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Category:Slides and Viewgraphs
MONTHYEARML23152A2022023-06-0101 June 2023
2022 Davis-Besse End-of-Cycle Meeting Presentation
ML22222A1102022-07-21021 July 2022
KM Session Final
ML22178A1952022-06-27027 June 2022
2021 Davis Besse Nuclear Power Station End-of-Cycle Meeting Presentation
ML22028A3922022-02-0101 February 2022
Licensee Regulatory Conference Presentation
ML22028A3972022-02-0101 February 2022
NRC Regulatory Conference Presentation
ML21176A1992021-06-25025 June 2021
Slideshow Presentation for 2020 End -of-Cycle Public Meeting for Davis-Besse and Perry
ML20210M0712020-07-27027 July 2020
Combined End-of-Cycle 2019 Public Meeting Slide Presentation
ML19249D0212019-09-0606 September 2019
End-of-Cycle Summary Handout (2018)
ML18310A3802018-11-0808 November 2018
Pre-Submittal Meeting Davis-Besse Nuclear Power Station (DB) Post-Shutdown Emergency Plan (PSEP) License Amendment Request
ML18180A1962018-06-29029 June 2018
Slides for Davis Besse 2017 EOC Open House
ML17229B3382017-08-17017 August 2017
Presentation for 2016 Davis-Besse EOC Open House
ML16174A3152016-06-21021 June 2016
Annual Assessment Meeting Open House June 21, 2016
ML16117A1822016-04-22022 April 2016
Industry Slides for the Spring 2016 Conference Call Regarding the Steam Generator Tube Inservice Inspections
ML15156A6962015-06-11011 June 2015
Annual Assessment Meeting Open House Handout
ML14224A1112014-08-25025 August 2014
Safety Culture Presentation for Brazil, U.S. Workshop on Safety and Security Culture - August 25, 2014
ML14218A0542014-08-0707 August 2014
Handout Davis-Besse EOC Mtg
ML14050A4002014-02-20020 February 2014
NRC Presentation for Davis-Besse Steam Generator Replacement Webinar
ML13322B3112013-11-13013 November 2013
NFPA 805 Transition - Meeting Slides, 11/13/2013
ML13294A5972013-10-21021 October 2013
FENOC Presentation Slides for Public Meeting September 24, 2013
ML13220A0632013-08-30030 August 2013
Dsd ED2013 3267 Presentation, Primary Water Stress Corrosion Cracking Tests and Metallurgical Analyses of Davis-Besse Control Rod Drive Mechanism Nozzle #4.
ML13157A0642013-06-0606 June 2013
June 11, 2013 NRC Presentation
ML13159A0092013-06-0404 June 2013
Notable Failures in Nondustructive Testing - June 4, 2013 Public Meeting
ML13078A2492013-03-20020 March 2013
Project Overview-Public Mtg 3-20-13 Non Proprietary
ML12269A0612012-09-26026 September 2012
FENOC Presentation for 2012-09-26 Public Meeting
ML12227A4172012-08-15015 August 2012
NRC End-Of-Cycle Assessment 2011 Meeting Presentation
ML12221A2642012-08-0909 August 2012
NRC Public Meeting NRC Presentation 8/9/12
ML12221A2682012-08-0909 August 2012
FENOC Shield Building Cracking Davis-Besse Public Meeting 8/9/12
ML12138A0732012-05-14014 May 2012
FENOC-Davis-Besse Nuclear Power Station, Unit 1 Docket No. 50-346, License No. NPF-3 Submittal of Contractor Root Cause Assessment Report-Section 5
ML12132A3442012-05-11011 May 2012
NRC-AERB Bilateral Meeting Slide Presentation (Nro/De), Aerb, India - May 16-17, 2012
ML1206901712012-02-29029 February 2012
Slides and View Graphs - Boric Acid Corrosion Testing Program: Industry Perspective
ML12200A2402012-02-23023 February 2012
Presentation Slides on Davis-Besse Shield Building Crack
ML1204402842012-02-16016 February 2012
Public Meeting Construction Experiences - Evaluate Impact of Concrete Degradation
ML1200501462012-01-0505 January 2012
Public Meeting FENOC Slides
ML12004A0102012-01-0404 January 2012
Public Meeting NRC Slides
ML12200A2492011-12-22022 December 2011
Presentation Slides on Shield Building /Containment Delamination
ML11220A2542011-08-0101 August 2011
DBNPS-Info Meeting Slides
ML11221A3012011-08-0101 August 2011
521- R326C B&W Tech Cross Training - Chapter 16 Davis-Besse Loss of All Feedwater
ML1117303602011-06-21021 June 2011
FENOC Licensee Slides for 6-21-11 All FENOC Meeting
ML1116400632011-06-15015 June 2011
EOC NRC Slides for Public Meeting
ML1117209902011-06-15015 June 2011
Meeting Presentation NRC Annual Assessment Meeting: Davis-Besse Nuclear Power Station.
ML1032103472010-11-16016 November 2010
FENOC 11/16/10 Public Meeting Presentation Slides
ML1025103462010-09-0909 September 2010
SIT Exit Meeting Presentation Slides
ML1021501112010-07-29029 July 2010
NRC Slides for Davis-Besse; July 29, 2010; Annual Assessment Meeting
ML1021501182010-07-29029 July 2010
Licensee Slides for Davis-Besse Annual Assessment Meeting
ML1015400332010-06-0303 June 2010
Licensee Slides for June 3, 2010 Public Meeting Presentation
ML1015400342010-06-0303 June 2010
NRC Slides for June 3, 2010 Public Meeting Presentation
ML1009102662010-03-31031 March 2010
Slides FENOC and NRC Senior Management Briefing, 3-31-10
ML0920202872009-07-15015 July 2009
Meeting Slides, NRC Annual Assessment Meeting Davis-Besse Nuclear Power Station
ML0920202972009-07-15015 July 2009
NRC Slides from EOC Meeting
ML0814104322008-05-13013 May 2008
Meeting Slides, Davis-Besse Annual Assessment Meeting, Reactor Oversight Program - Cy 2007
2023-06-01
[Table view]
Category:Report
MONTHYEARL-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023
Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments
L-22-253, Submittal of Pressure and Temperature Limits Report, Revision 52023-01-10010 January 2023
Submittal of Pressure and Temperature Limits Report, Revision 5
L-22-211, Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report2022-09-29029 September 2022
Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report
L-22-216, Submittal of Pressure and Temperature Limits Report. Revision 42022-09-27027 September 2022
Submittal of Pressure and Temperature Limits Report. Revision 4
L-22-149, Post Accident Monitoring Report2022-06-23023 June 2022
Post Accident Monitoring Report
ML22202A4362022-04-0808 April 2022
Enclosure F: Updated Inputs to 52 EFPY P-T Operating Curves
ML22202A4372022-03-0202 March 2022
Enclosure G: Framatome Inc. Document 86-9344713-000, Davis-Besse Reactor Vessel Embrittlement Fluence Reconciliation Through 60 Years
IR 05000346/20210902021-12-16016 December 2021
Reissue Davis-Besse NRC Inspection Report (05000346/2021090) Preliminary White Finding
ML21322A2892021-12-0909 December 2021
Approval of Plant-Specific Analysis of Certain Reactor Vessel Internal Components in Accordance with License Renewal Commitment No. 53
ML20302A3022020-09-25025 September 2020
1 to Technical Requirements Manual
ML19255H0992019-10-10010 October 2019
Staff Assessment of Flooding Focused Evaluation
L-19-189, 54010-CALC-01, Davis-Besse Nuclear Power Station: Evaluation of Risk Significance of Permanent ILRT Extension.2019-07-29029 July 2019
54010-CALC-01, Davis-Besse Nuclear Power Station: Evaluation of Risk Significance of Permanent ILRT Extension.
ML22262A1522019-05-0101 May 2019
Framatome Inc., Document ANP-2718NP, Revision 007, Appendix G Pressure-Temperature Limits for 52 EFPY for the Davis-Besse Nuclear Power Station
ML22202A4332019-04-30030 April 2019
Enclosure C: Framatome ANP-2718NP, Rev. 7, Appendix G Pressure-Temperature Limits for 52 EFPY for the Davis-Besse Nuclear Power Station
L-18-108, Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformance Identified in Response to Regulatory Issue Summary 2015-06, Tornado Missile....2018-04-12012 April 2018
Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformance Identified in Response to Regulatory Issue Summary 2015-06, Tornado Missile....
ML18149A2812018-02-16016 February 2018
2017 ATI Environmental Inc. Midwest Laboratory Radiological Environmental Monitoring Program
L-17-270, Notification of Emergency Core Cooling System (ECCS) Evaluation Model Change Pursuant to 10 CFR 50.462017-09-0101 September 2017
Notification of Emergency Core Cooling System (ECCS) Evaluation Model Change Pursuant to 10 CFR 50.46
ML17086A0322017-03-31031 March 2017
Enclosure B to L-17-105, Areva Report ANP-3542NP, Revision 1, Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility at 60 Years
L-17-088, Independent Spent Fuel Storage Installation Changes, Tests and Experiments2017-03-27027 March 2017
Independent Spent Fuel Storage Installation Changes, Tests and Experiments
ML17026A0082016-12-31031 December 2016
Areva Report ANP-3542NP, Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility for Davis-Besse Nuclear Power Station, Unit No. 1 at 60 Years (Non Proprietary)
L-16-229, Submittal of Pressure and Temperature Limits Report, Revision 32016-07-28028 July 2016
Submittal of Pressure and Temperature Limits Report, Revision 3
L-16-148, Fatigue Monitoring Program Evaluation of Reactor Coolant Pressure Boundary Components for Effects of the Reactor Coolant Environment on Fatigue Usage (I.E., Environmentally-Assisted Fatigue)2016-04-21021 April 2016
Fatigue Monitoring Program Evaluation of Reactor Coolant Pressure Boundary Components for Effects of the Reactor Coolant Environment on Fatigue Usage (I.E., Environmentally-Assisted Fatigue)
L-15-288, Response to NRC Letter. Request for Information, Per 10 CFR 50.54(f) Regarding Recommendations 2.1. 2.3. and 9.3. of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2015-10-0202 October 2015
Response to NRC Letter. Request for Information, Per 10 CFR 50.54(f) Regarding Recommendations 2.1. 2.3. and 9.3. of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
ML15230A2892015-08-25025 August 2015
Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review
L-14-401, First Energy Nuclear Operating Company (FENOC) Expedited Seismic Evaluation Process (ESEP) Reports Response to NRC Request for Information Pursuant to 10 CFR50.54(f) Regarding Recommendation.1 of the Near-Term Task Force (NTTF) Review of In2014-12-19019 December 2014
First Energy Nuclear Operating Company (FENOC) Expedited Seismic Evaluation Process (ESEP) Reports Response to NRC Request for Information Pursuant to 10 CFR50.54(f) Regarding Recommendation.1 of the Near-Term Task Force (NTTF) Review of In
ML14353A0602014-11-0303 November 2014
2734296-R-010, Rev. 0, Expedited Seismic Evaluation Process (ESEP) Report Davis-Besse Nuclear Power Station
L-14-289, Pressure and Temperature Limits Report. Revision 22014-09-22022 September 2014
Pressure and Temperature Limits Report. Revision 2
L-14-259, Firstenergy Nuclear Operating Company'S (Fenoc'S) Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2014-08-28028 August 2014
Firstenergy Nuclear Operating Company'S (Fenoc'S) Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)
ML14141A5252014-06-30030 June 2014
Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident
L-14-167, Report of Facility Changes, Tests and Experiments for the Period Ending May 26, 20142014-06-18018 June 2014
Report of Facility Changes, Tests and Experiments for the Period Ending May 26, 2014
ML14134A5172014-05-30030 May 2014
Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident
L-14-148, CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2014-05-19019 May 2014
CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models
ML14112A3152014-04-21021 April 2014
Review of Draft Plant-Specific Supplement 52 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding
L-14-104, Firstenergy Nuclear Operating Co. Response to NRC Request for Information Pursuant to 10 CFR 50.54 (F) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2014-03-11011 March 2014
Firstenergy Nuclear Operating Co. Response to NRC Request for Information Pursuant to 10 CFR 50.54 (F) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
ML14007A6702014-02-21021 February 2014
Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies)
ML14042A2942014-02-19019 February 2014
Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Davis-Besse Nuclear Power Station, TAC No.: MF0961
ML13340A1592013-11-26026 November 2013
Davis-Besse Nuclear Power Station Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix a
ML13340A1472013-11-26026 November 2013
Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant - Response to RAI Associated with Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident (TAC Nos. MF0116 & MF0
ML13340A1632013-10-0909 October 2013
Davis-Besse Nuclear Power Station Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix C to Appendix G
ML13340A1622013-10-0909 October 2013
Davis-Besse Nuclear Power Station Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix B (2 of 2)
ML13340A1602013-10-0909 October 2013
Davis-Besse Nuclear Power Station Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix B (1 of 2)
ML13340A1582013-10-0909 October 2013
Davis-Besse Nuclear Power Station Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1
L-13-154, CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2013-05-28028 May 2013
CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models
L-13-157, Generic Safety Issue 191 Resolution Plan2013-05-15015 May 2013
Generic Safety Issue 191 Resolution Plan
ML13009A3752012-12-12012 December 2012
Enclosure B to L-12-444, Calculation No. 32-9195651-000, Equivalent Margins Assessment of Davis-Besse Transition Welds for 52 EFPY - Non-Proprietary.
L-12-347, FENOC Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Flooding Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2012-11-27027 November 2012
FENOC Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Flooding Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident
ML13135A2452012-08-10010 August 2012
Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B - Seismic Walkdown Checklists (Swcs), Sheet 202 of 379 Through Sheet 379 of 379
ML13135A2442012-08-10010 August 2012
Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B - Seismic Walkdown Checklists (Swcs), Sheet 1 of 379 Through Sheet 201 of 379
ML13135A2432012-08-10010 August 2012
Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix a - Resumes and Qualifications
ML13135A2422012-08-10010 August 2012
Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Cover Through Page 176
2023-08-07
[Table view]
Category:Miscellaneous
MONTHYEARL-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023
Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments
IR 05000346/20210902021-12-16016 December 2021
Reissue Davis-Besse NRC Inspection Report (05000346/2021090) Preliminary White Finding
L-18-108, Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformance Identified in Response to Regulatory Issue Summary 2015-06, Tornado Missile....2018-04-12012 April 2018
Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformance Identified in Response to Regulatory Issue Summary 2015-06, Tornado Missile....
L-17-088, Independent Spent Fuel Storage Installation Changes, Tests and Experiments2017-03-27027 March 2017
Independent Spent Fuel Storage Installation Changes, Tests and Experiments
L-16-148, Fatigue Monitoring Program Evaluation of Reactor Coolant Pressure Boundary Components for Effects of the Reactor Coolant Environment on Fatigue Usage (I.E., Environmentally-Assisted Fatigue)2016-04-21021 April 2016
Fatigue Monitoring Program Evaluation of Reactor Coolant Pressure Boundary Components for Effects of the Reactor Coolant Environment on Fatigue Usage (I.E., Environmentally-Assisted Fatigue)
ML15230A2892015-08-25025 August 2015
Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review
L-14-401, First Energy Nuclear Operating Company (FENOC) Expedited Seismic Evaluation Process (ESEP) Reports Response to NRC Request for Information Pursuant to 10 CFR50.54(f) Regarding Recommendation.1 of the Near-Term Task Force (NTTF) Review of In2014-12-19019 December 2014
First Energy Nuclear Operating Company (FENOC) Expedited Seismic Evaluation Process (ESEP) Reports Response to NRC Request for Information Pursuant to 10 CFR50.54(f) Regarding Recommendation.1 of the Near-Term Task Force (NTTF) Review of In
ML14353A0602014-11-0303 November 2014
2734296-R-010, Rev. 0, Expedited Seismic Evaluation Process (ESEP) Report Davis-Besse Nuclear Power Station
L-14-259, Firstenergy Nuclear Operating Company'S (Fenoc'S) Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2014-08-28028 August 2014
Firstenergy Nuclear Operating Company'S (Fenoc'S) Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)
ML14141A5252014-06-30030 June 2014
Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident
L-14-167, Report of Facility Changes, Tests and Experiments for the Period Ending May 26, 20142014-06-18018 June 2014
Report of Facility Changes, Tests and Experiments for the Period Ending May 26, 2014
L-14-104, Firstenergy Nuclear Operating Co. Response to NRC Request for Information Pursuant to 10 CFR 50.54 (F) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2014-03-11011 March 2014
Firstenergy Nuclear Operating Co. Response to NRC Request for Information Pursuant to 10 CFR 50.54 (F) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
ML13340A1472013-11-26026 November 2013
Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant - Response to RAI Associated with Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident (TAC Nos. MF0116 & MF0
ML13340A1592013-11-26026 November 2013
Davis-Besse Nuclear Power Station Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix a
ML13340A1602013-10-0909 October 2013
Davis-Besse Nuclear Power Station Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix B (1 of 2)
ML13340A1582013-10-0909 October 2013
Davis-Besse Nuclear Power Station Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1
ML13340A1622013-10-0909 October 2013
Davis-Besse Nuclear Power Station Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix B (2 of 2)
ML13340A1632013-10-0909 October 2013
Davis-Besse Nuclear Power Station Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix C to Appendix G
L-13-157, Generic Safety Issue 191 Resolution Plan2013-05-15015 May 2013
Generic Safety Issue 191 Resolution Plan
L-12-347, FENOC Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Flooding Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2012-11-27027 November 2012
FENOC Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Flooding Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident
ML13008A0312012-08-10010 August 2012
Davis-Besse Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Cover Through Appendix a, Resumes and Qualifications, Page A-39
ML13135A2462012-08-10010 August 2012
Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix C - Area Walk-by Checklists (Awcs) Through End
ML13135A2452012-08-10010 August 2012
Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B - Seismic Walkdown Checklists (Swcs), Sheet 202 of 379 Through Sheet 379 of 379
ML13135A2442012-08-10010 August 2012
Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B - Seismic Walkdown Checklists (Swcs), Sheet 1 of 379 Through Sheet 201 of 379
ML13135A2432012-08-10010 August 2012
Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix a - Resumes and Qualifications
ML13135A2422012-08-10010 August 2012
Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Cover Through Page 176
L-12-283, Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B, Seismic Walk-Down Checklists, Sheet 364 of 461 Through Appendix C, Area Walk-By Checklists, Sheet 20 of 1392012-08-10010 August 2012
Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B, Seismic Walk-Down Checklists, Sheet 364 of 461 Through Appendix C, Area Walk-By Checklists, Sheet 20 of 139
ML13008A0642012-08-10010 August 2012
Davis-Besse Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B, Seismic Walk-Down Checklists, Sheet 244 of 461 Through Sheet 363 of 461
ML13008A0632012-08-10010 August 2012
Davis-Besse Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B, Seismic Walk-Down Checklists, Sheet 121 of 461 Through Sheet 243 of 461
ML13008A0622012-08-10010 August 2012
Davis-Besse Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B, Seismic Walk-Down Checklists, Page B-1 Through Sheet 120 of 416
ML12213A3372012-07-27027 July 2012
SB-00-20: CR-2011-03346 Evaluation
ML12213A3352012-07-27027 July 2012
Review of Technical Assessment Report No. 25539-200 COR-0000-00001
L-12-196, FENOC-Davis-Besse Nuclear Power Station, Unit 1 Docket No. 50-346, License No. NPF-3 Submittal of Contractor Root Cause Assessment Report-Section 72012-05-14014 May 2012
FENOC-Davis-Besse Nuclear Power Station, Unit 1 Docket No. 50-346, License No. NPF-3 Submittal of Contractor Root Cause Assessment Report-Section 7
ML12138A0582012-05-14014 May 2012
FENOC-Davis-Besse Nuclear Power Station, Unit 1 Docket No. 50-346, License No. NPF-3 Submittal of Contractor Root Cause Assessment Report-Section 3
ML12138A0812012-05-14014 May 2012
FENOC-Davis-Besse Nuclear Power Station, Unit 1 Docket No. 50-346, License No. NPF-3 Submittal of Contractor Root Cause Assessment Report-Section 6
ML12138A0492012-05-14014 May 2012
FENOC-Davis-Besse Nuclear Power Station, Unit 1 Docket No. 50-346, License No. NPF-3 Submittal of Contractor Root Cause Assessment Report-Section 2
ML12138A0672012-05-14014 May 2012
FENOC-Davis-Besse Nuclear Power Station, Unit 1 Docket No. 50-346, License No. NPF-3 Submittal of Contractor Root Cause Assessment Report-Section 4
ML12138A0732012-05-14014 May 2012
FENOC-Davis-Besse Nuclear Power Station, Unit 1 Docket No. 50-346, License No. NPF-3 Submittal of Contractor Root Cause Assessment Report-Section 5
L-12-071, 10 CFR 50.46 Report of Significant Changes or Errors in the Loss of Coolant Accident Evaluation Model2012-03-16016 March 2012
10 CFR 50.46 Report of Significant Changes or Errors in the Loss of Coolant Accident Evaluation Model
ML12200A2122011-11-21021 November 2011
Containment Shield Building Issue
ML12200A2102011-11-17017 November 2011
Containment System Primary Steel Containment an Shield Building
ML12213A3482011-10-28028 October 2011
Table of Contents to Isolated Crack Indication Identified by Impulse Response Testing of the Shield Building
L-11-319, Pressure and Temperature Limits Report2011-10-27027 October 2011
Pressure and Temperature Limits Report
ML11301A2302011-06-0101 June 2011
Reference: State Energy Consumption Estimates 1960 Through 2009
ML1101007582011-01-10010 January 2011
Pressure Temperature Limits Report Attachment
ML11301A2232010-07-31031 July 2010
Chp Regional Application Centers: Activities and Selected Results for Fiscal Year 2009
ML1015201162010-05-26026 May 2010
Field Report Control Rod Drive Mechanism Number 4 Ultrasonic Results
ML1012704392010-05-0505 May 2010
Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants
ML1005396232010-02-22022 February 2010
Lessons Learned Task Force Action Plan Regarding Stress Corrosion Cracking Dec 2009 (Final Update)
L-09-068, Independent Spent Fuel Storage Installation - 10 CFR 72.48 Report of Dry Fuel Storage Facility Changes, Tests, and Experiments2009-02-27027 February 2009
Independent Spent Fuel Storage Installation - 10 CFR 72.48 Report of Dry Fuel Storage Facility Changes, Tests, and Experiments
2023-08-07
[Table view] |
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- This section of results are from a model with the following parameters:
- 0.6% VF i.e. 0.6% of the elements in the first 0.1 under the horizontal rebars (bottom 180°) are given a 7% expansion to simulate
- Nominal 12" spacing -Assumes 12" spacing and includes lap regions -Both horizontal and vertical 12" nominal PII Page, 50 ego 142 2/23/2012
_2012 Exhibit 51 -Appendix Mesh: Nominal 12" z Standi: Stand;: v.... PII Page 51 CS!i 142 2/23/2012
_ 2012 Exhib i t 51 -Appendix Outer 2/1 Frozen (7%
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Exh i b i l51 -Appendix Outer 8" Nominal 12" Rebar, 0.6% c Standi: Standi: PII Page 5 5 <Sf5 _ 2/23/2012 Exhibit 51 -Appendix Outer 10" Nominal 12" Rebar, 0.6% Stand.: ific Stand.: /23/201 Pli Page 56 c5fb ;1.42 _ 2012 Exhibit 51 -
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Nominal 12" Rebar, 0.6% stand" cific Stand" PII Page 57 Cftl 142 2/23/2012 Exhibit 51 -Appendix Inner 61/ @ 2%
Nominal 12" Rebar, 0.6% Stand;: eifie Stand;: PII P a ge 58 egg 1 4 2 2/23/2012
_ 2012 Exhibit 51 -Appendix Inner 6/1 @ 3%
Nominal 12" Rebar, 0.6% Stand;; Stand;: P I I Page 59 _ 2/23/2012 Exh i bit 51 -Appendix Inner 6/1 @ 4%
Nominal 12" Rebar, 0.6% Standc Stand" PII Page 60 C$tJ142")/23/2012
_ 2012 Exhibit 51 -Appendix Inner 6" @ 5%
Nominal 12" Rebar, 0.6% Standc clfic Stand.:: PII Pag e 6 1 C6El 1 4 2 2/23/2012
_ 2012 Exhibit 51 -Appendix Inner 6" @ 6% Expansion Nominal 12" Rebar, 0.6% VF Standi: Standc 2/23/2012 PI\ Page. 62 Cf.t2 _
Exhibit 51 -Appendix All Frozen (7%
Nominal 12" Rebar, 0.6% Debonding but no laminar cracks fie Standi' Standi: PII Pag e 63 cro 14 2 2/23/2012
_ 2012 W
S -n/'..J 0 -.. ...... N N Z _. -::::l OQ ::::0 -ro (J) c S c: r-t (J) S -0 N -IIIW IIIW I ::a m N /'..J 0 J>::a 0* en < m x'0 =r-Pl lO §: eD (J1 ->.m "'" , -0"0 (l)f-' a.. I\) * "'" X Exhibit 51 -Appendix Minimum 12" Rebar, 0.6%
- This section of results are from a model with the following parameters:
- 0.6% VF i.e. 0.6% of the elements in the first 0.1" under the horizontal rebars (bottom 180°) are given a 7% expansion to simulate ice freezi ng. Minimum 12" spacing -Assumes minimum 12/1 spacing -Both horizontal and vertical at least 12/1 spacing Pl j Page 65 <65 142 2/23/2012
_ 2012 Exhibit 51 -Appendix Mesh: Minimum 12" z z ODS: job.odb Jan 21 07:33:31 Pacific Standa ODB: job.odb Jan 21 07:33: 31 Pacific Standa "step: Step-1 yStep: Step-1 y "Increment ltncrement 2/23/2012 PII Page 66 cS6 142 _ 2012 Exhibit 51 -Appendix Outer 2" Frozen (7%
Minimum 12" Rebar, 0.6% z y ODB: job.odb Step-1 "Increment Primary Var: Jan 2209:43:51 Pacific Stand" DAMAGET (Avg: 75%) 1.0 0.9 O.B 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0.0 z yStep: Step-1 ltncrement Primary Var: n Jan 22 09: 43: 51 Pacific Standi: PI! Page 67 CfJ1142 2/23/2012
_ 2012 Exhibit 51 -Appendix Outer 4/1 Minimum 12" Rebar, 0.6% z y 008: job.odb Step-2 'Increment Primary Var: Jan 22 09:43: 51 Pacific Standi' DAMAGET (Avg: 75%) 1.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0.0 z yStep: Step-2 Jtncrement Primary Var: Jan 2209: 43:51 Pacific Stand.: PII Pa g e 68 c88 14 2 2/23/2012
_ 2012 Exhibit 51 -Appendix Outer 6" Minimum 12" Rebar, 0.6% z y ODB: job.odb ,;;tep: Step-3 'Increment Primary Var: Jan 2209:43:51 Pacific Stand" DAMAGET (Avg: 75%) 1.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0.0 z ystep: Step-3 lfncrement Primary Var: Jan 22 09: 43 : 51 Pacific Sta ndc PII Page 6 9 COO 14 2 2/23/2012
_ 2012 Exhib i t 51 -Appendix Outer 8" Minimum 12" Rebar, 0.6% z y OD6: job.o db -.Step: Step-4 "Increment Primary Var : Jan 2209: 43:51 Pacific Stand" DAMAGET (Avg : 75% ) 1.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0.0 z yStep: Step-4 ltncrement 1 Primary Var: Jan 22 09:43: 51 Pacific Standi: PII Page 70 0Jft) 142 2/23/2012
_ 2012 Exhibit 51 -Appendix Outer 10" Minimum 12" Rebar, 0.6% z y ODB: job.odb ,,:;tep: Step-5 'Increment Primary Var: Jan 22 09: 43:51 Pacific Stand, DAMAGET (A v g: 75%) 1.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0 , 1 0 , 0 z yStep: Step-5 ltncrement Pr i mary Var: n Jan 22 09: 43:51 Pacific Standi: PII Page 71 qfi 142 2/23/2012
_ 2012 Exhibit 51 -Appendix Inner 6" @ 1%
Minimum 12" Rebar, 0.6% z y ODS: job.odb Step-6 'Increment Primary Var: DAt-1AGET (Avg: 75%) 1.0 0.9 0 .8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0.0 Jan 22 09: 43: 51 Pacific Standi: z n Jan 2209:43 : 51 Pacific Stand" yStep: Step-6 lfncrement Primary Var: PII Page 72 cW 142 2/23/2012
_ 2012 Exhibit 51 -Appendix Inner 6" @ 2%
Minimum 12" Rebar, 0.6% z y ODB: job.odb Step-6 'Increment Primary Var: DAMAGET (Avg : 75%) 1.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0.0 Jan 22 09 : 43 : 51 Pacific Standi: z Jan 2209: 43:51 Pacific Standi: yStep: Step-6 ltncrement Primary Var: PI! Page 73 q13 142 2/23/2012
_ 2012 Exhibit 51 -Appendix Inner 6" @ 3%
Minimum 12" Rebar, 0.6% z y ODB : job.odb "step: Step-6 "Increment Primary Var: DAMAGET (AVg: 75%) 1.0 0.9 O.S 0.7 0.6 0.5 0.4 0.3 0.2 -0.1 0 .0 Jan 22 09: 43 : 51 Pacific Stand" z n Jan 2209:43:51 Pacific Stand" yStep: Step-6 llncrement Primary Var: PII Pa,ge 74 _ 2/23/2012 Exhibit 51 -Appendix Inner 6" @ 4%
Minimum 12" Rebar, 0.6% z y ODB: job , odb ,?tep: Step-6 'Increment Primary Var: DAMAGET (A v g : 75% ) 1.0 0 , 9 0 , 8 0,7 0 , 6 0 , 5 0.4 0 , 3 0,2 0 , 1 0 , 0 Jan 22 09:43: 51 Pacific Standc z n Jan 2209:43:51 Pacific Standi: yStep: Step-6 ltncrement Primary Var: PII Page 75 qf5 142 2/23/2012
_ 2012 Exhibit 51 -Appendix Inner 6" @ 5%
Minimum 12" Rebar, 0.6% z OOB: job.odb y Step-6 "Increment Primary Var: OAMAGET (Avg: 75%) 1.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0.0 Jan 22 09:43:51 Pacific Stand.: z Jan 22 09:43:51 Pacific Standi: yStep: Step-6 ltncrement Pri mary Var: PI! Page 76 <Ji16 142 2/23/2012
_ 2012 Exhibit 51 -Arpendix Inner 6" @ 6%
Minimum 12" Rebar, 0.6% z y ODS: job.odb Step-6 'Increment Primary Var: DAMAGET (Avg: 75%) 1.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0.0 Jan 22 09:43:51 Pacific Standi: z n Jan 22 09 : 43 : 51 Pacific Stand" ystep: Step-6 ltncrement 1 Primary Var: PII Page 77 err? 14 2 2/23/2012
_ 2012 Exh i bit 51 -Appendix All Frozen (7%
Minimum 12" Rebar, 0.6% z y ODS: job.odb ,?tep: Step-6 'Increment Primary Var: DAMAGET (Avg: 75%) 1.0 0.9 O.S 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0.0 Jan 22 09:43:51 Pacific Standi' z Jan 22 09: 43: 51 Pacific Standi: yStep: Step-6 ltncrement Primary Var: PH Page 78 1 42 2/23/2012
_ ion x, :.0 c: (J) a.. Cl. << I LO 15:c x UJ 0... V) !:i ::l V)u.. > LLI M*' a::: N M N ("Ij N N 0 N ""0 '" r-i i a.. 0 <Xll!) (l) 01;Qrc! Po. >< W u.. > ... -c.. <C £:a LLI V') +-' ::s LLI V') (J) a:::: V) tlO s::: Z N (J) LLI N M 0N u.. -..: (Yi, N-.. N Exhibit 51 -Appendix . Dense Rebar, 1%
- This section of results are from a model with the following parameters: 1% VF i.e. 1% of the elements in the first 0.1" under the horizontal rebars (bottom 180°) are given a 7% expansion to simulate ice freezing. Dense rebar -Assumes some sub-6" spacing (2" to 6" centers) -Based on the photo earlier in these slides PII Page 81 @ 142 _ 2012 2/23/2012 Exhibit 51 -Appendix Mesh: Dense z z fic Standar y 1. PI!2/23/2012 Page 82 em _
Exhibit 51 -Appendix Outer 2" Frozen (7%
Dense Rebar, 1% z y XStep: Incre Primary Var: DAMAGET PII 2/23/2012 Page 8 3 <83 1_
Exhibit 51 -Appendix Outer 4" Dense Rebar, 1% z y Increm Primary Var: DAMAGET PII.2/23/2012 P a g e 8 4 <84 1 4_
Exhibit 51 -Appendix Outer 6" Dense Rebar, 1% z y Incremen Primary Var: DAMAGET PII 2/23/2012 Page 85 <8f5 142 _ 2012 Exhibit 51 -Appendix Outer 8" Dense Rebar, 1% z y Increment Primary Var: DAMAGET PII 2/23/2012 Page 86 cst 142 _ 2012 Exhibit 51 -Appendix Outer 10" Dense Rebar, 1% Z nnR
- iii " : 51 Pacif i c Standar Y --.1-. xStep: Increment Primary Var: DAMAGET PII Page 87 _ 2/23/2012 Exhibit 51 -Appendix All Frozen (7%
Dense Rebar, 1% Z nnR * *... _ ..._--.. 1: 51 Pacific Standar Increment 1 Primary Var: DAMAGET PII 2/23/2012 Page 88 egg 1 _
Exhibit 51 -Appendix Freezing Results NOMINAL 6" REBAR, 1% VF PII Page 89 <8f9 142 2/23/2012
_2012 Exhibit 51 -Appendix Nominal 6" Rebar} 1%
- This section of results are from a model with the following parameters: 1% VF i.e. 1% of the elements in the first 0.1" under the horizontal rebars (bottom 180°) are given a 7% expansion to simulate ice freezing.
- Nominal 6" spaced rebar -Assumes 6" spacing and includes lap regions Page' 90 <!to 142 2/23/2012
_2012 Exhibit 51 -Appendix Mesh: Nominal 6" Standi: y PI!2/23/2012 Page 91 cOO. _
Exhib i t 51 -Appendix Outer 2" Frozen (7%
Nominal 6" Rebar, 1% Standa , 2/23/2012 PII P;;l.ge 92 GJi 1_
Exhibit 51 -Appendix Outer 4/1 Nominal 6" Rebar, 1% Standa PI! Page 93 _ 2/23/2012 Exhibit Appendix Outer 6" Frozen Nominal 6" Rebar, 1% VF c Standa 2/23/2012 PII . Page 94 cif4 l42 _ 2012 Exh i bit 51 -Appendix Outer 8/1 Frozen Nominal 6'1 Rebar, 1% VF 5tanda PI!2/23/2012 Page 95 _
Exhibit 51 -Appendix Outer 10" Nominal 6" Rebar, 1% ific Standa PI!2/23/2012 Page 96 .<Jj6 _
Exhibit 51 -Appendix Inner 6" @ 1% Expansion Nominal 6" Rebar, 1% VF Standa PII 2/23/2012 Page 97 _
Exhibit 51 -Appendix Inner 6" @ 2% Expansion Nominal 6" Rebar, 1% VF Standa PII 2/23/2012 Page 98 egg _
Exh i bit 51 -Appendix Inner 6" @ 3%
Nominal 6" Rebar, 1% iflc Standa PII Page 9 9 <00 142 2/23/2012
_ 2012 Exhibit 51 -Append i x Inner 6" @ 4% Expansion Nominal 6" Rebar, 1% VF Standa Standa 2/23/2012 PII Page 100 R1b _
Exhibit 51 -Appendix Inner 6" @ 5%
Nominal 6" Rebar, 1% standa Standa PII Page 101 1m. 142 2/23/2012
_ 2012 Exhibit 51 -Appendix
- Inner 6/1 @ 6% Expansion Nominal 6" Rebar, 1% VF Standa c Standa PlI 2/23/2012 Page 1 02 _ 2012
- Exhibit 51 -Appendix All Frozen (7%
Nominal 6" Rebar, 1% Standa fic Standa PII Page 103 M 142 2/23/2012 Exhibit 51 -Appendix Freezing Results 12" VERTICALS ONLY, 1% 2/23/2012 PII P age *104 Nf4 1_
Exhibit 51 -Appendix 12/1 Verticals Only, 1%
- This section of results are from a model with the following parameters: 1% VF i.e. 1% o/the elements in the/irstO.1" under the horizontal rebars (bottom 180°) are given a 7% expansion to simulate ice freezing. Nominal 12" spacing 0/verticals only -Assumes 12" spacing and includes lap regions -Horizontal bars stay at 6" nominal spacing PII Page 105 m 1 42 2/23/2012
_ 2012 Exh i bit 51 -Appendix Mesh: 12" Verticals Standa y 2/23/2012 PII Page 106 R16 l42 _ 2012 Exhibit 51 -Appendix Outer 2/1 Frozen (7%
12" Verticals Only, 1% Standa PlI Page 107 Ntl142 2/23/2012
_ 2012 Exhibit 51 -Appendix Outer 4" Frozen 12" Verticals Only, 1% VF standa 2/23/2012 PII P age 1 08 NJ8 14_
Exhibit 51 -Appendix Outer 6" Frozen 12" Verticals Only, 1% VF Standa 2123/2012 PII Page 1 0 9 1<00 _
Exhibit 51 -Appendix Outer 8" Frozen 12" Verticals Only, 1% VF Standa PII 2/23/2012 l?age 110 nJQ
Exhibit 51 -Appendix Outer 10" 12" Verticals Only, 1% c Standa PI! Page 111 1<1fJ. 142 2/23/2012
_ 2012 Exhibit 51 -Append i x Inner 6" @ 1% Expansion 12" Verticals Only, 1% VF Standa PII 2/23/2012 Page 112 HQ 142 _
Exhibit 51 -Appendix Inner 6" @ 2% Expansion 12" Verticals Only, 1% VF c Standa PI 2/23/2012 Page 113 1<1; 1 _
Exhibit 51 -Appendix Inner 61/ @ 3% Expansion 12" Verticals Only, 1% VF Standa PII 2/23/2012 Page 114 _
Ex h ib i t 51 -Append i x . Inner 6" @ 4%
12" Verticals Only, 1% Standa Standa Pl Page lIS]q f5 2/23/2012 _
Exhibit 51 -Appendix Inner 6" @ 5% Expansion 12" Verticals Only, 1% VF Standa Standa 2/23/2012 PI! Page 116 1116 _
Exhibit 51 -Appendix Inner 6/1 @ 6% Expansion 12" Verticals Only, 1% VF fie Standa e Standa 2/23/2012 P II Page 117 1C l f7 1 4_
Exhibit 51 -Appendix All Frozen (7% Expansion) 12" Verticals Only, 1% VF Standa Standa .2/23/2012 PI! Page 1 18 1=1:18 14_
LL. > ?ft-t-I a!<< a! c... .... <<V) +-' z::::J V) OJ -0::: tlO s::: 0 N OJ N OJ .-f !..... N Z u.. -... (Y') N-... N 0 Exhibit 51 -Appendix Nominal 12/1 Rebar, 1%
- This section of results are from a model with the following parameters: 1% VF i.e. 1% of the elements in the first 0.1" under the horizontal rebars (bottom 180°) are given a 7% expansion to simulate ice freezing. Nominal 12" spacing -Assumes 12" spacing and includes lap regions -Both horizontal and vertical 12" nominal spacing 2/23/2012 1?age 120:r:ro 142 Exhibit 51 -Appendix Mesh: Nominal 12" stand" Standi: y PI! Page 121 m. 142 2/23/2012
_ 2012 E xhib i t 51 -Appendix Outer 21/ Frozen (7% Expansion)
Nominal 12" Rebar, 1% VF Standar c Standar 2/23/2012 PII P a ge 122 m 1 4 2. _ 2012 Exhibit 51 -Appendix Outer 4" Nominal 12" Rebar, 1% Standar Standar Page 123 1m 142 2/23/2012 PII _ 2012 Exhibit 51 -Append i x Outer 61/ Frozen Nominal 12" Rebar, 1% VF Standar ific Standar 2/23/2012 PI! Page 12 4 Rt4 _
Exhibit 51 -Appendix Outer 8" Nominal 12" Rebar, 1% Standar fic Standar PII Page 125 _ 2/23/2012 Exhibit 51 -Appendix Outer 10" Nominal 12" Rebar, 1% Standar Standar PII Page 126 m 142 2/23/20 12 _ 2012 Exhibit 51 -Append i x . Inner 6/1 @ 1%
Nominal 12/1 Rebar, 1% Standar Standar PII Page 127 m _ 2/23/2012 Exhibit 51 -Appendix Inner 6" @ 2% Expansion Nominal 12" Rebar, 1% VF Standar Standar PII 2/23/2012 Page 128 p.z18 _
Exhibit 51 -Appendix Inner 6" @ 3%
Nominal 12" Rebar, 1% Standar Standar PII Page 1 29 1Cl191 4 2 2/23/2012
_ 2012 Exhibit 51 -Appendix Inner 6" @ 4%
Nominal 12" Rebar, 1% Standar Ific Standar PII Pag e .130 100 1 42 2/23/2012
_ 2012 Exhibit 51 -Appendix Inner 6/1 @ 5% Expansion Nominal 12/1 Rebar, 1% VF Standar Standar PI!2/23/2012 Page 131 1@.. _
Exhibit 51 -Appendix Inner 6" @ 6% Expansion Nominal 12" Rebar, 1% VF Standar Standar 2/23/2012 PII Page 132 m l42 _ 2012 Exhibit 51 -Appendix All Frozen (7%
Nominal 12" Rebar, 1% Standar Standar PH Page 133 P.3f3 142 2/23/2012
_ 2012
-0 C Q) << , L() :0 .c x UJ V') 1--' ::s V'I Q) a:::: b.O C N , D:: <C , , -N <:l' rl rl Q) 0"1 CU 0. N -i I 0 N -CL a N m N r..J Exhibit 51 -Appendix Minimum 12" Rebar, 1%
- This section of results are from a model with the following parameters: 1% VF i.e. 1% of the elements in the first 0.1" under the horizontal rebars (bottom 180°) are given a 7% expansion to simulate ice freezing. Minimum 12" spacing -Assumes minimum 12" spacing -Both horizontal and vertical at least 12" spacing PII 2/23/2012 Page 13513f5 142 _ 2012 Exhibit 51 -Appendix Mesh: Minimum 12" z OD6: job ,o db Jan 2107:33:31 Pacific Standa z 006: job,odb Jan 21 07:33:31 Pacific Standa ,?tep: Step-1 yStep: Step-1 y 'Increment ltncrement PII Page 13 6 R\f6 1 42 2/23/2012.
_ 201-2 Exhibit 51 -Appendix Outer 2" Frozen (7%
Minimum 12" Rebar, 1% z y 006: job.odb "step: Step-l 'lncrement Primary Var: Jan 21 07: 33: 31 Pac i fic Standa OAMAGET (Avg : 75% ) 1.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0.0 z yStep : Step-l 1 Primary Var: Jan 21 07:33: 31 Pac i fic Standa PII Page 13 7 J.q3ff 142 2/23/2012
_ 2012 Exhibit 51 -Append i x Outer 4" Minimum 12" Rebar, 1% z ODS: job.odb y ,?tep: Step-2 'Increment Primary Var: Jan 2107:33:31 Pacific Standa OAMAGET (Avg: 75%) 1.0 0.9 0.8 0.7 0.6 0 .5 0.4 0.3 0.2 0.1 0.0 ZOOS: job.odb t yStep: Step-2 ..... lfncrement 1 Primary Var: Jan 2107:33 : 31 Pacific Standa PII Page 138 142 _ 20L2 2/23/2012 Exhibit 51 -Append i x Outer 6" Minimum 12" Rebar, 1% z y ODS: job.odb -.Step: step-3 "Increment Primary Var: Jan 21 07: 33:31 Pacific Standa DAMAGET (Avg : 75%) 1.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0.0 z yStep: Step-3 ltncrement Primary Var: tJan 21 07:33:31 Pacific Standa PI Page 139 1 2/23/2012
_
Exhibit 51 -Appendix Outer 8/1 Minimum 12" Rebar, 1% z y 006: job.odb ,?tep: Step-4 "Increment Primary Var: Jan 21 07:33:31 Pacific Standa DAMAGET (Avg: 75%) 1.0 0.9 O.B 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0.0 z yStep: Step-4 ltncrement Primary Var: Jan 2107:33:31 Pacific Standa PII Page 140 _ 2/23/2012 Exhibit 51 -Appendix Outer 10" Minimum 12" Rebar, 1% z y ODB: job.odb Step-5 'Increment Primary Var: Jan 21 07:33:31 Pacific Standa DAMAGET (Avg: 75%) 1.0 -0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0.0 z yStep: Step-5 ltncrement Primary Var: Jan 2107:33:31 Pacific Standa PII Page 141 1 4 2 2/23/2012
_ 2012 Exhibit 51 -Appendix All Frozen (7%
Minimum 12" Rebar, 1% z y ODB: job.odb -?tep: Step-6 'Increment Primary Var: DAMAGET (Avg: 75%) 1.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0.0 Jan 2107:33:31 Pacific Standa z Jan 2107:33:31 Pacific Standa yStep: Step-6 ltncrement Primary Var: PII Page 142 f4I2 142 2/23/2012
-_ 2012 Exhibit 51: Freezing and Rebar Spacing Study Appendix VIII-52 © 2012. Performance Improvement Exhibit 51 Freezing Failure and Rebar Spacing Sensitivity Study Background and Purpose A set of analyses was performed to quantify the propensity to propagate a laminar crack due to freezing of ice under the horizontal rebars. The study was done using a wide range of rebar densities, as this seems to be a key factor in the observed extent and therefore the propagation of the laminar cracks. Specifically, the issue is the density of rebars in 2 dimensions (not 3 dimensions) in the outer face (OF) rebar mat. There are locations, such as the top 20 feet of the walls where the nominal spacing ofthe horizontal rebars is 6". With laps and normal construction tolerances, this can lead to regions where there is less than 2" of clear spacing between the horizontal rebars. It was also observed that in some locations the vertical rebars were crowded on either side of the jacking bars in order to accommodate the hydraulic jacking heads used during the slip-forming operation.
An example of this is shown in the following figure. Figure 1: Tight rebar spacing around a hydraulic jacking head "Enabling Event" Considered In these models, the "enabling event" is a freezing failure in which the "sides" of the shoulders freeze first and trap moisture in the centers of the shoulders.
The "sides" of the shoulders include the regions where the shoulders transition into a wall thickness of 30", including the flute valleys and the transition
© 2012. Performance Improvement International Page 1 Page 1 of 6 Exh i b i t 51 to the base cylinder.
As the temperature drops outside, the shoulders freeze after the thinner parts of the wall (the flute "valleys" and the thinner midsections between the shoulders).
The shoulders insulate the OF rebar mat and delay changes in temperature in the middle of the shoulders. As the concrete near the outer surface of the building freezes, temperature and pore pressure gradients are formed in the concrete. Model Details ***
- Figure 2: Mesh: View from the Right and Left Page 2© 2012. Performance Improvement International-Page :2 of 6 Exhibit 5 1 Figure 3: Detailed Mesh Section Material Properties Concrete:
- Elastic modulus =4.94 Msi, Poisson =0.2
- Elastic modulus =29 Msi, Poisson =0.3 loads and Boundary Conditions The*******************
- The model © 2012. Performance Improvement International Page 3 Page 3 of 6 Exhib i t 51 Analysis Design Water expands 9% when it freezes, I!!!!!!!!!!!!!!!!
This serves as a calibration for the rebar density study and also serves to partially validate that this failure mode is at least plausible. Once a good calibration is achieved in the regions with dense rebar, additional models are run in regions with less rebar density to test the influence of the rebar density. Scenarios Considered Five sets of different rebar spacing scenarios were modeled. They inciuded: <6" -Tightly-spaced rebar with a pattern based on the figure above. In this scenario, the vertical rebars have a variable spacing from 2" to 6". The horizontal bars have a nominal spacing of 6" with laps. This results in a ciear spacing between bars of 0.6" to 4.6". 6" nominal-Both horizontal and vertical bars have a nominal 6" spacing, inciuding laps, which creates a clear spacing between bars of 2.6" in some locations and 4.6" in others. 6"H/12"V -Horizontal bars are spaced with the same nominal 6" inciuding laps. The vertical bars are given a nominal 12" spacing, inciuding laps. 12" nominal-Both horizontal and vertical bars have a nominal 12" spacing, inciuding laps. s>12" -Both horizontal and vertical bars are placed 12" from each other, but no laps are included and the bars are 8" from the boundary edges of the model, simulating a scenario with bars that are more sparse than 12". Page 4 © 2012. Performance Improvement International Page 4 of 6 Exh i bit 51 Results Summa y The results are summarized in the table below. The "rebar spacing" variable is summarized above and presented in the legend, and the "extent of cracking" is a scale from 0 to 3 that serves to simplify the extent of the damage observed in each model. The meaning of each level from 0 to 3 is described in the third legend following the table below. A level of "3" is a complete delamination along the OF rebar mat similar to the center of shoulder 9 *****. A level of "a" is no damage. What the results show is that there is a clear trend toward more damage with tighter rebar spacing. The models with all 12" rebar spacing showed no laminar cracks at all. Motivating Rebar Extent of Legend: Rebar Spacing <6" Sub..{j" spacing, e.g. 2",4" 6" ominal 6" spacing of all bars, w/ laps 6"/12" 'aminal 6" spacing horizontals and Nominal 12" spacing verticals 12" Nominal 12" spacing of all bars, w/laps >12" Wider than 12" spaCing Legend: Extent of laminar cracks o No 'aminar 1 Sparse, up to 12" x 2 Continuous, up to 24" x 24'3 Extensive, larger than 24" x with localized double cracks Table 1: Results summary Note that no models were created to analyze scenarios with no motivating force as the rebar spacing alone is not capable of causing a failure without a motivating force. © 2012. Performance Improvement International Page 5 Page 5 of 6 Exhibit 51 Conclusions This study shows that only a small fraction of the voids under the rebars need to fill with water and freeze in order to get laminar cracks. And, for a given motivating force, there are large laminar cracks that form in regions with dense rebar and none form in regions with sparse rebar. This study shows that freezing of ice under the horizontal rebars is a plausible failure mode by establishing the conditions under which this modality matches the observed failures and then further testing the mode to show that there is no failure in regions with sparse rebar. This study shows that for the same motivating force, there are large laminar cracks that form in regions with dense rebar and do not form in regions with sparse rebar. With a given motivating force, *************************
all of the models with 6" spacing of rebar showed the development of some laminar cracks, while none of the models with 12" spacing of both horizontals and verticals showed any laminar cracking.
This study establishes that rebar spacing is a probable contributing factor because the tighter rebar spacing can facilitate crack propagation.
In regions with wider rebar spacing, damage is less likely because of the absence of this contributing factor. © 2012. Performance Improvement International
-Page 6 Page 6 of 6 Exhibit 52: Test Report from the University of Colorado © 2012. Performance Improvement International-
_ Appendix
