|
|
| Line 18: |
Line 18: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:1 Core Design and Safety Analysis Methodology Transition License Amendment Request September 20, 2012Wolf Creek Nuclear O perating CorporationWCNOC-NRC Pre-app lication Meeting 2 Meeting Agenda*Meeting Purpose / Objectives*Introductions*Transition to Westinghouse Analysis Methodologies-Analysis Methodologies-Alternative Source Term-SetpointUncertainty Analyses*License Amendment Request (LAR) Content and Schedule*Questions/Discussion 3 Introductions*NRC*WCNOC Team *Westinghouse Support *Teleconference Attendees 4 4 Transition to Westinghouse Analysis Methodologies*Current State-WCNOC'sCore Design & Safety Analysis organizations performed t he USAR Chapter 4 and 15 analyses in-house*The USAR Chapter 4 Core Design and Thermal-Hydraulic (T-H) analyses are performed by WCNOC using standard Westinghouse methods through a Technology Transfer agreement*The USAR Chapter 15 non-LOCA transient analysis are performed by WCNOC using vendor-independent methods 5*Current State (cont.)*The USAR Chapter 15 LOCA analyses are performed by Westinghouse*Reactor Trip System (RTS) and Engineered Safety Features Actuation System (ESFAS) instrumentationsetpointsperformed by WCNOC Transition to Westinghouse Analysis Methodologies 6 6 Transition to Westinghouse Analysis Methodologies*Future State-The bulk of the safety analyses will be standard Westinghouse analysis methodologies*Containment response to be addressed when changes are required to support plant modifications-All Westinghouse methods previously approved by the NRC for application at plants like WCGS-All analyses to be performed by Westinghouse in accordance with Westinghouse QA processes 7 7 Transition to Westinghouse Analysis Methodologies*Future State (cont.)-Core design and fuel rod design*No change for Core Design or Fuel Rod design tools/methods-Non-LOCA Transient Analyses*W-RETRAN-02 and VIPRE-W-Apply Alternative Source Term in radiological dose consequences analyses*Provide additional margin for control room/control building envelope in-leakage requirements-RTS and ESFAS instrumentationsetpointsand supporting uncertainty analyses being performed | | {{#Wiki_filter:WCNOC-NRC Pre-application Meeting Core Design and Safety Analysis Methodology Transition License Amendment Request September 20, 2012 Wolf Creek Nuclear Operating Corporation 1 |
|
| |
|
| using current Westinghousesetpointmethodology 8 8 Transition to Westinghouse Analysis Methodologies*Teaming Agreement with Westinghouse-Westinghouse is responsible for all Core Design and Safety Analysis (CDSA) activities at WCGS*Westinghouse maintains an office at the site -Currently 3 Westinghouse CDSA employees are on site
| | Meeting Agenda |
| -Supplemented by Safety Analysis and Licensing staff at HQ and Dallas*Activities include:-Methodology transition support
| | * Meeting Purpose / Objectives |
| -Full scope core design (including upcoming Cycle 20)-Plant support in the CDSA function area 9 9 Transition to Westinghouse Analysis Methodologies*Summary of Important Changes-Safety analyses will be performed to support a future measurement uncertainty recapture (MUR) poweruprateapplication*No current plans to pursue the MURuprate-DNB Correlations used with VIPRE-W*WRB-2 will continue to be used as the primary DNB correlation to be used for T/H analyses*ABB-NV and WLOP DNB correlations will be used for low-pressure conditions or below the first mixing vane grid 10 10 Transition to Westinghouse Analysis Methodologies*Summary of Important Changes (cont.) -Non-LOCA transients and accidents*W-RETRAN-02 used in most non-LOCA analyses*Continued use of LOFTRAN code in selected analyses *Continued use of TWINKLE and FACTRAN 1-D kinetics codes for reactivity insertion transient analyses 11 11 Transition to Westinghouse Analysis Methodologies*Summary of Important Changes (cont.)-Steam Generator Tube Rupture*Current WCNOC methodology shows SG overfill*Westinghouse methodology is margin to overfill*The revised SGTR analysis using Westinghouse methodology shows margin to overfill-Supporting reactor operator response time evaluations in progress -Dose consequences are calculated assuming overfill does not occur 12 12 Transition to Westinghouse Analysis Methodologies*Summary of Important Changes (cont.)-InstrumentationSetpoints*Calculations being performed on RTS Instrumentation, ESFAS Instrumentation, and Loss of Power Diesel Generator (LOP DG) Start Instrumentation Functions using current Westinghousesetpointmethodology*Adopt TSTF-493 Rev. 4, Option B 13 13 Transition to Westinghouse Analysis Methodologies*Summary of Important Changes (cont.)-Alternative Source Term (per RegGuide 1.183) will be used in radiological dose
| | * Introductions |
| | * Transition to Westinghouse Analysis Methodologies |
| | - Analysis Methodologies |
| | - Alternative Source Term |
| | - Setpoint Uncertainty Analyses |
| | * License Amendment Request (LAR) Content and Schedule |
| | * Questions/Discussion 2 |
|
| |
|
| consequences calculations*Offsite and Control Room Dose calculations only*No changes to the EQ dose analyses 14 14 Transition to Westinghouse Analysis Methodologies*Alternative Source Term (AST) | | ===Introductions=== |
| Implementation-Consistent withRegGuide 1.183, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Plants"-Any exceptions to theRegGuide will be identified-Full Scope Implementation*RegGuide 1.183 C. 1.2.1-Full implementationaddessesall characteristics of the AST, i.e., the composition and magnitude of the radioactive material, its chemical and physical form, and the timing of its release 15 15 Transition to Westinghouse Analysis Methodologies*AST Implementation (cont.)-No changes to the EQ dose analyses*RegGuide 1.183 C. 1.3.5-Licensees may use either the TID 14844 or AST assumptions for performing the EQ analyses-New atmospheric dispersion (X/Q) values are being calculated*EAB and LPZ (X/Q) values are being calculated in accordance withRegGuide 1.145*Control Room (X/Q) values were calculated in accordance withRegGuide 1.194 16 16 Transition to Westinghouse Analysis Methodologies*AST Implementation (cont.)-Current licensing basis changes associated with the reanalysis*TEDE acceptance criterion*Revised analysis assumptions*Revised analysis results 17 17 Transition to Westinghouse Analysis Methodologies*AST Implementation (cont.)-Dose consequence analyses reanalyzed with AST*MainSteamlineBreak (USAR Section 15.1.5.3)*Loss of Non-Emergency AC Power (USAR Section 15.2.6.3)*Locked Rotor (USAR Section 15.3.3.3) | | * NRC |
| *Rod Ejection (USAR Section 15.4.8.3)*Letdown Line Break (USAR Section 15.6.2.1)*Steam Generator Tube Rupture (USAR Section 15.6.3.3)*Loss of Coolant Accident (USAR Section 15.6.5.4)*Waste Gas Decay Tank Failure (USAR Section 15.7.1)*Liquid Waste Tank Failure (USAR Section 15.7.2)*Fuel Handling Accident (USAR Section 15.7.4) 18 18 Transition to Westinghouse Analysis Methodologies*TSTF-493 Rev. 4, Option B-Scope:*RTS Instrumentation*ESFAS Instrumentation*LOP DG Start Instrumentation-Updated uncertainty analyses andsetpointswill be performed using the current Westinghousesetpoint methodology Transition to Westinghouse Analysis Methodologies*TSTF-493 Rev. 4, Option B (cont.)-TheSetpointControl Program (SCP) to be addressed in Section 5.5.19 ofTSs-The Allowable Values will be removed from TS Table 3.3.1-1, Table 3.3. | | * WCNOC Team |
| 2-1, and SR 3.3.5.3-SR 3.3.5.3 TripSetpointwill be relocated to SCP-The Nominal TripSetpoints, As Left Tolerance values, As Found Toleranc e values and operability determination criteria will be included in the SCP 19 Transition to Westinghouse Analysis Methodologies*TSTF-493 Rev. 4, Option B (cont.)-The WCGS SCP will be based on the Westinghouse SCP Process Flow Diagram (recently discussed in the 6/28/12 NRC-DCPP meeting)20 21 21 Transition to Westinghouse Analysis Methodologies*License Amendment Request-Content*Attachments -Evaluation, Proposed TS Changes (Markups), Revised TS pages, Proposed TS Bases Changes (for information only), Proposed COLR Changes (for information only)*Enclosures-Plant specific WCAP Licensing Report>>Description of safety analyses assumptions>>Description of safety analyses results Transition to Westinghouse Analysis Methodologies*License Amendment Request (cont.)-Content (cont.)*Enclosures-Plant specific WCAP containing thesetpointmethodology for the uncertainty analyses and setpoints-Plant specific WCAP containing the WCGSsetpointcalculations-WCGS proposed SCP 22 Transition to Westinghouse Analysis Methodologies*License Amendment Request (cont.)-Content -Enclosures (cont.)*Report for full scope impl ementation of Alternative Source Term-Description of the analysis assumptions-Description of t he analysis results-Tables containing the CLB assumptions and results and reanalysis assumptions and results -A table identifying the conformance toRegGuide 1.183 and any exceptions-A table that address the issues identified in RIS 2006-04 23 24 24 Transition to Westinghouse Analysis Methodologies | | * Westinghouse Support |
| *License Amendment Request (cont.)-Potential Technical Specification Changes*TS 3.3.1, RTS Instrumentation*TS 3.3.2, ESFAS Instrumentation*TS 3.3.5, LOP DG St art Instrumentation*New TS 5.5.19,SetpointControl Program*TS 5.6.5, CORE OPERATING LIMITS REPORT (COLR) 25 Schedule*Submit LAR to NRCAugust 2013*NRC Acceptance Review *RAI Process*Start of Refueling Outage 20January 5, 2015*Cycle 21 StartupFebruary 9, 2015 26Questions/Discussion}} | | * Teleconference Attendees 3 |
| | |
| | Transition to Westinghouse Analysis Methodologies |
| | * Current State |
| | - WCNOCs Core Design & Safety Analysis organizations performed the USAR Chapter 4 and 15 analyses in-house |
| | * The USAR Chapter 4 Core Design and Thermal-Hydraulic (T-H) analyses are performed by WCNOC using standard Westinghouse methods through a Technology Transfer agreement |
| | * The USAR Chapter 15 non-LOCA transient analysis are performed by WCNOC using vendor-independent methods 4 |
| | |
| | Transition to Westinghouse Analysis Methodologies |
| | * Current State (cont.) |
| | * The USAR Chapter 15 LOCA analyses are performed by Westinghouse |
| | * Reactor Trip System (RTS) and Engineered Safety Features Actuation System (ESFAS) instrumentation setpoints performed by WCNOC 5 |
| | |
| | Transition to Westinghouse Analysis Methodologies |
| | * Future State |
| | - The bulk of the safety analyses will be standard Westinghouse analysis methodologies |
| | * Containment response to be addressed when changes are required to support plant modifications |
| | - All Westinghouse methods previously approved by the NRC for application at plants like WCGS |
| | - All analyses to be performed by Westinghouse in accordance with Westinghouse QA processes 6 |
| | |
| | Transition to Westinghouse Analysis Methodologies |
| | * Future State (cont.) |
| | - Core design and fuel rod design |
| | * No change for Core Design or Fuel Rod design tools/methods |
| | - Non-LOCA Transient Analyses |
| | * W-RETRAN-02 and VIPRE-W |
| | - Apply Alternative Source Term in radiological dose consequences analyses |
| | * Provide additional margin for control room/control building envelope in-leakage requirements |
| | - RTS and ESFAS instrumentation setpoints and supporting uncertainty analyses being performed using current Westinghouse setpoint methodology 7 |
| | |
| | Transition to Westinghouse Analysis Methodologies |
| | * Teaming Agreement with Westinghouse |
| | - Westinghouse is responsible for all Core Design and Safety Analysis (CDSA) activities at WCGS |
| | * Westinghouse maintains an office at the site |
| | - Currently 3 Westinghouse CDSA employees are on site |
| | - Supplemented by Safety Analysis and Licensing staff at HQ and Dallas |
| | * Activities include: |
| | - Methodology transition support |
| | - Full scope core design (including upcoming Cycle 20) |
| | - Plant support in the CDSA function area 8 |
| | |
| | Transition to Westinghouse Analysis Methodologies |
| | * Summary of Important Changes |
| | - Safety analyses will be performed to support a future measurement uncertainty recapture (MUR) power uprate application |
| | * No current plans to pursue the MUR uprate |
| | - DNB Correlations used with VIPRE-W |
| | * WRB-2 will continue to be used as the primary DNB correlation to be used for T/H analyses |
| | * ABB-NV and WLOP DNB correlations will be used for low-pressure conditions or below the first mixing vane grid 9 |
| | |
| | Transition to Westinghouse Analysis Methodologies |
| | * Summary of Important Changes (cont.) |
| | - Non-LOCA transients and accidents |
| | * W- RETRAN-02 used in most non-LOCA analyses |
| | * Continued use of LOFTRAN code in selected analyses |
| | * Continued use of TWINKLE and FACTRAN 1-D kinetics codes for reactivity insertion transient analyses 10 |
| | |
| | Transition to Westinghouse Analysis Methodologies |
| | * Summary of Important Changes (cont.) |
| | - Steam Generator Tube Rupture |
| | * Current WCNOC methodology shows SG overfill |
| | * Westinghouse methodology is margin to overfill |
| | * The revised SGTR analysis using Westinghouse methodology shows margin to overfill |
| | - Supporting reactor operator response time evaluations in progress |
| | - Dose consequences are calculated assuming overfill does not occur 11 |
| | |
| | Transition to Westinghouse Analysis Methodologies |
| | * Summary of Important Changes (cont.) |
| | - Instrumentation Setpoints |
| | * Calculations being performed on RTS Instrumentation, ESFAS Instrumentation, and Loss of Power Diesel Generator (LOP DG) Start Instrumentation Functions using current Westinghouse setpoint methodology |
| | * Adopt TSTF-493 Rev. 4, Option B 12 |
| | |
| | Transition to Westinghouse Analysis Methodologies |
| | * Summary of Important Changes (cont.) |
| | - Alternative Source Term (per Reg Guide 1.183) will be used in radiological dose consequences calculations |
| | * Offsite and Control Room Dose calculations only |
| | * No changes to the EQ dose analyses 13 |
| | |
| | Transition to Westinghouse Analysis Methodologies |
| | * Alternative Source Term (AST) |
| | Implementation |
| | - Consistent with Reg Guide 1.183, Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Plants |
| | - Any exceptions to the Reg Guide will be identified |
| | - Full Scope Implementation |
| | * Reg Guide 1.183 C. 1.2.1- Full implementation addesses all characteristics of the AST, i.e., the composition and magnitude of the radioactive material, its chemical and physical form, and the timing of its release 14 |
| | |
| | Transition to Westinghouse Analysis Methodologies |
| | * AST Implementation (cont.) |
| | - No changes to the EQ dose analyses |
| | * Reg Guide 1.183 C. 1.3.5- Licensees may use either the TID 14844 or AST assumptions for performing the EQ analyses |
| | - New atmospheric dispersion (X/Q) values are being calculated |
| | * EAB and LPZ (X/Q) values are being calculated in accordance with Reg Guide 1.145 |
| | * Control Room (X/Q) values were calculated in accordance with Reg Guide 1.194 15 |
| | |
| | Transition to Westinghouse Analysis Methodologies |
| | * AST Implementation (cont.) |
| | - Current licensing basis changes associated with the reanalysis |
| | * TEDE acceptance criterion |
| | * Revised analysis assumptions |
| | * Revised analysis results 16 |
| | |
| | Transition to Westinghouse Analysis Methodologies |
| | * AST Implementation (cont.) |
| | - Dose consequence analyses reanalyzed with AST |
| | * Main Steamline Break (USAR Section 15.1.5.3) |
| | * Loss of Non-Emergency AC Power (USAR Section 15.2.6.3) |
| | * Locked Rotor (USAR Section 15.3.3.3) |
| | * Rod Ejection (USAR Section 15.4.8.3) |
| | * Letdown Line Break (USAR Section 15.6.2.1) |
| | * Steam Generator Tube Rupture (USAR Section 15.6.3.3) |
| | * Loss of Coolant Accident (USAR Section 15.6.5.4) |
| | * Waste Gas Decay Tank Failure (USAR Section 15.7.1) |
| | * Liquid Waste Tank Failure (USAR Section 15.7.2) |
| | * Fuel Handling Accident (USAR Section 15.7.4) 17 |
| | |
| | Transition to Westinghouse Analysis Methodologies |
| | * TSTF-493 Rev. 4, Option B |
| | - Scope: |
| | * RTS Instrumentation |
| | * ESFAS Instrumentation |
| | * LOP DG Start Instrumentation |
| | - Updated uncertainty analyses and setpoints will be performed using the current Westinghouse setpoint methodology 18 |
| | |
| | Transition to Westinghouse Analysis Methodologies |
| | * TSTF-493 Rev. 4, Option B (cont.) |
| | - The Setpoint Control Program (SCP) to be addressed in Section 5.5.19 of TSs |
| | - The Allowable Values will be removed from TS Table 3.3.1-1, Table 3.3.2-1, and SR 3.3.5.3 |
| | - SR 3.3.5.3 Trip Setpoint will be relocated to SCP |
| | - The Nominal Trip Setpoints, As Left Tolerance values, As Found Tolerance values and operability determination criteria will be included in the SCP 19 |
| | |
| | Transition to Westinghouse Analysis Methodologies |
| | * TSTF-493 Rev. 4, Option B (cont.) |
| | - The WCGS SCP will be based on the Westinghouse SCP Process Flow Diagram (recently discussed in the 6/28/12 NRC-DCPP meeting) 20 |
| | |
| | Transition to Westinghouse Analysis Methodologies |
| | * License Amendment Request |
| | - Content |
| | * Attachments - Evaluation, Proposed TS Changes (Markups), Revised TS pages, Proposed TS Bases Changes (for information only), Proposed COLR Changes (for information only) |
| | * Enclosures |
| | - Plant specific WCAP Licensing Report |
| | >> Description of safety analyses assumptions |
| | >> Description of safety analyses results 21 |
| | |
| | Transition to Westinghouse Analysis Methodologies |
| | * License Amendment Request (cont.) |
| | - Content (cont.) |
| | * Enclosures |
| | - Plant specific WCAP containing the setpoint methodology for the uncertainty analyses and setpoints |
| | - Plant specific WCAP containing the WCGS setpoint calculations |
| | - WCGS proposed SCP 22 |
| | |
| | Transition to Westinghouse Analysis Methodologies |
| | * License Amendment Request (cont.) |
| | - Content - Enclosures (cont.) |
| | * Report for full scope implementation of Alternative Source Term |
| | - Description of the analysis assumptions |
| | - Description of the analysis results |
| | - Tables containing the CLB assumptions and results and reanalysis assumptions and results |
| | - A table identifying the conformance to Reg Guide 1.183 and any exceptions |
| | - A table that address the issues identified in RIS 2006-04 23 |
| | |
| | Transition to Westinghouse Analysis Methodologies |
| | * License Amendment Request (cont.) |
| | - Potential Technical Specification Changes |
| | * TS 3.3.1, RTS Instrumentation |
| | * TS 3.3.2, ESFAS Instrumentation |
| | * TS 3.3.5, LOP DG Start Instrumentation |
| | * New TS 5.5.19, Setpoint Control Program |
| | * TS 5.6.5, CORE OPERATING LIMITS REPORT (COLR) 24 |
| | |
| | Schedule |
| | * Submit LAR to NRC August 2013 |
| | * NRC Acceptance Review |
| | * RAI Process |
| | * Start of Refueling Outage 20 January 5, 2015 |
| | * Cycle 21 Startup February 9, 2015 25 |
| | |
| | Questions/Discussion 26}} |
Letter Sequence Meeting |
|---|
TAC:ME9495, Clarify Application of Setpoint Methodology for LSSS Functions (Open) |
|
MONTHYEARML12249A0292012-09-0606 September 2012
9/20/12 Notice of Meeting with Wolf Creek Nuclear Operating Corporation to Discuss Transition from Current to NRC-Approved Westinghouse Methodologies for Performing the Core Design and Non-LOCA Safety Wolf Creek Station
Project stage: Meeting
ML12263A3622012-09-20020 September 2012
Pre-application Meeting Slide Core Design and Safety Analysis Methodology Transition License Amendment Request TAC No. ME9495)
Project stage: Meeting
ML12276A2652012-11-0101 November 2012
Meeting Summary with Wolf Creek Nuclear Operating Corporation to Discuss Transition from Current to NRC-Approved Westinghouse Methodologies for Performing the Core Design and Non-LOCA Safety Analysis at Wolf Creek
Project stage: Meeting
ET 13-0023, License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis2013-08-13013 August 2013
License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis
Project stage: Request
2012-09-20
[Table View] |
|
|---|
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
WCNOC-NRC Pre-application Meeting Core Design and Safety Analysis Methodology Transition License Amendment Request September 20, 2012 Wolf Creek Nuclear Operating Corporation 1
Meeting Agenda
- Meeting Purpose / Objectives
- Analysis Methodologies
- Alternative Source Term
- Setpoint Uncertainty Analyses
- License Amendment Request (LAR) Content and Schedule
Introductions
- Teleconference Attendees 3
Transition to Westinghouse Analysis Methodologies
- WCNOCs Core Design & Safety Analysis organizations performed the USAR Chapter 4 and 15 analyses in-house
- The USAR Chapter 4 Core Design and Thermal-Hydraulic (T-H) analyses are performed by WCNOC using standard Westinghouse methods through a Technology Transfer agreement
- The USAR Chapter 15 non-LOCA transient analysis are performed by WCNOC using vendor-independent methods 4
Transition to Westinghouse Analysis Methodologies
- Reactor Trip System (RTS) and Engineered Safety Features Actuation System (ESFAS) instrumentation setpoints performed by WCNOC 5
Transition to Westinghouse Analysis Methodologies
- The bulk of the safety analyses will be standard Westinghouse analysis methodologies
- Containment response to be addressed when changes are required to support plant modifications
- All Westinghouse methods previously approved by the NRC for application at plants like WCGS
- All analyses to be performed by Westinghouse in accordance with Westinghouse QA processes 6
Transition to Westinghouse Analysis Methodologies
- Core design and fuel rod design
- No change for Core Design or Fuel Rod design tools/methods
- Non-LOCA Transient Analyses
- Apply Alternative Source Term in radiological dose consequences analyses
- Provide additional margin for control room/control building envelope in-leakage requirements
- RTS and ESFAS instrumentation setpoints and supporting uncertainty analyses being performed using current Westinghouse setpoint methodology 7
Transition to Westinghouse Analysis Methodologies
- Westinghouse is responsible for all Core Design and Safety Analysis (CDSA) activities at WCGS
- Currently 3 Westinghouse CDSA employees are on site
- Supplemented by Safety Analysis and Licensing staff at HQ and Dallas
- Methodology transition support
- Full scope core design (including upcoming Cycle 20)
- Plant support in the CDSA function area 8
Transition to Westinghouse Analysis Methodologies
- Summary of Important Changes
- Safety analyses will be performed to support a future measurement uncertainty recapture (MUR) power uprate application
- No current plans to pursue the MUR uprate
- DNB Correlations used with VIPRE-W
- WRB-2 will continue to be used as the primary DNB correlation to be used for T/H analyses
- ABB-NV and WLOP DNB correlations will be used for low-pressure conditions or below the first mixing vane grid 9
Transition to Westinghouse Analysis Methodologies
- Summary of Important Changes (cont.)
- Non-LOCA transients and accidents
- W- RETRAN-02 used in most non-LOCA analyses
- Continued use of LOFTRAN code in selected analyses
- Continued use of TWINKLE and FACTRAN 1-D kinetics codes for reactivity insertion transient analyses 10
Transition to Westinghouse Analysis Methodologies
- Summary of Important Changes (cont.)
- Steam Generator Tube Rupture
- Current WCNOC methodology shows SG overfill
- The revised SGTR analysis using Westinghouse methodology shows margin to overfill
- Supporting reactor operator response time evaluations in progress
- Dose consequences are calculated assuming overfill does not occur 11
Transition to Westinghouse Analysis Methodologies
- Summary of Important Changes (cont.)
- Instrumentation Setpoints
- Calculations being performed on RTS Instrumentation, ESFAS Instrumentation, and Loss of Power Diesel Generator (LOP DG) Start Instrumentation Functions using current Westinghouse setpoint methodology
Transition to Westinghouse Analysis Methodologies
- Summary of Important Changes (cont.)
- Alternative Source Term (per Reg Guide 1.183) will be used in radiological dose consequences calculations
- Offsite and Control Room Dose calculations only
- No changes to the EQ dose analyses 13
Transition to Westinghouse Analysis Methodologies
Implementation
- Consistent with Reg Guide 1.183, Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Plants
- Any exceptions to the Reg Guide will be identified
- Full Scope Implementation
- Reg Guide 1.183 C. 1.2.1- Full implementation addesses all characteristics of the AST, i.e., the composition and magnitude of the radioactive material, its chemical and physical form, and the timing of its release 14
Transition to Westinghouse Analysis Methodologies
- AST Implementation (cont.)
- No changes to the EQ dose analyses
- New atmospheric dispersion (X/Q) values are being calculated
- Control Room (X/Q) values were calculated in accordance with Reg Guide 1.194 15
Transition to Westinghouse Analysis Methodologies
- AST Implementation (cont.)
- Current licensing basis changes associated with the reanalysis
- TEDE acceptance criterion
- Revised analysis assumptions
- Revised analysis results 16
Transition to Westinghouse Analysis Methodologies
- AST Implementation (cont.)
- Dose consequence analyses reanalyzed with AST
- Main Steamline Break (USAR Section 15.1.5.3)
- Loss of Non-Emergency AC Power (USAR Section 15.2.6.3)
- Locked Rotor (USAR Section 15.3.3.3)
- Rod Ejection (USAR Section 15.4.8.3)
- Letdown Line Break (USAR Section 15.6.2.1)
- Loss of Coolant Accident (USAR Section 15.6.5.4)
- Waste Gas Decay Tank Failure (USAR Section 15.7.1)
- Liquid Waste Tank Failure (USAR Section 15.7.2)
- Fuel Handling Accident (USAR Section 15.7.4) 17
Transition to Westinghouse Analysis Methodologies
- Scope:
- LOP DG Start Instrumentation
- Updated uncertainty analyses and setpoints will be performed using the current Westinghouse setpoint methodology 18
Transition to Westinghouse Analysis Methodologies
- The Setpoint Control Program (SCP) to be addressed in Section 5.5.19 of TSs
- The Allowable Values will be removed from TS Table 3.3.1-1, Table 3.3.2-1, and SR 3.3.5.3
- SR 3.3.5.3 Trip Setpoint will be relocated to SCP
- The Nominal Trip Setpoints, As Left Tolerance values, As Found Tolerance values and operability determination criteria will be included in the SCP 19
Transition to Westinghouse Analysis Methodologies
- The WCGS SCP will be based on the Westinghouse SCP Process Flow Diagram (recently discussed in the 6/28/12 NRC-DCPP meeting) 20
Transition to Westinghouse Analysis Methodologies
- License Amendment Request
- Content
- Attachments - Evaluation, Proposed TS Changes (Markups), Revised TS pages, Proposed TS Bases Changes (for information only), Proposed COLR Changes (for information only)
- Plant specific WCAP Licensing Report
>> Description of safety analyses assumptions
>> Description of safety analyses results 21
Transition to Westinghouse Analysis Methodologies
- License Amendment Request (cont.)
- Content (cont.)
- Plant specific WCAP containing the setpoint methodology for the uncertainty analyses and setpoints
- Plant specific WCAP containing the WCGS setpoint calculations
- WCGS proposed SCP 22
Transition to Westinghouse Analysis Methodologies
- License Amendment Request (cont.)
- Content - Enclosures (cont.)
- Description of the analysis assumptions
- Description of the analysis results
- Tables containing the CLB assumptions and results and reanalysis assumptions and results
- A table identifying the conformance to Reg Guide 1.183 and any exceptions
- A table that address the issues identified in RIS 2006-04 23
Transition to Westinghouse Analysis Methodologies
- License Amendment Request (cont.)
- Potential Technical Specification Changes
Schedule
- Submit LAR to NRC August 2013
- Start of Refueling Outage 20 January 5, 2015
- Cycle 21 Startup February 9, 2015 25
Questions/Discussion 26
