 11 |
| | |
| | AREVA Technical Topics Application of Critical Power Correlation to Co-Resident Fuel |
| | * Application of EMF-2245(P)(A) - Application of Siemens Power Corporations Critical Power Correlations to Co-Resident Fuel |
| | * Indirect method used in the QCNPS and DNPS application |
| | * A best estimate process is used to develop additive constants over the range of applicability |
| | - Balanced approach to develop additive constants over the entire range of applicability |
| | - Evaluate results over ranges in inlet enthalpy, pressure and mass flux |
| | - ECPR is the major figure of merit |
| | * Application of the process to OPTIMA2 fuel results in a significant trend at low mass fluxes using the AREVA correlation |
| | * Conservative approach is applied at low mass fluxes to ensure appropriate CPR results for design, licensing and monitoring |
| | * The conservative approach will be discussed in the LAR for plant specific application 12 |
| | |
| | AREVA Technical Topics Crud and Corrosion Aspects of Current Water Chemistry Programs |
| | * The current coolant chemistry program and the addition of On-Line-Nobel-Chemistry (OLNC) may lead to elevated liftoff (crud and oxide) |
| | - Increased uncertainty in liftoff conditions |
| | * AREVA is taking a proactive approach to evaluate liftoff conditions, define a Bounding Administrative Liftoff and assess the potential consequences on fuel related licensing analyses |
| | - Treatment of higher than normal liftoff is not explicitly described in all approved topical reports |
| | - The evaluation process is described here for plant specific application |
| | * Utilize plant specific data from QCNPS and Plant A to establish a liftoff baseline |
| | - Plant A selected as a comparative reference based on similar feedwater chemistry, OLNC program, fuel rod performance, etc. |
| | - Data includes reactor coolant and feedwater chemistry, liftoff measurements, fuel rod power history, etc. |
| | AREVA considers all available data to make judgments for a specific plant to support the license basis 13 |
| | |
| | AREVA Technical Topics Crud and Corrosion Aspects of Current Water Chemistry Programs |
| | * Bounding Administrative Liftoff values are defined by applying conservative adjustments to the liftoff baseline |
| | - Conservative adjustments account for effects of OLNC and operational variations |
| | * Bounding Administrative Liftoff must be defined for the limiting core location (Peak Liftoff) and an average fuel rod (Rod Average Liftoff) |
| | - Peak Liftoff is needed to assess fuel rod analysis criteria |
| | - Rod Average Liftoff is needed to assess the impact on other events/accidents |
| | * Potential impact on fuel related licensing analysis |
| | - Fuel rod analysis - Fast transients |
| | - Neutronic safety analysis - Steady-State operation and slow transients |
| | - Stability - LOCA |
| | - Mechanical Design AREVA has an on-going surveillance program at Plant A to assess the impact of OLNC 14 |
| | |
| | AREVA Technical Topics Crud and Corrosion Aspects of Current Water Chemistry Programs |
| | * Preliminary evaluation results |
| | - Fuel rod analysis criteria are satisfied |
| | - Delta-CPR for fast transients is expected to increase by approximately 0.02 |
| | - Explicitly incorporating a Bounding Administrative Liftoff in licensing analyses mitigates the risk of not establishing appropriate operating limits or exceeding established licensing limits |
| | * The technique applied for fast transient evaluation and the evaluation results are consistent with the technique applied for an operability assessment performed in 2009 to address elevated liftoff |
| | - Administrative penalties were applied to the MCPR operating limit |
| | * Treatment of higher than normal liftoff using Bounding Administrative Liftoff will be discussed in the LAR for plant specific application Bounding Administrative Liftoff will be accounted for in all fast transient analyses until data becomes available that demonstrates liftoff conditions are within normal expectations. |
| | 15 |
| | |
| | Fuel Transition LAR Schedule Fuel Transition (Consistent with August 27, 2013 Meeting) |
| | * LAR Submittal: February 2015 |
| | * Amendment Need Date: March 2016 |
| | * QCNPS Unit 2 implementation: March 2016 |
| | * DNPS Unit 3 implementation: November 2016 |
| | * QCNPS Unit 1 implementation: March 2017 |
| | * DNPS Unit 2 implementation: November 2017 16 |
| | |
| | Fuel Transition LAR Schedule Concurrent Reviews |
| | * Spent Fuel Pool (SFP) Criticality Safety Analysis (CSA) LAR |
| | - SFP CSA for ATRIUM 10XM will follow the same methodology used in the QCNPS rack insert application currently under review |
| | - QCNPS SFP CSA for ATRIUM 10XM will be completed under 10 CFR 50.59 |
| | - DNPS SFP CSA for ATRIUM 10XM will be submitted as a LAR (SFP CSA LAR) |
| | * Submittal scheduled for August 2014 |
| | - Fuel Transition LAR does not depend on NRC approval of SFP CSA LAR |
| | - SFP CSA LAR does not depend on NRC approval of Fuel Transition LAR |
| | * Alternative Source Term (AST) |
| | - If accident dose increases by more than 10% as a result of fuel transition, AST analysis will require revision and results will be included in the fuel transition LAR 17 |
| | |
| | Summary |
| | * Exelon transitioning to AREVA ATRIUM 10XM fuel |
| | * Established transition process followed by industry will be used |
| | * NRC-approved methodologies will be used for the transition analyses |
| | * Exelon will be asking for NRC review of the inclusion of AREVA approved generic methodologies as applicable to support licensing analyses and associated DNPS and QCNPS TS changes in support of the transition to AREVA ATRIUM 10XM fuel |
| | * One license amendment request will address both DNPS and QCNPS |
| | * LAR submittal will include QCNPS reports to support the NRC review of the LAR for DNPS and QCNPS |
| | * Representative QCNPS Unit 2 Cycle Analysis Report will be provided to the NRC in support of their review of the DNPS and QCNPS LAR |
| | * Exelon and AREVA are identifying and addressing technical issues to support the NRCs review 18 |
| | |
| | DNPS/QCNPS Fuel Transition DISCUSSION 19}} |
Letter Sequence Meeting |
|---|
|
|
MONTHYEARML13225A7492013-08-12012 August 2013
NRR E-mail Capture - Slide Deck for Exelon Pre-Submittal Meeting
Project stage: Request
ML13193A0482013-08-14014 August 2013
Notice of Forthcoming Meeting with Exelon Generation Company, LLC (EGC) Regarding Areva Xm Fuel Transition Request for Dresden and Quad Cities Nuclear Stations
Project stage: Meeting
ML13238A1882013-08-26026 August 2013
8/27/2013 - Notice of Forthcoming Meeting with Exelon Generation Company, LLC (Egc)Regarding Areva Xm Fuel Transition Request for Dresden and Quad Cities Nuclear Stations
Project stage: Meeting
ML14232A7852014-05-19019 May 2014
Fuel Transition License Amendment Request Pre-Submittal Update Meeting
Project stage: Meeting
ML14219A2822014-08-0707 August 2014
Notice of Forthcoming Meeting with Exelon Generation Company, LLC (EGC) Regarding Areva Xm Fuel Transition Request for Dresden and Quad Cities Nuclear Stations
Project stage: Meeting
RS-14-238, Transmittal of Proprietary Meeting Slides2014-08-25025 August 2014
Transmittal of Proprietary Meeting Slides
Project stage: Request
ML14241A6332014-09-11011 September 2014
Summary of August 23, 2014, Meeting with Exelon Generation Company, LLC Regarding Areva Xm Fuel Transition Request for Dresden and Quad Cities Nuclear Station
Project stage: Meeting
ML14226B0122014-09-11011 September 2014
May 19, 2014 Summary of Meeting with Exelon Generation Company, LLC Regarding Areva Xm Fuel Transition for Dresden and Quad Cities Nuclear Stations
Project stage: Meeting
ML14246A5762014-09-17017 September 2014
Request for Withholding Proprietary Information from Public Disclosure (TAC Nos. MF2422, MF2423, MF2424, and MF2425)
Project stage: Other
ML14254A1532014-09-22022 September 2014
8/19/2014, Summary of Closed Meeting with Exelon Generation Company, LLC, Regarding Areva Am Fuel Transition for Dresden and Quad Cities Nuclear Stations
Project stage: Meeting
2014-08-25
[Table View] |
|
|---|
Category:Meeting Briefing Package/Handouts
MONTHYEARML24029A1742024-01-30030 January 2024
Constellation Pre-Application January 30, 2024, Meeting Slides - Proposed Alternative to Utilize Code Case N-932, Alternative Requirements for Acceptance of Containment Base Metal Corrosion or Erosion
ML23317A0712023-11-14014 November 2023
NRC Pre-Submittal Meeting on November 14th, 2023 - TSTF-591 and Selected 50.69 License Condition Updates (EPID L-2023-LLM-0098) (Slides)
ML23255A1042023-08-11011 August 2023
Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout
ML23173A0472023-06-28028 June 2023
SLRA - NRC Presubmittal Meeting Slides - 6-28-23
ML23173A0462023-06-28028 June 2023
DNPS SLR Pre-submittal Meeting Presentation Rev. 1
ML23145A1322023-06-27027 June 2023
June 27, 2023, Dresden Nuclear Power Station Subsequent License Renewal Environmental Pre-application Public Meeting - Constellation Slides
ML23165A0242023-06-27027 June 2023
June 27, 2023, Dresden Nuclear Power Station Subsequent License Renewal Environmental Pre-application Public Meeting - NRC Slides
ML23055A2712023-03-0202 March 2023
March 2, 2023, Preapplication Meeting to Discuss Planned Amendments to Adopt TSTF-505 and 10 CFR 50.69 (EPID L-2023-LRM-0007) - Slides
ML21314A4472021-11-10010 November 2021
Slides for Presubmittial Meeting for Proposed Alternative to Adopt ASME Code Case N-921 to Extend the Inservice Inspection Interval
ML21194A1822021-07-13013 July 2021
and Quad Cities Nuclear Generating Stations 2020 Annual Assessment Meeting Slides
ML20258A0302020-09-22022 September 2020
Decommissioning Licensing Action Submittal Plan for Byron and Dresden Stations Early Shutdowns
ML20261G7322020-09-16016 September 2020
Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a
ML20238B8572020-08-25025 August 2020
Quad 2019 Hq Online EOC Slides
ML20178A4202020-06-30030 June 2020
NEI Slides for June 30, 2020, Public Meeting on COVID-19 Response
ML20170B0212020-06-23023 June 2020
NRC Pre-Submittal Meeting Byron Unit 2 One-Time Deferral of Reactor Pressure Vessel Head Penetration Nozzle (Rpvhpn) Inspections
ML20163A6552020-06-16016 June 2020
6-16-20 Byron Unit 2 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections
ML20169A5592020-06-16016 June 2020
Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections (Rev 1)
ML19318F9512019-11-20020 November 2019
Presentation Slides for November 20, 2019, Pre-Application Meeting - Request for Revision to Quality Assurance Program Internal Audit Frequency
ML19161A2572019-06-0404 June 2019
BWR Fleet Msv/Srv - Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019
ML19151A6602019-05-31031 May 2019
BWR Fleet Mssv/Srv Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019
ML19022A2002019-01-23023 January 2019
Request for Use of ASME Code Case N-879 for Exelon Nuclear Power Plants
ML18347B3142018-12-19019 December 2018
Bwrvip/Asme Relief Request Discussion December 19, 2018
ML18334A2162018-11-30030 November 2018
Presentation Slides: Exelon BWR MSIV (Boiling-Water Reactor - Main Steam Isolation Valve) Leakage Optimization for NRC Pre-Submittal Meeting of December 6, 2018
ML18319A1272018-11-19019 November 2018
Slides for 11/19/18 Public Meeting - Exelon Fleet LAR for Common Language for TS 5.7 High Radiation Areas
ML18054B3592018-02-27027 February 2018
Slide: NRC Pre-Submittal Meeting for Exelon Fleet LAR to Relocate TS Unit Staff Qualification ANSI Requirements to the QATR, February 27, 2018, Profile Info: Submitted by Frank Mascitelli
ML17156A7972017-06-0505 June 2017
Presentation for 2016 Dresden Nuclear Power Station EOC Open House
ML17142A2382017-05-25025 May 2017
OEDO-17-00280 - Briefing Package for Drop-In Visit on June 9, 2017, by Senior Management of Exelon Generation Company, LLC with Chairman Svinicki, Commissioner Baran, and Commissioner Burns
ML16314E4812016-11-14014 November 2016
Part 37 Applicability to Reactor Vessels and Associated Structures, Systems, and Components While in Safstor Awaiting Active Decommissioning Activities - November 14, 2016
ML16189A4332016-07-12012 July 2016
July 12, 2016, Public Meeting with NRC - Exelon Decommissioning Licensing Action Submittal Plan
ML16189A2552016-07-0707 July 2016
Annual Assessment Meeting/Open House (Hand Out)
ML16077A1562016-03-22022 March 2016
Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards
ML16075A3292016-03-16016 March 2016
OEDO-16-00165 - Briefing Package for Drop-In Visit on March 23, 2016, by Senior Management of Exelon Generation Company, LLC with the NRC Executive Director for Operations
ML15013A1562015-01-14014 January 2015
Meeting Slide Regarding Dresden Nuclear Power Station Pre-Application Meeting for Providing Natural Gas as a Primary Fuel to Station Auxiliary Heating Boilers
RS-14-238, Transmittal of Proprietary Meeting Slides2014-08-25025 August 2014
Transmittal of Proprietary Meeting Slides
ML14167A4122014-06-17017 June 2014
NRC Slides for Quad Cities 2013 EOC Public Meeting
ML14232A7852014-05-19019 May 2014
Fuel Transition License Amendment Request Pre-Submittal Update Meeting
ML13149A2062013-05-22022 May 2013
NRC Slides from Public Meeting
ML12164A5962012-06-12012 June 2012
Annual Assessment Meeting Slides
ML1208701402012-03-27027 March 2012
Licensee Slides for Exelon Fleet Pre-Submittal Public Meeting 4-10-12 Licensed Operator Eligibility Requirements LAR
ML1203301242012-02-0909 February 2012
Handout for Public Meeting on February 9, 2012 (Slides)
ML1109602872011-04-0505 April 2011
Quad Cities Nuclear Power Station 2010 End-of-Cycle Assessment Presentation (Short)
ML1016800822010-06-15015 June 2010
Annual Assessment Meeting, Reactor Oversight Program - 2009, Slides
ML0919803632009-08-20020 August 2009
Summary of Licensing Counterparts Meeting with Exelon Generation Company, to Discuss Licensing Practices and Processes
ML0914003382009-05-14014 May 2009
Slides Presented at the Dresden Station 2008 EOC Public Meeting
ML0911802252009-04-0707 April 2009
NRC - Quad Cities Annual Assessment Meeting Slides
ML0911802142009-04-0707 April 2009
NRC End-of-Cycle Meeting Slides
ML0812007842008-06-0202 June 2008
Meeting Slides, Nrc/Exelon Licensing Counterparts Meeting.
ML0814405062008-05-22022 May 2008
EOC Summary Meeting Slides
ML0812209792008-04-30030 April 2008
Meeting Slides, Dresden Annual Assessment Meeting, Reactor Oversight Program - Cy 2007.
ML0714404642007-05-23023 May 2007
End-of-Cycle Meeting - NRC Slides
2024-01-30
[Table view]
Category:Slides and Viewgraphs
MONTHYEARML24029A1742024-01-30030 January 2024
Constellation Pre-Application January 30, 2024, Meeting Slides - Proposed Alternative to Utilize Code Case N-932, Alternative Requirements for Acceptance of Containment Base Metal Corrosion or Erosion
ML23317A0712023-11-14014 November 2023
NRC Pre-Submittal Meeting on November 14th, 2023 - TSTF-591 and Selected 50.69 License Condition Updates (EPID L-2023-LLM-0098) (Slides)
ML23251A0782023-09-0606 September 2023
DRE1 Decom Pre-Submittal Slides
ML23255A1042023-08-11011 August 2023
Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout
ML23173A0472023-06-28028 June 2023
SLRA - NRC Presubmittal Meeting Slides - 6-28-23
ML23173A0462023-06-28028 June 2023
DNPS SLR Pre-submittal Meeting Presentation Rev. 1
ML23145A1322023-06-27027 June 2023
June 27, 2023, Dresden Nuclear Power Station Subsequent License Renewal Environmental Pre-application Public Meeting - Constellation Slides
ML23165A0242023-06-27027 June 2023
June 27, 2023, Dresden Nuclear Power Station Subsequent License Renewal Environmental Pre-application Public Meeting - NRC Slides
ML23055A2712023-03-0202 March 2023
March 2, 2023, Preapplication Meeting to Discuss Planned Amendments to Adopt TSTF-505 and 10 CFR 50.69 (EPID L-2023-LRM-0007) - Slides
NEI 99-01, Slides - Constellation - Pre-Application EP 2/23/2023 Meeting Slides2023-02-21021 February 2023
Slides - Constellation - Pre-Application EP 2/23/2023 Meeting Slides
ML22053A2912022-02-22022 February 2022
NRC Slides for February 25, 2022 Meeting - Acceptance Review of Proposed Alternative to Adopt ASME Code Case N-921 at Dresden and Quad Cities
ML21314A4472021-11-10010 November 2021
Slides for Presubmittial Meeting for Proposed Alternative to Adopt ASME Code Case N-921 to Extend the Inservice Inspection Interval
ML21194A1822021-07-13013 July 2021
and Quad Cities Nuclear Generating Stations 2020 Annual Assessment Meeting Slides
ML21162A3322021-06-11011 June 2021
BWR Fleet Relief Request Associated with RPV Instrument Nozzle Repairs
ML20258A0302020-09-22022 September 2020
Decommissioning Licensing Action Submittal Plan for Byron and Dresden Stations Early Shutdowns
ML20261G7322020-09-16016 September 2020
Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a
ML20238B8572020-08-25025 August 2020
Quad 2019 Hq Online EOC Slides
ML20178A4202020-06-30030 June 2020
NEI Slides for June 30, 2020, Public Meeting on COVID-19 Response
ML20170B0212020-06-23023 June 2020
NRC Pre-Submittal Meeting Byron Unit 2 One-Time Deferral of Reactor Pressure Vessel Head Penetration Nozzle (Rpvhpn) Inspections
ML20169A5592020-06-16016 June 2020
Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections (Rev 1)
ML20163A6552020-06-16016 June 2020
6-16-20 Byron Unit 2 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections
ML18347B3142018-12-19019 December 2018
Bwrvip/Asme Relief Request Discussion December 19, 2018
ML18334A2162018-11-30030 November 2018
Presentation Slides: Exelon BWR MSIV (Boiling-Water Reactor - Main Steam Isolation Valve) Leakage Optimization for NRC Pre-Submittal Meeting of December 6, 2018
ML18319A1272018-11-19019 November 2018
Slides for 11/19/18 Public Meeting - Exelon Fleet LAR for Common Language for TS 5.7 High Radiation Areas
ML18207A1882018-07-26026 July 2018
Slides for Dresden 2017 EOC Open House
ML18086A8432018-03-27027 March 2018
NUREG-1021, Revision 11 Implementation
ML18054B3592018-02-27027 February 2018
Slide: NRC Pre-Submittal Meeting for Exelon Fleet LAR to Relocate TS Unit Staff Qualification ANSI Requirements to the QATR, February 27, 2018, Profile Info: Submitted by Frank Mascitelli
ML17156A7972017-06-0505 June 2017
Presentation for 2016 Dresden Nuclear Power Station EOC Open House
ML16314E4812016-11-14014 November 2016
Part 37 Applicability to Reactor Vessels and Associated Structures, Systems, and Components While in Safstor Awaiting Active Decommissioning Activities - November 14, 2016
ML16189A4332016-07-12012 July 2016
July 12, 2016, Public Meeting with NRC - Exelon Decommissioning Licensing Action Submittal Plan
ML16189A2552016-07-0707 July 2016
Annual Assessment Meeting/Open House (Hand Out)
ML16077A1562016-03-22022 March 2016
Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards
ML15135A4252015-05-19019 May 2015
EOC Mtg Slides
ML15013A1562015-01-14014 January 2015
Meeting Slide Regarding Dresden Nuclear Power Station Pre-Application Meeting for Providing Natural Gas as a Primary Fuel to Station Auxiliary Heating Boilers
RS-14-238, Transmittal of Proprietary Meeting Slides2014-08-25025 August 2014
Transmittal of Proprietary Meeting Slides
ML14167A4122014-06-17017 June 2014
NRC Slides for Quad Cities 2013 EOC Public Meeting
ML14232A7852014-05-19019 May 2014
Fuel Transition License Amendment Request Pre-Submittal Update Meeting
ML13149A2062013-05-22022 May 2013
NRC Slides from Public Meeting
ML12164A5962012-06-12012 June 2012
Annual Assessment Meeting Slides
ML1208701402012-03-27027 March 2012
Licensee Slides for Exelon Fleet Pre-Submittal Public Meeting 4-10-12 Licensed Operator Eligibility Requirements LAR
ML1205906462012-03-0505 March 2012
February 9, 2012 - Summary of Meeting with Exelon Nuclear Regarding Future Submittal of Amendment to Use Netco Spent Fuel Pool Inserts
ML1203301242012-02-0909 February 2012
Handout for Public Meeting on February 9, 2012 (Slides)
ML11201A2132011-07-20020 July 2011
Summary of Public Meeting to Discuss Exelon'S Plans for Implementing an Electronic Document Control System (Edocs) for Use by NRC Inspectors with U.S. Nuclear Regulatory Commission (NRC) Region III Staff
ML1113202162011-05-11011 May 2011
Slides for Dresden Nuclear Power Station End-Of-Cycle Public Open House
ML1109602782011-04-0505 April 2011
Quad Cities Nuclear Power Station 2010 End-of-Cycle Annual Assessment Meeting Presentation (Long)
ML1109602872011-04-0505 April 2011
Quad Cities Nuclear Power Station 2010 End-of-Cycle Assessment Presentation (Short)
ML1016800822010-06-15015 June 2010
Annual Assessment Meeting, Reactor Oversight Program - 2009, Slides
ML1012000332010-04-28028 April 2010
Annual Assessment Meeting Slides
ML0929400522009-10-22022 October 2009
Meeting Power Uprate Meeting Slides
ML0914003382009-05-14014 May 2009
Slides Presented at the Dresden Station 2008 EOC Public Meeting
2024-01-30
[Table view] |
Text
Fuel Transition License Amendment Request Pre-Submittal Update Meeting Exelon Generation Company, LLC Dresden and Quad Cities Stations May 19, 2014
Meeting Agenda
- August 27, 2013 Pre-Submittal Meeting Summary
Meeting Objectives
- Describe the transition process from Westinghouse to AREVA fuel supply
- Communicate transition plan
- Address technical topics associated with the proposed transition
- Discuss licensing activities and schedule
- Obtain NRC/Exelon alignment on LAR content
- Obtain NRC input on the transition plan 2
=
Background===
- Dresden Nuclear Power Station (DNPS) and Quad Cities Nuclear Power Station (QCNPS) are both General Electric BWR/3 reactors with Mark I containments
- DNPS Units 2 and 3 - 2957 MWt
- QCNPS Units 1 and 2 - 2957 MWt
- Renewed Operating License expires
- DNPS Unit 2 - 12/22/2029
- DNPS Unit 3 - 01/12/2031
- QCNPS Units 1 and 2 - 12/14/2032
- DNPS and QCNPS fuel transition project began in December 2012 when AREVA was awarded a contract for fuel beginning in 2016
- April 2013 through present AREVA has been collecting and evaluating plant data needed for fuel transition
- In June 2013 fuel transition LAR planning activities began 3
=
Background===
AREVA ATRIUM 10XM Fuel - Key Features
- 10x10 lattice - 91 fuel rod locations
- 3 X 3 Square internal water channel
- Debris filter lower tie plate
- Extensive operating experience 4
Licensing Approach
- Exelon will be asking for NRC review of the inclusion of AREVA approved generic methodologies as applicable to support licensing analyses and associated DNPS and QCNPS TS changes in support of the transition to AREVA ATRIUM 10XM fuel
- Current licensing basis will be retained for events not impacted by the change in fuel design
- Exelon will also be requesting a revision to the ATWS RPT steam dome pressure setpoint
- help mitigate (lower) the peak reactor vessel pressure following an ATWS event during the short term phase of the event
- reducing the setpoint provides additional margin by reducing the ATWS peak pressure without adversely impacting plant operation
- analysis performed using approved AREVA methodologies 5
Licensing Approach Revise TS and COLR to incorporate AREVA fuel analysis methods and setpoint changes as necessary
- Proposed TS changes will be provided with LAR
- TS 3.3.4.1, Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation, Surveillance Requirement (SR) 3.3.4.1.4.b, Reactor Vessel Steam Dome Pressure-High , revised to reflect new setpoint
- TS 5.6.5, Core Operating Limits Report (COLR), changed to add AREVA analytical methods and remove any legacy methodologies that are no longer applicable
- Applicable TS bases will be revised as necessary
- Individual COLRs will be revised as part of the reload process 6
Licensing Approach
- LAR will provide AREVA proprietary reports for QCNPS
- Mechanical Design Report
- Fuel Rod Design Report
- Thermal-Hydraulic Design Report
- Fuel Cycle Design Report
- Reload Safety Analysis Report
- LOCA Break Spectrum Analysis Report
- LOCA-ECCS Analysis MAPLHGR Limit Report
- AREVA will generate these reports for both DNPS and QCNPS, however, the LAR will only include the reports for QCNPS since the application of the methodologies is the same for both stations
- The reports for DNPS will be available prior to the first load of AREVA ATRIUM 10XM fuel at DNPS
- LAR will provide listing of current BWR Approved Topical Reports for DNPS and QCNPS that are still applicable 7
Licensing Approach
- Representative QCNPS Unit 2 Cycle Analysis Report will be provided to the NRC in support of their review of the LAR
- This representative Cycle Analysis Report is intended to support the LAR review for DNPS Units 2 and 3 and QCNPS Units 1 and 2
- Purpose of representative analyses is to demonstrate the applicability of AREVA methodology to DNPS and QCNPS at current operating conditions
- The basis for ensuring that the analyses provided will be representative for both plants is that the plants are the same in many aspects (power, flow, core size, etc.)
- Approach supports the applicability of the LAR review for DNPS Units 2 and 3 and QCNPS Units 1 and 2 8
August 27, 2013 Pre-Submittal Meeting Summary
- Exelon will utilize an established transition process followed by industry
- One License Amendment Request will be submitted for both DNPS and QCNPS
- Follow-up Issues Raised During Meeting
- Finalize approach on channel bow, verify it will be submitted as part of the LAR as a plant specific method, and come back with a proposed solution later as to how this needs to be addressed (i.e., license condition or SE summary)
- Channel Bow evaluation will be performed using approved methodologies
- The approach and results of the evaluation will be discussed in the LAR for plant specific application
- This discussion is intended to support NRC review and resolution in the subsequent safety evaluation 9
August 27, 2013 Pre-Submittal Meeting Summary
- Follow-up Issues Raised During Meeting (continued)
- Finalize approach to completing the Spent Fuel Pool (SFP) Criticality Safety Analysis (CSA) for DNPS and QCNPS (i.e., analysis for only one station and implementation under 50.59 at the other) and include as topic in future pre-submittal meetings
- A separate LAR will be submitted to address SFP CSA for DNPS Units 2 and 3 only (submittal scheduled for August 2014)
- QCNPS Units 1 and 2 criticality changes will be completed under 10 CFR 50.59 using the QCNPS rack insert application currently under review as a basis
- DNPS SFP CSA analysis will follow the same methodology used in the QCNPS rack insert application currently under review
- Status and schedule for release of the draft and final Standard Review Plan (SRP) revision for reactivity insertion accidents
- Use of 230 cal/gram as the appropriate upper limit for coolability
- LAR approach to be used depends on schedule for issuance of the revised SRP 10
August 27, 2013 Pre-Submittal Meeting Summary
- Follow-up Issues Raised During Meeting (continued)
- Address any maneuvering restrictions associated with the new fuel and how those restrictions account for current Westinghouse fuel
- Both Westinghouse fuel and ATRIUM 10XM fuel utilize barrier cladding
- There will be no changes to Westinghouse maneuvering restrictions
- Exelon intends to apply Westinghouse and AREVA specific fuel conditioning rules to Westinghouse and AREVA fuel respectively
- AREVA Critical Power Evaluator (ACE)
- Approved LTR uses an integrated peaking factor based on the local fuel rod peaking factors that could lead to non-conservative CPR predictions
- Generic ACE supplement review completed by NRC and SE issued on March 31, 2014
- Generic supplement will be used for DNPS and QCNPS fuel transition LAR submittal, Exelon specific ACE supplement will not be required 11
AREVA Technical Topics Application of Critical Power Correlation to Co-Resident Fuel
- Application of EMF-2245(P)(A) - Application of Siemens Power Corporations Critical Power Correlations to Co-Resident Fuel
- Indirect method used in the QCNPS and DNPS application
- A best estimate process is used to develop additive constants over the range of applicability
- Balanced approach to develop additive constants over the entire range of applicability
- Evaluate results over ranges in inlet enthalpy, pressure and mass flux
- ECPR is the major figure of merit
- Application of the process to OPTIMA2 fuel results in a significant trend at low mass fluxes using the AREVA correlation
- Conservative approach is applied at low mass fluxes to ensure appropriate CPR results for design, licensing and monitoring
- The conservative approach will be discussed in the LAR for plant specific application 12
AREVA Technical Topics Crud and Corrosion Aspects of Current Water Chemistry Programs
- The current coolant chemistry program and the addition of On-Line-Nobel-Chemistry (OLNC) may lead to elevated liftoff (crud and oxide)
- Increased uncertainty in liftoff conditions
- AREVA is taking a proactive approach to evaluate liftoff conditions, define a Bounding Administrative Liftoff and assess the potential consequences on fuel related licensing analyses
- Treatment of higher than normal liftoff is not explicitly described in all approved topical reports
- The evaluation process is described here for plant specific application
- Utilize plant specific data from QCNPS and Plant A to establish a liftoff baseline
- Plant A selected as a comparative reference based on similar feedwater chemistry, OLNC program, fuel rod performance, etc.
- Data includes reactor coolant and feedwater chemistry, liftoff measurements, fuel rod power history, etc.
AREVA considers all available data to make judgments for a specific plant to support the license basis 13
AREVA Technical Topics Crud and Corrosion Aspects of Current Water Chemistry Programs
- Bounding Administrative Liftoff values are defined by applying conservative adjustments to the liftoff baseline
- Conservative adjustments account for effects of OLNC and operational variations
- Bounding Administrative Liftoff must be defined for the limiting core location (Peak Liftoff) and an average fuel rod (Rod Average Liftoff)
- Peak Liftoff is needed to assess fuel rod analysis criteria
- Rod Average Liftoff is needed to assess the impact on other events/accidents
- Potential impact on fuel related licensing analysis
- Fuel rod analysis - Fast transients
- Neutronic safety analysis - Steady-State operation and slow transients
- Stability - LOCA
- Mechanical Design AREVA has an on-going surveillance program at Plant A to assess the impact of OLNC 14
AREVA Technical Topics Crud and Corrosion Aspects of Current Water Chemistry Programs
- Preliminary evaluation results
- Fuel rod analysis criteria are satisfied
- Delta-CPR for fast transients is expected to increase by approximately 0.02
- Explicitly incorporating a Bounding Administrative Liftoff in licensing analyses mitigates the risk of not establishing appropriate operating limits or exceeding established licensing limits
- The technique applied for fast transient evaluation and the evaluation results are consistent with the technique applied for an operability assessment performed in 2009 to address elevated liftoff
- Administrative penalties were applied to the MCPR operating limit
- Treatment of higher than normal liftoff using Bounding Administrative Liftoff will be discussed in the LAR for plant specific application Bounding Administrative Liftoff will be accounted for in all fast transient analyses until data becomes available that demonstrates liftoff conditions are within normal expectations.
15
Fuel Transition LAR Schedule Fuel Transition (Consistent with August 27, 2013 Meeting)
- LAR Submittal: February 2015
- Amendment Need Date: March 2016
- QCNPS Unit 2 implementation: March 2016
- DNPS Unit 3 implementation: November 2016
- QCNPS Unit 1 implementation: March 2017
- DNPS Unit 2 implementation: November 2017 16
Fuel Transition LAR Schedule Concurrent Reviews
- Spent Fuel Pool (SFP) Criticality Safety Analysis (CSA) LAR
- SFP CSA for ATRIUM 10XM will follow the same methodology used in the QCNPS rack insert application currently under review
- QCNPS SFP CSA for ATRIUM 10XM will be completed under 10 CFR 50.59
- DNPS SFP CSA for ATRIUM 10XM will be submitted as a LAR (SFP CSA LAR)
- Submittal scheduled for August 2014
- Fuel Transition LAR does not depend on NRC approval of SFP CSA LAR
- SFP CSA LAR does not depend on NRC approval of Fuel Transition LAR
- If accident dose increases by more than 10% as a result of fuel transition, AST analysis will require revision and results will be included in the fuel transition LAR 17
Summary
- Exelon transitioning to AREVA ATRIUM 10XM fuel
- Established transition process followed by industry will be used
- NRC-approved methodologies will be used for the transition analyses
- Exelon will be asking for NRC review of the inclusion of AREVA approved generic methodologies as applicable to support licensing analyses and associated DNPS and QCNPS TS changes in support of the transition to AREVA ATRIUM 10XM fuel
- One license amendment request will address both DNPS and QCNPS
- Representative QCNPS Unit 2 Cycle Analysis Report will be provided to the NRC in support of their review of the DNPS and QCNPS LAR
- Exelon and AREVA are identifying and addressing technical issues to support the NRCs review 18
DNPS/QCNPS Fuel Transition DISCUSSION 19
