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| | {{#Wiki_filter:'2/23/2012 SHIELD BUILDING / CONTAINMENT DELAMINATION: |
| | DAVIS-BESSE |
| | & CRYSTAL RIVER BRYCE LEHMAN -NRR/DLR JIM NEURAUTER |
| | -REGION III/DRS DANIEL RICH -REGION II/DRP 1 Agenda" Davis-Besse Condition |
| | & Licensee's Position" NRC's Position on Davis-Besse" Impact on License Renewal" Status Update on Crystal River o Impact on License Renewal" Similarities |
| | & Differences Between Plants~Yy 1 2/23/2012 Davis-Besse Shield Building" Free-standing steel containment vessel surrounded by reinforced concrete shield building" Shield Building Functions: |
| | A 13 Environmental |
| | & external missile protection for containment vessel 13 Biological shielding during normal operation and accident conditions I 13 Means for collection and filtration of fission product leakage following accident Initial Condition o Laminar crack identified in architectural flute shoulder area during hydro-demolition for replacement of reactor vessel closure head (October 1 Oth)o Crack found on the vertical side of the opening (left side, looking from the outside), generally along main reinforcing steel, and extends -6'across the top and "-4' across the bottom 2 2/23/2012 Construction Opening Flute/Shoulder Geometry 3 2/23/2012 Condition Assessment 7* "Chipping back" along cracked areas revealed crack extended beyond construction opening* Impulse Response (IR)methodology employed to investigate extent of crack* IR testing indicated crack extended -38' above construction opening* (4) core bores taken to validate IR results 13 Indicated crack existed near outer reinforcement mat[3 IR testing performed on 15 of 16 flute shoulders a Based on results, licensee assumed cracking throughout all shoulders o Core bores taken on 1 2 shoulders to confirm crack boundaries c] Core bores inspected using boroscope to identify crack depths and widths 13 Very tight, less than 0.01" Condition Assessment o IR testing performed on 4 of 8 flute areas o Core bores taken from 6 of 8 flute areas" IR testing and core bores confirmed laminar cracking not present in flute areas 13 One flute did have a vertical crack, but determined to be isolated condition ii IR testing performed in 7 of 8 areas between flute shoulders io Two small regions adjacent to Main Steam Line penetration blockouts are cracked a3 Extent of cracking unique to penetrations o Cracking regions exist at top 20'of Shield Building wall outside shoulder area o Spring line area appears to have little or no cracking (top 5')4 2/23/2012 Condition Assessment Summary" Cracking is generic to all flute shoulder regions" Cracks are confined to flute shoulder regions with exception of top 20' of Shield Building wall and two small regions near MSL penetrations o Cracking exists at top 20' of Shield Building wall outside shoulder region o Cracks are very tight, <0.01 ", and located near the outer reinforcing mat'I Licensee's Position" Believe sampling method of IR testing and core bores has characterized the extent of cracking in the structure o Primary concern is ability of outside rebar to perform its intended function. |
| | Observations of construction opening and testing indicate concrete is attached to rebar mat o Based on structural evaluation, cracking does not impact ability of structure to perform its intended safety functions" Root cause is underway 5 2/23/2012 NRC's Position o NRC informed licensee it could restart (1 2/2)13 Licensee developed a model with reasonable assumptions which demonstrated a reasonable expectation of operability 13 Staff continues to evaluate whether the shield building conforms to the design code requirements in the CLB" This is currently being addressed by Region III in inspection space.* The inspection is ongoing and the focus has shifted to resolving the question regarding compliance with the design and licensing basis. Region III is developing a plan/timeline for resolution and issuance of the inspection report.NRC's Position o NRC issued CAL which included commitments to: 11 Determine root cause and develop a long-term monitoring program (due 2/28/12)13 Select multiple un-cracked areas to investigate to verify the cracking is not spreading (due 90 days)13 Analyze known cracked areas to verify the cracks are not growing o] Decision was made to leave code compliance questions out of the CAL and to focus on confirming assumptions made in the operability calculations |
| | [I Focus on continued operability going forward 13 Address design through ongoing inspection 6 |
| | 2/23/2012 License Renewal Impact S7 L" The degraded shield building is a Part 50 issue affecting license renewal" DLR needs to understand if the degradation is age-related, and if so how it will be managed o DLR will issue an RAI asking the applicant to explain how the unique OE will be addressed by its Aging Management Programs (AMP)13 This will be tracked as an Open Item in the SER CR-3 Update: Timeline it 2" Dec. 2008: o Oct. 2009: "Mar. 2010: " Dec. 2010: "Jan. 2011: "Mar. 2011: oJun. 2011: " Jul. 2011: License Renewal Application (LRA) submitted. |
| | Delamination of containment concrete in Bay 3-4.Applicant starts repair of concrete in Bay 3-4.SER issued with open item for containment repair.ACRS Subcommittee meeting.5 Committee requested additional meeting after closeout of.open item forcontainment repair.New delamination identified in containment Bay 5-6.NRC informs the applicant that a revised schedule for LRA review will be established after information on the containment repair plan is submitted. |
| | Spalling and delamination identified in Bay 1-2.n Concrete sections(approx. |
| | 1.5" x 1 2' x 3' & 5) fell on Intermediate Building 7 2/23/2012 CR-3 Update: Recent Activities" Licensee reviewing repair proposals from Bechtel and URS 13 Anticipate contracts to be in place by Jan. 31 13 Repairs expected to require 2 to 3 years to complete 13 Detensioning currently on hold -will be included as part of the repair contract" Licensee installed temporary anchors to limit propagation of delaminations and prevent future delaminations o Staff expects licensee to submit a license amendment but that is not certain at this point o Region II planning appropriate inspections during demolition, repair and testing 8 2/23/2012 CR-3 Update: Original Delamination I"5 Delamination.. |
| | October 2009 Buttress Extent ofi.. Repair/Replacement 57ft X 82ft Buttress #3#4 CR-3 Update: Original Delamination Delamination between buttress 3 & 4 9 2/23/2012 CR-3 Update: Possible Impacts on LR-AMPs V"I Program Impact Concrete and prestressing tendons: Enhanced inspection IWL and surveillance frequency; additional devices such as strain gauges to monitor cracks; and scanning of concrete at different locations. |
| | Containment Leakage Type A, B, and C tests: Test 10 CFR 50 App. J f e u ny frequency. |
| | Tendons: Revision to the program and data since most of the vertical and hoop tendons will be re-tensioned. |
| | Containment Tendons: Major revision to the program to identify sample Tendon Prestress size, frequency; new regression analysis based on re-tensioned data.Comparison of Davis-Besse |
| | & CR-3 o Similar crack geometry[] Laminar cracking around circumference of building o Similarities end there 10 2/23/2012 Differences Between Davis-Besse and CR-3 o Laminar cracking in the reinforced concrete shield building 0 0 Crack widths between 5 -10 mils Cracking along outer reinforcement mat (2-3" from exterior face)o Laminar cracking in the prestressed concrete-containment building" Crack widths between 125 -2750 mils" Cracking in the plane of horizontal prestressing tendons (8-9" from exterior face)o Cracking due to redistribution of prestressing forces, weak aggregate, and lack of radial reinforcement o Root cause still under investigation Summary" Although similar at first glance, Davis-Besse and Crystdl River are different issues a Acceptance of one has no bearing on the other." Both issues are Part 50 concerns which have an impact on license renewal o The Regions and Headquarters will continue to work together to ensure continued functionality (Part 50) and to ensure aging is properly managed (Part 54)11}} |
Revision as of 23:47, 1 August 2018
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Category:Meeting Agenda
MONTHYEARPMNS20231217, Nuclear Generating Plant License Termination Plan Public Meeting2023-11-29029 November 2023 Nuclear Generating Plant License Termination Plan Public Meeting PMNS20211401, Meeting with Energy Harbor Nuclear Corp. (Ehnc) Regarding a Proposed Alternative to Certain Steam Generator Inspection Requirements at Davis-Besse Nuclear Power Station, Unit No. 12021-10-27027 October 2021 Meeting with Energy Harbor Nuclear Corp. (Ehnc) Regarding a Proposed Alternative to Certain Steam Generator Inspection Requirements at Davis-Besse Nuclear Power Station, Unit No. 1 ML15183A4792015-07-0101 July 2015 Ltr. 07/01/15 D.C. Cook U.S. Nuclear Regulatory Commission Region III 2015 Operator Licensing Workshop (Public Meeting)(Drm) ML15182A4412015-07-0101 July 2015 Notice and Agenda - 2015 Operator Licensing Workshop ML15183A3862015-07-0101 July 2015 Ltr. 07/01/15 Prairie Island U.S. Nuclear Regulatory Commission Region III 2015 Operator Licensing Workshop (Public Meeting) (Drm) ML15183A3992015-07-0101 July 2015 Ltr. 07/01/15 Point Beach U.S. Nuclear Regulatory Commission Region III 2015 Operator Licensing Workshop (Public Meeting) (Drm) ML15183A4632015-07-0101 July 2015 Ltr. 07/01/15 Monticello U.S. Nuclear Regulatory Commission Region III 2015 Operator Licensing Workshop (Public Meeting) (Drm) ML15183A4842015-07-0101 July 2015 Ltr. 07/01/15 Davis-Besse U.S. Nuclear Regulatory Commission Region III 2015 Operator Licensing Workshop (Public Meeting) (Drm) ML15183A4782015-07-0101 July 2015 Ltr. 07/01/15 Duane Arnold U.S. Nuclear Regulatory Commission Region III 2015 Operator Licensing Workshop (Public Meeting) (Drm) ML15183A4452015-07-0101 July 2015 Ltr. 07/01/15 Perry U.S. Nuclear Regulatory Commission Region III 2015 Operator Licensing Workshop (Public Meeting) (Drm) ML15183A4722015-07-0101 July 2015 Ltr. 07/01/2015 Fermi U.S. Nuclear Regulatory Commission Region III 2015 Operator Licensing Workshop (Public Meeting) (Drm) ML14169A4772014-06-13013 June 2014 Operator License Workshop Invitation ML14077A1052014-03-18018 March 2014 March 25, 2014, Notice of Category 3 Forthcoming Meetings to Discuss the Draft Supplemental Environmental Impact Statement for the License Renewal of Davis-Besse, Unit 1 ML13350A4002013-12-18018 December 2013 1/16/14 - Notice of Meeting in Crystal River, Fl, to Discuss and Accept Public Comments Related to the Crystal River Unit 3 Nuclear Generating Station Post-Shutdown Decommissioning Activities Report ML13280A9062013-10-21021 October 2013 Forthcoming Meeting with Firstenergy Nuclear Operating Company (FENOC) to Discuss Voluntary Risk Informed Fire Protection Amendment for Davis-Besse ML13252A1712013-09-0909 September 2013 9/24/13 - Notice of Public Meeting - Firstenergy Nuclear Operating Company (Fenoc)(Beaver Valley, Perry, and Davis-Besse) ML13225A1992013-08-13013 August 2013 Correction - 08/29/13 Notice of Forthcoming Meeting with Duke Energy Florida: Crystal River, Unit 3 Nuclear Generating Plant Decommissioning Submittals ML13221A5412013-08-12012 August 2013 Notice of Forthcoming Meeting with Duke Energy Florida, Crystal River, Unit 3 Nuclear Generating Plant Decommissioning Submittals ML12300A4032012-10-26026 October 2012 11/8/2012 Meeting Notice with Duke Energy to Discuss NRC Order on Mitigation Strategies for Beyond-design-Basis External Events ML12285A3122012-10-15015 October 2012 11/1/12 Forthcoming Meeting Via Conference Call with Duke Energy, Inc. Representing Florida Power Corporate Concerning Generic Letter 2004-02 and Draft Proposed Strainer Fiber Bypass Test Plan for Crystal River ML12269A0612012-09-26026 September 2012 FENOC Presentation for 2012-09-26 Public Meeting ML12158A4002012-06-0808 June 2012 6/26/2012 Forthcoming Meeting Firstenergy Nuclear Operating Company (FENOC) ML12138A3312012-05-17017 May 2012 05/31/2012, Notice of Significant Licensee Meeting (non-public) Regarding Operator Licensing Workshop and Meeting ML12200A2492011-12-22022 December 2011 Presentation Slides on Shield Building /Containment Delamination ML11307A4102011-10-18018 October 2011 Public Meeting Memo ML1116400632011-06-15015 June 2011 EOC NRC Slides for Public Meeting ML11153A1652011-06-0909 June 2011 06/28/11 Notice of Forthcoming Meeting to Discuss the Draft Supplemental Environmental Impact Statement for the License Renewal of Crystal River Unit 3 Nuclear Generating Plant ML1110806902011-04-20020 April 2011 Notice of Meeting with First Energy Nuclear Operating Company (FENOC) to Discuss a Proposed LAR to Delete Technical Specification 5.5.8g, Steam Generator (SG) Program Auxiliary Feedwater Header Inspections ML1107405412011-03-31031 March 2011 4/21/11 Notice of Forthcoming Meeting with Progress Energy, Crystal River, Unit 3, to Discuss Licensee'S Overall Plans Associated with an EPU Application ML1108406312011-03-29029 March 2011 Notice of Forthcoming Pre-Application Meeting with Carolina Power & Light Co. and Florida Power Corp., Brunswick Units 1 & 2, Crystal River Unit 3, and H.B. Robinson Unit 2, to Discuss Transition to the Requirements of National Fire.. ML1028702612010-10-22022 October 2010 11/04/10 Notice of Meeting to Discuss the License Renewal Process and Environmental Scoping for Davis-Besse Nuclear Power Station License Renewal Application Review ML1027404282010-10-0101 October 2010 Notice of Forthcoming Meeting with Florida Power Corporation (Progress Energy) to Discuss the Crystal River Proposed License Amendment Request to Support Implementation of the Independent Spent Fuel Storage Facility (ISFSI) Project ML1020904022010-07-21021 July 2010 Summary of Petition Review Board Discussion with Petitioner Thomas Saporito, 2.206 Petition G20090690 ML1019003912010-07-0909 July 2010 Forthcoming Conference Call with Crystal River Unit 3 Nuclear Generating Plant - Progress Energy to Discuss the Licensee'S 10 CFR 50.59 Evaluation ML1016601412010-06-17017 June 2010 Notice of Forthcoming Meeting with Progress Energy to Discuss Licensee'S Plans for Repairing the Containment at Crystal River, Unit 3 L-02-002, G20100238/EDATS: OEDO-2010-0305 - Ltr. Tom Gurdziel, 2.206 - Firstenergy - Davis-Besse2010-04-15015 April 2010 G20100238/EDATS: OEDO-2010-0305 - Ltr. Tom Gurdziel, 2.206 - Firstenergy - Davis-Besse ML1009102662010-03-31031 March 2010 Slides FENOC and NRC Senior Management Briefing, 3-31-10 ML0908604012009-04-0202 April 2009 04/16/09 Notice of Meeting to Discuss the License Renewal Process and Environmental Scoping for CR-3 Nuclear Generating Plant, License Renewal Application Review ML0830800052008-10-31031 October 2008 Meeting Slides, Progress Energy Public Meeting, NRC Region II Visit ML0806705292008-03-0606 March 2008 Draft Scheduling Notes for Briefing on Reactor Materials Issues on 04/28/2008 ML0733711662007-12-0303 December 2007 Notice of Meeting with Progress Energy & Duke Energy Regarding Fire Probabilistic Risk Assessment for the Pilot Plants Transitioning to the National Fire Protection Association Standard NFPA 805 ML0724100052007-08-29029 August 2007 Revised Notice - Date Change of Meeting with Progress Energy Florida to Discuss Status of the Power Uprates at Crystal River, Unit 3 ML0723302222007-08-28028 August 2007 09/12/2007 Notice of Meeting with Firstenergy to Discuss the August 3, 2007 License Amendment Request for Conversion to Improved Technical Specifications for Davis-Besse, Unit 1 ML0723500152007-08-23023 August 2007 Notice of Meeting with Progress Energy Florida to Discuss the Status of the Power Uprates at Crystal River, Unit 3 ML0722201892007-08-0808 August 2007 NRC EOC Public Meeting Slides ML0717103462007-06-21021 June 2007 Revised Notice of Meeting with Firstenergy to Discuss Response to Nrc'S 05/14/2007, Demand for Information Regarding Fenoc'S Re-analysis of the Timeline and Root Causes for the 2002 Davis-Besse Reactor Pressure Vessel Head Degradation Event ML0716202122007-06-13013 June 2007 Notice of Meeting with Firstenergy Regarding May 14, 2007 Demand for Information Davis-Besse ML0715203432007-06-0707 June 2007 Notice of Meeting with Union of Concerned Scientists Re Davis-Besse Nuclear Power Station 10 CFR 2.206 Petition Concerning Protection Against Control Rod Drive Mechanism (CRDM) Nozzle Leakage Fast Corrosion Scenario ML0710105412007-04-12012 April 2007 Crystal River Unit 3, Meeting Notice Regarding Power Uprates, Steam Generator Replacement, and Installation of an Independent Spent Fuel Storage Facility ML0700900122007-01-11011 January 2007 Notice of Forthcoming Pre-Submittal Meeting with Firstenergy Nuclear Operating Co. (FENOC) to Discuss Proposed Davis-Besse Measurement Uncertainty Recapture (Mur) Power Update License Amendment Request 2023-11-29
[Table view] Category:Meeting Briefing Package/Handouts
MONTHYEARML23335A0822023-12-0707 December 2023 NRC -Crystal River LTP Public Mtg Slide Deck Final ML23335A0832023-12-0707 December 2023 ADPCR3 - Crystal River LTP Public Mtg Slide Deck Final 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 ML20022A0262020-01-22022 January 2020 NEI Presentation Status Update for Ropte Short Term Action Plan: Removed Planned Unavailability for Mitigating Systems Performance Index 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 ML17227A2362016-02-18018 February 2016 Presentation Slides from February 18, 2016, Meeting with Duke Energy Regarding Crystal River Unit 3, Cyber Security Plan Implementation Schedule Milestone 8 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 ML14024A2632014-01-16016 January 2014 Handouts for Post-Shutdown Decommissioning Activities Report Public Meeting, January 16, 2014 ML13322B3112013-11-13013 November 2013 NFPA 805 Transition - Meeting Slides, 11/13/2013 ML13308A0072013-11-0101 November 2013 Open Phase Resolution Update Meeting Duke Energy Entitled Open Phase Detection and Protection. ML13294A5972013-10-21021 October 2013 FENOC Presentation Slides for Public Meeting September 24, 2013 ML13238A3072013-08-29029 August 2013 Slide for 08/29/13 Meeting CR-3 Decommissioning Submittals 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 ML12305A2752012-11-0101 November 2012 11/1/12 Meeting Presentation - Regarding GSI-191 Strainer Fiber Bypass Test Plan on November 1, 2012 for Crystal River 3 Generating Plant 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 ML12221A2682012-08-0909 August 2012 FENOC Shield Building Cracking Davis-Besse Public Meeting 8/9/12 ML12221A2642012-08-0909 August 2012 NRC Public Meeting NRC Presentation 8/9/12 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 ML12004A0102012-01-0404 January 2012 Public Meeting NRC Slides ML12200A2492011-12-22022 December 2011 Presentation Slides on Shield Building /Containment Delamination ML11314A2552011-11-10010 November 2011 Summary of Pubic Meeting with Crystal River Nuclear Plant Docket No. 50-302 ML11307A4072011-11-0707 November 2011 Pp Presentation NRC Regulatory Conference Presentation 11/07/2011 ML11220A2542011-08-0101 August 2011 DBNPS-Info Meeting Slides ML11180A2752011-06-28028 June 2011 Preliminary Site-Specific Results of the License Renewal Environmental Review for Crystal River Unit 3 ML1117209902011-06-15015 June 2011 Meeting Presentation NRC Annual Assessment Meeting: Davis-Besse Nuclear Power Station. ML1116400632011-06-15015 June 2011 EOC NRC Slides for Public Meeting ML1116400592011-06-0707 June 2011 Meeting Summary - Crystal River Nuclear Plant - Presentation Slides ML11123A0422011-04-21021 April 2011 4/21/11 Crystal River Unit 3 Meeting Slides Regarding EPU Pre-Application ML1025810962010-09-0202 September 2010 Unit #3 Containment Investigation and Repair ML1021501182010-07-29029 July 2010 Licensee Slides for Davis-Besse Annual Assessment Meeting ML1021501112010-07-29029 July 2010 NRC Slides for Davis-Besse; July 29, 2010; Annual Assessment Meeting ML1019405242010-06-30030 June 2010 2010 June 30 NRC Technical Meeting ML1013200462010-05-12012 May 2010 Annual Assessment Meeting Presentation 2023-12-07
[Table view] Category:Slides and Viewgraphs
MONTHYEARML23335A0832023-12-0707 December 2023 ADPCR3 - Crystal River LTP Public Mtg Slide Deck Final ML23335A0822023-12-0707 December 2023 NRC -Crystal River LTP Public Mtg Slide Deck Final ML23152A2022023-06-0101 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 ML22028A3972022-02-0101 February 2022 NRC Regulatory Conference Presentation ML22028A3922022-02-0101 February 2022 Licensee 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 ML20022A0262020-01-22022 January 2020 NEI Presentation Status Update for Ropte Short Term Action Plan: Removed Planned Unavailability for Mitigating Systems Performance Index 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 ML17227A2362016-02-18018 February 2016 Presentation Slides from February 18, 2016, Meeting with Duke Energy Regarding Crystal River Unit 3, Cyber Security Plan Implementation Schedule Milestone 8 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 ML14024A2632014-01-16016 January 2014 Handouts for Post-Shutdown Decommissioning Activities Report Public Meeting, January 16, 2014 ML13322B3112013-11-13013 November 2013 NFPA 805 Transition - Meeting Slides, 11/13/2013 ML13308A0072013-11-0101 November 2013 Open Phase Resolution Update Meeting Duke Energy Entitled Open Phase Detection and Protection. 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. ML13238A3072013-08-29029 August 2013 Slide for 08/29/13 Meeting CR-3 Decommissioning Submittals 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 ML13134A1732013-05-13013 May 2013 Public Meeting Summary - Category 3 - Annual Assessment Meeting - Crystal River Unit 3 Nuclear Plant ML13078A2492013-03-20020 March 2013 Project Overview-Public Mtg 3-20-13 Non Proprietary ML12305A2752012-11-0101 November 2012 11/1/12 Meeting Presentation - Regarding GSI-191 Strainer Fiber Bypass Test Plan on November 1, 2012 for Crystal River 3 Generating Plant 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 ML12184A1382012-07-0202 July 2012 Public Meeting Summary of Category 3 - Annual Assessment Meeting Crystal River 2011 Annual Assessment Meeting Summary 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 ML11314A2552011-11-10010 November 2011 Summary of Pubic Meeting with Crystal River Nuclear Plant Docket No. 50-302 ML11307A4072011-11-0707 November 2011 Pp Presentation NRC Regulatory Conference Presentation 11/07/2011 ML11221A3012011-08-0101 August 2011 521- R326C B&W Tech Cross Training - Chapter 16 Davis-Besse Loss of All Feedwater ML11220A2542011-08-0101 August 2011 DBNPS-Info Meeting Slides ML11180A2752011-06-28028 June 2011 Preliminary Site-Specific Results of the License Renewal Environmental Review for Crystal River Unit 3 2023-06-01
[Table view] |
Text
'2/23/2012 SHIELD BUILDING / CONTAINMENT DELAMINATION:
DAVIS-BESSE
& CRYSTAL RIVER BRYCE LEHMAN -NRR/DLR JIM NEURAUTER
-REGION III/DRS DANIEL RICH -REGION II/DRP 1 Agenda" Davis-Besse Condition
& Licensee's Position" NRC's Position on Davis-Besse" Impact on License Renewal" Status Update on Crystal River o Impact on License Renewal" Similarities
& Differences Between Plants~Yy 1 2/23/2012 Davis-Besse Shield Building" Free-standing steel containment vessel surrounded by reinforced concrete shield building" Shield Building Functions:
A 13 Environmental
& external missile protection for containment vessel 13 Biological shielding during normal operation and accident conditions I 13 Means for collection and filtration of fission product leakage following accident Initial Condition o Laminar crack identified in architectural flute shoulder area during hydro-demolition for replacement of reactor vessel closure head (October 1 Oth)o Crack found on the vertical side of the opening (left side, looking from the outside), generally along main reinforcing steel, and extends -6'across the top and "-4' across the bottom 2 2/23/2012 Construction Opening Flute/Shoulder Geometry 3 2/23/2012 Condition Assessment 7* "Chipping back" along cracked areas revealed crack extended beyond construction opening* Impulse Response (IR)methodology employed to investigate extent of crack* IR testing indicated crack extended -38' above construction opening* (4) core bores taken to validate IR results 13 Indicated crack existed near outer reinforcement mat[3 IR testing performed on 15 of 16 flute shoulders a Based on results, licensee assumed cracking throughout all shoulders o Core bores taken on 1 2 shoulders to confirm crack boundaries c] Core bores inspected using boroscope to identify crack depths and widths 13 Very tight, less than 0.01" Condition Assessment o IR testing performed on 4 of 8 flute areas o Core bores taken from 6 of 8 flute areas" IR testing and core bores confirmed laminar cracking not present in flute areas 13 One flute did have a vertical crack, but determined to be isolated condition ii IR testing performed in 7 of 8 areas between flute shoulders io Two small regions adjacent to Main Steam Line penetration blockouts are cracked a3 Extent of cracking unique to penetrations o Cracking regions exist at top 20'of Shield Building wall outside shoulder area o Spring line area appears to have little or no cracking (top 5')4 2/23/2012 Condition Assessment Summary" Cracking is generic to all flute shoulder regions" Cracks are confined to flute shoulder regions with exception of top 20' of Shield Building wall and two small regions near MSL penetrations o Cracking exists at top 20' of Shield Building wall outside shoulder region o Cracks are very tight, <0.01 ", and located near the outer reinforcing mat'I Licensee's Position" Believe sampling method of IR testing and core bores has characterized the extent of cracking in the structure o Primary concern is ability of outside rebar to perform its intended function.
Observations of construction opening and testing indicate concrete is attached to rebar mat o Based on structural evaluation, cracking does not impact ability of structure to perform its intended safety functions" Root cause is underway 5 2/23/2012 NRC's Position o NRC informed licensee it could restart (1 2/2)13 Licensee developed a model with reasonable assumptions which demonstrated a reasonable expectation of operability 13 Staff continues to evaluate whether the shield building conforms to the design code requirements in the CLB" This is currently being addressed by Region III in inspection space.* The inspection is ongoing and the focus has shifted to resolving the question regarding compliance with the design and licensing basis. Region III is developing a plan/timeline for resolution and issuance of the inspection report.NRC's Position o NRC issued CAL which included commitments to: 11 Determine root cause and develop a long-term monitoring program (due 2/28/12)13 Select multiple un-cracked areas to investigate to verify the cracking is not spreading (due 90 days)13 Analyze known cracked areas to verify the cracks are not growing o] Decision was made to leave code compliance questions out of the CAL and to focus on confirming assumptions made in the operability calculations
[I Focus on continued operability going forward 13 Address design through ongoing inspection 6
2/23/2012 License Renewal Impact S7 L" The degraded shield building is a Part 50 issue affecting license renewal" DLR needs to understand if the degradation is age-related, and if so how it will be managed o DLR will issue an RAI asking the applicant to explain how the unique OE will be addressed by its Aging Management Programs (AMP)13 This will be tracked as an Open Item in the SER CR-3 Update: Timeline it 2" Dec. 2008: o Oct. 2009: "Mar. 2010: " Dec. 2010: "Jan. 2011: "Mar. 2011: oJun. 2011: " Jul. 2011: License Renewal Application (LRA) submitted.
Delamination of containment concrete in Bay 3-4.Applicant starts repair of concrete in Bay 3-4.SER issued with open item for containment repair.ACRS Subcommittee meeting.5 Committee requested additional meeting after closeout of.open item forcontainment repair.New delamination identified in containment Bay 5-6.NRC informs the applicant that a revised schedule for LRA review will be established after information on the containment repair plan is submitted.
Spalling and delamination identified in Bay 1-2.n Concrete sections(approx.
1.5" x 1 2' x 3' & 5) fell on Intermediate Building 7 2/23/2012 CR-3 Update: Recent Activities" Licensee reviewing repair proposals from Bechtel and URS 13 Anticipate contracts to be in place by Jan. 31 13 Repairs expected to require 2 to 3 years to complete 13 Detensioning currently on hold -will be included as part of the repair contract" Licensee installed temporary anchors to limit propagation of delaminations and prevent future delaminations o Staff expects licensee to submit a license amendment but that is not certain at this point o Region II planning appropriate inspections during demolition, repair and testing 8 2/23/2012 CR-3 Update: Original Delamination I"5 Delamination..
October 2009 Buttress Extent ofi.. Repair/Replacement 57ft X 82ft Buttress #3#4 CR-3 Update: Original Delamination Delamination between buttress 3 & 4 9 2/23/2012 CR-3 Update: Possible Impacts on LR-AMPs V"I Program Impact Concrete and prestressing tendons: Enhanced inspection IWL and surveillance frequency; additional devices such as strain gauges to monitor cracks; and scanning of concrete at different locations.
Containment Leakage Type A, B, and C tests: Test 10 CFR 50 App. J f e u ny frequency.
Tendons: Revision to the program and data since most of the vertical and hoop tendons will be re-tensioned.
Containment Tendons: Major revision to the program to identify sample Tendon Prestress size, frequency; new regression analysis based on re-tensioned data.Comparison of Davis-Besse
& CR-3 o Similar crack geometry[] Laminar cracking around circumference of building o Similarities end there 10 2/23/2012 Differences Between Davis-Besse and CR-3 o Laminar cracking in the reinforced concrete shield building 0 0 Crack widths between 5 -10 mils Cracking along outer reinforcement mat (2-3" from exterior face)o Laminar cracking in the prestressed concrete-containment building" Crack widths between 125 -2750 mils" Cracking in the plane of horizontal prestressing tendons (8-9" from exterior face)o Cracking due to redistribution of prestressing forces, weak aggregate, and lack of radial reinforcement o Root cause still under investigation Summary" Although similar at first glance, Davis-Besse and Crystdl River are different issues a Acceptance of one has no bearing on the other." Both issues are Part 50 concerns which have an impact on license renewal o The Regions and Headquarters will continue to work together to ensure continued functionality (Part 50) and to ensure aging is properly managed (Part 54)11