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TAC:MD0197, Steam Generator Tube Integrity (Withdrawn, Closed) |
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MONTHYEARML0606004582006-01-31031 January 2006 Westinghouse Electric Company LLC LTR-CDME-05-209-NP, Steam Generator Tube Alternate Repair Criteria for the Portion of the Tube within the Tubesheet at the Wolf Creek Generating Station. Project stage: Request ET 06-0015, Supplement to Revision to Technical Specifications - Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process2006-03-28028 March 2006 Supplement to Revision to Technical Specifications - Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process Project stage: Request ML0609001572006-04-10010 April 2006 Withholding from Public Disclosure, LTR-CDME-05-209-P, MD0197 Project stage: Other ML0616500992006-06-27027 June 2006 Request for Additional Information (RAI) Related to License Amendment Request (LAR) to Revise the Steam Generator Program Project stage: RAI WO 07-0012, Response to Request for Additional Information Related to License Amendment Request to Revise the Steam Generator Program2007-05-0303 May 2007 Response to Request for Additional Information Related to License Amendment Request to Revise the Steam Generator Program Project stage: Response to RAI ML0716504002007-06-19019 June 2007 Notice of Meeting with Wolf Creek Nuclear Corp Regarding Nrc'S Request for Additional Information on 2/21/06 Licensee Amendment Request Re SG Tube Surveillance Program, Wolf Creek Generating Station Project stage: RAI ML0719303772007-07-11011 July 2007 Handouts (NRC and Licensee) for Meeting with Representatives of Wolf Creek Nuclear Operating Corporation Project stage: Meeting ML0719802032007-08-0707 August 2007 Summary of Meeting with Representatives of Wolf Creek Nuclear Operating Corporation for Wolf Creek Generating Station to Discuss Second Request for Additional Information for Steam Generator Tube Surveillance Program LAR Project stage: RAI ML0722700022007-08-30030 August 2007 Topical Report, Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ET 07-0043, Response to Request for Additional Information Related to License Amendment Request to Revise the Steam Generator Program2007-09-27027 September 2007 Response to Request for Additional Information Related to License Amendment Request to Revise the Steam Generator Program Project stage: Response to RAI ML0730901272007-11-0808 November 2007 Notice of Meeting with Wolf Creek Nuclear Operating Corporation to Discuss NRC Staff'S Request for Additional Information on Licensee'S Supplemental Letter to Letter Dated September 27, 2007, to Application Dated February 21, 2006 Project stage: RAI ML0732500032007-11-21021 November 2007 Memo to Thomas G. Hiltz Key Issues for Discussion for November 28, 2007 Meeting on Steam Generator Tube Inspection License Amendment (Tac MD0197) Project stage: Meeting ML0733004182007-11-29029 November 2007 Topical Report Withholding Information from Public Disclosure (Tac No. MD0197) Project stage: Other ML0733700452008-01-0404 January 2008 Summary of Meeting with Wolf Creek Nuclear Operating Corporation Representatives Re Steam Generator Tube Surveillance Program Project stage: Meeting 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*. Project stage: Request ML0804300062008-02-27027 February 2008 Request for Withholding Information from Public Disclosure, 01/11/2008 Affidavit Executed by J. A. Gresham, Westinghouse Electric Company LLC Project stage: Withholding Request Acceptance ML0804501852008-02-28028 February 2008 Withdrawal of License Amendment Request on Steam Generator Tube Inspections Project stage: Withdrawal RS-08-047, Withdrawal of License Amendment Request Related Steam Generator Tube Alternate Repair Criteria2008-04-0101 April 2008 Withdrawal of License Amendment Request Related Steam Generator Tube Alternate Repair Criteria Project stage: Withdrawal 2007-06-19
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Category:Meeting Briefing Package/Handouts
MONTHYEARML23275A1712023-10-16016 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 ML0701601892006-12-19019 December 2006 12/19/2006, Viewgraphs from Meeting with Wolf Creek Generating Station to Discuss License Renewal Process and Environmental Scoping ML0635603582006-11-30030 November 2006 Industry Presentation Slides: MRP-139 Analysis Basis ML0635603462006-11-30030 November 2006 November 30, 2006 NRC Presentation Slides: Wolf Creek Flaw Evaluation 2023-10-16
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Enclosure II to ET 08-0006 Westinghouse Electric Company LLC LTR-CDME-08-2, Rev. I NP-Attachment, "Meeting Handouts from the December 13, 2007 Meeting with Wolf Creek and NRR on H*/B*" NON-PROPRIETARY Westinghouse Non-Proprietary Class 3 LTR-CDME-08-2, Rev. I NP-Attachment Wolf Creek Nuclear Operating Corporation Meeting Handouts from the December 13, 2007 Meeting with Wolf Creek and NRR on H*/B*January 11, 2008 Westinghouse Electric Company LLC.P.O. Box 158 Madison, PA 15663© 2008 Westinghouse Electric Company LLC All Rights Reserved H *Calculation Process Wolf Creek/NRC/Westinghouse Working Meeting 12/13/2007 1
H* Calculation Flow Chart a,c,e 2 Details of Analysis Models* Review Westinghouse Analysis Tools i NRC Present Review Analysis 3 Crevice Pressure Models Depth Dependent Model Compared to Limiting Median Crevice Pressure 4 Discussion on Depth Dependent Crevice Pressure" RAI questioned use of "limiting median" crevice pressure-This was debated at length by W and chosen as the most conservative approach in 2006-RAI recommended use of "depth dependent" crevice pressure as more conservative based on use of WCAP equations and crevice pressure test data" Crevice length based on H* (assumed)* Pullout forces based on results of tubesheet FEA analysis in WCAP" H* WCAP FEA results were based on NOP conditions (pressure and temperature) ace* Consistent use of SLB condition yields significantly shorter H*5 H *vs.Crevice Pressure Models (circa January 2007-White Paper, Rev 0)a,c,e 6 Current Status- December 2007* After review of NRC analysis-Resulted in 2-pass H* calculation using depth based crevice pressure* Questioning attitude on all of our methods and inputs le Recognition of different approach to crevice pressure application 7
H* vs. Crevice Pressure Models a,c,e 8 H* vs. Crevice Pressure Models (September 2007) a,c,e 9-Discussion on Depth Dependent Crevice Pressure* W performed calculations based on depth-based crevice pressure-First pass to calibrate H* is based on full tubesheet depth-Second pass is based on the H* from the first pass* Depth Dependent Crevice Pressure is not the most conservative application for the entire tubesheet-Limiting median crevice pressure is more conservative for Rts>30 )-H* based on limiting median crevice pressure is expected to be the most conservative 0 Conservatisms identified in current review 10 Conservatisms Application of Crevice Pressure-Current analysis assumes total crevice pressure applied to both tube and tubesheet-Entire pressure is not transmitted-to the tubesheet* Published paper (Goodier)-If pressure on TS is reduced, H* decreases significantly
- Poisson effects are ignored-Pressure on tube ID causes local Poisson expansion and increased resistance to pullout when axial force is applied-Axial differential thermal expansion between tube and tubesheet causes Poisson expansion of tube due to friction resistance between the tube and tubesheet and increases the axial resistance 11 Effect of Reduced Pressure and Poisson Effect on Tubesheet Hole a,c,e 12 Effect of Consistent Application of SLB Conditions on FEA TS Displacement 13 H* Conclusion a,c,e 14 B* Discussion
- H* may not be limiting for all cases near center of TS Due to consistent application of SLB conditions to FEA model* No significant effect of contact pressure-Absence of correlation between loss coefficient and contact pressure has no effect-Analysis uses an essentially bounding correlation of.loss coefficient to contact pressure (Ref. RAI 2 Response & July Meeting)15 B* vs. H*a,c,e 16 Conclusion
- Recommended (September 20C B* is limiting at inspection profile)7) is bounding TS center but not greater than C of RAI 2 maximum H* shown in Appendix response-H* is limiting at all other radii Recommended H* (2007 most conservative-RAI 2 response) is e Bounds analysis using depth dependent crevice pressure assuming no tube below H*17 H* Uncertainties Example. Monte Carlo 18 H* Calculation Flow Chart a,ce 19 Integrated MC is not Possible a,c,e 20 Simulation for H*a,c,e 21 What is "H* mean"?22 Variability of H* in Individual Parameters a,c,e 23 H*- MC Results a,c,e 24 MC Results Based on Over-Conservative Crevice Pressure Model -(Demonstration Purposes Only)0.500-0.450-- Ifean=15.99413 0.400--0.350--0.300--0.250--0.200-7 0.150--0.100--0.050--0-000 12 14 16 1 8 20 5% 7/ 5%14.5669 17.4562 Discussion on Alpha (a significant variable for H*)* Issue-The Code provides values of alpha for different materials for design which are required for use for certified design-Other data indicates that alpha may vary from the Code value depending on specific tests (i.e. ANTER data)" Conundrum-There are many design circumstances which would be more or less conservative if a non-Code value of alpha were used, e.g.,* Bolting loads* Tube loads in once-through SG-Does that mean all designs are potentially non-conservative?" Conclusion for MC Analysis-Have to settle on a meanvalue of alpha but recognize that the value may vary* The code provides little guidance on variability 9 Individual test may provide basis of variability but may have questionable pedigree-Use the mean value with the greatest pedigree (ASME Code Value)-Use the variability defined by individual test (ANTER) data 26 Discussion on Residual Pullout Force Hydraulic Expansion process is controlled to achieve minimum expansion pressure-Tolerance is one-sided in greater expansion pressure direction-If minimum expansion pressure is not achieved, the tube is re-expanded to meet the required minimum pressure-It is possible for an entire expansion to be missed, but all tubes that were expanded achieved at least the minimum expansion pressure All tests that have been performed have demonstrated positive pullout force-Several different test programs-Tube "locks up" after very small translation in ideal test-Real SG conditions cause tube and tubesheet bending "that lock" up tube even at cold conditions (e.g., tube hole runout, misalignment)
.Temperature and pressure multiply the lockup forces-Imperfections that cause tube cracking lock the tube in place (BLG/OXP) a,c,e Room temperature data is used to avoid correction for temperature effects-Uncertainty ofoc Variability depends on values of ETS, Et and Syt-This requires the dependent input calculations using the pullout test data 27 Other Conservatisms a,c,e 28 Detection of Tube Separation at H** The prerequisite for tube pullout is complete tube separation at, or below, H*-H* is defined as the point where the pullout forces are equilibrated
-Independent confirmation .that forces are not transmitted below H** Non-prototypic (but highly conservative with respect to H) test suggests .that under ideal conditions a very small"slip" may occur-Extremely unlikely Assume 360 degree TW crack at H* or below-Preliminary mockup of two tubes butted together in a collar look like a tube-end signal to bobbin-/ in. long 40%TW xO.005" wide EDM notch is clearly visible to bobbin in straight tube 29