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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 2
iI~~PW ~PwsEnry
.1000i.0erg 3
4 Delamination Close-up 5 &"tPWM WsEne
Location of the Delarnination Note - Tendon depiction is for illustrative 0 purposes and is not an exact scale 0 toNOL
,01 6 A00 0 I 140 509600 Energ
CONDITION ASSESSMENT RESULTS 7 &',P~mesEwgy
I
EL 250' A B C I A I R I I A B C Pour 16 240' D E F D E F Pour 15 230' IR scans completed G H I G H Pour 14 per PT-407T: EL 220' Blue = no delamination J K L J . K L. Pour 13 210' M N 0 M N 0 Pour 12 200' P Q R p Q R Pour 11 P,, 0 E
EL 190' S T U S T U Pour 10 EL 180' Actual IR scan output V W X v w x Pour 9 170' data: AuX Bldg Roof EL 167' 8" y Z AA Y Pour 8 Blue = no delamination 6'x 36'@ EL 164" EL 160' Yellow= transition AB1 AC AD z 14' Pour 7 Red = delaminated EL 150' Intermediate Bldg Roof EL 149' 0" x AA W8x18' Pour 6 AE EL 143"
- EL 140' 8'x8' ' x12' AB Pour 5 AF 22 24' Ex Pour--- EL 130' AG AC Pour 4 Drawing scale EL 119' EL 120' Is not exact Equipment Hatch Pour 3
EL 110' z \ Pour 2 13' x 42' @ EL 93' EL 100' 10' x 60'@ EL 93' 10'x 16 Pour 1
- EL 90' Final locations of IR scans inside the buildings and associated scanning
%OPm% Enqg 8 dimensions were reconciled with actual data sheets on Nov 2 3rd 2009
7
B C A B C A B C Pour 16 240' D E F D E F D E F Pour 15 EL 230' G H I G H G H Pour 14 EL 220' IR scans completed Pour 13 Ji K L J K L . K L per PT 407T: 210' M N 0 M N 0 M N Pour 12 Blue = no delaminatior 200' Fuel Transfer Bldg Roof @ EL 200' 4" P Q R Ed P 16' P Q R Pour 11 EL 190' x
Q EL 182' S T U S T U Pour 10 EL 180' Actual IR scan output R 14' x 34' X V W X Pour 9 V W X 12' EL 170' data:
8' y Z AA y Z AA Pour 8 Blue = no delamination 4'x8' xW'EL 160' "1 EL 160' Yellow= transition 7'x 10' 4'x 26' Pour 7 AB AC AD AB AC AD Red = delaminated 10' x60' EL 150' Intermediate Bldg Roof Intermediate Bldg Roof Pour 6 EL 14 3r' EL 149' 0" EL 149' 0" EL 140' Pour 5 Drawing scale Po- -- EL 130' 20' 20' x12' Is not exact X 12' Pour 4 9' X 9' EL 119' EL 120' EL 119' Pour 3 EL 110' 11, X; Pour 2 42' x*2' EL 100' 7E EL 95' ... .: EL 95' Pour 1
~i~i EL 90' Final locations of IR scans inside the buildings and associated scanning
~2Puus~nq g 9 dimensions were reconciled with actual data sheets on Nov 231 2009
6 m3u M~u~ 5 mmmmcea comm"ua RXW4U.7WAI Crystal River Nuclear Power Plant CQystaRIM,. FL ft. D- m MOSILrT 1.
SCALE 1C
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Core Bores Buttress Spans 2 4 - 5 (as of Jan 111h 2009) a 1Butress #3 I IButtress # 4 " ale Buttress #75 I uttress # 2
- A B C A B C A B C D E F D E
- F D E F G H *I H pg ;G, H II J. K L ,jo, GJ e* K L J K 0:
M N 0 M N
- SGR P Q R PI, OPENING * -R P Q 9
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V W X V W x Y Z AA y Z AA V AUX. BLDG. RO EL 16T.8 AB AC AD 'TinS.
z L ~us
- a INTERMEDIATE AE *AA B=11. RtOO EL. 1494r pow, AF AB VON AG AC EQUIPMENT HATCH
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RBCN-0014 RBCN-0015 RBCN-O010 12
CreJ* Bores .. [*. [ * *['W.* [* IJ m7 Buttress#6 1.
Buttress #2 I Buttress#5 C
=t A B C.., A B C A B C *0*1v 4"* "
lp Ii D E F D E F D E F 9
G H I "G H I G *H I J K L J K L J K L -" 1)
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- 9 S Tr U S T U R V W *, X V W X 9o~
1W Y Z AA Y Z AA POLOt1 AB AC AD AB AC AD INTERMEDIATE INTERMEDIATE BLDG. ROOF BLG. ROOF EL. 149-0 EL 14-W 4=
MMA 4
ILfl POUR 2 RBCN-001 1 RBCN-0012 RBCN-0013 13
2 6 3 5 A
Note - IR mobility values are for relative Ta."OCOW LM=WrM" comparison only. Wsemmw ILCuwnw-wtmT The geometry is different than the containment cylinder.
Cytal River I 12 Nuclear Power Plant I Cryo Rkvw, FL 0.6 0.4 a IlaJ MOBILTY SCALE 00 CORE LOC.ATION (SCUD) 00 CM LOCATIO(MT) NOTE:
LOCATION CF WRE IN THEF9ELD SHOULD60VVM 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 BUTTRESS04 90, Drawing scale is not exact 15 I&ftogm Enery