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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
MONTHYEARML24310A0672024-11-0505 November 2024 Constellation NRC Pre-Submittal Meeting Slides - Proposed Alternative for Reactor Vessel Closure Stud Exam Optimization ML24270A0042024-10-0202 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 ML21165A1942021-06-16016 June 2021 Joint Annual Assessment Meeting for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation ML21165A2882021-06-16016 June 2021 Joint Annual Assessment for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation (Updated) 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 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 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 ML19168A1692019-06-18018 June 2019 June 18 Public Meeting Slides (Exelon) ML19168A1452019-06-18018 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) 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.
1 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
- JA F -C A LC-RAD-04410, Rev. 1
- FitzPatrick FHA analysis fur ther updated with two revisions by way of 10 CFR 50.59 Screening and Evaluation.
- JA F -C A LC-RAD-04410, Rev. 2 (2018) utilized higher RPF with the fuel (GNF2) in use at that time.
- JA F -C A LC-RAD-04410, Rev. 3 (2021) incorporated new GNF3 fuel type.
3 Dose Analysis Updates:
- ExistingFitzPatrick FHA analysis (JAF-C A LC-RAD- 04410, Rev. 3) models:
- 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 0.304Dose 4.68 2. 74 0.306 Limit 5 6.3 6.3Limit 5 6.3 6.3
4 Dose Analysis Updates (cont.):
- RevisedFitzPatrick FHA analysis (JAF-C A LC-RAD- 04410, Rev. 4) models:
- 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 H o u r s 24 - 104 Hours > 104 Hours Control EAB LPZ Control EAB LPZControl EAB LPZ Room Room Room GNF2 2.1 3 2.98 0.333GNF2 4.95 0.541 0.0605GNF2 4.94 0.285 0.0319 Dose Dose Dose GNF3 2.03 2.84 0. 317GNF3 4. 71 0. 51 5 0.0576GNF3 4. 71 0. 2 71 0.0303 Dose Dose Dose Limit 5 6.3 6.3Limit 5 6.3 6.3Limit 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.
6 Proposed Schedule:
- Target Submit Date: 3 August 2023
- Requested Approval Date: 3 August 2024
- Implementation Date: 2 September 2024
7