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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 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 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 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 ML1025810962010-09-0202 September 2010 Unit #3 Containment Investigation and Repair ML1019405242010-06-30030 June 2010 2010 June 30 NRC Technical Meeting ML1013200462010-05-12012 May 2010 Annual Assessment Meeting Presentation 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 ML1029106492009-12-28028 December 2009 Failure Modes of CR-3 Containment Concrete Delamination Issue ML1010603462009-11-20020 November 2009 Unit #3 Containment Delamination Update ML1029205092009-11-16016 November 2009 Presentation to Pnsc Containment Update & Discussion of Repair Options ML1029105912009-11-0505 November 2009 Unit #3 Containment Update by Garry Miller ML1029105902009-11-0505 November 2009 2009 Nov 5 - NRC Telecon Briefing.Pdf 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 ML1007504142009-10-14014 October 2009 Email from F. Saba to R. Kuntz, Et Al, Subj: Fyi: Pop for E. Leeds Briefing ML1007504252009-10-13013 October 2009 Email W/Briefing on CR3 Containment Project Overview ML0913201652009-05-12012 May 2009 Summary of Category 3 Public/Open House Meeting with Crystal River to Discuss Annual Assessment ML1029106992009-01-23023 January 2009 2.7 Inadequate Vibration During-Pour ML0830800052008-10-31031 October 2008 Meeting Slides, Progress Energy Public Meeting, NRC Region II Visit ML0810103922008-04-0808 April 2008 Public Meeting - Progress Energy Slides ML0612206932006-05-30030 May 2006 & 11/15/2006 Summary of Conference Calls with Florida Power Corporation. Progress Energy Presentation Slides ML0610304862006-04-11011 April 2006 NRC CY2005 Annual Assessment Meeting - Crystal River - Presentation Slides ML0610305062006-04-11011 April 2006 Presentation Slides for 04/11/06 NRC Public Meeting ML0615301932006-03-27027 March 2006 NFPA 805 Pilot Observation Visit Trip Report - March 2006 - Handouts ML0525604472005-08-17017 August 2005 B&W Owners Group Reactor Vessel Working Group Summary of the Plans of the B&Wog Reactor Vessel Integrity Program ML0523604402005-08-11011 August 2005 Attachment 4 - Progress Energy Slides ML0511903302005-04-26026 April 2005 Steam Generator Inspection Presentation ML0436402692004-12-0909 December 2004 Progress Energy, Meeting Briefing of 12/9/04, Fire Protection Program ML0403505052004-01-0707 January 2004 Meeting Handouts with Progress Energy to Discuss Fire Protection Initiatives ML0327206212003-09-24024 September 2003 Examiner - Vendor Matrix with Phone Number ML0327206112003-09-22022 September 2003 Exam Process ML0327206422003-02-27027 February 2003 Project Plan Sample ML0213404582002-05-16016 May 2002 Training Managers Conference Handouts 2023-12-07
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http://nggweb/cr3environmentalradcontrol/chemist ry/out/podchem. pdf (2-year plot)
Primary to Secondary Leakrate / RM-A12 Method 3.5-3-
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Provide a description of the inspections performed including the areas examined and the probes used.
Scope A B 100% Full Length Bobbin Coil (UTS to LTS) 15,232 14,748 100% Upper and Lower Roll Transition Of The Non-Sleeved Tubes Inservice 15,232 14,748 Using MRPC 34% Bobbin Coil of the Inservice Sleeves Examined Full Length of the Sleeve 55 54 34% MRPC of the Rolled Joints in the UTS and 15S of the Inservice Sleeves (Plus 55 54 6" below the end of the sleeve) 34% MRPC exam UTS and 15S of Remainder Lane Region Un-sleeved tubes 13 10 34% MRPC @ 15S Exam Of One Tube Boundary Around Lane/Wedge Region 45 45 Sleeved and Un-Sleeved Tubes Visual Inspection of ALL Plugs 598 1566 100% MRPC of the I-600 Rolled Plugs 20 47 100% MRPC of the Dents Adjacent to Explosive Plugged Tubes 17 66 34% MRPC of all Dents LTS +4" to UTE 160 70 34% MRPC in the Lower Tube Sheet Crevice Area, +4" to -8" from the LTSF in 2054 1387 the Sludge Pile Region 100% MRPC of the Inservice Tubes with IGA in the First Span N/A 167 Mi Progres Energy
The scope of the inspection and the expansion criteria Scope 100% Full Length Bobbin Coil 100%/6 Inspection, no further expansion Is possible 100% Upper and Lower Roll Transition Of The Non-Sleeved Tubes Inservice 100% Inspection, no further expansion Is possible Using MRPC 34% Bobbin Coil of the Inservice Sleeves Examined Full Length of the Sleeve IF C-I: THEN NO EXPANSION REQUIRED IF C-2 or C-3:. THEN Inspect the remaining tubes inthe affected OTSG and 20% additional tubes inthe other OTSG.
34% MRPC of the Rolled Joints in the UTS and 15S of the Inservice Sleeves (Plus IEC-1: ITHE NO EXPANSION REQUIRED 6" below the end of the sleeve) jfC-2 or C-3:. THEN Inspect the remaining tubes Inthe affected OTSG and 20% additional tubes inthe other OTSG.
34% MRPC exam UTS and 15S of Remainder Lane Region Un-sleeved tubes IF C-1: THEN NO EXPANSION REQUIRED IF C-2 or C-3:. THEN Inspect the remaining tubes inthe affected OTSG and 20% additional tubes inthe other OTSG.
34% MRPC @ 15S Exam Of One Tube Boundary Around Lane/Wedge Region IEC-I: THEN NO EXPANSION REQUIRED Sleeved and Un-Sleeved Tubes LFC-2 or C-3:. IHEN Inspect the remaining tubes Inthe affected OTSG and 20% additional tubes Inthe other OTSG.
Visual Inspection of ALL Plugs 100% Inspection, no further expansion Is possible 100% MRPC of the I-600 Rolled Plugs 100% Inspection, no further expansion Is possible 100% MRPC of the Dents Adjacent to Explos Plugged Tubes 100% Inspection, no further expansion is possible 34% MRPC of all Dents LTS +4" to UTE IFC-1: TH3N NO EXPANSION REQUIRED IFC-2 or C-3:. THEN Inspect the remaining tubes inthe affected OTSG and 20% additional tubes Inthe other OTSG.
34% MRPC in the Lower Tube Sheet Crevice Area, +4" to -8" from the LTSF in IFC-1: THEN NO EXPANSION REQUIRED the Sludge Pile Region IEC-2 or C-3:. THEN Inspect the remaining tubes inthe affected OTSG and 20% additional tubes inthe other OTSG.
100% MRPC of the Inservice Tubes with IGA in the First Span (B OTSG) N/A doG Progress Energy
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TYPICAL TUBE END CRACKING EC'T Indications 3/16" -1/2 "1 V'* Characteristics
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