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MONTHYEARML12298A4282012-10-26026 October 2012 Notice of Preapplication Meeting with Union Electric Company to Discuss Callaway Plant, Unit 1, License Amendment Request to Change Licensing Basis and Analysis of Integrated Head Assembly Consistent with Regulatory Guide 1.61 Revision 1 Project stage: Meeting ML12320A3052012-11-15015 November 2012 Licensee Slides for November 15, 2012 Public Meeting to Discuss License Amendment to Use Reg Guide 1.6 Revision 1 Project stage: Meeting ML12321A1882012-11-20020 November 2012 Summary of Preapplication Meeting with Union Electric Company to Discuss Callaway Plant, Unit 1, License Amendment Request to Change Licensing Basis and Analysis of Integrated Head Assembly Consistent with Regulatory Guide 1.61 Revision 1 Project stage: Meeting 2012-11-15
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Category:Meeting Briefing Package/Handouts
MONTHYEARML24157A0642024-06-13013 June 2024 Earls 2024 Workshop Presentation ULNRC-06767, Presentation Information for Planned Pre-Application Meeting2022-09-0606 September 2022 Presentation Information for Planned Pre-Application Meeting ULNRC-06753, Presentation Information for Pre-Submittal Meeting Regarding Updated Spent Fuel Criticality Safety Analysis2022-06-23023 June 2022 Presentation Information for Pre-Submittal Meeting Regarding Updated Spent Fuel Criticality Safety Analysis ML22047A0952022-02-15015 February 2022 Presentation Information for Planned Pre-Application Meeting (Closed Meeting), Non-Proprietary (Redacted) Version for Closed Meeting ML22047A0942022-02-15015 February 2022 Presentation Information for Planned Pre-Application Meeting (Public Meeting) ML21271A6132021-09-28028 September 2021 Enclosure 2: Callaway Unit 1 Presentation Information for Planned Pre-Application Meeting (Closed Meeting), Non-Proprietary (Redacted) Version for Closed Meeting ML21271A6122021-09-28028 September 2021 Enclosure 1: Callaway Unit 1 Presentation Information for Planned Pre-Application Meeting (Public Meeting) ML21211A0712021-07-30030 July 2021 Meeting Slides for Pre-submittal Teleconference to Discuss EP Revision LAR ML21123A2622021-05-0303 May 2021 Presentation Information for Planned Pre-Application Meeting (Closed Meeting), Non-Proprietary (Redacted) Version for Closed Meeting ML21123A2602021-05-0303 May 2021 Presentation Information for Planned Pre-Application Meeting (Public Meeting) ML21050A2042021-03-31031 March 2021 March 2021 Meeting Slides ML20248H4672020-09-0404 September 2020 Rict & 50.69 LARs - NRC Pre-Submittal Meeting Slides ML20170A2032020-06-24024 June 2020 6/24/2020 - Pre-Submittal Meeting for Callaway Plant License Amendment Request to Defer Steam Generator Eddy Current Testing ML19247B3842019-09-12012 September 2019 GSI-191 / GL 2004-02 Licensing Amendment Request ML18158A5532018-06-14014 June 2018 Pre-Submittal Meeting for Full Implementation of Alternative Source Term ML16236A0952016-08-25025 August 2016 and Wolf Creek Generating Station - August 25, 2016, Class 1E Electrical Equipment Air Conditioning System Pre-Application Meeting ML16152A1232016-06-0101 June 2016 Strainer Testing for GSI-191 ML14050A4022014-02-20020 February 2014 License Renewal Public Meeting Slides 2 20 2014 ML13042A1882013-02-11011 February 2013 01/31/2013 Summary of the Public Meeting to Discuss the Results of the Grand Gulf Nuclear Station License Renewal Inspection IR 05000483/20120092013-01-25025 January 2013 1/17/2013 - Summary of Public Meeting to Discuss the Results of the Callaway Nuclear Plant License Renewal Inspection (05000483-12-009) ML12320A3052012-11-15015 November 2012 Licensee Slides for November 15, 2012 Public Meeting to Discuss License Amendment to Use Reg Guide 1.6 Revision 1 ML12241A2912012-08-29029 August 2012 UHS Meeting Slides August 29, 2012 ML12241A2922012-08-29029 August 2012 Class 1E AC Meeting Slides August 29, 2012 ML1115400922011-06-0303 June 2011 Summary of Annual Performance Assessment Meeting with Union Electric Company to Discuss the Callaway Plant Performance for the NRC Inspection Period Ending December 31, 2010 ML1115304052011-05-26026 May 2011 Licensee Slide'S from 5/26/11 Pre-Application Meeting ML1008804082010-03-25025 March 2010 Licensee Slides Pre-LAR Submittal Telecon 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 ML0932104872009-11-17017 November 2009 Summary of Regulatory Conference with Ameren Ue Regarding Callaway Plant ML0927302752009-10-15015 October 2009 Summary of Meeting with Union Electric Company to Discuss Proposed Risk-Informed Technical Specification License Amendment for Callaway Plant, Unit 1, and Future Adoption of Initiative 4b ML0916002532009-06-0808 June 2009 Summary of Annual Performance Assessment Meeting with Amerenue for Callaway Plant ML0910502042009-04-14014 April 2009 Summary of Meeting with Amerenue to Discuss Engineering Related Topics Pertaining to Callaway ML0904400462009-01-13013 January 2009 Public Scoping Meeting Presentation Slides ML0815404352008-06-0202 June 2008 Summary of Meeting to Discuss Annual Safety Performance Assessment for Callaway for 2007 ML0802504052008-01-23023 January 2008 Licensee Handout for Meeting with Union Electric Company on the Callaway Plant Relief Request I3R-10 to Use Plastic Pipe in the Safety-Related Essential Service Water (ESW) System ML0729505272007-10-22022 October 2007 Summary of Meeting with Amerenue Callaway Plant to Discuss Various Topics, Including: Essential Service Water; Current Problem Identification & Resolution Crosscutting Issue; Recent Human Performance Improvements ML0721102382007-07-24024 July 2007 Performanc Contracting, Inc.'S Powerpoint Slide, Proposed Wolf Creek/Callaway Test Configuration ML0716000102007-06-0707 June 2007 Summary of Meeting with Union Electric Co Re Callaway Annual Performance Assessment ML0628602302006-10-12012 October 2006 Handout for Meeting with Nuclear Energy Institute (NEI) to Discuss Concerns Related to Operability Determination of Main Steam and Feedwater Isolation Valves with Dual Actuator Trains 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 ML0613001302006-05-0909 May 2006 Meeting Summary of 05/04/2006 end-of-cycle Performance Assessment ML0520804072005-07-27027 July 2005 Summary of Meeting with Union Electric Company Concerning Callaway Plant ML0330402882003-10-30030 October 2003 Meeting Handout Materials Regarding STARS-IRAG/NRC Meeting to Discuss Topics Taken from the June 10.11, 2003, Workshop ML0319206482003-06-10010 June 2003 Meeting Handouts for STARS-IRAG/NRC Workshop to Discuss Selected Topics Listed in the Agenda Attached to Meeting Notice ML0310604602003-04-15015 April 2003 Meeting Handout to Discuss Licensee'S Program to Replace the Steam Generators at Callaway ML0231200242002-11-0707 November 2002 Meeting Handouts - Meeting with Strategic Teaming and Resources Sharing - Integrated Regulatory Affairs Group ML0208705662002-04-15015 April 2002 Meetingsummary with Stars and the NRC to Inform the NRC About Current Stars Activities ML0208107562002-03-19019 March 2002 Operator Licensing Workshop Meeting Summary 2024-06-13
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24157A0642024-06-13013 June 2024 Earls 2024 Workshop Presentation ULNRC-06767, Presentation Information for Planned Pre-Application Meeting2022-09-0606 September 2022 Presentation Information for Planned Pre-Application Meeting ULNRC-06753, Presentation Information for Pre-Submittal Meeting Regarding Updated Spent Fuel Criticality Safety Analysis2022-06-23023 June 2022 Presentation Information for Pre-Submittal Meeting Regarding Updated Spent Fuel Criticality Safety Analysis ML22047A0942022-02-15015 February 2022 Presentation Information for Planned Pre-Application Meeting (Public Meeting) ML22047A0952022-02-15015 February 2022 Presentation Information for Planned Pre-Application Meeting (Closed Meeting), Non-Proprietary (Redacted) Version for Closed Meeting ML21271A6122021-09-28028 September 2021 Enclosure 1: Callaway Unit 1 Presentation Information for Planned Pre-Application Meeting (Public Meeting) ML21271A6132021-09-28028 September 2021 Enclosure 2: Callaway Unit 1 Presentation Information for Planned Pre-Application Meeting (Closed Meeting), Non-Proprietary (Redacted) Version for Closed Meeting ML21211A6012021-07-30030 July 2021 Annual Assessment Meeting (Public) ML21123A2622021-05-0303 May 2021 Presentation Information for Planned Pre-Application Meeting (Closed Meeting), Non-Proprietary (Redacted) Version for Closed Meeting ML21123A2602021-05-0303 May 2021 Presentation Information for Planned Pre-Application Meeting (Public Meeting) ML20248H4672020-09-0404 September 2020 Rict & 50.69 LARs - NRC Pre-Submittal Meeting Slides ML20170A2032020-06-24024 June 2020 6/24/2020 - Pre-Submittal Meeting for Callaway Plant License Amendment Request to Defer Steam Generator Eddy Current Testing ML19247B3842019-09-12012 September 2019 GSI-191 / GL 2004-02 Licensing Amendment Request ML18158A5532018-06-14014 June 2018 Pre-Submittal Meeting for Full Implementation of Alternative Source Term ML16236A0952016-08-25025 August 2016 and Wolf Creek Generating Station - August 25, 2016, Class 1E Electrical Equipment Air Conditioning System Pre-Application Meeting ML16152A1232016-06-0101 June 2016 Strainer Testing for GSI-191 ML14050A4022014-02-20020 February 2014 License Renewal Public Meeting Slides 2 20 2014 ML13042A1882013-02-11011 February 2013 01/31/2013 Summary of the Public Meeting to Discuss the Results of the Grand Gulf Nuclear Station License Renewal Inspection IR 05000483/20120092013-01-25025 January 2013 1/17/2013 - Summary of Public Meeting to Discuss the Results of the Callaway Nuclear Plant License Renewal Inspection (05000483-12-009) ML12320A3052012-11-15015 November 2012 Licensee Slides for November 15, 2012 Public Meeting to Discuss License Amendment to Use Reg Guide 1.6 Revision 1 ML12241A2912012-08-29029 August 2012 UHS Meeting Slides August 29, 2012 ML12241A2922012-08-29029 August 2012 Class 1E AC Meeting Slides August 29, 2012 ML12096A3942012-03-14014 March 2012 Enclosure 5: Callaway Public Meeting Slides ML1115400922011-06-0303 June 2011 Summary of Annual Performance Assessment Meeting with Union Electric Company to Discuss the Callaway Plant Performance for the NRC Inspection Period Ending December 31, 2010 ML1115304052011-05-26026 May 2011 Licensee Slide'S from 5/26/11 Pre-Application Meeting ML1008804082010-03-25025 March 2010 Licensee Slides Pre-LAR Submittal Telecon 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 ML0932104872009-11-17017 November 2009 Summary of Regulatory Conference with Ameren Ue Regarding Callaway Plant ML0927302752009-10-15015 October 2009 Summary of Meeting with Union Electric Company to Discuss Proposed Risk-Informed Technical Specification License Amendment for Callaway Plant, Unit 1, and Future Adoption of Initiative 4b ML0910502042009-04-14014 April 2009 Summary of Meeting with Amerenue to Discuss Engineering Related Topics Pertaining to Callaway ML0904400462009-01-13013 January 2009 Public Scoping Meeting Presentation Slides ML0815404352008-06-0202 June 2008 Summary of Meeting to Discuss Annual Safety Performance Assessment for Callaway for 2007 ML0802504052008-01-23023 January 2008 Licensee Handout for Meeting with Union Electric Company on the Callaway Plant Relief Request I3R-10 to Use Plastic Pipe in the Safety-Related Essential Service Water (ESW) System ML0729505272007-10-22022 October 2007 Summary of Meeting with Amerenue Callaway Plant to Discuss Various Topics, Including: Essential Service Water; Current Problem Identification & Resolution Crosscutting Issue; Recent Human Performance Improvements ML0721102382007-07-24024 July 2007 Performanc Contracting, Inc.'S Powerpoint Slide, Proposed Wolf Creek/Callaway Test Configuration ML0628602302006-10-12012 October 2006 Handout for Meeting with Nuclear Energy Institute (NEI) to Discuss Concerns Related to Operability Determination of Main Steam and Feedwater Isolation Valves with Dual Actuator Trains 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 ML0615106012006-05-23023 May 2006 EPRI HRA Users Group Review of Draft NUREG-1842 ML0611002222006-04-18018 April 2006 Summary of Meeting with Union Electric Company Regarding Callaway Plant, Which Discussed Recent Plant Performance and Various Topics ML0533202252005-12-0101 December 2005 Ri Schedule 05- Mcmurtray; Lessons Learned from Security-Based Table Top Drills ML0520804072005-07-27027 July 2005 Summary of Meeting with Union Electric Company Concerning Callaway Plant ML0430903882004-11-0404 November 2004 Docket No. 50-483 - Licensee'S Slides for Meeting Held on November 4, 2004, to Discuss Its Application on the Steam Generators Replacement in Fall 2005 (Tac No. MC4437) ML0422602762004-08-12012 August 2004 Meeting Summary of the August 8, 2004 Public Workshop - Region IV Operator Licensing Feedback ML0408501912004-03-23023 March 2004 Docket No. 50-483 - Slides from Meeting Held on March 23, 2004, to Discuss Licensee'S License Amendment Request Application Dated December 17, 2003 ML0316806212003-07-17017 July 2003 Licensee'S Handouts, Slides and Viewgraphs, 53 Pages, S107210 ML0316806062003-07-17017 July 2003 NRC Handout, Slides and Viewgraphs, 103 Pages, S107211 ML0211402982002-04-24024 April 2002 Annual Performance Assessment Meeting for Callaway Plant ML0206503632002-03-0606 March 2002 02-27-02 Callaway/Ameren Ue Meeting Summary 2024-06-13
[Table view] |
Text
License Amendment Request To use Reg. Guide 1.61 Rev. 1
Meeting Agenda
- Introductions Fred Lyon/Tom Elwood
- Meeting Purpose Tom Elwood
- Plant Modification Description Walt Muskopf
- Results & Conclusion Walt Muskopf
- Schedule S h d l T Tom El Elwood d
Introductions
Introduction of Meeting g Attendees
- Tom Elwood (Supervising Engineer Engineer, Regulatory Affairs)
- Walt Muskopf (Project Manager - Major Projects)
- Dave Shafer (Licensing Consultant)
- Alan Stalker (Project Manager, Major Projects & Upgrades)
- Frank F k Gregory G (Structural (St t l Supervisory S i Engineer)
E i ) - by b phone h
- David Maxham (Technical Consultant) - by phone
- Jeff J ff Sh Shulman l (Project (P j t Engineer)
E i ) (by (b phone) h )
- Mike Henry (Project Manager) 3
Meeting Purpose
- Inform NRC of forthcoming LAR to be submitted in December 2012
- LAR will request prior NRC approval to use the methodology in Reg. Guide 1.61 Rev. 1 in lieu of Reg. Guide 1.61 Rev. 0 for analysis y of new Integrated g Head Assembly y ((IHA),
), similar to Diablo Canyon
- Damping values determined using weighted average methodology in Reg. Guide 1.61 Rev. 1 will be used for the response spectrum analysis of the IHA only only.
- Includes development of reaction loads from the IHA on the Replacement Reactor Vessel Closure Head (RRVCH) and on the containment cavity wall embedments.
embedments
Plant Modification Description Current Reactor Vessel Closure Head (RVCH) ( )
Current RVCH Assembled Current RVCH Cable Hookups 5
Plant Modification Discussion Current Reactor Vessel Closure Head (RVCH) ( )
Current RVCH in Cavity Current RVCH on Stand 6
Plant Modification Description New Replacement Reactor Vessel Closure Head (RRVCH) with Integrated Head Assembly (IHA) 7
Plant Modification Discussion Major j Features of the Integrated g Head Assembly y ((IHA))
I t Integrated t d Lift Rig Ri CRDM Fans Integrated Missile Shield Quick Detach Seismic Supports Head Vent Valves Relocated Folding Cable Supports Integrated Ductwork Integrated Shielding 8
8
Plant Modification Description Comparison of Original and Replacement CRDM Seismic Supports Current CRDM Seismic Platform IHA CRDM Seismic Ring g
9
Plant Modification Description Integrated g Head Assemblyy (IHA) ( )
- IHA is a new steel structure
- Damping values from Reg. Guide 1.61 Rev. 1 will be used for the response spectrum analysis of the IHA only.
- IHA is predominantly a bolted steel structure, therefore application of Reg.
Reg Guide 1.61 1 61 Rev.
Rev 1 provides a more realistic representation of this steel structure.
- Application of Reg. Guide 1.61 Rev. 1 prevents an overly conservative design of the IHA and the need to redesign the existing i ti containment t i t cavity it wallll seismic i i anchorh embedments.
- Reg. Guide 1.61 Rev. 1 will also be used to develop the reaction loads from the IHA on the Replacement Reactor Vessel Closure Head (RRVCH) and on the containment cavity wall embedments.
10
Use of Reg. Guide 1.61 Rev. 1 Current Licensing g Basis ((FSAR Table 3.7(N)-1) ( ) )
Reg Guide 1 1.61 61 Rev Rev. 0 Reg. Guide 1.61 Rev. 0 Damping Values Structure St t or Operating O ti Basis B i Safe S f Shutdown Sh td Component Earthquake (OBE) Earthquake (SSE)
Welded 2% 4%
Connections Bolted 4% 7%
Connections 11
Use of Reg. Guide 1.61 Rev. 1 Proposed p Change g to Licensing g Basis
Welded 4%
Connections Bolted-Bearing 7%
Connections Note: For steel structures with a combination of different connection types, use the lowest specified damping value, or as an alternative, lt ti use a weighted i ht d average damping d i value l based b d on the number of each type present in the structure.
12
Use of Reg. Guide 1.61 Rev. 1 Proposed p Change g to Licensing g Basis ((cont.))
Component Welded 3%
Connections Bolted-Bearing 5%
Connections
- Note from Table 1 will also be applied to OBE &
LOCA 13
Use of Reg. Guide 1.61 Rev. 1 Requested q Approval pp of Methodology gy Changes g 10 CFR 50.59(c)(2)(viii) requires NRC approval of licensee-proposed changes that result in a departure from a method of evaluation described in the FSAR used in establishing the design bases or in the safety analyses.
- For the Callaway IHA seismic analysis, the methodology of Reg. Guide 1.61 Rev. 1 is being used, as modified by applying the footnote of Table 1 for the SSE to Table 2 for the OBE as well (where the footnote does not appear).
- P NEI 96 Per 96-07, 07 a proposed d change h constitutes tit t a departure d t ffrom a method th d off evaluation if it:
- changes any element of the analysis methodology described in the FSAR unless the results are conservative or essentially the same, or
- uses new or different methods of evaluation that are not approved by the NRC for the intended application.
Although Reg. Guide 1.61 Rev. 1 is an NRC-approved Reg. Guide, and although Diablo Canyons license amendment and accompanying SER dated September 29, 2010 provides precedence for use of Reg. Guide 1.61 Rev. 1, due to differences between Diablo Canyons IHA design and licensing basis in comparison to Callaways Callaway s, and in light of the above-described modified use of Reg. Guide 1.61 Rev. 1, Ameren Missouri has conservatively determined that its proposed use of Reg. Guide 1.61 Rev. 1, as modified, is a departure from a method of evaluation and thus requires prior NRC approval.
14
Use of Reg. Guide 1.61 Rev. 1 Weighted Average Damping Values for IHA Response Spectrum Analysis Total of 315 connections in the IHA which transfer a significant level of inertia load load.
- 267 Bearing - Bolted / Pinned Connections
- 84.8% bearing - bolted connections
- No friction - bolted connections
- Based upon p the footnote to Reg.
g Guide 1.61 Rev. 1, Table 1 and the quantities above, the weighted average is calculated below For OBE:
(3% x 48 + 5% x 267) / (48+267)
(48 267) = 4.70%
For SSE:
(4% x 48 + 7% x 267) / (48+267) = 6.54%
15
Use of Reg. Guide 1.61 Rev. 1 Actual Damping p g Values Used in Analyses y Table 1: IHA Seismic and LOCA Load Analysis Method Summary OBE SSE LOCA Horizontal Vertical Horizontal Vertical Horizontal Vertical Analysis USM1 USM1 USM1 USM1 Response Response Method Response Response Response Response Spectra3 Spectra3 Spectra2 Spectra2 Spectra2 Spectra2 D
Damping i 4 50%
4.50% 4 50%
4.50% 6 25%
6.25% 6 25%
6.25% 6 25%
6.25% 6 25%
6.25%
- 1. USM refers to the use of Uniform Support Motion (enveloped spectra) p ) as inputp to the response p spectra p analysis.
y
- 2. OBE and SSE enveloped response spectra inputs were applied where the IHA tie rods are attached to the containment cavity wall and where the IHA lift rods and the bottom ring beam are attached to the RRVCH.
- 3. LOCA response spectra inputs were applied where the IHA lift rods and the bottom ring beam are attached to the RRVCH.
16
Results & Conclusion Preliminary stress ratios for all safety-related safety related and non-safety-related linear components, plate components p p and connections are less than 1.0 and, therefore, meet the ASME Code.
17
Summary Ameren Missouri will be requesting prior NRC approval to use the methodology in Reg Reg. Guide 1.61 1 61 Rev.
Rev 1 in lieu of Reg Reg.
Guide 1.61 Rev. 0 for analysis of the new Integrated Head Assembly (IHA).
1 will be used for the response spectrum analysis of the IHA only.
- Includes development of reaction loads from the IHA on the Replacement Reactor Vessel Closure Head (RRVCH) and on the containment cavity wall.
Schedule
- License Amendment Request will be submitted in December 2012.
- Design Change Package complete by October 2013
- Request R t NRC approvall off Li License Amendment Request by September 2013 19
Open Discussion License Amendment Request to use Reg Guide 1 Reg. 1.61 61 Rev Rev. 1 Questions?
20