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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
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Category:Meeting Briefing Package/Handouts
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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 - 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NRC Presubmittal Meeting Slides - 6-28-23 ML23173A0462023-06-28028 June 2023 DNPS SLR Pre-submittal Meeting Presentation Rev. 1 ML23165A0242023-06-27027 June 2023 June 27, 2023, Dresden Nuclear Power Station Subsequent License Renewal Environmental Pre-application Public Meeting - NRC Slides ML23145A1322023-06-27027 June 2023 June 27, 2023, Dresden Nuclear Power Station Subsequent License Renewal Environmental Pre-application Public Meeting - Constellation 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) - 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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) 2024-08-07
[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
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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
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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.
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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