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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
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RIC 2006 Session W3D GSI 191 Industry Actions for GSI 191 Maurice (Mo) Dingler Technical Staff Engineer
Wolf Creek Nuclear Operating Company 3/8/06 2 Key Message GSI 191 is a priority issue for the industry Licensees are implementing hardware changes at the earliest possible outage The many facets of GSI 191 resolution are stretching the capabilities of the industry to resolve all facets by end of 2007
-Chemical effects issue is evolving as tests are being completed by the
industry-Downstream effects of debris on fuel is not a well understood phenomena-Manufacturing, scheduling ,strainer testing 3 Industry Produced Documents major onesNEI 02-01 "Condition Assessment Guide lines Debris Source Inside PWR Containments"NEI 04-07 "Pressurized Water Reactor Sump Performance Evaluation Methodology"WCAP 16362 -NP "PRA Modeling for Sump Blockage"WCAP 16406-P "Evaluation of Downstream Sump Debris Efforts in Support of GSI 191"WCAP 16204 "Evaluation of Potential WRG&EPG Changes to address NRC Bulletin 2003-01 Recommendations"Letter 2005-429 "Transmittal of two WOG Documents -Template to Support WOG chemistry Efforts Follow on Testing and Framework to InterimSafety Assessment for GSI 191"WCAP 16530 "Evaluation of Post-Accident Chemical Effects in Containment Sump Fluids to Support GSI 191" EPRI 101805 "Design Basis Accident Testing of PWR Unqualified Original Equipment Manufacturer Coatings" 4 After Initial Evaluations Plants reviewing evaluations for refinements to the initial evaluation Downstream Wear/ Blockage
-Pumps/Valves/Fuel concerns Possible solutions
-Change out valves and pump wear surfaces
-Change the debris source term Change insulation Install debris interceptorHave vendor test to determi ne screen specific bypass factorDetermine hardness factors of the certain debris Combination of all 5 After Initial Evaluations Chemical Effects
-Data provided to hardware vendors to determine head loss with a plant specific debris mix and
screen-Head loss concerns Possible solutions
-Install screens with margin to handle
-Change the Buffer agent to less "reactive"agent
-Combination of all 6 After Initial Evaluations NOTE-Each potential solution is plant depended and can impact other aspects of the evaluation 7 Future issues This is a change in the License basis for the plant
-Methods has to be in place to maintain as-built to the evaluation or evaluate any changes Understand the evaluation Know your margins
-Coatings nonqualified
-Latent debris
-Changes to flow balances when the throttle value openings are change. -Changes in coating types -use generic or specific
-Changes in insulations 8 Future Issues Cont.
-Examples of new programs that will be needed to be put in place Latent Debris
-Periodic surveys that monitor changes-NRC SE Requirement
-Enhancements to current cont ainment cleanliness programs Coatings--Periodic assessment be identifie d, described, and implemented during routine outages-NRC SE Requirements Enhancement to Equipment /Rad Protection labeling programs
-need to understand changes to amounts 9 Summary The evaluations will be completed. Sump screens can and will be replaced Downstream effects will be addressed Chemical effects will be addressed Plants will need to understand the evaluations so they can address future
issues as they occur.