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| | issue date = 08/18/2014 | | | issue date = 08/18/2014 |
| | title = Enclosure - Example AMP - July 17, 2014, Summary of Meeting with Exelon Corporation to Discuss Request for Additional Information No. 4 to the Calvert Cliffs ISFSI License Renewal Application (Docket No. 72-08) TAC L24475 | | | title = Enclosure - Example AMP - July 17, 2014, Summary of Meeting with Exelon Corporation to Discuss Request for Additional Information No. 4 to the Calvert Cliffs ISFSI License Renewal Application (Docket No. 72-08) TAC L24475 |
| | author name = Dunn D S | | | author name = Dunn D |
| | author affiliation = NRC/NMSS/SFST | | | author affiliation = NRC/NMSS/SFST |
| | addressee name = | | | addressee name = |
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| | docket = 05000317, 05000318, 07200008 | | | docket = 05000317, 05000318, 07200008 |
| | license number = | | | license number = |
| | contact person = Goshen J M | | | contact person = Goshen J |
| | case reference number = TAC L24475 | | | case reference number = TAC L24475 |
| | package number = ML14230A903 | | | package number = ML14230A903 |
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| {{#Wiki_filter:AgingManagementProgramAging Management Program Example for Stress Corrosion CrackingDarrellS.DunnDarrell S. DunnMeeting to Discuss the Request for Additional Information Responses Regarding the Calvert Cliffs Independent Spent pggppFuel Storage Facility License Renewal July 17, 2014 Stress Corrosion Cracking BackgroundInformationBackground Information *304 and 316 Stainless steels are susceptibletochloridestresssusceptible to chloride stress corrosion cracking (SCC)-Sensitization from welding increases susceptibility-Crevice and pitting corrosion can be precursors to SCC-SCC possible with low surface chloride concentrations 2/3oftherequirements*Welded stainless steel canisters have sufficient through wall tensile residual stresses for SCCAthiSCCfldd2/3 of the requirements for SCC are present in welded stainless steel *Atmospheric SCC of welded stainless steels has been observed-Component failures in 16-33 years-Estimated crack growth rates of 0.11 canisters gto 0.91 mm/yr2 Regulatory Basis*10 CFR 72.42(a), 72.240(c): TLAAs that demonstrate that ITS SSCs will continue to perform their intended function for the period of extended operation.AdescriptionoftheAMPformanagementofissuesassociatedA description of the AMP for management of issues associated with aging that could adversely affect ITS SSCs.*Guidance: NUREG-1927 AMP Elements:1.Scope of the Program2.Preventive Actions 3.Parameters Monitored/Inspected6.Acceptance Criteria7.Corrective Actions 8.Confirmation Process 4.Detection of Aging Effects 5.Monitoring and Trending9.Administrative Controls10.Operating Experience3 AMP Element 1 ScopeoftheProgramScope of the Program NUREG-1927: The scope of the program should include the specific structuresandcomponentssubjecttoanAMR*Welded stainless steel dry storage canistersFabricationandclosureweldsstructures and components subject to an AMR-Fabrication and closure welds -Weld heat affected zones-LocationswheretemporarysupportsorfixtureswereLocations where temporary supports or fixtures were attached by welding-Crevice locations -Surface areas where atmospheric deposits preferentially occursSurfaceareaswithalowerthanaveragetemperature-Surface areas with a lower than average temperature 4 AMP Element 2PreventativeActionsPreventative ActionsNUREG-1927: Preventive actions should mitigate or prevent the applicableagingeffects*Aging Management Program (AMP) is for conditionmonitoringapplicable aging effectscondition monitoring. -Preventative actions are not presently incorporated into existing dry storage canister designs*Future designs or amendments could include -Surface modification to impart compressive residual ffstresses on welds and weld heat affected zones-Materials with improved localized corrosion and SCC resistanceresistance5 AMP Element 3ParametersMonitored/InspectedParameters Monitored/InspectedNUREG-1927: Parameters monitored or inspected should be linked to theeffectsofagingontheintendedfunctionsoftheparticularstructure*Canister surfaces, welds, and weld heat affected the effects of aging on the intended functions of the particular structure and component,,zones for discontinuities and imperfections *Size and location of localized corrosion (e.g., (gpitting and crevice corrosion) and stress corrosion cracks*Appearance and location of atmospheric deposits on the canister surfaces6 AMP Element 4DetectionofAgingEffects(1/2)Detection of Aging Effects (1/2)NUREG-1927: Define method or technique, frequency, sample size, datacollection,andtimingtoensuretimelydetectionofagingeffects*Qualified and demonstrated technique to detect evidence oflocalizedcorrosionandSCC:data collection, and timing to ensure timely detection of aging effectsof localized corrosion and SCC:-Remote visual inspection, e.g. EVT-1, VT-1, VT-3, or Eddy Current Testing (ET) may be appropriatePdidttifidiiiSCCldi*Pending detection findings, sizing SCC would require volumetric methods7 AMP Element 4DetectionofAgingEffects(2/2)Detection of Aging Effects (2/2)*Sample sizep-Minimum of one canister at each site-Canisters with the greatest susceptibility *Data Collection-Documentation of the examination of the canisterLocationandappearanceofdeposits-Location and appearance of deposits*Frequency-Every5yearsEvery 5 years*Timing of Inspections -Within 25 years of initial loading8 AMP Element 5MonitoringandTrendingMonitoring and TrendingNUREG-1927:Should provide for prediction of the extent of the effects ofagingandtimelycorrectiveormitigativeactions*Document canister condition particularly at welds andcrevicelocationsusingimagesandvideoof aging and timely corrective or mitigativeactionsand crevice locations using images and video that will allow comparison in subsequent examinations *Changes to the size and number of any corrosion product accumulations *Location and sizing of localized corrosion and stress corrosion cracking 9 AMP Element 6 AcceptanceCriteria(1/2)Acceptance Criteria (1/2)NUREG-1927: Acceptance criteria, against which the need for corrective action will be evaluated; should ensure that SSC functions *No indications of: ;are maintained-Pitting or crevice corrosion -Stress corrosion cracking -Corrosion products near crevices -Corrosion products on or adjacent to fabrication welds, closureweldsandweldsfortemporarysupportsorclosure welds, and welds for temporary supports or attachments10 AMP Element 6 AcceptanceCriteria(2/2)Acceptance Criteria (2/2)*Locations with corrosion products require additional examination for localized corrosion and/or SCC*Size of the area affected and the depth of penetration if localized corrosion and/or SCC is identifiedidentified*Canisters with localized corrosion and/or SCC mustbeevaluatedforcontinuedserviceinmust be evaluated for continued service in accordance with ASME B&PV Code Section XI IWB-3514.1 and IWB-3640 11 AMP Element 7CorrectiveActionsCorrective ActionsNUREG-1927:Corrective actions, including root cause determination andpreventionofrecurrence,shouldbetimely*Supplemental inspections to determine the extentofconditionatthesiteand prevention of recurrence, should be timelyextent of condition at the site *Subsequent inspections of canisters with indications*Canisters that do not meet the prescribed evaluation criteria must be repaired or removed pfrom service12 AMP Element 8ConfirmationProcessConfirmation ProcessNUREG-1927:Confirmation process should ensure that preventive actions are adequate & appropriate corrective actions have been *Licensee Quality Assurance Program consistent with10CFR72SubpartGor10CFR50qpppcompleted & are effectivewith 10 CFR 72 Subpart G, or 10 CFR 50 Appendix B*Ensure that inspections, evaluations, and p,,corrective actions are completed in accordance with the Site Specific or General Licensees CorrectiveActionProgram(CAP)Corrective Action Program (CAP)-Extent of condition-Evaluation for continued service-Repair, replace, mitigation actions13 AMP Element 9AdministrativeControlsAdministrative ControlsNUREG-1927: Administrative controls should provide a formal review andapprovalprocess*Licensee Quality Assurance Program consistent with10CFR72SubpartGor10CFR50and approval processwith 10 CFR 72 Subpart G, or 10 CFR 50 Appendix B*Trainingrequirementsforinspectors*Training requirements for inspectors*Records retention requirements14 AMP Element 10OperationalExperienceOperational ExperienceNUREG-1927:Include past corrective actions; provide objective evidencetosupportadeterminationthattheeffectsofagingwillbe*NoreportedcasesoflocalizedcorrosionorSCCinevidence to support a determination that the effects of aging will be adequately managed so that the SSC intended functions will be maintained during the period of extended operation*No reported cases of localized corrosion or SCC in welded stainless steel canisters*Atmospheric deposits on canister surfaces have been observed *Several reported cases of chloride induced SCC from atmosphericdepositsobservedinoperatingreactorsatmospheric deposits observed in operating reactors (NRC Information Notice 2012-20)*Laboratory and field test data on conditions necessary for yychloride induced SCC and SCC growth rates 15 AcronymsAcronymsAMP: Aging management program TLAA: time limiting aging analysisAMR: Aging management reviewASME B&PV code: American Society ITS: Important to safety SCC: Stress corrosion crackingyof Mechanical Engineers Boiler and Pressure Vessel code CAP: Corrective action programgSSC: Structures systems and componentspgCFR: Code of Federal RegulationsEVT1:Enhancedvisualtesting1VT-1: Visual Testing-1 (ASME B&PV code Section XI, Article IWA-2200) VT3:VisualTesting3(ASMEB&PVEVT-1: Enhanced visual testing-1(Boiling water reactor vessels and internals project, BWRVIP-03)VT-3: Visual Testing-3 (ASME B&PV code Section XI, Article IWA-2200)16}} | | {{#Wiki_filter:Aging Management Program Example for Stress Corrosion Cracking Darrell S. Dunn Meeting to Discuss the Request for Additional Information Responses p Regarding g g the Calvert Cliffs Independent p Spent p |
| | Fuel Storage Facility License Renewal July 17, 2014 |
| | |
| | Stress Corrosion Cracking Background Information |
| | * 304 and 316 Stainless steels are susceptible to chloride stress corrosion cracking (SCC) |
| | - Sensitization from welding increases susceptibility |
| | - Crevice and pitting corrosion can be precursors to SCC |
| | - SCC possible with low surface chloride concentrations |
| | * Welded stainless steel canisters have sufficient through wall tensile residual stresses for SCC 2/3 of the requirements |
| | * At Atmospheric h i SCC off welded ld d stainless steels has been observed for SCC are present in - Component failures in 16-33 years welded stainless steel - Estimated crack ggrowth rates of 0.11 to 0.91 mm/yr canisters 2 |
| | |
| | Regulatory Basis |
| | * 10 CFR 72.42(a), 72.240(c): |
| | TLAAs that demonstrate that ITS SSCs will continue to perform their intended function for the period of extended operation. |
| | A description of the AMP for management of issues associated with aging that could adversely affect ITS SSCs. |
| | * Guidance: NUREG-1927 AMP Elements: |
| | : 1. Scope of the Program 6. Acceptance Criteria |
| | : 2. Preventive Actions 7. Corrective Actions |
| | : 3. Parameters Monitored/Inspected 8. Confirmation Process |
| | : 4. Detection of Aging Effects 9. Administrative Controls |
| | : 5. Monitoring and Trending 10. Operating Experience 3 |
| | |
| | AMP Element 1 Scope of the Program NUREG-1927: The scope of the program should include the specific structures and components subject to an AMR |
| | * Welded stainless steel dry storage canisters |
| | - Fabrication and closure welds |
| | - Weld heat affected zones |
| | - Locations where temporary supports or fixtures were attached by welding |
| | - Crevice locations |
| | - Surface areas where atmospheric deposits preferentially occurs |
| | - Surface areas with a lower than average temperature 4 |
| | |
| | AMP Element 2 Preventative Actions NUREG-1927: Preventive actions should mitigate or prevent the applicable aging effects |
| | * Aging Management Program (AMP) is for condition monitoring monitoring. |
| | - Preventative actions are not presently incorporated into existing dry storage canister designs |
| | * Future designs or amendments could include |
| | - Surface modification to impart compressive residual stresses on welds and weld heat affected ff zones |
| | - Materials with improved localized corrosion and SCC resistance 5 |
| | |
| | AMP Element 3 Parameters Monitored/Inspected NUREG-1927: Parameters monitored or inspected should be linked to the effects of aging on the intended functions of the particular structure and component |
| | * Canister surfaces,, welds,, and weld heat affected zones for discontinuities and imperfections |
| | * Size and location of localized corrosion (e.g., ( g pitting and crevice corrosion) and stress corrosion cracks |
| | * Appearance and location of atmospheric deposits on the canister surfaces 6 |
| | |
| | AMP Element 4 Detection of Aging Effects (1/2) |
| | NUREG-1927: Define method or technique, frequency, sample size, data collection, and timing to ensure timely detection of aging effects |
| | * Qualified and demonstrated technique to detect evidence of localized corrosion and SCC: |
| | - Remote visual inspection, e.g. EVT-1, VT-1, VT-3, or Eddy Current Testing (ET) may be appropriate |
| | * PPending di d detection t ti fifindings, di sizing i i SCC would ld require i |
| | volumetric methods 7 |
| | |
| | AMP Element 4 Detection of Aging Effects (2/2) |
| | * Sample p size |
| | - Minimum of one canister at each site |
| | - Canisters with the greatest susceptibility |
| | * Data Collection |
| | - Documentation of the examination of the canister |
| | - Location and appearance of deposits |
| | * Frequency |
| | - Every 5 years |
| | * Timing of Inspections |
| | - Within 25 years of initial loading 8 |
| | |
| | AMP Element 5 Monitoring and Trending NUREG-1927: Should provide for prediction of the extent of the effects of aging and timely corrective or mitigative actions |
| | * Document canister condition particularly at welds and crevice locations using images and video that will allow comparison in subsequent examinations |
| | * Changes to the size and number of any corrosion product accumulations |
| | * Location and sizing of localized corrosion and stress corrosion cracking 9 |
| | |
| | AMP Element 6 Acceptance Criteria (1/2) |
| | NUREG-1927: Acceptance criteria, against which the need for corrective action will be evaluated;; should ensure that SSC functions are maintained |
| | * No indications of: |
| | - Pitting or crevice corrosion |
| | - Stress corrosion cracking |
| | - Corrosion products near crevices |
| | - Corrosion products on or adjacent to fabrication welds, closure welds welds, and welds for temporary supports or attachments 10 |
| | |
| | AMP Element 6 Acceptance Criteria (2/2) |
| | * Locations with corrosion products require additional examination for localized corrosion and/or SCC |
| | * Size of the area affected and the depth of penetration if localized corrosion and/or SCC is identified |
| | * Canisters with localized corrosion and/or SCC must be evaluated for continued service in accordance with ASME B&PV Code Section XI IWB-3514.1 and IWB-3640 11 |
| | |
| | AMP Element 7 Corrective Actions NUREG-1927: Corrective actions, including root cause determination and prevention of recurrence, should be timely |
| | * Supplemental inspections to determine the extent of condition at the site |
| | * Subsequent inspections of canisters with indications |
| | * Canisters that do not meet the prescribed evaluation criteria must be repaired p or removed from service 12 |
| | |
| | AMP Element 8 Confirmation Process NUREG-1927: Confirmation process should ensure that preventive q |
| | actions are adequate & appropriate pp p corrective actions have been completed & are effective |
| | * Licensee Quality Assurance Program consistent with 10 CFR 72 Subpart G G, or 10 CFR 50 Appendix B p |
| | * Ensure that inspections, , evaluations,, and corrective actions are completed in accordance with the Site Specific or General Licensees Corrective Action Program (CAP) |
| | - Extent of condition |
| | - Evaluation for continued service |
| | - Repair, replace, mitigation actions 13 |
| | |
| | AMP Element 9 Administrative Controls NUREG-1927: Administrative controls should provide a formal review and approval process |
| | * Licensee Quality Assurance Program consistent with 10 CFR 72 Subpart G G, or 10 CFR 50 Appendix B |
| | * Training requirements for inspectors |
| | * Records retention requirements 14 |
| | |
| | AMP Element 10 Operational Experience NUREG-1927: Include past corrective actions; provide objective evidence to support a determination that the effects of aging will be adequately managed so that the SSC intended functions will be maintained during the period of extended operation |
| | * No reported cases of localized corrosion or SCC in welded stainless steel canisters |
| | * Atmospheric deposits on canister surfaces have been observed |
| | * Several reported cases of chloride induced SCC from atmospheric deposits observed in operating reactors (NRC Information Notice 2012-20) |
| | * Laboratoryy and field test data on conditions necessaryy for chloride induced SCC and SCC growth rates 15 |
| | |
| | Acronyms AMP: Aging management program TLAA: time limiting aging analysis AMR: Aging management review ITS: Important to safety ASME B&PV code: American Societyy SCC: Stress corrosion crackingg of Mechanical Engineers Boiler and Pressure Vessel code SSC: Structures systems and components CAP: Corrective action pprogram g |
| | VT-1: Visual Testing-1 (ASME B&PV CFR: Code of Federal Regulations code Section XI, Article IWA-2200) |
| | EVT-1: |
| | EVT 1: Enhanced visual testing testing-1 1 VT-3: |
| | VT 3: Visual Testing-3 Testing 3 (ASME B&PV (Boiling water reactor vessels and code Section XI, Article IWA-2200) internals project, BWRVIP-03) 16}} |
|
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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 ML23157A0352023-06-0606 June 2023 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation 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) ML22013A3942022-01-13013 January 2022 Presentation Information for Pre-Submittal Meeting Regarding Relief Request to Use the Carbon Fiber Reinforced Polymer (Cfrp) Composite System 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) ML21144A0172021-05-24024 May 2021 Spent Fuel Pool Cooling - Shutdown Cooling Licensing Design Basis License Amendment Request Pre-Submittal Meeting ML21134A0162021-05-24024 May 2021 Spent Fuel Pool Cooling - Shutdown Cooling Licensing Design Basis License Amendment Request - NRC Pre-submittal Meeting Telecon May 24, 2021 (EPID L-2021-LRM-0051) (Slides) ML20261G7322020-09-16016 September 2020 Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a ML20246G8772020-09-0303 September 2020 Licensee'S Presentation for September 3, 2020 Public Telephone Conference 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 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 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 ML19246B7162019-08-29029 August 2019 Meeting Between NRC and Exelon Regarding Calvert Cliffs-2 LAR to Use Framatome ATF LTAs 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 ML18276A0712018-10-0404 October 2018 Exelon'S Presentation for October 4, 2018 Public Pre-Submittal Meeting on Planned Calvert Cliffs 10CFR50.69 LAR ML18171A0842018-06-21021 June 2018 GSI-191 Program Use of Risk Metrics for Containment Sump Tech Spec Operability Determination June 21, 2018 Public Meeting Slides (MF8521, MF8522; L-2016-LRM-0001) ML18190A3922018-06-14014 June 2018 Licensee Presentation Material for June 14, 2018 Public Meeting ML18136A4932018-05-16016 May 2018 Licensee'S Slides for Pre-Application Meeting W/Exelon Re Planned GSI-191 LAR for Calvert Cliffs (L-2016-LRM-0001) ML18096A0222018-04-0404 April 2018 Annual Assessment Meeting 04/04/2018 Handouts ML18096A9902018-03-12012 March 2018 NRC Pre-Submittal Call Briefing Notes, Calvert Cliffs Emergency Planning Future Licensing Actions 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 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 ML17143A1612017-05-23023 May 2017 Annual Assessment Meeting Handout and Sign in Sheet ML16274A0012016-09-30030 September 2016 PWR MSIP Analysis and Measurements 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 ML15321A3702015-12-0101 December 2015 GSI-191 Program Strainer Head Loss Testing and Option 2b Closure Approach ML15308A1072015-11-0505 November 2015 TSTF-505 LAR - NRC Pre-Submittal, November 5, 2015 Meeting Slides ML15282A0832015-10-0808 October 2015 October 8, 2015, Public Meeting Regarding the NFPA-805 License Amendment Application - Final ML15279A4992015-10-0808 October 2015 October 8, 2015, Public Meeting Regarding the NFPA-805 License Amendment Application ML15222A5472015-08-31031 August 2015 GSI 191 Program Chemical Effects Testing Update Option 2b Closure Approach ML15152A0822015-06-0404 June 2015 Presentation for the June 4, 2015 Public Meeting Regarding the National Fire Protection Association Standard 805 License Amendment Request ML14230A9132014-08-18018 August 2014 Enclosure - Fuel Performance and Cask Internals - July 17, 2014, Summary of Meeting with Exelon Corporation to Discuss Request for Additional Information No. 4 to the Calvert Cliffs ISFSI License Renewal Application (Docket No. 72-08) TAC L ML14230A9112014-08-18018 August 2014 Enclosure - Example AMP - July 17, 2014, Summary of Meeting with Exelon Corporation to Discuss Request for Additional Information No. 4 to the Calvert Cliffs ISFSI License Renewal Application (Docket No. 72-08) TAC L24475 ML14230A9102014-08-18018 August 2014 Enclosure - July 17, 2014, Summary of Meeting with Exelon Corporation to Discuss Request for Additional Information No. 4 to the Calvert Cliffs ISFSI License Renewal Application (Docket No. 72-08) TAC L24475 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) 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 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) ML22124A1492022-05-10010 May 2022 (Ccnpp) Control Element Assembly (CEA) Recovery Time Improvement Project LAR Pre-Submittal Non-Proprietary (Public) ML22124A1482022-05-10010 May 2022 (Ccnpp) Control Element Assembly (CEA) Recovery Time Improvement Project LAR Pre-Submittal Redacted (Public) ML22013A3942022-01-13013 January 2022 Presentation Information for Pre-Submittal Meeting Regarding Relief Request to Use the Carbon Fiber Reinforced Polymer (Cfrp) Composite System 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 ML21144A0172021-05-24024 May 2021 Spent Fuel Pool Cooling - Shutdown Cooling Licensing Design Basis License Amendment Request Pre-Submittal Meeting ML21134A0162021-05-24024 May 2021 Spent Fuel Pool Cooling - Shutdown Cooling Licensing Design Basis License Amendment Request - NRC Pre-submittal Meeting Telecon May 24, 2021 (EPID L-2021-LRM-0051) (Slides) ML20261G7322020-09-16016 September 2020 Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a ML20246G8772020-09-0303 September 2020 Licensee'S Presentation for September 3, 2020 Public Telephone Conference 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 ML20163A6542020-06-18018 June 2020 2020 NRC Annual Assessment Webinar Presentation - Pennsylvania and Maryland Facilities (Beaver Valley, Calvert Cliffs, Limerick, Peach Bottom, Susquehanna) 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 ML20168A3192020-06-15015 June 2020 Joint Annual Assessment Meeting for Pa/Md Power Plants - Webinar Presentation ML19246B7162019-08-29029 August 2019 Meeting Between NRC and Exelon Regarding Calvert Cliffs-2 LAR to Use Framatome ATF LTAs 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 ML18276A0712018-10-0404 October 2018 Exelon'S Presentation for October 4, 2018 Public Pre-Submittal Meeting on Planned Calvert Cliffs 10CFR50.69 LAR ML18171A0842018-06-21021 June 2018 GSI-191 Program Use of Risk Metrics for Containment Sump Tech Spec Operability Determination June 21, 2018 Public Meeting Slides (MF8521, MF8522; L-2016-LRM-0001) ML18136A4932018-05-16016 May 2018 Licensee'S Slides for Pre-Application Meeting W/Exelon Re Planned GSI-191 LAR for Calvert Cliffs (L-2016-LRM-0001) 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 ML16328A2832016-11-18018 November 2016 Supplemental Presentation Slides for 10/25/2016 Public Meeting Via E-mail from K.Greene to R.Guzman Calvert Cliffs GSI-191 Resolution Update ML16307A4902016-10-25025 October 2016 Presentation Slides from Public Meeting Calvert Cliffs GSI-191 Resolution Update ML16274A0012016-09-30030 September 2016 PWR MSIP Analysis and Measurements ML16242A1782016-09-0101 September 2016 Presentation Slides from Public Meeting Regarding Calvert Cliffs GSI-191 Resolution Update ML16198A0012016-07-18018 July 2016 Presentation Slides from Public Meeting Regarding Calvert Cliffs GSI-191 Resolution Update ML16077A1562016-03-22022 March 2016 Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards ML15321A3702015-12-0101 December 2015 GSI-191 Program Strainer Head Loss Testing and Option 2b Closure Approach ML15308A1072015-11-0505 November 2015 TSTF-505 LAR - NRC Pre-Submittal, November 5, 2015 Meeting Slides ML15279A4992015-10-0808 October 2015 October 8, 2015, Public Meeting Regarding the NFPA-805 License Amendment Application ML15282A0832015-10-0808 October 2015 October 8, 2015, Public Meeting Regarding the NFPA-805 License Amendment Application - Final ML15222A5472015-08-31031 August 2015 GSI 191 Program Chemical Effects Testing Update Option 2b Closure Approach ML15152A0822015-06-0404 June 2015 Presentation for the June 4, 2015 Public Meeting Regarding the National Fire Protection Association Standard 805 License Amendment Request ML14230A9132014-08-18018 August 2014 Enclosure - Fuel Performance and Cask Internals - July 17, 2014, Summary of Meeting with Exelon Corporation to Discuss Request for Additional Information No. 4 to the Calvert Cliffs ISFSI License Renewal Application (Docket No. 72-08) TAC L ML14230A9112014-08-18018 August 2014 Enclosure - Example AMP - July 17, 2014, Summary of Meeting with Exelon Corporation to Discuss Request for Additional Information No. 4 to the Calvert Cliffs ISFSI License Renewal Application (Docket No. 72-08) TAC L24475 ML14230A9102014-08-18018 August 2014 Enclosure - July 17, 2014, Summary of Meeting with Exelon Corporation to Discuss Request for Additional Information No. 4 to the Calvert Cliffs ISFSI License Renewal Application (Docket No. 72-08) TAC L24475 ML14230A9092014-08-18018 August 2014 Enclosure - Generic Concrete AMP CC ISFSI - July 17, 2014, Summary of Meeting with Exelon Corporation to Discuss Request for Additional Information No. 4 to the Calvert Cliffs ISFSI License Renewal Application (Docket No. 72-08) TAC L24475 ML14230A9082014-08-18018 August 2014 Enclosure - Elements of an AMP CC ISFSI - July 17, 2014, Summary of Meeting with Exelon Corporation to Discuss Request for Additional Information No. 4 to the Calvert Cliffs ISFSI License Renewal Application (Docket No. 72-08) TAC L24475 2024-01-30
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Aging Management Program Example for Stress Corrosion Cracking Darrell S. Dunn Meeting to Discuss the Request for Additional Information Responses p Regarding g g the Calvert Cliffs Independent p Spent p
Fuel Storage Facility License Renewal July 17, 2014
Stress Corrosion Cracking Background Information
- Sensitization from welding increases susceptibility
- Crevice and pitting corrosion can be precursors to SCC
- SCC possible with low surface chloride concentrations
- Welded stainless steel canisters have sufficient through wall tensile residual stresses for SCC 2/3 of the requirements
- At Atmospheric h i SCC off welded ld d stainless steels has been observed for SCC are present in - Component failures in 16-33 years welded stainless steel - Estimated crack ggrowth rates of 0.11 to 0.91 mm/yr canisters 2
Regulatory Basis
TLAAs that demonstrate that ITS SSCs will continue to perform their intended function for the period of extended operation.
A description of the AMP for management of issues associated with aging that could adversely affect ITS SSCs.
- 1. Scope of the Program 6. Acceptance Criteria
- 2. Preventive Actions 7. Corrective Actions
- 3. Parameters Monitored/Inspected 8. Confirmation Process
- 4. Detection of Aging Effects 9. Administrative Controls
- 5. Monitoring and Trending 10. Operating Experience 3
AMP Element 1 Scope of the Program NUREG-1927: The scope of the program should include the specific structures and components subject to an AMR
- Welded stainless steel dry storage canisters
- Fabrication and closure welds
- Weld heat affected zones
- Locations where temporary supports or fixtures were attached by welding
- Crevice locations
- Surface areas where atmospheric deposits preferentially occurs
- Surface areas with a lower than average temperature 4
AMP Element 2 Preventative Actions NUREG-1927: Preventive actions should mitigate or prevent the applicable aging effects
- Preventative actions are not presently incorporated into existing dry storage canister designs
- Future designs or amendments could include
- Surface modification to impart compressive residual stresses on welds and weld heat affected ff zones
- Materials with improved localized corrosion and SCC resistance 5
AMP Element 3 Parameters Monitored/Inspected NUREG-1927: Parameters monitored or inspected should be linked to the effects of aging on the intended functions of the particular structure and component
- Canister surfaces,, welds,, and weld heat affected zones for discontinuities and imperfections
- Size and location of localized corrosion (e.g., ( g pitting and crevice corrosion) and stress corrosion cracks
- Appearance and location of atmospheric deposits on the canister surfaces 6
AMP Element 4 Detection of Aging Effects (1/2)
NUREG-1927: Define method or technique, frequency, sample size, data collection, and timing to ensure timely detection of aging effects
- Qualified and demonstrated technique to detect evidence of localized corrosion and SCC:
- Remote visual inspection, e.g. EVT-1, VT-1, VT-3, or Eddy Current Testing (ET) may be appropriate
- PPending di d detection t ti fifindings, di sizing i i SCC would ld require i
volumetric methods 7
AMP Element 4 Detection of Aging Effects (2/2)
- Minimum of one canister at each site
- Canisters with the greatest susceptibility
- Documentation of the examination of the canister
- Location and appearance of deposits
- Every 5 years
- Within 25 years of initial loading 8
AMP Element 5 Monitoring and Trending NUREG-1927: Should provide for prediction of the extent of the effects of aging and timely corrective or mitigative actions
- Document canister condition particularly at welds and crevice locations using images and video that will allow comparison in subsequent examinations
- Changes to the size and number of any corrosion product accumulations
AMP Element 6 Acceptance Criteria (1/2)
NUREG-1927: Acceptance criteria, against which the need for corrective action will be evaluated;; should ensure that SSC functions are maintained
- Pitting or crevice corrosion
- Stress corrosion cracking
- Corrosion products near crevices
- Corrosion products on or adjacent to fabrication welds, closure welds welds, and welds for temporary supports or attachments 10
AMP Element 6 Acceptance Criteria (2/2)
- Locations with corrosion products require additional examination for localized corrosion and/or SCC
- Size of the area affected and the depth of penetration if localized corrosion and/or SCC is identified
- Canisters with localized corrosion and/or SCC must be evaluated for continued service in accordance with ASME B&PV Code Section XI IWB-3514.1 and IWB-3640 11
AMP Element 7 Corrective Actions NUREG-1927: Corrective actions, including root cause determination and prevention of recurrence, should be timely
- Supplemental inspections to determine the extent of condition at the site
- Subsequent inspections of canisters with indications
- Canisters that do not meet the prescribed evaluation criteria must be repaired p or removed from service 12
AMP Element 8 Confirmation Process NUREG-1927: Confirmation process should ensure that preventive q
actions are adequate & appropriate pp p corrective actions have been completed & are effective
- Ensure that inspections, , evaluations,, and corrective actions are completed in accordance with the Site Specific or General Licensees Corrective Action Program (CAP)
- Extent of condition
- Evaluation for continued service
- Repair, replace, mitigation actions 13
AMP Element 9 Administrative Controls NUREG-1927: Administrative controls should provide a formal review and approval process
- Training requirements for inspectors
- Records retention requirements 14
AMP Element 10 Operational Experience NUREG-1927: Include past corrective actions; provide objective evidence to support a determination that the effects of aging will be adequately managed so that the SSC intended functions will be maintained during the period of extended operation
- No reported cases of localized corrosion or SCC in welded stainless steel canisters
- Atmospheric deposits on canister surfaces have been observed
- Laboratoryy and field test data on conditions necessaryy for chloride induced SCC and SCC growth rates 15
Acronyms AMP: Aging management program TLAA: time limiting aging analysis AMR: Aging management review ITS: Important to safety ASME B&PV code: American Societyy SCC: Stress corrosion crackingg of Mechanical Engineers Boiler and Pressure Vessel code SSC: Structures systems and components CAP: Corrective action pprogram g
VT-1: Visual Testing-1 (ASME B&PV CFR: Code of Federal Regulations code Section XI, Article IWA-2200)
EVT-1:
EVT 1: Enhanced visual testing testing-1 1 VT-3:
VT 3: Visual Testing-3 Testing 3 (ASME B&PV (Boiling water reactor vessels and code Section XI, Article IWA-2200) internals project, BWRVIP-03) 16