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MONTHYEARML19168A1692019-06-18018 June 2019 June 18 Public Meeting Slides (Exelon) Project stage: Request ML19176A0042019-07-15015 July 2019 Summary of Meeting with Exelon Generation Company, LLC, on a Planned License Amendment Request Regarding the Relaxation of Containment Differential Pressure Requirements Project stage: Meeting 2019-06-18
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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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FitzPatrick Nuclear Power Plant Application For License Amendment Primary Containment P deletion and Torus level band margin Project Background Need for Change Technical Specification Proposal Operational Safety Benefits Supporting Documentation Lessons Learned Summary 1
FitzPatrick Nuclear Power Plant Application For License Amendment Project Background
- Primary Containment Technical Specification (TS) dP implementation (1978) was intended as temporary short-term mitigation until MARK I hydrodynamic loads were analyzed and necessary modifications completed demonstrating adequate design (NUREG 0661).
- NUREG 0661 Provided direction to restore an identified reduction in Safety Margin for, among other things, structural loading of the Mark I Torus.
- JAF maintained a Tech Spec Required Minimum Drywell to Torus Differential Pressure (Min DP) and reduced the allowable water level range in response to the Mark I Containment Long Term Program (NUREG-0661).
2
FitzPatrick Nuclear Power Plant Application For License Amendment Need for Change To sustain primary Containment dP at Fitzpatrick, it takes frequent venting of the Torus or nitrogen make-up to the Drywell. This adds operation of the Standby Gas System (SBGT) and cycling large primary containment vent and purge valves (PCIVs). This adds hours on the SBGT charcoal filters, and frequent cycles on valves along with operator actions.
The increase in Torus water level band will provide operational margin. This will reduce the number of RHR operations required to maintain Torus level during required RCIC/HPCI testing.
3 2
FitzPatrick Nuclear Power Plant Application For License Amendment Technical Specification (TS) Proposal TS-3.6.2.2 Suppression Pool water Level Increase water band from >13.88 ft and < 14 ft to < 14.25 ft TS- 3.6.2.4 Drywell-to-Suppression Chamber Differential Pressure and associated Bases Delete TS-3.3.5.1 Emergency Core Cooling System (ECCS)
Instrumentation Table 3.3.5.1-1, Function 3.e, increase allowable value from < 14.5 ft to < 14.75 ft 4
FitzPatrick Nuclear Power Plant Application For License Amendment Operational Safety Benefits Minimizes the time Primary Containment vent and purge isolation valves (PCIVs) are open for maintaining containment parameters at power.
Reduces the frequent distraction requiring Licensed operators to go to the Relay Room for containment control operations.
5
FitzPatrick Nuclear Power Plant Application For License Amendment Supporting Documentation
- Technical Report (TR) 13-0541-TR-002 Rev1.0 JAF Mark I Torus Suppression Chamber Program 0P Pool Swell Loading Determination for Normal Operation, Rev. 1, May 2018.
- GE Report 005N1724 Short-Term Containment Analysis for Zero Drywell-to-Wetwell Pressure Differential dated May 2019
- NRC Letter dated December 12, 1984, James A. FitzPatrick Nuclear Power Plant, MARK I CONTAINMENT LONG TERM PROGRAM
- NRC Letter dated January 22, 1985, Nine Mile Point Nuclear Station, Unit No.1 MARK I CONTAINMENT LONG TERM PROGRAM
- NRC Letter dated January 7, 1986, Nine Mile Point Nuclear Station, Unit No.1 SUPPRESSION POOL TEMPERATURE/PRESSURE Amendment No.76 to delete the requirement to maintain a drywell to suppression chamber differential pressure.
6
FitzPatrick Nuclear Power Plant Application For License Amendment Technical Report (TR) 13-0541-TR-002 Rev1.0 JAF Mark I Torus Suppression Chamber Program 0P Pool Swell Loading Determination for Normal Operation Analyzed the Torus structural impact for 0P and increased Torus water level
- Additional water in downcomers due to 0P normal operation
- Increased Torus maximum water volume due to level Evaluated OE, GE report and modifications
- IN 2003 water in vent pipe bowls
- SRV discharges (increased bore size / throat diameter of the main valve)
- Large and Small Bore piping systems
- Incorporated GE 005N1724 Rev 0 April 2019 results in TR Conclusion - All affected structural elements met code requirements with adequate margin and no additional modifications are required.
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FitzPatrick Nuclear Power Plant Application For License Amendment GE 005N1724 Rev 0 April 2019, Short-Term Containment Analysis for Zero Drywell-to-Wetwell Pressure Differential (PD)
Performed an updated containment short-term analysis
- GEH used the same methods that have been used previously in the current analysis of record (NEDC-33087P, Rev 001) and approved by the NRC.
- Evaluated effects on short-term containment pressure and temperature response to the limiting Design Basis Loss of Coolant Accident.
Results
- The existing pool swell, condensation oscillation and chugging loads bound the results of the GEH analysis.
- GEH results demonstrate that all existing vent thrust loads remain valid except for the downcomer mitre bend vent thrust loads (increased 8%). Imperias analysis conservatively bounds GEH calculated vent thrust loads.
- New peak drywell pressure and temperature remain bounded by the design drywell pressure and temperature (56 psig and 309 F).
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FitzPatrick Nuclear Power Plant Application For License Amendment Lessons Learned from Other Utilities NMP1 deletion of Containment dp TS Amendment 76 dated January 7, 1986 Performed Finite Element Analysis using improved computer and finite element technology Code reconciliation and use of the 1999 lower safety factor implemented in the ASME Code and approved by NRC in subsequent editions QSTF facility tested and provided results for the JAF 0.0 dP PS load case.
(NEDE 23545P, 21944P)
Use of Workbook to assist reviews (NEI 96-06) 9 9
FitzPatrick Nuclear Power Plant Application For License Amendment Summary This will benefit plant operations by minimizing cycling of containment valves, diversion of Control Room operators, operation of the Standby Gas System (SBGT) extending charcoal filter life and reduce nitrogen make-up. This will also reduce RHR system operations by increasing the Torus level band.
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