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Category:Meeting Briefing Package/Handouts
MONTHYEARML24029A1742024-01-30030 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 ML24003A1812024-01-0808 January 2024 Handout - Byron-Braidwood Core Monitoring and Support System LAR Pre-Submittal Meeting January 8,2024 ML23345A0362023-12-11011 December 2023 ATWS Uet December 11, 2023 Pre-submittal Meeting Slides 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) ML23229A4832023-08-17017 August 2023 RR 20-Year ISI Pre-Submittal NRC Meeting Handout ML23229A0132023-08-17017 August 2023 Relief Request for Alternative Requirements for Byron Unit 1 Reactor Pressure Vessel Inservice Inspection Intervals NRC Meeting Handout ML23255A1042023-08-11011 August 2023 Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout ML23163A1642023-06-12012 June 2023 2022 Braidwood/Byron End-of-Cycle Meeting Presentation ML23033A6662023-02-0909 February 2023 Summary of Public Meeting with Constellation Energy Generation, LLC (Constellation) to Discuss Its Request for Alternatives for Certain Steam Generator Weld Inspections for Calvert Cliffs 1 & 2, Byron 1 & 2, Braidwood 1 & 2, and Ginna ML23033A6672023-01-30030 January 2023 Public Call with Constellation January 30, 2023 (Slides) ML22159A3332022-06-0909 June 2022 Presentation Slides for Braidwood and Byron 2021 End of Cycle Meeting 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 ML21166A3722021-06-15015 June 2021 End-of-Cycle Meeting Presentation 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 ML20209A5322020-07-24024 July 2020 2019 Braidwood and Byron End-of-Cycle Presentation 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 ML19318F9512019-11-20020 November 2019 Presentation Slides for November 20, 2019, Pre-Application Meeting - Request for Revision to Quality Assurance Program Internal Audit Frequency 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 ML18218A1122018-08-0808 August 2018 Reactor Pressure Vessel Head Penetration Nozzle Post Peening Follow-up Inspection Relief Requests for Byron Unit 2 and Braidwood Unit 1 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 ML17296A2032017-10-0303 October 2017 Accident Tolerant Fuel Lead Test Assembly Deployment 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 ML17132A1772017-05-25025 May 2017 LAR for Control Room Cooling at Byron and Braidwood Stations ML16334A4642016-12-0505 December 2016 Westinghouse Pre-Application Meeting: License Amendment Request to Modify Byron Station Facility Operating License in Support of the Molybdenum-99 Isotope Production Project - December 5, 2016 ML16327A3702016-11-25025 November 2016 Enclosure 3: Exelon Byron Station Design (Meeting 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 ML16062A4222016-03-0202 March 2016 Meeting Slides for March 7, 2016 Public Meeting to Discuss Backfit Appeal ML15342A1012015-12-0909 December 2015 TORMIS Computer Code Methodology Public Meeting Slides ML15232A6832015-08-27027 August 2015 Stations Auxiliary Feedwater System - Unit Cross-tie License Amendment Request ML15209A9722015-07-30030 July 2015 Alloy 600 PWSCC Mitigation Plan for Reactor Vessel Head Penetration Nozzles Utilizing Cavitation Peening at Byron and Braidwood ML15133A4732015-05-20020 May 2015 Digital Upgrades of the Non-Safety Related NSSS Control Systems at Byron and Braidwood Stations ML14342A8122014-12-10010 December 2014 Presentation Slides for December 10, 2014 Meeting on Alloy 600 PWSCC Mitigation for Rvh Nozzles ML14261A1112014-09-22022 September 2014 2014 NEI Fire Protection Information Forum NRC Public Slides ML14251A4852014-09-10010 September 2014 Byron/Braidwood Auxiliary Feedwater Cross-Tie ML14051A0592014-02-20020 February 2014 2/06/2014, NRC Presentation Slides (Public Meeting with Exelon Generation Company, Nuclear Energy Industry, and Cask System Vendors to Discuss Issues with Spent Fuel Vacuum Drying Process) ML14051A0662014-02-20020 February 2014 2/06/2014, Exelon Presentation Slides (Public Meeting with Exelon Generation Company, Nuclear Energy Industry, and Cask System Vendors to Discuss Issues with Spent Fuel Vacuum Drying Process) ML13275A0402013-08-20020 August 2013 License Renewal Process and Environmental Scoping Meeting Slides ML13227A3922013-08-14014 August 2013 2012 Byron End-of-Cycle Public Meeting NRC Presentation ML13227A3892013-08-14014 August 2013 2012 Byron End-of-Cycle Public Meeting Licensee'S Presentation 2024-01-08
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24029A1742024-01-30030 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 ML24003A1812024-01-0808 January 2024 Handout - Byron-Braidwood Core Monitoring and Support System LAR Pre-Submittal Meeting January 8,2024 ML23345A0362023-12-11011 December 2023 ATWS Uet December 11, 2023 Pre-submittal Meeting Slides 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) ML23229A4832023-08-17017 August 2023 RR 20-Year ISI Pre-Submittal NRC Meeting Handout ML23229A0132023-08-17017 August 2023 Relief Request for Alternative Requirements for Byron Unit 1 Reactor Pressure Vessel Inservice Inspection Intervals NRC Meeting Handout ML23229A1722023-08-17017 August 2023 RR Pen-75 Pre-Submittal NRC Meeting Handout ML23255A1042023-08-11011 August 2023 Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout ML23163A1642023-06-12012 June 2023 2022 Braidwood/Byron End-of-Cycle Meeting Presentation 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 ML23033A6662023-02-0909 February 2023 Summary of Public Meeting with Constellation Energy Generation, LLC (Constellation) to Discuss Its Request for Alternatives for Certain Steam Generator Weld Inspections for Calvert Cliffs 1 & 2, Byron 1 & 2, Braidwood 1 & 2, and Ginna ML23033A6672023-01-30030 January 2023 Public Call with Constellation January 30, 2023 (Slides) ML22159A3332022-06-0909 June 2022 Presentation Slides for Braidwood and Byron 2021 End of Cycle Meeting ML22098A0512022-04-11011 April 2022 2 Cycle 25 High Burnup Lead Test Assembly NRC Pre-Submittal Meeting on April 22, 2022 (EPID L-2022-LRM-0022) (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 ML21166A3722021-06-15015 June 2021 End-of-Cycle Meeting Presentation 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 ML20209A5322020-07-24024 July 2020 2019 Braidwood and Byron End-of-Cycle Presentation 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) 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 ML18218A1122018-08-0808 August 2018 Reactor Pressure Vessel Head Penetration Nozzle Post Peening Follow-up Inspection Relief Requests for Byron Unit 2 and Braidwood Unit 1 ML18086A8432018-03-27027 March 2018 NUREG-1021, Revision 11 Implementation 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 ML17291B0282017-10-17017 October 2017 Submittal of Slide Package Westinghouse Encore Lead Test Rod Program Byron Unit 2 (Proprietary/Non-Proprietary) ML17296A2032017-10-0303 October 2017 Accident Tolerant Fuel Lead Test Assembly Deployment ML17132A1772017-05-25025 May 2017 LAR for Control Room Cooling at Byron and Braidwood Stations ML16334A4452016-12-0505 December 2016 Pre-submittal Meeting Byron UT RR Presentation ML16077A1562016-03-22022 March 2016 Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards ML16062A4222016-03-0202 March 2016 Meeting Slides for March 7, 2016 Public Meeting to Discuss Backfit Appeal ML15342A1012015-12-0909 December 2015 TORMIS Computer Code Methodology Public Meeting Slides ML15232A6832015-08-27027 August 2015 Stations Auxiliary Feedwater System - Unit Cross-tie License Amendment Request ML15209A9722015-07-30030 July 2015 Alloy 600 PWSCC Mitigation Plan for Reactor Vessel Head Penetration Nozzles Utilizing Cavitation Peening at Byron and Braidwood ML15204A4932015-07-23023 July 2015 Bb Station Requests for Relief for Alternate Examination Frequency ML15204A5052015-07-23023 July 2015 EPRI Tech Basis for Brd-Byr Head RR ML15133A4732015-05-20020 May 2015 Digital Upgrades of the Non-Safety Related NSSS Control Systems at Byron and Braidwood Stations ML14342A8122014-12-10010 December 2014 Presentation Slides for December 10, 2014 Meeting on Alloy 600 PWSCC Mitigation for Rvh Nozzles ML14261A1112014-09-22022 September 2014 2014 NEI Fire Protection Information Forum NRC Public Slides ML14251A4852014-09-10010 September 2014 Byron/Braidwood Auxiliary Feedwater Cross-Tie ML14051A0662014-02-20020 February 2014 2/06/2014, Exelon Presentation Slides (Public Meeting with Exelon Generation Company, Nuclear Energy Industry, and Cask System Vendors to Discuss Issues with Spent Fuel Vacuum Drying Process) ML14051A0592014-02-20020 February 2014 2/06/2014, NRC Presentation Slides (Public Meeting with Exelon Generation Company, Nuclear Energy Industry, and Cask System Vendors to Discuss Issues with Spent Fuel Vacuum Drying Process) ML13275A0402013-08-20020 August 2013 License Renewal Process and Environmental Scoping Meeting Slides 2024-01-08
[Table view] |
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Byron Station TORMIS Computer Code Methodology License Amendment Request December 9, 2015
Agenda
- Introductions and Opening Remarks
- TORMIS Computer Code Methodology use and preliminary results
- License Amendment Request
- Overview
- Proposed Updated Final Safety Analysis Report (UFSAR) Changes
- Summary and Conclusions 1
Meeting Purpose
- Outline the key attributes of the proposed License Amendment Request:
- Utilize the TORMIS computer code methodology regarding tornado missile protection
- Engage the NRC in an open and transparent dialog regarding the proposed approach to identify technical and regulatory areas of concern that warrant additional discussion to ensure they are adequately addressed in the License Amendment Request
- Provide clarification to any NRC questions 2
TORMIS Computer Code Methodology
- Exelon is proposing to use the TORMIS methodology to assess tornado missile strike probability for equipment important to safety that is currently not protected from tornado missiles at Byron Station
- TORMIS uses a Monte Carlo simulation method that simulates tornado strikes on a nuclear station
- The TORMIS analysis is performed in accordance with the requirements of:
- NRC Safety Evaluation Report (SER) (November 1983) for TORMIS; and
- RIS 2008-14, Use of TORMIS Computer Code for Assessment of Tornado Missile Protection (June 2008)
- Approximately 136 individual targets were evaluated:
- Over 27.7 billion TORMIS tornado missile simulations were performed
- The requirements for missile strike probability discussed in the TORMIS SER have been met; and the issues identified in RIS 2008-14 have been addressed 3
License Amendment Request - Overview
- NRC approval is requested for use of the TORMIS computer code methodology
- Utilization of the TORMIS computer code methodology has no impact on the Technical Specifications (TS); therefore, this License Amendment Request contains no TS changes 4
License Amendment Request - Overview (contd)
- The complete TORMIS analysis consists of the following five volumes):
- Volume I TORMIS Results
- Contains the analysis results and TORMIS control data inputs
- Volume II Tornado Hazard
- Develops the tornado hazard data inputs to TORMIS
- Volume III Plant Model and Missile Characteristics
- Contains the plant model and missile characteristics data
- Volume IV Computer Code Verification
- Includes the TORMIS verification documentation
- Volume V Finite Element Analysis
- Develops the critical missile velocities that produce crimping of the:
- Diesel AFP exhaust pipe cover plates
License Amendment Request - Overview (contd)
- Exelon intends on submitting only Volume I of the TORMIS analysis, excluding the input and output files. Volume I includes the following topics:
- Calculation Methodology
- Methodology Limitations and Conservatisms
- Major Assumptions and Engineering Judgments
- Calculation Inputs
- Details of the Calculation
- Acceptance Criteria
- Conclusion
- A complete discussion on how the Byron Station TORMIS analysis complies with the requirements of the NRC TORMIS SER and RIS 2008-14 is presented in the TORMIS analysis, Volume I, Section 9, Acceptance Criteria
- The TORMIS analysis results will now allow certain components/equipment to be credited in various design analysis that previously were not credited due to lack of tornado missile protection 6
License Amendment Request - Overview (contd)
- The availability of this equipment may now be used as input changes to existing design analysis methodologies, utilizing the normal licensee design change processes, to yield more favorable analytical results/consequences; for example:
- Operability Evaluation 13-007, Ultimate Heat Sink Capability with Loss of Service Water Cooling Tower Fans, is currently in place which demonstrates operability of the UHS assuming no Essential Service Water Cooling Tower (SXCT) fans are available for post-tornado Reactor Coolant System (RCS) cooldown
- The TORMIS analysis results demonstrate that either 2 or 3 SXCT fans survive a tornado strike on the facility
- Crediting SXCT fans in the existing the UHS post-tornado cooldown analysis will yield favorable results and allow closure of the associated Operability Evaluation 7
License Amendment Request - UFSAR Changes
- The UFSAR will be revised to reflect use of the TORMIS methodology. The following USFSAR section will be revised as appropriate:
- Section 3.5, Missile Protection 8
Summary and Conclusions
- NRC approval of the TORMIS computer code methodology will:
- Resolve the current Byron Station tornado missile protection deficiencies and provide an acceptable tool to resolve future tornado protection issues should they arise
- Demonstrate the availability of components/equipment which may be used as input changes to existing design analysis methodologies, utilizing the normal licensee design change processes, to yield favorable results/consequences; e.g., the UHS post-tornado cooldown design basis analysis
- Enable resolution and closeout of open Operability Evaluations e.g., Operability Evaluation 13-007, Ultimate Heat Sink Capability with Loss of Service Water Cooling Tower Fans 9
Questions ?
10
Byron Station TORMIS Computer Code Methodology License Amendment Request December 9, 2015
Agenda
- Introductions and Opening Remarks
- TORMIS Computer Code Methodology use and preliminary results
- License Amendment Request
- Overview
- Proposed Updated Final Safety Analysis Report (UFSAR) Changes
- Summary and Conclusions 1
Meeting Purpose
- Outline the key attributes of the proposed License Amendment Request:
- Utilize the TORMIS computer code methodology regarding tornado missile protection
- Engage the NRC in an open and transparent dialog regarding the proposed approach to identify technical and regulatory areas of concern that warrant additional discussion to ensure they are adequately addressed in the License Amendment Request
- Provide clarification to any NRC questions 2
TORMIS Computer Code Methodology
- Exelon is proposing to use the TORMIS methodology to assess tornado missile strike probability for equipment important to safety that is currently not protected from tornado missiles at Byron Station
- TORMIS uses a Monte Carlo simulation method that simulates tornado strikes on a nuclear station
- The TORMIS analysis is performed in accordance with the requirements of:
- NRC Safety Evaluation Report (SER) (November 1983) for TORMIS; and
- RIS 2008-14, Use of TORMIS Computer Code for Assessment of Tornado Missile Protection (June 2008)
- Approximately 136 individual targets were evaluated:
- Over 27.7 billion TORMIS tornado missile simulations were performed
- The requirements for missile strike probability discussed in the TORMIS SER have been met; and the issues identified in RIS 2008-14 have been addressed 3
License Amendment Request - Overview
- NRC approval is requested for use of the TORMIS computer code methodology
- Utilization of the TORMIS computer code methodology has no impact on the Technical Specifications (TS); therefore, this License Amendment Request contains no TS changes 4
License Amendment Request - Overview (contd)
- The complete TORMIS analysis consists of the following five volumes):
- Volume I TORMIS Results
- Contains the analysis results and TORMIS control data inputs
- Volume II Tornado Hazard
- Develops the tornado hazard data inputs to TORMIS
- Volume III Plant Model and Missile Characteristics
- Contains the plant model and missile characteristics data
- Volume IV Computer Code Verification
- Includes the TORMIS verification documentation
- Volume V Finite Element Analysis
- Develops the critical missile velocities that produce crimping of the:
- Diesel AFP exhaust pipe cover plates
License Amendment Request - Overview (contd)
- Exelon intends on submitting only Volume I of the TORMIS analysis, excluding the input and output files. Volume I includes the following topics:
- Calculation Methodology
- Methodology Limitations and Conservatisms
- Major Assumptions and Engineering Judgments
- Calculation Inputs
- Details of the Calculation
- Acceptance Criteria
- Conclusion
- A complete discussion on how the Byron Station TORMIS analysis complies with the requirements of the NRC TORMIS SER and RIS 2008-14 is presented in the TORMIS analysis, Volume I, Section 9, Acceptance Criteria
- The TORMIS analysis results will now allow certain components/equipment to be credited in various design analysis that previously were not credited due to lack of tornado missile protection 6
License Amendment Request - Overview (contd)
- The availability of this equipment may now be used as input changes to existing design analysis methodologies, utilizing the normal licensee design change processes, to yield more favorable analytical results/consequences; for example:
- Operability Evaluation 13-007, Ultimate Heat Sink Capability with Loss of Service Water Cooling Tower Fans, is currently in place which demonstrates operability of the UHS assuming no Essential Service Water Cooling Tower (SXCT) fans are available for post-tornado Reactor Coolant System (RCS) cooldown
- The TORMIS analysis results demonstrate that either 2 or 3 SXCT fans survive a tornado strike on the facility
- Crediting SXCT fans in the existing the UHS post-tornado cooldown analysis will yield favorable results and allow closure of the associated Operability Evaluation 7
License Amendment Request - UFSAR Changes
- The UFSAR will be revised to reflect use of the TORMIS methodology. The following USFSAR section will be revised as appropriate:
- Section 3.5, Missile Protection 8
Summary and Conclusions
- NRC approval of the TORMIS computer code methodology will:
- Resolve the current Byron Station tornado missile protection deficiencies and provide an acceptable tool to resolve future tornado protection issues should they arise
- Demonstrate the availability of components/equipment which may be used as input changes to existing design analysis methodologies, utilizing the normal licensee design change processes, to yield favorable results/consequences; e.g., the UHS post-tornado cooldown design basis analysis
- Enable resolution and closeout of open Operability Evaluations e.g., Operability Evaluation 13-007, Ultimate Heat Sink Capability with Loss of Service Water Cooling Tower Fans 9
Questions ?
10