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Category:Slides and Viewgraphs
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
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
ML0713506512007-05-0808 May 2007
Slides, Category 2 Public Meeting with NEI on the Implications of the Wolf Creek Dissimilar Metal Weld Inspections.
ML0713506532007-05-0808 May 2007
Slides, Recommendations for Critical Flaw Size Calculations (in Wolf Creek Advanced Fea Project).
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.
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
ML0632100802006-11-16016 November 2006
Industry Presentations: Nov. 16, 2006 Public Meeting
ML0632100772006-11-16016 November 2006
NRC Presentation: NRC Perspective on Wolf Creek Inspection Results
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
ML0617902332006-03-0808 March 2006
RIC 2006 Presentation - W3D - Maurice E. Dingler - GSI 191
ML0516705662005-06-16016 June 2005
Summary of Annual Performance Assessment Meeting with NRC Re Oversight Process and Safety Performance at Wolf Creek Generating Station
2023-10-16
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Text
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.
