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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 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) ML23255A1042023-08-11011 August 2023 Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout ML23170A0082023-06-29029 June 2023 Decommissioning Presentation for NRC Pre-submittal Meeting, June 29, 2023 ML23157A0352023-06-0606 June 2023 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation Slides ML23094A1492023-04-11011 April 2023 Licensee Presentation on Whr Exemption Request for Public Meeting on April 11, 2023 ML23076A0442023-03-16016 March 2023 Pb U2 Scram Barrier Presentation KT Session 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) ML21095A0162021-04-0505 April 2021 2021 RIC Session T12 - DOE-Sponsored Light Water Reactor Sustainability Program 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) ML20168A3192020-06-15015 June 2020 Joint Annual Assessment Meeting for Pa/Md Power Plants - Webinar Presentation ML19318F9512019-11-20020 November 2019 Presentation Slides for November 20, 2019, Pre-Application Meeting - Request for Revision to Quality Assurance Program Internal Audit Frequency ML19317C9952019-11-12012 November 2019 In-Service Testing Supplemental Position Indication Relief Request NRC Pre-Application Meeting November 18, 2019 ML19308B9262019-11-0505 November 2019 ACRS Plant License Renewal Subcommittee - Peach Bottom Atomic Power Station Units 2 and 3 Subsequent License Renewal Safety Evaluation Report (SER) with Confirmatory Item ML19256E3852019-09-12012 September 2019 SLR Dseis Public Meeting Sept 12 2019 - Scott Portzline - Former Three Mile Island Alert Presentation ML19256E3522019-09-12012 September 2019 Slides - Peach Bottom SLRA Dseis Public Meeting - Sep 12 2019 ML19157A0542019-06-0606 June 2019 Joint Annual Assessment Meeting (Webinar) for Pennsylvania Power Plants - NRC Presentation Slides 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 ML19084A0982019-03-22022 March 2019 Potential Topics for Pre-Application Meetings for Peach Bottom SLRA 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 ML18144A6932018-05-31031 May 2018 License Amendment Request for Expanded Actions for LEFM Flow Meter Conditions - NRC Pre-Submittal Meeting May 31, 2018 ML18141A3072018-05-21021 May 2018 18 - SLR Status 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 ML17320A2002017-11-15015 November 2017 Insights from Implementing FLEX in the Peach Bottom Seismic PRA Model ML17257A1612017-09-19019 September 2017 September 19, 2017 Pre-application Public Meeting Presentation on Peach Bottom Subsequent License Renewal Application 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 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 ML12159A2662012-06-11011 June 2012 County Generating Station Pre-Application Meeting Extended Power Uprate: Replacement Steam Dryers. June 11, 2012 ML12130A0992012-05-0909 May 2012 Annual Assessment Meeting Slides Presentation Rev. 0, 2012 ML12130A1172012-05-0909 May 2012 Pb 2012 Public Mtg Attendance Sheet April 2012 ML1208701402012-03-27027 March 2012 Licensee Slides for Exelon Fleet Pre-Submittal Public Meeting 4-10-12 Licensed Operator Eligibility Requirements LAR ML12262A4762012-02-22022 February 2012 TMI Alert Portzline Presentation NUREG-0654 Public Mtg ML1110800952011-04-14014 April 2011 NRC Slides for Peach Bottom Public Meeting on April 13, 2011 ML0919803632009-08-20020 August 2009 Summary of Licensing Counterparts Meeting with Exelon Generation Company, to Discuss Licensing Practices and Processes ML11228A2312009-08-13013 August 2009 State-of-the-Art Reactor Consequence Analyses (Soarca); Semi-Annual Briefing for Commission Tas ML0918109342009-06-16016 June 2009 Hand-outs for June 16, 2009 Public Meeting with Exelon ML11228A2302009-04-14014 April 2009 State-of-the-Art Reactor Consequence Analyses; Semi-Annual Briefing for Commission Technical Assistants ML0907908502009-03-16016 March 2009 Presentation: Introduction to Nuclear Graphite Workshop 2024-01-30
[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 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) ML23251A0782023-09-0606 September 2023 DRE1 Decom Pre-Submittal Slides ML23255A1042023-08-11011 August 2023 Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout ML23170A0082023-06-29029 June 2023 Decommissioning Presentation for NRC Pre-submittal Meeting, June 29, 2023 ML23157A0352023-06-0606 June 2023 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation Slides ML23094A1492023-04-11011 April 2023 Licensee Presentation on Whr Exemption Request for Public Meeting on April 11, 2023 ML23076A0442023-03-16016 March 2023 Pb U2 Scram Barrier Presentation KT Session 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 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 ML20175A8722020-06-23023 June 2020 Risk-Informed Inservice Inspection - U.S Nuclear Regulatory Commission (NRC) - Four Element Risk-Informed Approach ML20170B0212020-06-23023 June 2020 NRC Pre-Submittal Meeting Byron Unit 2 One-Time Deferral of Reactor Pressure Vessel Head Penetration Nozzle (Rpvhpn) Inspections ML20163A6542020-06-18018 June 2020 2020 NRC Annual Assessment Webinar Presentation - Pennsylvania and Maryland Facilities (Beaver Valley, Calvert Cliffs, Limerick, Peach Bottom, Susquehanna) 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) ML20168A3192020-06-15015 June 2020 Joint Annual Assessment Meeting for Pa/Md Power Plants - Webinar Presentation ML19308B9262019-11-0505 November 2019 ACRS Plant License Renewal Subcommittee - Peach Bottom Atomic Power Station Units 2 and 3 Subsequent License Renewal Safety Evaluation Report (SER) with Confirmatory Item ML19256E3852019-09-12012 September 2019 SLR Dseis Public Meeting Sept 12 2019 - Scott Portzline - Former Three Mile Island Alert Presentation ML19256E3522019-09-12012 September 2019 Slides - Peach Bottom SLRA Dseis Public Meeting - Sep 12 2019 ML19157A0542019-06-0606 June 2019 Joint Annual Assessment Meeting (Webinar) for Pennsylvania Power Plants - NRC Presentation Slides 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 ML18275A3712018-09-25025 September 2018 Subsequent License Renewal Environmental Scoping Meeting 9-25-18 ML18141A3072018-05-21021 May 2018 18 - SLR Status 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 ML18017A1172018-01-18018 January 2018 NRC PBAPS SLRA Pre-Submittal Meeting Jan 2018 PM Copy ML17320A2002017-11-15015 November 2017 Insights from Implementing FLEX in the Peach Bottom Seismic PRA Model ML17257A1612017-09-19019 September 2017 September 19, 2017 Pre-application Public Meeting Presentation on Peach Bottom Subsequent License Renewal Application ML16106A2792016-04-15015 April 2016 Meeting Slides for License Amendment Request for Measurement Uncertainty Recapture Uprate NRC Pre-Submittal Meeting April 26, 2016 ML16077A1562016-03-22022 March 2016 Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards ML13255A3762013-09-16016 September 2013 Soarca Peach Bottom Uncertainty Analysis (UA) Acrc Briefing - Sept 2013 ML12159A2662012-06-11011 June 2012 County Generating Station Pre-Application Meeting Extended Power Uprate: Replacement Steam Dryers. June 11, 2012 ML12130A0992012-05-0909 May 2012 Annual Assessment Meeting Slides Presentation Rev. 0, 2012 ML12124A0782012-04-26026 April 2012 Power Point Presentation: Peach Bottom - Timing and Criteria for RCS Failure ML1208701402012-03-27027 March 2012 Licensee Slides for Exelon Fleet Pre-Submittal Public Meeting 4-10-12 Licensed Operator Eligibility Requirements LAR NRC-2012-0022, Comment (18) of Scott D. Portzline on Behalf of Three Mile Island Alert, on State of the Art Reactor Consequence Analyses (Soarca) Reports2012-02-28028 February 2012 Comment (18) of Scott D. Portzline on Behalf of Three Mile Island Alert, on State of the Art Reactor Consequence Analyses (Soarca) Reports ML12262A4762012-02-22022 February 2012 TMI Alert Portzline Presentation NUREG-0654 Public Mtg ML1110800952011-04-14014 April 2011 NRC Slides for Peach Bottom Public Meeting on April 13, 2011 ML1011100672010-04-20020 April 2010 NRC Slides for Peach Bottom Atomic Power Station Annual Assessment Meeting April 19, 2010 ML1011100652010-04-20020 April 2010 Slides for PBAPS Aam, April 19, 2010 ML0929400522009-10-22022 October 2009 Meeting Power Uprate Meeting Slides ML11228A2312009-08-13013 August 2009 State-of-the-Art Reactor Consequence Analyses (Soarca); Semi-Annual Briefing for Commission Tas ML0918109342009-06-16016 June 2009 Hand-outs for June 16, 2009 Public Meeting with Exelon ML11228A2302009-04-14014 April 2009 State-of-the-Art Reactor Consequence Analyses; Semi-Annual Briefing for Commission Technical Assistants 2024-01-30
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Exelon@
Generation
Background
../ Spent fuel racks in both pools contain Boraflex neutron absorber material for criticality control
../ Existing licensing basis k(inf-cold core) < 1.362 (approved 5/93)
../ 10% pool average Boraflex B-1 0 areal density loss
../ BADGER testing and RACKLIFE analyses performed to monitor condition of Boraflex
- Condition of Boraflex in individual cells dependent upon numerous factors, including gamma exposure, water chemistry and temperature
- Unit 2 racks showing slightly faster degradation than Unit 3
../ RACKLIFE analyses indicated 10 % threshold would be exceeded in Fall 2008
- 11""="==",,,,,..,,"
Exelon@
Generation LAR Submittal - Summary
~---.._-,
../ Submitted License Amendment Request (LAR) in June 2008, requesting change in Tech Spec 4.3.1.1.a
../ Determine in-rack impact of using less reactive bundle
- Choose reasonable point in time when mitigation strategy can be implemented - May 2012
- Identify design basis Reactivity Equivalent Beginning of life (REBOl) assembly that bounds future assembly designs
- Based upon RACKll FE projections, determine pool average Boraflex areal density loss
- Using REBOl, determine reactivity penalty (NETCO criticality analysis)
Exelen, Generation LAR Submission - Summary (cont.
../ Determine Tech Spec impact of using less reactive bundle
- Determine k(inf-cc) for REBOL assembly (GNF criticality analysis)
- k(inf-cc) < 1.318
- Confirm REBOL design bounds all previous fuel designs either stored or in-use at site (GNF criticality analysis)
Exelon@
Generation RAls
../ NRC Request for Additional Information (RAI) issued January 2009
../ RAI significant questions included:
- Use of RACKLIFE for determination of Boraflex degradation at PBAPS (NETCO criticality analysis)
- Use of CASMO for in-core and in-rack criticality analyses (NETCO criticality analysis)
- Use of k(eff) 0.95 for off-normal conditions (NETCO criticality analysis)
- Numerous questions regarding GNF criticality analysis
../ NRC requested 45 day response
Exelon@
Generation RAI Responses
./ Exelon removed conservatisms to meet criticality criterion of k(eff) < 0.95 without defining a new REBOL assembly
- Corrections required to criticality analyses in response to NRC RAls necessitated using lower peak reactivity bundle
./ Challenge for Exelon was to determine if pool average Boraflex B-1 0 areal density loss is compatible with chosen REBOL design
./ Using REBOL analyzed, Exelon determined B-10 areal density loss is limit for keeping k(eff) < 0.95
./ Based upon RACKLIFE analysis, NETCO determined this loss corresponded to May 201 0
Exelen.
Generation RAI Responses (cont.)
~ May 201 0 date does not allow sufficient time to procure and install new spent fuel racks
~ Exelon determined additional step required (new, lower peak reactivity REBOl) was necessary to meet May 2012
~ Exelon indicated in RAI response that additional lAR with new, lower peak reactivity REBOl would be resubmitted
Exelon@
Generation RAI Responses (eont.)
"~,
v" Responding to questions raised by NRC Staff regarding GNF criticality, Exelon:
- Reviewed and determined GNF could not support evaluating new REBOl lattice in time to respond to RAls
- Determined that inclusion of duplicate, in-pool criticality analyses was confusing
- Identified that the GNF criticality analysis was not a necessary component of the original lAR
- The only datum required from GNF was the determination of k(inf cc) < 1.318, which was necessary for the lAR submission v" In the RAI responses, Exelon indicated that the GNF document has been withdrawn
Exelon Generation Status of Boraflex Management
../ BADGER testing scheduled for both pools in 1Q201 0
../ Additional RACKLIFE calculations underway (based upon previous BADGER testing) to project Boraflex degradation through 2016
../ Budgetary estimate and estimated schedule for new, spent fuel racks obtained
../ Alternative methods of criticality control under investigation for PBAPS