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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 ML20022A0262020-01-22022 January 2020 NEI Presentation Status Update for Ropte Short Term Action Plan: Removed Planned Unavailability for Mitigating Systems Performance Index 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 ML14024A2632014-01-16016 January 2014 Handouts for Post-Shutdown Decommissioning Activities Report Public Meeting, January 16, 2014 ML13308A0072013-11-0101 November 2013 Open Phase Resolution Update Meeting Duke Energy Entitled Open Phase Detection and Protection. ML13238A3072013-08-29029 August 2013 Slide for 08/29/13 Meeting CR-3 Decommissioning Submittals ML13134A1732013-05-13013 May 2013 Public Meeting Summary - Category 3 - Annual Assessment Meeting - Crystal River Unit 3 Nuclear Plant 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 ML12184A1382012-07-0202 July 2012 Public Meeting Summary of Category 3 - Annual Assessment Meeting Crystal River 2011 Annual Assessment Meeting Summary ML12132A3442012-05-11011 May 2012 NRC-AERB Bilateral Meeting Slide Presentation (Nro/De), Aerb, India - May 16-17, 2012 ML1204402842012-02-16016 February 2012 Public Meeting Construction Experiences - Evaluate Impact of Concrete Degradation 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 ML11180A2752011-06-28028 June 2011 Preliminary Site-Specific Results of the License Renewal Environmental Review for Crystal River Unit 3 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 ML11102A0052011-04-12012 April 2011 Progress Energy - Slides for NFPA 805 Pre-LAR Application Meeting April 12, 2011 ML1034806342010-12-16016 December 2010 Summary of Meeting with Florida Power Corporation Regarding Crystal River'S Proposed License Amendment Request to Support the Independent Spent Fuel Storage Facility Project ML1029201882010-10-19019 October 2010 Appendix Slides ML1029205162010-09-20020 September 2010 Photo ML1029200732010-09-20020 September 2010 Containment 40 Undated Delamination Investigation Report ML1025903962010-09-15015 September 2010 Summary of Public Meeting - Special Inspection Results Crystal River Nuclear Plant ML1025810962010-09-0202 September 2010 Unit #3 Containment Investigation and Repair ML1024402052010-09-0202 September 2010 NRC Special Inspection Team Exit Meeting for Crystal River - September 2, 2010 ML1019405242010-06-30030 June 2010 2010 June 30 NRC Technical Meeting ML1011803132010-03-19019 March 2010 E-Mail from Kuntz to Craver, Crystal River Containment Repair Plan Update ML1028710902010-03-0808 March 2010 Mar 8 Pnsc De Tensioning Briefing ML1028710912010-03-0303 March 2010 Mar 3 Pnsc De Tensioning Briefing P1 ML1028804582010-02-18018 February 2010 7.8 Excessive Water Jet Pressure Part 3 ML1028702742010-02-0606 February 2010 6.4 Rigid and Flexible Sleeves ML1029105792009-12-28028 December 2009 Email - from: Thomas, George to: Lake, Louis Cc: Khanna, Meena; Franke, Mark; Farzam, Farhad; Carrion, Robert; Masters, Anthony; Nausdj@Ornl.Gov Dated Monday, December 28, 2009 6:15 PM Subject: CR-3 Schedule and Root Cause Failure Modes Upd ML1011708192009-12-0303 December 2009 Root Cause Analysis - PII Metrics as of Dec 3rd 2009 ML16175A6062009-11-20020 November 2009 Unit #3, Containment Delamination Update ML1010603462009-11-20020 November 2009 Unit #3 Containment Delamination Update ML1029306172009-11-16016 November 2009 2009 Nov 16- Pnsc - Repair Update Final ML1029205092009-11-16016 November 2009 Presentation to Pnsc Containment Update & Discussion of Repair Options ML1029306522009-11-12012 November 2009 2009 Nov 12 - Containment Unfolded Graphics_Ir Mosaic.Pptx ML1029105542009-11-12012 November 2009 Email - from Orf, Tracy to: Lake, Louis Dated Thursday, November 12, 2009 7:05 Am Subject: FW: CR3 Information Update ML1029105772009-11-0606 November 2009 Containment Unfolded Buttress 2 to 5 ML1029105912009-11-0505 November 2009 Unit #3 Containment Update by Garry Miller ML1029105902009-11-0505 November 2009 2009 Nov 5 - NRC Telecon Briefing.Pdf ML1029105932009-11-0404 November 2009 Email - Subject: CR3 Status Meeting ML1029106712009-10-30030 October 2009 2009 Oct 30 - Root Cause Analysis Metrics.Pptx ML1029107232009-10-29029 October 2009 Condition Assessment (29Oct09).doc ML1029106722009-10-29029 October 2009 2009 Oct 29_NRC Copy_Containment Delamination.Pptx ML1007504252009-10-13013 October 2009 Email W/Briefing on CR3 Containment Project Overview ML1028804922009-10-0505 October 2009 10/6/09 Crystal River 3 Nuclear Safety Review Committee Handout Page ML0913201652009-05-12012 May 2009 Summary of Category 3 Public/Open House Meeting with Crystal River to Discuss Annual Assessment 2023-12-07
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APPENDIX SLIDES SGR Opening Sequence & Identification of Delamination Condition Assessment Results CR3 Design Features Graphics Original Construction Photos 1 #TiaFie't.
Progress Energy APPENDIX SLIDES SGR OPENING SEQUENCE &IDENTIFICATION OF DELAMINATION iI~~PW ~PwsEnry 2
.1000i.0erg 3
4 Delamination Close-up*&"tPWM WsEne 5 Location of the Delarnination Note -Tendon depiction is for illustrative purposes and is not an exact scale 0 NOL to 0 6 A 0 0 0 ,01 I 140 509600 Energ CONDITION ASSESSMENT RESULTS&',P~m esEwgy 7 I
EL250'-- ----EL 250'A B C I A I R I I A B C IR scans completed per PT-407T: Blue = no delamination E Actual IR scan output data: Blue = no delamination Yellow= transition Red = delaminated Drawing scale Is not exact D E F G H I J K L M N 0 P Q R S T U V W X y Z AA AB1 AC AD D E F G H J .K L.M N 0 p Q R P,, 0 S T U v w x Intermediate Bldg Roof EL 149' 0" 8'x8' ' x12'22 Ex 24'EL 119'AE AF AG Y z AA AB AC AuX Bldg Roof EL 167' 8" 6'x 36'@ EL 164" 14'W8x18' x EL 143" Pour 16-EL 240'Pour 15-EL 230'Pour 14-- EL 220'Pour 13-EL 210'Pour 12-EL 200'Pour 11--EL 190'Pour 10--EL 180'Pour 9-EL 170'Pour 8--EL 160'Pour 7--EL 150'Pour 6-- EL 140'Pour 5 Pour--- EL 130'Pour 4-- EL 120'Pour 3----- -----EL 110'Pour 2--EL 100'Pour 1------EL 90'Equipment Hatch z\10' x 60'@ EL 93'13' x 42' @ EL 93'10'x 16%OPm% Enqg 8 Final locations of IR scans inside the buildings and associated scanning dimensions were reconciled with actual data sheets on Nov 2 3 rd 2009 I 7
- 7 7- 1Y B C A B C A B C D E F G H I Ji K L M N 0 IR scans completed per PT 407T: Blue = no delaminatior Ed Actual IR scan output data: P Q R Fuel Transfer Bldg Roof @ EL 200' 4" 16'x EL 182'D E F G H J K L M N 0 P Q R S T U V W X y Z AA AB AC AD D E F G H.K L M N P Q R S T U V W X y Z AA AB AC AD 14' x 34'X 12'Pour 16-EL 240'Pour 15-- EL 230'Pour 14-- EL 220'Pour 13-EL 210'Pour 12-EL 200'Pour 11--EL 190'Pour 10--EL 180'Pour 9-- EL 170'Pour 8--EL 160'Pour 7--EL 150'Pour 6-- EL 140'Pour 5 Po- -- EL 130'Pour 4-- EL 120'Pour 3--EL 110'Pour 2--EL 100'Pour 1-- EL 90'8'Blue = no delamination Yellow= transition Red = delaminated Drawing scale Is not exact 4'x8' xW'EL 160' "1 7'x 10' 4'x 26'1 0' x60'EL 1 4 3 r'20'X 12'9' X 9'EL 119'11, X;7E EL 95'Intermediate Bldg Roof EL 149' 0" Intermediate Bldg Roof EL 149' 0" 20' x12'EL 119'42' ... .: EL 95'~i~i~2Puus~nq g 9 Final locations of IR scans inside the buildings and associated scanning dimensions were reconciled with actual data sheets on Nov 231 2009 6 m3u 5 M~u~mmmmcea comm"ua RXW4U.7WAI Crystal River Nuclear Power Plant CQysta RIM,. FL ft. D- m MOSILrT 1.SCALE 1C 2 6 3 5 A R8MtCNO11 T T T R80t4-012 T T T RBcN.0013 7 7 I A 0 lý V A', L. A (I A E)*4."..,a H I m R1 0 MM IRW BW& ""4 m440 p a R 5 T Z M C0 #A'-.A4 G. A 4 K L~40*T u v v y z AA AB M -AD qlga4 cm IA K A'+*.%mpg M14-U I Cqrstal River Nuclear Power Plant PAL8074I645I F4JIom1wUý i CiryvW P, F TWMULMY CMPAUWiI?GE JL.-A.G-M UI'MOBILITY gm-U A.+ "4:. a L iii LZ_.j.A'.NA-4 a4 i ..i ...I I ..IL-Core Bores Buttress Spans 2 4 -5 (as of Jan 111h 2009)I uttress # 2 a 1Butress #3 I IButtress
- 4 " ale A B C A B C A B D E F G H *I J. K L M N 0 P Q R 9 S T U V W X Y Z AA AB AC AD D E
- F H pg ,jo, GJ K L* SGR PI, OPENING * -R--"~ 06 D E;G, H J K 0: M N P Q S T V W y Z AA Buttress #75 C F II L ~us U " x pow, VON'TinS.INTERMEDIATE B=11. RtOO EL. 1494r AE AF AG V z AB AC AUX. BLDG. RO EL 16T.8 EQUIPMENT HATCH/RBCN-0014 RBCN-0015 RBCN-O010 12 CreJ* Bores ..[ IJ I Buttress#5 m7 Buttress#6 1.Buttress #2 A B C.., 4"* " C=t C A B C A B D E F G H I J K L M N 0 P 4 R FUEL TRANSFER BLDG. ROOF EL 200'-4'D E F" G H I J K L M N 0 P a R* I PC; ý10* 9 S Tr U V W *, X Y Z AA AB AC AD D E F 9 G *H I J K L M N 0 P a R S T U V W X Y Z AA AB AC AD*0*1v lp Ii 4-" 1)Pm Is 9o~ 1W POLO t1 MMA ILfl POUR 2 INTERMEDIATE BLDG. ROOF EL. 149-0 INTERMEDIATE BLG. ROOF EL 14-W 4=4 RBCN-001 1 RBCN-0012 RBCN-0013 13 2 6 3 5 A Note -IR mobility values are for relative comparison only.The geometry is different than the containment cylinder.Ta."OCOW LM=WrM" Wsemmw IL Cuwnw-wtmT I Cytal River Nuclear Power Plant 12 I Cryo Rkvw, FL 0.6 a 0.4 IlaJ MOBILTY SCALE 00 CORE LOC.ATION (SCUD)00 CM LOCATIO (MT)NOTE: LOCATION CF WRE IN THE F9ELD SHOULD 60VVM 4 CONTAINMENT STRUCTURE DOME NITS 14 46 Condition Assessment of the Dome Core Bore Locations as of Nov 26th2OO9 BUTTRESS #1 PERSONNEL ACCESS BUTTRESS #2 BUTTRESS #3 ACCESS BUTTRESS 04 90, Drawing scale is not exact I& ftogm Enery 15