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Category:Meeting Briefing Package/Handouts
MONTHYEARML24270A0042024-10-0202 October 2024 Fitpatrick Pre-submittal Meeting Slides, October 2, 2024 ML24137A1882024-05-16016 May 2024 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation Slides ML24100A7672024-04-11011 April 2024 Meeting Slides - Preapplication with Constellation on Planned Fleet Alternative Request to Adopt OMN-2 ML24089A2612024-04-0909 April 2024 Slides - Constellation - Pre-Application Regarding Hooded Masks 4/9/2024 Meeting Slides (L-2024-LLM-0041) ML24029A1742024-01-30030 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) ML23262B2602023-09-19019 September 2023 Slides - Constellation - Pre-Application EP 9/25/2023 Meeting Handout ML23255A1042023-08-11011 August 2023 Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout ML23174A0012023-06-23023 June 2023 Pre-submittal Meeting Slides Regarding Update to the FitzPatrick Fuel Handling Accident Analysis with Impacts to Technical Specifications, June 26, 2023 ML23157A0352023-06-0606 June 2023 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation Slides ML22187A0652022-06-0808 June 2022 Joint Annual Assessment Meeting for Pa/Md/Nj/Ny Nuclear Power Plants - NRC Presentation 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 ML21165A2882021-06-16016 June 2021 Joint Annual Assessment for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation (Updated) ML21165A1942021-06-16016 June 2021 Joint Annual Assessment Meeting for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation ML20269A3452020-09-28028 September 2020 Pre-submittal Meeting for Request for One-Time Exemption from 10 CFR Part 50, Appendix E, Biennial EP Exercise (Offsite) Due to COVID-19- Entergy Presentation Slides ML20261G7322020-09-16016 September 2020 Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a 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 ML19168A1452019-06-18018 June 2019 June 18 Public Meeting Slides (Exelon) ML19168A1692019-06-18018 June 2019 June 18 Public Meeting Slides (Exelon) ML19168A1592019-06-17017 June 2019 June 20 Public Meeting Slides (Exelon) 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 ML18292A5252018-10-19019 October 2018 License Amendment Request: Pre-submittal Meeting ML18255A0142018-09-12012 September 2018 BWROG Presentation Slides for Public Meeting Sept 12 2018 ML18255A0102018-09-12012 September 2018 NRC Slides for Target Rock Public Meeting ML18107A3342018-04-10010 April 2018 Tech Spec 3.3.5.2a Change Pre-Submittal Meeting Presentation Slides 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 ML17047A6212017-02-14014 February 2017 Exit Meeting for the 4th Quarter 2016 ML14169A0722014-06-19019 June 2014 Entergy Public Meeting Presentation Slides ML11350A1242011-12-0101 December 2011 ROP Monthly Public Meeting Dec 2011 NEI Handouts Enclosure 2 ML1117906392011-06-28028 June 2011 Summary of Meeting with Entergy Operations Inc ML1113605612011-05-16016 May 2011 NRC Meeting Slides, Nine Mile Point & Fitzpatrick 2011 Annual Assessment Meeting ML1009900312010-04-13013 April 2010 Entergy Nuclear Operations (Entergy): Meeting Presentation 2009 Nuclear Safety Culture Assessment Meeting ML0913400442009-05-14014 May 2009 Annual Assessment Meeting Sign-in Sheet, April 30, 2009 ML0909100632009-03-31031 March 2009 Entergy Operations, Inc., Project Planning Slides for March 31, 2009, Nrc/Entergy Pre-Application Meeting - Power Uprates ML0810601032008-04-0303 April 2008 Slides from the 2008 James A. FitzPatrick Annual Assessment Meeting ML0731902202007-11-0707 November 2007 Meeting Handout Fitzpatrick GNF2 Introduction at Entergy ML0725306142007-09-21021 September 2007 Public Meeting Summary on the Reactor Oversight Process ML0726905292007-09-0505 September 2007 ACRS License Renewal Subcommittee Presentation September 5, 2007 ML0726905372007-09-0505 September 2007 License Renewal Safety Evaluation Report Staff Presentation to the ACRS ML0722600232007-08-0101 August 2007 Slides for Public Meeting Regarding the Draft SEIS for FitzPatrick - Aug 01, 2007 ML0716603032007-06-15015 June 2007 Aam Slides (NRC) 2024-05-16
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24270A0042024-10-0202 October 2024 Fitpatrick Pre-submittal Meeting Slides, October 2, 2024 ML24137A1882024-05-16016 May 2024 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation Slides ML24100A7672024-04-11011 April 2024 Meeting Slides - Preapplication with Constellation on Planned Fleet Alternative Request to Adopt OMN-2 ML24089A2612024-04-0909 April 2024 Slides - Constellation - Pre-Application Regarding Hooded Masks 4/9/2024 Meeting Slides (L-2024-LLM-0041) ML24029A1742024-01-30030 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) ML23262B2602023-09-19019 September 2023 Slides - Constellation - Pre-Application EP 9/25/2023 Meeting Handout ML23255A1042023-08-11011 August 2023 Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout ML23174A0012023-06-23023 June 2023 Pre-submittal Meeting Slides Regarding Update to the FitzPatrick Fuel Handling Accident Analysis with Impacts to Technical Specifications, June 26, 2023 ML23157A0352023-06-0606 June 2023 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation 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 ML22187A0652022-06-0808 June 2022 Joint Annual Assessment Meeting for Pa/Md/Nj/Ny Nuclear Power Plants - NRC Presentation 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 ML21165A2882021-06-16016 June 2021 Joint Annual Assessment for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation (Updated) ML21165A1942021-06-16016 June 2021 Joint Annual Assessment Meeting for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation ML21162A3322021-06-11011 June 2021 BWR Fleet Relief Request Associated with RPV Instrument Nozzle Repairs ML20269A3452020-09-28028 September 2020 Pre-submittal Meeting for Request for One-Time Exemption from 10 CFR Part 50, Appendix E, Biennial EP Exercise (Offsite) Due to COVID-19- Entergy Presentation Slides ML20261G7322020-09-16016 September 2020 Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a 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) ML20161A1002020-06-0909 June 2020 James F. FitzPatrick Nuclear Power Plant - Figure 1, Current Lineup, and Figure 2, Revised Lineup, for Pre-Submittal Meeting Between NRC and Exelon for Planned License Amendment Request to Modify TS SR 3.6.1.3 - June 9, 2020 ML20157A1522020-06-0404 June 2020 Pre-Submittal Meeting Between NRC and Exelon for Planned License Amendment Request to Modify Technical Specification 3.6.1.3 Surveillance Requirement 3.6.1.3 - June 9, 2020 ML19168A1452019-06-18018 June 2019 June 18 Public Meeting Slides (Exelon) ML19168A1692019-06-18018 June 2019 June 18 Public Meeting Slides (Exelon) ML19168A1592019-06-17017 June 2019 June 20 Public Meeting Slides (Exelon) 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 ML18255A0142018-09-12012 September 2018 BWROG Presentation Slides for Public Meeting Sept 12 2018 ML18107A3342018-04-10010 April 2018 Tech Spec 3.3.5.2a Change Pre-Submittal Meeting Presentation Slides ML18075A1232018-03-20020 March 2018 Entergy Nuclear Operations - March 20, 2018, Presentation Slides for Surveillance Frequency Control Program, UFSAR Change Considerations ML17047A6212017-02-14014 February 2017 Exit Meeting for the 4th Quarter 2016 ML14169A0722014-06-19019 June 2014 Entergy Public Meeting Presentation Slides ML1113605612011-05-16016 May 2011 NRC Meeting Slides, Nine Mile Point & Fitzpatrick 2011 Annual Assessment Meeting ML0909100632009-03-31031 March 2009 Entergy Operations, Inc., Project Planning Slides for March 31, 2009, Nrc/Entergy Pre-Application Meeting - Power Uprates ML0810601032008-04-0303 April 2008 Slides from the 2008 James A. FitzPatrick Annual Assessment Meeting ML0810600902008-04-0303 April 2008 NRC Slides for the 2008 FitzPatrick Annual Assessment Meeting ML0808400822008-03-0606 March 2008 ACRS Fitzparick Lr Presentation ML0808400482008-03-0606 March 2008 ACRS NRC, Fitzpatrick Lr SER ML0731902202007-11-0707 November 2007 Meeting Handout Fitzpatrick GNF2 Introduction at Entergy ML0725306142007-09-21021 September 2007 Public Meeting Summary on the Reactor Oversight Process ML0726905292007-09-0505 September 2007 ACRS License Renewal Subcommittee Presentation September 5, 2007 ML0726905372007-09-0505 September 2007 License Renewal Safety Evaluation Report Staff Presentation to the ACRS ML0722600232007-08-0101 August 2007 Slides for Public Meeting Regarding the Draft SEIS for FitzPatrick - Aug 01, 2007 ML0721405662007-06-21021 June 2007 License Renewal Exit Meeting Slides - June 21, 2007 ML0716603202007-06-15015 June 2007 2007 Entergy'S Slide Presentation, Journey to Excellence, from NRC Public Meeting to Discuss FitzPatrick Aam ML0716603032007-06-15015 June 2007 Aam Slides (NRC) ML0733409182007-05-31031 May 2007 05/31/2007 Presentation by J. Cudsworth NRC Treatment of Issues Other than Category 2 Issues for License Renewal 2024-05-16
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James A. FitzPatrick License Amendment Request: Pre-submittal Meeting Update to the FitzPatrick Fuel Handling Accident Analysis with Impacts to Technical Specifications Date: June 26, 2023 Presenter: Abul Hasanat, Christopher Staum
Proposed Change:
- The FitzPatrick Fuel Handling Accident (FHA) analysis is being revised to account for two major changes to support the transition from a Triangular Mast to an NF-500 Mast in 2024.
- These changes would increase dose consequences sufficiently that prior NRC approval is required.
-A single updated radial peaking factor (RPF) for both GNF2 & GNF3 fuel.
-Redefinition of recently irradiated fuel as it relates to Secondary Containment (SC) and Control Room Ventilation (CREVAS) operability.
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Proposed Change (cont.):
- Technical Specification (TS) impacted by way of TS Bases updates:
-Recently Irradiated Fuel definition changing from 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> to 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:
& #4: RB Exhaust Radiation & Refueling Floor Exhaust Radiation
-Recently Irradiated Fuel definition changing from 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> to 104 hours0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br />
- TS 3.7.4, Control Room Air Conditioning (AC) System
- TS 3.8.2, Electrical Power Systems/AC Sources Shutdown
- TS 3.8.5, Electrical Power Systems/DC Sources Shutdown
- TS 3.8.8, Electrical Power Systems/Distribution Systems-Shutdown 2
FitzPatrick FHA Licensing Basis History
- FitzPatrick FHA analysis further updated with two revisions by way of 10 CFR 50.59 Screening and Evaluation.
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Dose Analysis Updates:
- Both the Triangular Mast & NF-500 Mast with differing RPF
- Both GNF2 & GNF3 Fuel with differing RPF
- Credit for SC from 0 - 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> post reactor shutdown.
- Requires automatic action within 2 minutes.
0 - 96 Hours >96 Hours Control Room EAB LPZ Control Room EAB LPZ Dose 1.95 2.72 0.304 Dose 4.68 2.74 0.306 Limit 5 6.3 6.3 Limit 5 6.3 6.3 4
Dose Analysis Updates (cont.):
- Only the NF-500 Mast with fixed RPF (1.70)
- Both GNF2 & GNF3 Fuel with fixed RPF (1.70)
- Credit for CREVAS from 24 - 104 hours0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br /> post reactor shutdown.
- Requires Operator manual action within 8 minutes.
- Credit for SC from 0 - 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> post reactor shutdown.
- Requires automatic action within 2 minutes.
0 - 24 Hours 24 - 104 Hours > 104 Hours Control EAB LPZ Control EAB LPZ Control EAB LPZ Room Room Room GNF2 2.13 2.98 0.333 GNF2 4.95 0.541 0.0605 GNF2 4.94 0.285 0.0319 Dose Dose Dose GNF3 2.03 2.84 0.317 GNF3 4.71 0.515 0.0576 GNF3 4.71 0.271 0.0303 Dose Dose Dose Limit 5 6.3 6.3 Limit 5 6.3 6.3 Limit 5 6.3 6.3 5
Technical Justification:
- Fuel Mast and RPF modeling:
- Utilization of the NF-500 mast for refueling is planned starting with refueling outage J1R26 (September 2024). The existing FHA analysis does not support the RPF with current core loading strategies and the NF-500 mast. Therefore, changes to the RPF and elimination of the triangular mast were introduced into the FHA analysis.
- Transition of crediting the SC to CREVAS after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> was determined to provide relief for outage planning and management. The existing FHA does not credit CREVAS. Modeling of CREVAS at 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> necessitates an operator manual action of 8 minutes.
- Additional cases at 104 hours0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br /> post reactor shutdown demonstrated that neither SC or CREVAS are needed to produce acceptable FHA results.
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Proposed Schedule:
- Target Submit Date: 3 August 2023
- Requested Approval Date: 3 August 2024
- Implementation Date: 2 September 2024 7