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Category:Slides and Viewgraphs
MONTHYEARML24029A1742024-01-30030 January 2024 Constellation Pre-Application January 30, 2024, Meeting Slides - Proposed Alternative to Utilize Code Case N-932, Alternative Requirements for Acceptance of Containment Base Metal Corrosion or Erosion ML23317A0712023-11-14014 November 2023 NRC Pre-Submittal Meeting on November 14th, 2023 - TSTF-591 and Selected 50.69 License Condition Updates (EPID L-2023-LLM-0098) (Slides) ML23255A1042023-08-11011 August 2023 Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout ML23055A2712023-03-0202 March 2023 March 2, 2023, Preapplication Meeting to Discuss Planned Amendments to Adopt TSTF-505 and 10 CFR 50.69 (EPID L-2023-LRM-0007) - Slides NEI 99-01, Slides - Constellation - Pre-Application EP 2/23/2023 Meeting Slides2023-02-21021 February 2023 Slides - Constellation - Pre-Application EP 2/23/2023 Meeting Slides ML22053A2912022-02-22022 February 2022 NRC Slides for February 25, 2022 Meeting - Acceptance Review of Proposed Alternative to Adopt ASME Code Case N-921 at Dresden and Quad Cities ML21314A4472021-11-10010 November 2021 Slides for Presubmittial Meeting for Proposed Alternative to Adopt ASME Code Case N-921 to Extend the Inservice Inspection Interval ML21194A1822021-07-13013 July 2021 and Quad Cities Nuclear Generating Stations 2020 Annual Assessment Meeting Slides ML21162A3322021-06-11011 June 2021 BWR Fleet Relief Request Associated with RPV Instrument Nozzle Repairs ML20261G7322020-09-16016 September 2020 Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a ML20238B8572020-08-25025 August 2020 Quad 2019 Hq Online EOC Slides ML20178A4202020-06-30030 June 2020 NEI Slides for June 30, 2020, Public Meeting on COVID-19 Response ML20170B0212020-06-23023 June 2020 NRC Pre-Submittal Meeting Byron Unit 2 One-Time Deferral of Reactor Pressure Vessel Head Penetration Nozzle (Rpvhpn) Inspections ML20169A5592020-06-16016 June 2020 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections (Rev 1) ML20163A6552020-06-16016 June 2020 6-16-20 Byron Unit 2 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections ML18347B3142018-12-19019 December 2018 Bwrvip/Asme Relief Request Discussion December 19, 2018 ML18334A2162018-11-30030 November 2018 Presentation Slides: Exelon BWR MSIV (Boiling-Water Reactor - Main Steam Isolation Valve) Leakage Optimization for NRC Pre-Submittal Meeting of December 6, 2018 ML18319A1272018-11-19019 November 2018 Slides for 11/19/18 Public Meeting - Exelon Fleet LAR for Common Language for TS 5.7 High Radiation Areas ML18054B3592018-02-27027 February 2018 Slide: NRC Pre-Submittal Meeting for Exelon Fleet LAR to Relocate TS Unit Staff Qualification ANSI Requirements to the QATR, February 27, 2018, Profile Info: Submitted by Frank Mascitelli ML16314E4812016-11-14014 November 2016 Part 37 Applicability to Reactor Vessels and Associated Structures, Systems, and Components While in Safstor Awaiting Active Decommissioning Activities - November 14, 2016 ML16189A4332016-07-12012 July 2016 July 12, 2016, Public Meeting with NRC - Exelon Decommissioning Licensing Action Submittal Plan ML16077A1562016-03-22022 March 2016 Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards RS-14-238, Transmittal of Proprietary Meeting Slides2014-08-25025 August 2014 Transmittal of Proprietary Meeting Slides ML14167A4122014-06-17017 June 2014 NRC Slides for Quad Cities 2013 EOC Public Meeting ML14232A7852014-05-19019 May 2014 Fuel Transition License Amendment Request Pre-Submittal Update Meeting ML12164A5962012-06-12012 June 2012 Annual Assessment Meeting Slides ML1208701402012-03-27027 March 2012 Licensee Slides for Exelon Fleet Pre-Submittal Public Meeting 4-10-12 Licensed Operator Eligibility Requirements LAR ML1205906462012-03-0505 March 2012 February 9, 2012 - Summary of Meeting with Exelon Nuclear Regarding Future Submittal of Amendment to Use Netco Spent Fuel Pool Inserts ML1203301242012-02-0909 February 2012 Handout for Public Meeting on February 9, 2012 (Slides) ML11201A2132011-07-20020 July 2011 Summary of Public Meeting to Discuss Exelon'S Plans for Implementing an Electronic Document Control System (Edocs) for Use by NRC Inspectors with U.S. Nuclear Regulatory Commission (NRC) Region III Staff ML1109602872011-04-0505 April 2011 Quad Cities Nuclear Power Station 2010 End-of-Cycle Assessment Presentation (Short) ML1109602782011-04-0505 April 2011 Quad Cities Nuclear Power Station 2010 End-of-Cycle Annual Assessment Meeting Presentation (Long) ML1016800822010-06-15015 June 2010 Annual Assessment Meeting, Reactor Oversight Program - 2009, Slides ML0929400522009-10-22022 October 2009 Meeting Power Uprate Meeting Slides ML0911802142009-04-0707 April 2009 NRC End-of-Cycle Meeting Slides ML0911802252009-04-0707 April 2009 NRC - Quad Cities Annual Assessment Meeting Slides ML0812007842008-06-0202 June 2008 Meeting Slides, Nrc/Exelon Licensing Counterparts Meeting. ML0814405062008-05-22022 May 2008 EOC Summary Meeting Slides ML0811504162008-04-22022 April 2008 Pandemic Planning Utility Interface with NRC Slide Presentation ML0711704742007-04-18018 April 2007 EOC Meeting Slides ML0708200122007-03-22022 March 2007 Extended Power Uprate (EPU) Meeting, Handouts from March 22, 2007, Meeting ML0716601022007-03-20020 March 2007 Slides to Counterparts Meeting with Exelon to Discuss Current and Planned Licensing Activities and Process - Correction ML0705101392007-02-16016 February 2007 2007 Emergency Preparedness and Incident Response Public Meeting: Status of the EP Threat Based Project, 2/16/07 ML0616703252006-06-14014 June 2006 Public Meeting Licensee Presentation Slides for Quad Cities End-of-Cycle Plant Performance Annual Assessment ML0615106012006-05-23023 May 2006 EPRI HRA Users Group Review of Draft NUREG-1842 ML0610805702006-04-10010 April 2006 Quad Cities Unit 2 Dryer Inspection Results ML0608201202006-03-16016 March 2006 Exelon Slides from Public Meeting ML0617802832006-03-0707 March 2006 RIC 2006 Presentation - T2F - J. Bradley Fewell - Allegations ML0615901482006-03-0707 March 2006 RIC 2006 Presentation - T1E - Pamela B. Cowan - Licensing Issues ML0604603992005-11-0808 November 2005 Part 3 of the Meeting Slides, Quad Cities Replacement Steam Dryer Meeting on November 8 - 9, 2005 2024-01-30
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1 Quad Cities Station Update End-of-Cycle Meeting June 14, 2006 Tim Tulon Site Vice President 2 Topics:*Extended Power Uprate
-The problem-The fix*Radiation Reduction 3 Extended Power Uprate Completed
-Produce 912 megawatts electric
- NRC approval in December 2001
-Unit 2 in March 2002
-Unit 1 in December 2002Objective -Increase total generation output on both reactors 4 The Problem Increased steam flow Increased acoustic loads Increased Steam Dryer loads Increased steam line piping vibrations ERV actuator damage Steam Dryer cracks 5 Finding the Source
- Unprecedented testing and analysis determined the source of the vibration to the 'standpipes' on the steam lines where the valve attach to the piping.
-The length of the standpipe was increased to reduce the
acoustics inside the pipe. ---
Similar to tuning a pipe organ, or blowing over the top of a soda bottle.
ERV Standpipe 6 State-of-the-Art Testing and Analysis Conducted to Validate Vibration Source
- Testing conducted in six states
- Scale models of actual Quad Cities reactor and piping utilized
- Shaker table testing conducted to duplicate actual vibration levels 7 Actions Taken to Correct Vibration Problem
- Installed New Steam Dryers
-More robust
- Installed Acoustic Side Branch Modification
-Retune the steam system
- Installed Upgraded Valve Actuators
-'Hardened' the actuator 8 New Steam Dryers
- Both Quad Cities steam dryers were replaced in early 2005 with a more robust
design:-Increased stress margins on steam dryers
-Instrumentation provided validation of design load
-Strain gauges provided stress data for analytical purposes 9 2006 Electromatic Relief Valve Upgrade
- Late 2005 issues were discovered with the actuators on the Electromatic Relief Valves (ERVs) due to vibration.
- The ERV actuators have now been replaced with more robust design:-Several ERV actuator replacement options evaluated. New General Electric design proved to
be most rigorous as validated with shaker table tests.
10 Shaker Table TestingERV Actuator TestingERV Testing 11New ERV Actuator -vs-Previous New GE Design Previously Installed Design 12 2006 Acoustic Side Branch Modification Removing the Source of the Vibrations 13 2006 Acoustic Side Branch Modification
-Reduce dryer loading to increase stress margin for long-term operation of dryer
-Reduce overall MSL vibrations impacting ERV actuators and other attached main steam components
-Retuned the steam system 14 How Does the ASB Work?
The addition of the ASB increases the effective length of the ERV/SV standpipe, thereby
decreasing the frequency of the acoustic standing wave. It is similar to a muffler, the ASB
'tunes' the steam flow to reduce vibrations in the piping.
15 Acoustic Side Branch Mod Main Steam Safety Valve Electromatic Relief Valve ASBs 16 Unit 2 Startup Testing RESULTS:*EPU Flow Induced Vibration (FIV)
Reduced to ~ 50% Original Licensed Thermal Power Levels.-Meaning: today steam piping vibration levels at full-EPU power is approximately 50% than when the plant was first put in to commercial operation in 1972.
17 Typical Accelerometer Data ResultsQ2R18 Accelerometer TrendsTarget Rock Inlet Flange - X 00.050.10.150.20.250.30.350.4050010001500200025003000Core Thermal Power, MWtAcceleration, grms3A Target Rock Inlet Flange X1Historical (pre-ASB) EPU ValueHistorical (pre-ASB) OLTP Value3A Target Rock Inlet Flange X23A Target Rock Historical - X Last May w/o ASBs With ASBs 18 Conclusions
- Main Steam Line (MSL) vibrations are reduced
- The ASB modification effectiveness has been confirmed. This adds significant safety margin and substantially increased vibration tolerance to the steam dryer structural integrity and other
main steam line components.
- Both units can operate safely and reliably at EPU power levels.
ASBs Work!
19 Radiation Exposure Efforts 20 Station Has Taken Aggressive Actions to Reduce Radiation Exposure
- Chemical decontamination of reactor piping on both units
- Replacement of turbine blades which contained high sources of Cobalt 60
- Improved worker training / increased awareness through individual dose goals 21 486.0 436.3 336.2 190.0 162.00 rem100 rem 200 rem300 rem400 rem500 rem600 remQ2R16 (2002)Q2R17 (2004)Q2R18 (2006)Q2R18minus ASB / DryerQ2R19 projected (2008)Dose (person-rem)
Red line represents 150 rem -our path to full INPO points and industry best dose performance Red line represents 150 rem -our path to full INPO points and industry best dose performance U2 Outage Dose Reduction Trend Industry Best 22 Where Are We GoingINPO Collective Radiation Exposure Point Performance 6.2 9.7 10.00.00.0 0 points 1 points 2 points 3 points 4 points 5 points 6 points 7 points 8 points 9 points 10 pointsCurrent200720082009Full Points Industry Best Red line represents 150 rem -our path to full INPO points and industry best dose performance Red line represents 150 rem -our path to full INPO points and industry best dose performance 23 Questions?