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| | number = ML17306A084 | | | number = ML17306A084 |
| | issue date = 11/06/2017 | | | issue date = 11/06/2017 |
| | title = 11/06/2017, Meeting Slide for Teleconference with Exelon Generation Company, LLC - Criticality Analysis for NMP1 Boraflex Racks: No Boraflex Credit, 3 Out of 4 Loading, and Cell Blockers | | | title = Meeting Slide for Teleconference with Exelon Generation Company, LLC - Criticality Analysis for NMP1 Boraflex Racks: No Boraflex Credit, 3 Out of 4 Loading, and Cell Blockers |
| | author name = | | | author name = |
| | author affiliation = Exelon Generation Co, LLC | | | author affiliation = Exelon Generation Co, LLC |
Latest revision as of 20:19, 2 December 2019
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EPID:L-2017-LRM-0042, Meeting Slide for Teleconference with Exelon Generation Company, LLC - Criticality Analysis for NMP1 Boraflex Racks: No Boraflex Credit, 3 Out of 4 Loading, and Cell Blockers (Open) |
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MONTHYEARML17265A7672017-09-25025 September 2017 Notice of Forthcoming Closed Teleconference with Exelon Generation Company, LLC to Discuss Planned License Amendment Request to Remove Boraflex Credit for Nine Mile Point Nuclear Station, Unit 1 Project stage: Meeting ML17297A6292017-10-26026 October 2017 Summary of Meeting with Exelon Generation Company, LLC, on Planned Submittal of License Amendment Request to Remove Boraflex Credit and Use of Cell Blockers Project stage: Meeting ML17306A0842017-11-0606 November 2017 Meeting Slide for Teleconference with Exelon Generation Company, LLC - Criticality Analysis for NMP1 Boraflex Racks: No Boraflex Credit, 3 Out of 4 Loading, and Cell Blockers Project stage: Request ML17328A4422017-12-0505 December 2017 Summary of Teleconference with Exelon Generation Company, LLC on Planned Submittal of License Amendment Request to Remove Boraflex Credit and Use of Cell Blockers Project stage: Meeting 2017-11-06
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Category:Meeting Briefing Package/Handouts
MONTHYEARML24137A1882024-05-16016 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 ML23157A0352023-06-0606 June 2023 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation Slides ML23103A4072023-04-13013 April 2023 Presentation Slides for Information Call on 4/13/23 N2E Recirc Discharge Nozzle Weld Repair 2nd Request for Alternative ML22301A0132022-11-0303 November 2022 Pre-Submittal Meeting Presentation Slides - Risk Informed Completion Time (TSTF-505) and Risk Informed Categorization and Treatmentof SSCs (10 CFR 50.69) Proposed License Amendments ML22305A5922022-11-0303 November 2022 Pre-Submittal Meeting Presentation Slides - Risk Informed Completion Time (TSTF-505) and Risk Informed Categorization and Treatmentof SSCs (10 CFR 50.69) Proposed License Amendments-Updated ML22222A1122022-08-0404 August 2022 NMP1 Torus Corrosion Presentation for August 2022 Final 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) 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 ML20175A8722020-06-23023 June 2020 Risk-Informed Inservice Inspection - U.S Nuclear Regulatory Commission (NRC) - Four Element Risk-Informed Approach 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) ML20098D5082020-04-0909 April 2020 AST LOCA Approach to Elemental Iodine Removal - 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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 ML17325A2772017-11-28028 November 2017 November 28, 2017 Pre-Submittal Teleconference Re Planned TSTF-542 LAR Presentation ML17306A0842017-11-0606 November 2017 Meeting Slide for Teleconference with Exelon Generation Company, LLC - Criticality Analysis for NMP1 Boraflex Racks: No Boraflex Credit, 3 Out of 4 Loading, and Cell Blockers 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 ML16153A3452016-06-0101 June 2016 Sign in Sheet and Handout 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 ML14084A5342014-03-26026 March 2014 Nrc/Nei Presentation Slides: 13-02 OIP Template Update ML13340A0912013-11-0101 November 2013 Regulatory Conference/Public Meeting - Loss of Shutdown Cooling - Ceng Presentation/Slides ML13059A3742013-03-13013 March 2013 Summary of Category 1 Public Meeting with Nine Mile Point Nuclear Station, Unit 2 Representatives to Discus Planned Amendment Request on Implementation of Mellla+ ML1212100442012-04-0303 April 2012 Meeting Slides - NFPA-805 Pre-Application Meeting with NRC Staff April 3, 2012 ML1113605612011-05-16016 May 2011 NRC Meeting Slides, Nine Mile Point & Fitzpatrick 2011 Annual Assessment Meeting ML0926506592009-09-15015 September 2009 Slides from the Public Meeting with Constellation Energy - Nine Mile Point ISFSI Presentation ML0913400442009-05-14014 May 2009 Annual Assessment Meeting Sign-in Sheet, April 30, 2009 ML0827705652008-10-27027 October 2008 Extended Power Uprate Pre-Application Meeting Slides ML0634800282006-12-0404 December 2006 Slides, Nine Mile Point 1 Alternate Source Term, from Nrc/Constellation Energy Meeting ML0619102902006-03-27027 March 2006 03/27/2006 Powerpoint Presentation - Nine Mile Point License Renewal NMP1 Drywell 2024-05-16
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24137A1882024-05-16016 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 ML23157A0352023-06-0606 June 2023 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation Slides ML23103A4072023-04-13013 April 2023 Presentation Slides for Information Call on 4/13/23 N2E Recirc Discharge Nozzle Weld Repair 2nd Request for Alternative ML23080A2972023-03-21021 March 2023 Presentation Slides for Information Call on 3/21/23 N2E Recirc Discharge Nozzle Weld Repair Request for Alternative 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 ML22301A0132022-11-0303 November 2022 Pre-Submittal Meeting Presentation Slides - Risk Informed Completion Time (TSTF-505) and Risk Informed Categorization and Treatmentof SSCs (10 CFR 50.69) Proposed License Amendments ML22305A5922022-11-0303 November 2022 Pre-Submittal Meeting Presentation Slides - Risk Informed Completion Time (TSTF-505) and Risk Informed Categorization and Treatmentof SSCs (10 CFR 50.69) Proposed License Amendments-Updated ML22222A1122022-08-0404 August 2022 NMP1 Torus Corrosion Presentation for August 2022 Final 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 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 ML20175A8722020-06-23023 June 2020 Risk-Informed Inservice Inspection - U.S Nuclear Regulatory Commission (NRC) - Four Element Risk-Informed Approach 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 ML20098D5082020-04-0909 April 2020 AST LOCA Approach to Elemental Iodine Removal - NRC Public Meeting on RAI 6 - April 9, 2020 ML20022A0262020-01-22022 January 2020 NEI Presentation Status Update for Ropte Short Term Action Plan: Removed Planned Unavailability for Mitigating Systems Performance Index ML19158A1202019-06-10010 June 2019 Rict & 50.69 LARs NRC Pre-submittal Meeting ML19133A0912019-04-22022 April 2019 Supplement to Containment Oxygen Concentration License Amendment Request 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 ML17325A2772017-11-28028 November 2017 November 28, 2017 Pre-Submittal Teleconference Re Planned TSTF-542 LAR Presentation ML17306A0842017-11-0606 November 2017 Meeting Slide for Teleconference with Exelon Generation Company, LLC - Criticality Analysis for NMP1 Boraflex Racks: No Boraflex Credit, 3 Out of 4 Loading, and Cell Blockers ML16153A3442016-06-0101 June 2016 Oswego Chamber of Commerce Assessment Meeting Presentation ML16077A1562016-03-22022 March 2016 Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards ML14084A5342014-03-26026 March 2014 Nrc/Nei Presentation Slides: 13-02 OIP Template Update ML13340A0912013-11-0101 November 2013 Regulatory Conference/Public Meeting - Loss of Shutdown Cooling - Ceng Presentation/Slides ML13059A3742013-03-13013 March 2013 Summary of Category 1 Public Meeting with Nine Mile Point Nuclear Station, Unit 2 Representatives to Discus Planned Amendment Request on Implementation of Mellla+ ML1212100442012-04-0303 April 2012 Meeting Slides - NFPA-805 Pre-Application Meeting with NRC Staff April 3, 2012 ML1113605612011-05-16016 May 2011 NRC Meeting Slides, Nine Mile Point & Fitzpatrick 2011 Annual Assessment Meeting ML0926506592009-09-15015 September 2009 Slides from the Public Meeting with Constellation Energy - Nine Mile Point ISFSI Presentation ML0827705652008-10-27027 October 2008 Extended Power Uprate Pre-Application Meeting Slides ML0827503872008-09-29029 September 2008 Enclosure 2 Meeting Slides ML0811403012008-04-23023 April 2008 NRC Annual Performance Assessment Meeting ML0807901872008-03-18018 March 2008 NRC Annual Performance Assessment Slides, 2007 Reactor Oversight Program ML0712704232007-04-24024 April 2007 Constellation Slides - Nine Mile Point Meeting Annual Assessment Summary 2006-07 ML0710100842007-04-10010 April 2007 Slides for 04/24/2007 Nine Mile Point Annual Assessment Meeting ML0634800282006-12-0404 December 2006 Slides, Nine Mile Point 1 Alternate Source Term, from Nrc/Constellation Energy Meeting ML0630003542006-09-26026 September 2006 Slides for Constellation Energy Nine Mile Point 2 Extended Power Uprate Meeting 2024-05-16
[Table view] |
Text
Criticality Analysis for NMP1 Boraflex Racks: No Boraflex Credit, 3 out of 4 Loading, and Cell Blockers November 6, 2017 Pre-Submittal Briefing
Introduction
- NMP1 Spent Fuel Pool (SFP) 2 Boraflex Racks + 14 Boral Racks
Concerns of Boraflex degradation: proactively and conservatively address
Perform a new criticality analysis for the 2 Boraflex racks o No credit is taken for the residual Boraflex 3 out of 4 loading pattern is used to reduce reactivity o Permanent Cell Blockers will be installed in accordance with NEI 12-16 No changes were made on the Boral racks Revision to Technical Specifications (TS) 5.5 will be made on non-poison flux trap racks and Boraflex racks to reflect the current pool configuration and description in the current UFSAR.
1 NMP1 Criticality Analysis
New Criticality Analysis Overview
- Consistent with the Peak Reactivity Methodology Previously Approved Quad Cities: ML14346A306/ML16231A131 Dresden: ML15343A126
- Computer Codes: CASMO & MCNP5-1.51 2 NMP1 Criticality Analysis
New Criticality Analysis Overview (Contd)
- Analysis Results Summary Permanent cell blockers will be installed in specific locations in Boraflex racks o Maintains a sufficiently low reactivity area along interface with Boral racks o Precludes the need to leave an entire empty row along the interface with Boral racks Misload accident is precluded o Peak reactivity lattice is used o The empty cells are blocked with cell blockers Final K-eff o 0.9390: all normal/accident conditions and uncertainties and biases o Margin to regulatory limit of 0.011 o Includes an additional Administrative margin of 0.01 (biases) in SCCG value o Supports application of current TS limits for Boral Racks to Boraflex racks Achieves commonality and consistency between Boral and Boraflex racks 3 NMP1 Criticality Analysis
Criticality Safety Analysis Specifics
- Boraflex Storage Rack Design 4 NMP1 Criticality Analysis
Criticality Safety Analysis Specifics (Contd)
- SW Corner Storage Rack Configuration in SFP 5 NMP1 Criticality Analysis
Criticality Safety Analysis Specifics (Contd)
- No poison so maximum temperature is used (100 C, also bounds accident condition)
- Cell blockers are not modeled explicitly; steel is an absorber.
- Eccentric positioning and channel inclusion treated as a bias (bounding case is no channel, all eccentric to rack center; bias = 0.0182)
- Peak reactivity isotopic compositions from CASMO depletion calculations considering bounding Core Operating Parameters (COP)
- All reactivity calculations for K-eff determination are performed using MCNP5-1.51
- Accident conditions evaluated: Dropped bundle outside the racks, rack movement, pool temperature.
6 NMP1 Criticality Analysis
Criticality Safety Analysis Specific Results
- All actual as-built NMP1 fuel bundle lattices evaluated.
- Most reactive as-built actual lattice studies show that the negative reactivity introduced by the cell blockers > 0.11 delta-k
- Maximum K-calc for as-built lattices in the Boraflex racks with cell blockers is ~ 0.82 7 NMP1 Criticality Analysis
Interface Evaluation
- Boraflex Racks Located in the SW corner and adjacent to 14 Boral racks along the east and north Old flux trap style design: Flux traps (1.72) are parallel to N-S The geometry of the Boraflex racks with cell blockers creates a low reactivity configuration (Max K-calc=0.82 for as-built lattices).
- Boral Racks Boral neutron absorber panels on the outside of the Boral racks along the interface significantly reduce reactivity in the interface area.
- Interface gaps East interface gap is 3.15 and north interface gap is 1.9. Both gaps are larger than the Flux traps in Boraflex racks and hence further reduce the reactivity in the interface area.
8 NMP1 Criticality Analysis
Interface Evaluation (Contd)
- Cell to Cell Pitch Both racks are nearly identical for the N-S cell pitches.
E-W cell pitches are 7.805 for Boraflex and 6.06 for Boral racks.
Therefore, the racks on one side of the interface can be assumed to be a continuation of the rack on the other side of the interface.
- Max SFP temperature used, which yields 0.0144 delta-k over Min SFP temperature
- The bounding reactivity of the Boraflex rack used to show compliance with the regulatory requirements is K-calc = 0.8697
Conclusion:
The interface between the Boraflex and Boral racks in the SFP is an area of low importance (i.e., low reactivity) and no further evaluations are required.
9 NMP1 Criticality Analysis
TS Evaluation
- The Boral rack TS requires that all fuel lattices have a maximum enrichment of 4.6% U-235 and a SCCG 1.31.
- Will apply Boral racks TS to Boraflex racks.
- Super lattices were created from the existing most reactive as-built lattices to bound the above TS requirements.
Enrichment of each pin was increased to 4.6% U-235 and Gd rod loading was varied until the super lattice SCCG was slightly above 1.31 Each super lattice has a unique Gd loading that yields a SCCG of at least 1.31
- Design Basis Lattice The most reactive lattice (peak reactivity in the Boraflex rack) of all super lattices Used to perform the analysis calculations to show compliance with regulatory requirements (i.e., determination of Total Correction Factor (TCF))
10 NMP1 Criticality Analysis
Final Analysis Results
- Gray Boxes proprietary 11 NMP1 Criticality Analysis
Conclusions
The effective neutron multiplication factor (Keff) is less than or equal to 0.95 for all normal and accident conditions with 95% probability at a 95% confidence level.
- Supports application of current TS limits for Boral Racks to Boraflex racks Lattice initial maximum planar average enrichment (MPAE) 4.6 wt% U-235 Lattice standard cold core geometry (SCCG) Kinf 1.31
- Questions and Comments Thanks 12 NMP1 Criticality Analysis