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MONTHYEARML16095A0922016-03-31031 March 2016 Large Scale Penetration and Head Loss Test Plan 4/12/16 Project stage: Other ML16095A0782016-04-12012 April 2016 Slides for the WCGS Meeting Discussion 4/12/16 Project stage: Meeting ML16095A0852016-04-12012 April 2016 Large Scale Head Loss Test Specification 4/12/16 Project stage: Other ML16095A0802016-04-12012 April 2016 Large Scale Penetration Test Specification 4/12/16 Project stage: Other ML16106A1742016-04-22022 April 2016 Summary of Meeting with Wolf Creek Nuclear Operating Company to Discuss the Generic Safety Issue (GSI)-191 Testing Plan/Fiber Penetration and Head Loss Testing Approach for Wolf Creek Generating Station Project stage: Meeting 2016-04-12
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Category:Meeting Briefing Package/Handouts
MONTHYEARML24311A1572024-11-0606 November 2024 Slides for Pre-submittal Public Teleconference Meeting for License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML24180A0092024-06-28028 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 ML1016901162010-06-16016 June 2010 6/16/2010 Construction Reactor Oversight Process Category 2 Public Meeting Handout: Meeting Slides (Enforcement Cases) 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 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 2024-06-28
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24311A1572024-11-0606 November 2024 Slides for Pre-submittal Public Teleconference Meeting for License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML24180A0092024-06-28028 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 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). 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 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 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 2024-06-28
[Table view] |
Text
Fiber Penetration and Head Loss Testing Approach Meeting with NRC April 12, 2016 1
Outline
- Communicate Wolf Creek testing approach for fiber penetration and strainer head loss
- Overview of Wolf Creek Testing Program
- Fiber Penetration Testing Approach
- Strainer Head Loss Testing Approach 2
Overview of Sump Strainers Strainer A Strainer B 3
Overview of Testing Program
- Perform tank tests at Alden for fiber penetration and Flow strainer head loss Direction
- Use prototypical strainer Test modules for head loss testing Strainer
- Modify prototypical strainer modules for penetration Debris Introduction testing to eliminate bridging & Mixing
- Test strainer modules have Section same disk size, perforation size and core tube diameter Plenum as the plant strainer Box
- Maintain turbulence level for complete transport of fine To Flow debris 4 Loop
Overview of Testing Program (contd)
- Use methods previously reviewed by the NRC
- Similar to recent tank tests for Florida Power & Light at Alden witnessed by the NRC staff
- Follow NEI guidance on fibrous debris preparation*
- Determine threshold debris load that meets in-vessel and head loss criteria using test results
- Projected test start date: May 9, 2016 ZOI Fibrous Debris Preparation: Processing, Storage and Handling, Rev. 1, Jan 2012 (ADAMS Accession No. ML120481057) 5
Fiber Penetration Testing Approach
- Develop a curve fit from testing data to characterize rates of prompt and long-term penetration
- Apply curve fit to quantify total fiber penetration for the fiber load of each break at bounding plant conditions
- Determine compliance with the in-vessel fibrous debris quantity limit (WCAP-17788)
- Perform 30-day extrapolation for total fiber penetration as input to ex-vessel downstream effects analysis 6
Prevent Bridging for Penetration Testing
- Modified prototype strainer to eliminate possible bridging of fiber between adjacent disks, and between the strainer and its surrounding walls
- Preventing bridging in fiber-only penetration testing allows fiber to reach the perf plates and is conservative
- Test strainer module modification
- Remove every other disk
- Remove seismic cables
- Increase distance between edges of test strainer and surrounding walls
- Measured fiber penetration per unit area will be applied to the plant strainer surface area 7
Penetration Testing Conditions
- Prototypical pool chemistry at max pH (9.6)
- Testing temperature 120°F +/- 5°F
- Max strainer approach velocity (0.00612 ft/s)
- Prototypical fibrous debris concentrations
- Pool fiber concentration defined as total fiber quantity divided by pool volume
- Fiber concentration in test tank maintained at or below the prototypical value to allow debris bed to form slowly 8
Fiber Preparation and Introduction
- Nukon sheets baked single-sided into half thickness and cut into 2 x 2 cubes
- Debris preparation per the latest NEI Guidance*
- Fiber will be added to the test tank in batches
- Batching size will increase gradually to facilitate fiber bed formation on test strainer
- Total test fiber quantity will bound the max fiber load of largest DEGB ZOI Fibrous Debris Preparation: Processing, Storage and Handling, Rev. 1, Jan 2012 (ADAMS Accession No. ML120481057) 9
Collect Time-Dependent Penetration Data
- Penetrated fiber collected in 5-µm filter bags
- Each batch begins with a set of clean bags
- To measure long-term penetration, extended runtime and multiple bag changes will be done for selected batches
- Total runtime of the test exceeds duration from start of an accident to hot leg recirculation switchover
- A curve-fit will be developed to adequately model and bound testing results
- The curve-fit characterizes both prompt and long-term penetration 10
Head Loss Testing Approach
- Measure debris bed head loss for debris loading of various break sizes on a prototypical test module
- No modifications to test modules as done for penetration testing
- Chemical debris will not be added until all conventional debris has been introduced to test tank and head loss allowed to stabilize
- Perform flow sweeps for adjusting measured head losses to plant conditions
- After adding all conventional debris and at end of test 11
Head Loss Testing Approach (contd)
- Perform temperature sweep after adding all conventional debris to characterize debris bed
- Head Loss Test Conditions:
- Prototypical sump water chemistry at min pH (8.7)
- Test temperature approximately 120°F +/- 5°F
- Approach velocity from max strainer flow rate and net strainer surface area (0.00615 ft/s)
- Two head loss tests planned
- Test 1: Full Debris Load Test
- Test 2: Thin Bed Test
- Contingency test may be conducted depending on results of previous tests 12
Test 1: Full Debris Load Test
- Fibrous and particulate debris batched into test tank as homogeneous mixtures
- Addition of conventional debris ends when head loss is near prescribed value based on pump NPSH margin and strainer structural limit
- No alternating additions of fiber fines and small pieces 13
Test 1: Full Debris Load Test (contd)
- Cumulative conventional debris quantities of intermediate batches match debris loads of multiple break sizes
- Head loss allowed to stabilize before continuing addition
- Chemical debris batched into test tank after completing all conventional debris addition
- Head loss allowed to stabilize after each addition 14
Test 2: Thin Bed Test
- Particulate debris load for Test 2 will be informed by the threshold breaks identified in Test 1
- Particulate debris added to test tank at the beginning of test
- Nukon fiber fines added in batches until thin-bed conditions are met
- Chemical debris batched in afterwards 15
Test Debris Types Test Materials Debris Types at Plant Nukon
- Fibrous Content of Thermolag Pulverized Acrylic or
- IOZ, Epoxy and Alkyds Silicon Flour (10 µm)
- Particulate Content of Thermolag PCI PWR Dirt/Dust Mix* Latent Particulate Aluminum Oxyhydroxide Aluminum Precipitate Debris The size distribution of PCI PWR Dirt/Dust Mix meets requirements in Appendix VII of NEI 04-07 for surrogate of latent particulate debris 16
Quantity of Chemical Debris
- Evaluated chemical precipitate quantities using deterministic method per WCAP-16530-NP-A
- Max sump pool mass and temperature to increase aluminum release
- Max pH to increase aluminum release
- Conservatively higher aluminum inventory
- Max quantities of E-Glass of largest DEGB 17
Closing
- Wolf Creek is planning to use methods previously reviewed by the NRC staff
- Penetration data will be used to develop a curve fit that can be applied to any debris load (up to max for WCNOC)
- Head Loss test results will establish a threshold debris load
- Analysis will determine the threshold debris load that meets both the in-vessel and head loss criteria
- Threshold debris load will determine the break sizes that pass deterministically 18
Closing
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