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| | issue date = 05/08/2007 | | | issue date = 05/08/2007 |
| | title = 05/08/2007 Slides, Recommendations for Critical Flaw Size Calculations (in Wolf Creek Advanced Fea Project). | | | title = 05/08/2007 Slides, Recommendations for Critical Flaw Size Calculations (in Wolf Creek Advanced Fea Project). |
| | author name = Riccardella P C | | | author name = Riccardella P |
| | author affiliation = Structural Integrity Associates, Inc | | | author affiliation = Structural Integrity Associates, Inc |
| | addressee name = | | | addressee name = |
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MONTHYEARML0617201182006-06-27027 June 2006 Propriertary Withholding MRP-139, Electric Power Research Institute Project stage: Other ML0713506512007-05-0808 May 2007 Slides, Category 2 Public Meeting with NEI on the Implications of the Wolf Creek Dissimilar Metal Weld Inspections. Project stage: Request ML0713506462007-05-0808 May 2007 Industry Slides, Advanced Fea Crack Growth Calculations for Evaluation of PWR Pressurizer Nozzle Dissimilar Metal Weld Circumferential PWSCC, from Status Meeting on Implications of Wolf Creek Dissimilar Metal Weld Inspections Project stage: Request ML0713506532007-05-0808 May 2007 Slides, Recommendations for Critical Flaw Size Calculations (in Wolf Creek Advanced Fea Project). Project stage: Request ML0715705202007-06-27027 June 2007 Summary of Meeting with NRC Industry Representatives to Present a Matrix of Potential Modeling Cases for the Phase II Sensitivity, Benchmarking, and Validation Calculations in Their Advanced Finite Element Fracture Mechanics Analyses Project stage: Meeting 2007-05-08
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Category:Meeting Briefing Package/Handouts
MONTHYEARML24180A0092024-06-28028 June 2024 July 23, 2024, Portable Lighting Amendment 237 Meeting Slides ML24071A2102024-03-25025 March 2024 March 25, 2024, Portable Lighting Revised SE Meeting Slides ML24085A2732024-03-21021 March 2024 Comments for March 25, 2024 Meeting on Portable Lighting Revised SE ML23275A1712023-10-16016 October 2023 October 16, 2023, Licensee Pre-submittal Meeting Slides - License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2 for Wolf Creek Generating Station ML21333A1512021-11-29029 November 2021 Pre-Submittal Meeting Slides License Amendment Request Addressing Portable Lighting for Operator Manual Actions ML21179A0892021-07-13013 July 2021 Background Information July 13, 2021, Pre-Submittal Public Teleconference ML20308A7332020-11-18018 November 2020 Slides for GSI-191 Pre-Submittal Public Teleconference November 18, 2020 ML18299A0492018-10-30030 October 2018 Accident Analyses Methodology Transition LAR Public Meeting IR 05000482/20174072017-12-22022 December 2017 Summary of Closed Regulatory Conference to Discuss Wolf Creek, Unit 1, Security Inspection Report 05000482/2017407 ML16271A4822016-09-27027 September 2016 Summary of Regulatory Conference to Discuss Safety Significance of Wolf Creek Generating Station Emergency Generator Excitation Diode Apparent Violation ML16236A0952016-08-25025 August 2016 and Wolf Creek Generating Station - August 25, 2016, Class 1E Electrical Equipment Air Conditioning System Pre-Application Meeting ML16095A0782016-04-12012 April 2016 Slides for the WCGS Meeting Discussion 4/12/16 ML16095A0852016-04-12012 April 2016 Large Scale Head Loss Test Specification 4/12/16 ML16095A0802016-04-12012 April 2016 Large Scale Penetration Test Specification 4/12/16 ML16095A0922016-03-31031 March 2016 Large Scale Penetration and Head Loss Test Plan 4/12/16 ML14188C4812014-07-0707 July 2014 Summary of Annual Assessment Meeting with Wolf Creek Generating Station ML14134A1842014-05-14014 May 2014 Summary of Public Meeting to Discuss an Apparent Violation Identified at Wolf Creek Generating Station ML14038A3852014-02-0606 February 2014 1/22/2014 - Summary of Public Meeting to Discuss Corrective Actions Implemented to Address the Chilling Effect Letter ML13218A0212013-08-0707 August 2013 Licensee Slides, 08/07/13 Preapplication Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Long-Term Corrective Actions for Water Hammer Events in the Essential Service Water System at Wolf Creek ML13205A2142013-07-30030 July 2013 Operating Corporation - Slides for Pre-application Meeting on 7/30/13 - Core Design and Safety Analysis Methodology Transition License Amendment Request for Wolf Creek Generating Station ML12263A3622012-09-20020 September 2012 Pre-application Meeting Slide Core Design and Safety Analysis Methodology Transition License Amendment Request TAC No. ME9495) ML12191A1742012-07-0909 July 2012 6/25/2012 Summary of Public Meeting with Wolf Creek Nuclear Operating Corporation ML1110104292011-04-11011 April 2011 Summary of Annual Performance Assessment Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Wolf Creek Generating Station Performance for the NRC Inspection Period Ending December 31, 2010 ML1016204902010-06-16016 June 2010 Notice of Construction Reactor Oversight Process Category 2 Public Meeting Handout: Wolf Creek 2, Notice of Violation and Proposed Imposition of Civil Penalty, Dated 11/21/1984 ML1016901162010-06-16016 June 2010 6/16/2010 Construction Reactor Oversight Process Category 2 Public Meeting Handout: Meeting Slides (Enforcement Cases) ML1013404892010-05-14014 May 2010 Summary of Annual Performance Assessment Meeting with Wolf Creek Nuclear Operating Corporation to Discuss the Wolf Creek Generating Station Performance for the NRC Inspection Period from January 1 Through December 31, 2009 ML0933702032009-12-0303 December 2009 Summary of Public Meeting for Wolf Creek Generating Station ML0933801482009-11-20020 November 2009 Licensee Handouts from November 20, 2009, Public Meeting with Union Electric Company and Wolf Creek Nuclear Operating Company to Discuss GL 2004-02 Response Rai'S ML0913300232009-05-13013 May 2009 Meeting Slides, Successful Licensing of the Als Fpga Based Safety Related I&C Platform ML0912600692009-05-0606 May 2009 Lessons Learned Using Digital I&C Interim Staff Guidance Workshop ML0902102422009-01-15015 January 2009 Licensee Slides, January 15, 2009, Category 1 Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Changes to Post Fire Shutdown Unresolved Items Analysis Methods Pre-Application for Wolf Creek Generating Station ML0834700222008-12-11011 December 2008 Slides, Category 2 Public Meeting Digital Instrumentation and Control Steering Committee M080717, M080717-Commission Briefing Slides/Exhibits Briefing on Fire Protection2008-07-17017 July 2008 M080717-Commission Briefing Slides/Exhibits Briefing on Fire Protection ML0817706682008-06-25025 June 2008 Summary of Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Several Initiatives That Were Being Implemented to Improve Plant Performance at Wolf Creek ML0803706102008-01-11011 January 2008 Westinghouse Electric Company LLC, LTR-CDME-08-2, Rev. 1 NP-Attachment, Meeting Handouts from the December 13, 2007 Meeting with Wolf Creek and NRR on H*/B*. ML0729204682007-10-29029 October 2007 09/25/2007, Summary of Meeting Between the U.S. Nuclear Regulatory Commission Staff and Strategic Teaming and Resource Sharing Representatives to Discuss License Renewal Activities ML0721501532007-08-0202 August 2007 NRC Staff Handout for August 2, 2007, Meeting with Wolf Creek Nuclear Operating Corporation ML0721102382007-07-24024 July 2007 Performanc Contracting, Inc.'S Powerpoint Slide, Proposed Wolf Creek/Callaway Test Configuration ML0719303772007-07-11011 July 2007 Handouts (NRC and Licensee) for Meeting with Representatives of Wolf Creek Nuclear Operating Corporation ML0718606902007-06-19019 June 2007 06/19-20/2007 Slides,Fabrication Records Review, from Category 2 Public Meeting Between the NRC Staff and the Expert Panel for the Wolf Creek Advanced Finite Element Analyses (Fea) ML0716203882007-06-0101 June 2007 06/01/07 - Presentation Material, Advanced Fea Crack Growth Calculations for Evaluation of PWR Pressurizer Nozzle Dissimilar Metal Weld Circumferential Pwscc. ML0733409182007-05-31031 May 2007 05/31/2007 Presentation by J. Cudsworth NRC Treatment of Issues Other than Category 2 Issues for License Renewal ML0713703642007-05-17017 May 2007 Handout for Meeting with Wolf Creek Nuclear Operating Corporation on the Licensee'S Application for the Main Steam and Feedwater Isolation System (Msfis) Modification ML0713506532007-05-0808 May 2007 Slides, Recommendations for Critical Flaw Size Calculations (in Wolf Creek Advanced Fea Project). ML0713506462007-05-0808 May 2007 Industry Slides, Advanced Fea Crack Growth Calculations for Evaluation of PWR Pressurizer Nozzle Dissimilar Metal Weld Circumferential PWSCC, from Status Meeting on Implications of Wolf Creek Dissimilar Metal Weld Inspections ML0713506512007-05-0808 May 2007 Slides, Category 2 Public Meeting with NEI on the Implications of the Wolf Creek Dissimilar Metal Weld Inspections. ML0713603732007-05-0101 May 2007 Enclosure-1 05/01/2007 Dominion Engineering Presentation Advanced Fea Crack Growth Calculations for Evaluation of PWR Pressurizer Nozzle Dissimilar Metal Weld Circumferential Pwscc. ML0713603962007-05-0101 May 2007 Enclosure 2-05/01/2007 Engineering Mechanics Corporation of Columbus Presentation, NRC Welding Residual Stress Solutions as Generated by Battelle and Emc2. ML0701704732007-01-19019 January 2007 12/19/2006 Summary of Public Meetings Related to the Review of the Wolf Creek Generating Station License Renewal Application ML0635603632006-12-20020 December 2006 12/01/2006 Industry Meeting Handout: Draft Report (December 2006) - Implications of Wolf Creek Pressurizer Butt Weld Indications Relative to Safety Assessment and Inspection Requirements 2024-06-28
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24180A0092024-06-28028 June 2024 July 23, 2024, Portable Lighting Amendment 237 Meeting Slides ML24071A2102024-03-25025 March 2024 March 25, 2024, Portable Lighting Revised SE Meeting Slides ML23275A1712023-10-16016 October 2023 October 16, 2023, Licensee Pre-submittal Meeting Slides - License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2 for Wolf Creek Generating Station ML21333A1512021-11-29029 November 2021 Pre-Submittal Meeting Slides License Amendment Request Addressing Portable Lighting for Operator Manual Actions ML20310A2232020-11-19019 November 2020 Slides for ERO Staffing pre-submittal Public Teleconference November 19, 2020 (L-2020-LRM-0104) IR 05000482/20174072017-12-22022 December 2017 Summary of Closed Regulatory Conference to Discuss Wolf Creek, Unit 1, Security Inspection Report 05000482/2017407 ML16236A0952016-08-25025 August 2016 and Wolf Creek Generating Station - August 25, 2016, Class 1E Electrical Equipment Air Conditioning System Pre-Application Meeting ML16236A0972016-08-25025 August 2016 Operating Corporation - August 25, 2016, Core Design and Safety System Analysis Methodology Transition License Amendment Request Revised ML16095A0782016-04-12012 April 2016 Slides for the WCGS Meeting Discussion 4/12/16 ML14188C4812014-07-0707 July 2014 Summary of Annual Assessment Meeting with Wolf Creek Generating Station ML14134A1842014-05-14014 May 2014 Summary of Public Meeting to Discuss an Apparent Violation Identified at Wolf Creek Generating Station ML14038A3852014-02-0606 February 2014 1/22/2014 - Summary of Public Meeting to Discuss Corrective Actions Implemented to Address the Chilling Effect Letter ML13218A0212013-08-0707 August 2013 Licensee Slides, 08/07/13 Preapplication Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Long-Term Corrective Actions for Water Hammer Events in the Essential Service Water System at Wolf Creek ML13219A1932013-08-0707 August 2013 Licensee Slides (Final), 08/07/13 Preapplication Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Long-Term Corrective Actions for Water Hammer Events in the Essential Service Water System at Wolf Creek ML13205A2142013-07-30030 July 2013 Operating Corporation - Slides for Pre-application Meeting on 7/30/13 - Core Design and Safety Analysis Methodology Transition License Amendment Request for Wolf Creek Generating Station ML13121A4892013-05-0101 May 2013 End of Cycle Meeting Summary 4-18-13 ML12263A3622012-09-20020 September 2012 Pre-application Meeting Slide Core Design and Safety Analysis Methodology Transition License Amendment Request TAC No. ME9495) ML12191A1742012-07-0909 July 2012 6/25/2012 Summary of Public Meeting with Wolf Creek Nuclear Operating Corporation ML1110104292011-04-11011 April 2011 Summary of Annual Performance Assessment Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Wolf Creek Generating Station Performance for the NRC Inspection Period Ending December 31, 2010 ML1016901162010-06-16016 June 2010 6/16/2010 Construction Reactor Oversight Process Category 2 Public Meeting Handout: Meeting Slides (Enforcement Cases) ML1013404892010-05-14014 May 2010 Summary of Annual Performance Assessment Meeting with Wolf Creek Nuclear Operating Corporation to Discuss the Wolf Creek Generating Station Performance for the NRC Inspection Period from January 1 Through December 31, 2009 ML0933702032009-12-0303 December 2009 Summary of Public Meeting for Wolf Creek Generating Station ML0933801482009-11-20020 November 2009 Licensee Handouts from November 20, 2009, Public Meeting with Union Electric Company and Wolf Creek Nuclear Operating Company to Discuss GL 2004-02 Response Rai'S ML0913300232009-05-13013 May 2009 Meeting Slides, Successful Licensing of the Als Fpga Based Safety Related I&C Platform ML0912600762009-05-0606 May 2009 Lessons Learned Using Digital I&C Interim Staff Guidance Workshop Application of ISG-4 During Wolf Creek and Oconee Reviews ML0912600692009-05-0606 May 2009 Lessons Learned Using Digital I&C Interim Staff Guidance Workshop ML0902102422009-01-15015 January 2009 Licensee Slides, January 15, 2009, Category 1 Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Changes to Post Fire Shutdown Unresolved Items Analysis Methods Pre-Application for Wolf Creek Generating Station ML0834700222008-12-11011 December 2008 Slides, Category 2 Public Meeting Digital Instrumentation and Control Steering Committee M080717, M080717-Commission Briefing Slides/Exhibits Briefing on Fire Protection2008-07-17017 July 2008 M080717-Commission Briefing Slides/Exhibits Briefing on Fire Protection ML0817706682008-06-25025 June 2008 Summary of Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Several Initiatives That Were Being Implemented to Improve Plant Performance at Wolf Creek ML0813606472008-06-10010 June 2008 05/01/2008-Summary of Public Meeting on Safety Evaluation Report with Open Items Regarding the Wolf Creek Generating Station License Renewal Review ML0721102382007-07-24024 July 2007 Performanc Contracting, Inc.'S Powerpoint Slide, Proposed Wolf Creek/Callaway Test Configuration ML0720601382007-07-17017 July 2007 Slides from Meeting Between NRC Staff and Wolf Creek Panel Enclosures 2 to 3, Advanced Fea Crack Growth Calculations for Evaluation of PWR Pressurizer Nozzle Dissimilar Metal Weld Circumferential Pwscc. ML0719303772007-07-11011 July 2007 Handouts (NRC and Licensee) for Meeting with Representatives of Wolf Creek Nuclear Operating Corporation ML0718606902007-06-19019 June 2007 06/19-20/2007 Slides,Fabrication Records Review, from Category 2 Public Meeting Between the NRC Staff and the Expert Panel for the Wolf Creek Advanced Finite Element Analyses (Fea) ML0716203882007-06-0101 June 2007 06/01/07 - Presentation Material, Advanced Fea Crack Growth Calculations for Evaluation of PWR Pressurizer Nozzle Dissimilar Metal Weld Circumferential Pwscc. ML0733409182007-05-31031 May 2007 05/31/2007 Presentation by J. Cudsworth NRC Treatment of Issues Other than Category 2 Issues for License Renewal ML0713703642007-05-17017 May 2007 Handout for Meeting with Wolf Creek Nuclear Operating Corporation on the Licensee'S Application for the Main Steam and Feedwater Isolation System (Msfis) Modification ML0713506532007-05-0808 May 2007 Slides, Recommendations for Critical Flaw Size Calculations (in Wolf Creek Advanced Fea Project). ML0713506512007-05-0808 May 2007 Slides, Category 2 Public Meeting with NEI on the Implications of the Wolf Creek Dissimilar Metal Weld Inspections. ML0713603962007-05-0101 May 2007 Enclosure 2-05/01/2007 Engineering Mechanics Corporation of Columbus Presentation, NRC Welding Residual Stress Solutions as Generated by Battelle and Emc2. ML0713603732007-05-0101 May 2007 Enclosure-1 05/01/2007 Dominion Engineering Presentation Advanced Fea Crack Growth Calculations for Evaluation of PWR Pressurizer Nozzle Dissimilar Metal Weld Circumferential Pwscc. ML0701601892006-12-19019 December 2006 12/19/2006, Viewgraphs from Meeting with Wolf Creek Generating Station to Discuss License Renewal Process and Environmental Scoping ML0635603462006-11-30030 November 2006 November 30, 2006 NRC Presentation Slides: Wolf Creek Flaw Evaluation ML0635603582006-11-30030 November 2006 Industry Presentation Slides: MRP-139 Analysis Basis ML0632100772006-11-16016 November 2006 NRC Presentation: NRC Perspective on Wolf Creek Inspection Results ML0632100802006-11-16016 November 2006 Industry Presentations: Nov. 16, 2006 Public Meeting ML0622804372006-08-16016 August 2006 Handouts from Wolf Creek Nuclear Operating Corporation and from Union Electric Company for Meeting with NRC on the Main Steam Isolation Valve (MSIV) Operability Determination ML0618000292006-06-28028 June 2006 Handout for June 28, 2006, Meeting with Representatives of Wolf Creek Nuclear Operating Corporation for Wolf Creek Generating Station on the Main Steam and Feedwater Isolation System (Msfis) Controls Replacement Project ML0615106012006-05-23023 May 2006 EPRI HRA Users Group Review of Draft NUREG-1842 2024-06-28
[Table view] |
Text
Recommendations for Critical Flaw Size Calculations (in Wolf Creek Advanced FEA Project)
By Peter C. Riccardella May 8, 2007 Summary of Key Issues from [1] (Reference list on last slide)
- Material Properties for Use in Evaluation
- Inclusion of Secondary Stresses EPFM vs. Limit Load
- Plot of data from Battelle/NRC Full Scale Pipe Tests on SS and A-600 indicates that Limit Load (ANSC) works well for all flaw types tested
- Comparison of Fracture Toughness (J-R Curves)
indicates Alloy 182 not si gnificantly less tough than tested materials
- DPZP screening criteria [2] adapted to complex
crack tests gives reasonable results Can be used to screen current analyses of A-182 for appropriate analysis type Limit Load (ANSC) Applied to Battelle/NRC Full Scale Pipe Tests [4, 5]0.00.51.01.52.02.53.03.54.00.0%10.0%20.0%30.0%40.0%50.0%60.0%70.0%80.0%90.0%CF(Pm+Pb)/SmComplexThru-wallSurfaceWOL (Surf)ANSC-A-600;complexANSC-SS;complexANSC-SS;thruANSC-SS, surfANSC-SS surf;Pm=9ksiPure Axial LoadTests w/ Pressure + Bending (large symbols)42" Pipe Definition of Various Flaw Types Tested [4]
Compilation of J-R Curve Toughness Data for Relevant Materials [4-7]
0 2000 4000 6000 8000 10000 12000 140000.0000.0500.1000.1500.2000.2500.3000.3500.4000.4500.500Crack Extension (in)J (in-lb/in^2)A-182 (BT-4;600F)A-182 (BT-3;600F)A-182 (WT-4;600F)A-182 (BR-1;600F)A-82 (Mills 640F)A-600 (Mills 640F)A-600 (Mills 640F)A-600 (I1C; 550F)304SS (Landes;550F)304SS (Landes;550F)316SS (Landes;550F)304SS (A24C; 550F)304SS (A8; 550F)304 SAW (Landes;550F)CS DP2-F30C Dimensionless Plastic Zone (DPZP)
Screening Parameter [2]
where:= 1/2crack angle of through-wall crackd/t= fractional depth of surface crack D = OD of pipe DPZP Screening Criteria Adapted to Complex Cracks DPZP = (EJ i/ 2 f) Ú{-[+ d/t(-)]}D/4 where:= 1/2crack angle of through-wall portion of crackd/t= fractional depth of part through wall portion D = OD of pipe0.00.20.40.6 0.81.01.21.41.60123456789101112DPZPRatio (Pmax / P-NSC)A-182; 8" Dia.A-182; 16" Dia.
Inclusion of Secondary Stresses
- Dynamic tests cited in [1] as reason for including secondary stresses not compelling
- Static tests with large complex cracks indicate
large displacements required prior to crack
instability many times larger than expected displacements due to thermal loadings in plants, including stratification Schematic of Compliant Load Complex Crack Pipe Test [4]
~40 ft.Springs for Added Compliance16"NPS Pipe Load-Line Displacement to Fracture [4] (large in comparison to applied thermal displacements in plants)
At Actuator At Pipe Typical Surge Line Geometry (Westinghouse Plant)
~28 ft.~20 ft.~10 ft.14"NPSMax. Disp.
Locations Thermal Stratification Displacements in Surge Line Max. Dis p. Locations Recommendations
- Limit Load vs. EPFM -Apply DPZP Screening Criteria For DPZP > 1.0, use limit load (ANSC for actual flaw shape)For DPZP < 1.0, use limit lo ad with Wilkowski Z-Factor Correction
- Material Properties Use SS Base Metal Tensile Propertied (Flow Stress, Stress-Strain Curve)
- Secondary Stresses Overly Conservative to Include Full Value of Large
Stratification Moments in Surge Nozzle Limit Load Evaluations Include Piping Geometry of Typical Plant(s) to Determine
Effect of Secondary Stress on J-T Analyses References1.G. Wilkowski et al, "Draft Techni cal Note on Critical Flaw Size Evaluations for Circumferential Cr acks in Dissimilar Metal Welds", EMC2, April 9, 2007.2.Gery M. Wilkowski and Paul M. Scott, "A Statistical Based Circumferentially Cracked Pipe Fr acture Mechanics Analysis For Design or Code Implementation", Nuclear Engineering and Design 111 (1989) 173-187 3.G. Wilkowski et al, "Determinati on of the Elastic-Plastic Fracture Mechanics Z-Factor for Alloy 82/182 Weld Metal Flaws for Use in the ASME Section XI Appendix C Flaw Evaluation Procedures", (Draft)
ASME PVP2007-26733 4.NUREG/CR-4082, Volumes 7 & 8, "Degraded Piping Program -Phase 2", March 1984-January 19895.Pipe Fracture Encyclopedia, U.S. NRC, 1997 (A collection of NUREG Reports and Data Files from the DP2 and other programs distributed on CDs)6.W.J. Mills, C.M. Brown, "Fract ure Toughness of Alloy 600 and EN82H Weld in Air and Water", B-T-3264, BettisAPL, 7.J.D. Landes, J. McCabe, Toughness of Austenitic Stainless Steel Pipe Welds, EPRI NP-4768, October, 1988