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Category:Slides and Viewgraphs
MONTHYEARML24137A1882024-05-16016 May 2024 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation Slides ML23157A0352023-06-0606 June 2023 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation Slides ML21165A1942021-06-16016 June 2021 Joint Annual Assessment Meeting for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation ML21165A2882021-06-16016 June 2021 Joint Annual Assessment for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation (Updated) ML21025A1752021-01-26026 January 2021 License Amendment Request to Adopt TSTF-505 - Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b Pre-Application Meeting, January 26, 2021 (Slides) ML20163A6542020-06-18018 June 2020 2020 NRC Annual Assessment Webinar Presentation - Pennsylvania and Maryland Facilities (Beaver Valley, Calvert Cliffs, Limerick, Peach Bottom, Susquehanna) ML20168A3192020-06-15015 June 2020 Joint Annual Assessment Meeting for Pa/Md Power Plants - Webinar Presentation ML20058B1672020-02-27027 February 2020 Talen Energy Presentation Slides Susquehanna Steam Electric Station Pre-Application Meeting of February 27, 2020 License Amendment Request to Create an Action for an Inoperable Manual Synchronization Circuit ML19165A0062019-06-18018 June 2019 (SSES) License Amendment Request for Proposed Changes to Emergency Response Organization Staffing Augmentation. Pre-Submittal Call Meeting June 18, 2019 ML19157A0542019-06-0606 June 2019 Joint Annual Assessment Meeting (Webinar) for Pennsylvania Power Plants - NRC Presentation Slides ML15264A6872015-09-21021 September 2015 SSES Slide Presentation in Support of 9/23 Public Meeting EAL Scheme Change LAR ML14247A2612014-09-0303 September 2014 NRC Slides for 95002 Presentation for Susquehanna & PPL Public Meeting ML14182A3222014-06-10010 June 2014 Presentation in Support of PPL Meeting with NRC Staff License Transfer Pre-Application Meeting to Be Held July 2, 2014 ML14100A3712014-04-0909 April 2014 Susq 2014 Aam Slides ML13107B1962013-04-10010 April 2013 Slide Presentation for Susquehanna 2012 EOC Annual Assessment Meeting, on April 10, 2013 ML12296A6702012-10-16016 October 2012 SCCI Public Meeting - Slides, 10-16-12 ML12089A4302012-03-21021 March 2012 Aam 95002 Slide Presentation ML12089A1342012-03-21021 March 2012 Annual Assessment Meeting NRC Slide Presentation ML1114407092011-05-19019 May 2011 Aam Slides, May 19, 2011, 2010 Reactor Oversight Process ML1014503572010-05-25025 May 2010 PPL Slides for Susquehanna Annual Assessment Meeting, April 27, 2010 ML1014500762010-05-25025 May 2010 Susq NRC Slides for Aam, April 27, 2010 ML0919402082009-07-13013 July 2009 PPL Slides for Susquehanna SCWE Public Mtg July 6, 2009 ML0919401892009-07-0606 July 2009 Meeting Slides, NRC Susquehanna Safety Conscious Work Environment (SCWE Public Meeting ML0913906312009-06-0404 June 2009 ACRS Meeting with the U.S. Nuclear Regulatory Commission, - June 4, 2009, Slides ML0828807292008-05-31031 May 2008 Draft Comprehensive Plan for the Water Resources of the Susquehanna River Basin ML0915201302008-05-19019 May 2008 Annual Assessment Meeting Slides for 5/19/09, 2008 Reactor Oversight Process ML0811206272008-04-16016 April 2008 SSES 2007 ROP Slides ML0808103392008-03-18018 March 2008 Meeting on March 18, 2008 (NON-Proprietary Version) Presentation (Tac No. MD8099) ML0719802842007-07-19019 July 2007 Meeting Slides for Category 1 Working-Level Meeting with PPL to Discuss Steam Dryer Analysis, Licensing, Design Approach, and Power Asension Test Plans ML0733409182007-05-31031 May 2007 05/31/2007 Presentation by J. Cudsworth NRC Treatment of Issues Other than Category 2 Issues for License Renewal ML0715101782007-05-30030 May 2007 Attachment 2 to PLA-6211, Steam Dryer Replacement, NRC Meeting ML0714401792007-04-24024 April 2007 EOC 2006 Meeting Slides (PPL) ML0714401562007-04-24024 April 2007 EOC Meeting Slides (NRC) on NRC Annual Performance Assessment of Susquehanna Steam Electric Station - 2006 Reactor Oversight Program ML0632401502006-11-15015 November 2006 11/15/06 Environmental Scoping Meeting Slide Handouts ML0631701532006-11-0606 November 2006 Meeting Slides ML0611100212006-04-12012 April 2006 NRC Annual Assessment Meeting, PPL Susquehanna Slides ML0609602842006-04-0606 April 2006 Public Meeting, Susquehanna, Slides on Reactor Oversight Program - Cy 2005 ML0534604562005-12-0808 December 2005 Update on Control Cell Friction ML0536201842005-11-21021 November 2005 NRC-PPL Extended Power Uprate Pre-Submittal Meetings. Start-Up Testing/Large Transient Testing Process Topics ML0536201932005-11-15015 November 2005 NRC Extended Power Uprate Pre-Submittal Meeting, Susquehanna, Flow Induced Vibration Evaluation & Reactor Pressure Vessel Steam Dryer Analysis ML0514403502005-04-0606 April 2005 NRC Annual Assessment Meeting, PPL Susquehanna LLC Team (PPL Slides) ML0513704462005-04-0606 April 2005 Annual Assessment Meeting Notice, Slides ML0412100952004-04-27027 April 2004 PPL Susquehanna, LLC Slides for the Annual Assessment Meeting ML0411906342004-04-27027 April 2004 NRC Region I Slides for the Susquehanna Annual Assessment Meeting with NRC Re Reactor Oversight Program - Cy 2003 ML0315307242003-04-18018 April 2003 April 18, 2003 - RIC 2003 Presentation - F4 - Hubert J. Miller - Region I Breakout ML0314906962003-04-16016 April 2003 April 16, 2003 - RIC 2003 Presentation - W8 - Bryce L. Shriver - Safety Management - Promoting Safety Culture to Achieve Safe Performance ML0310400692003-03-31031 March 2003 Susquehanna Annual Assessment Meeting Slides for Region I and PPL Susquehanna, LLC ML0210903912002-04-16016 April 2002 PPL Susquehanna, LLC Annual Assessment Meeting Slides 2024-05-16
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Susguehanna Steam Electric Station Update on Control Cell Friction Andrew Dyszel PPL Susquehanna, LLC Nuclear Fuels & Analysis
&1~1 00 12'08/05 Page I . i ,l ppI .i.
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Agenda
- Review October 12 NRC Meeting Discussion
- Unit 1 Operation with Control Cell Friction
- Plan for Mid-Cycle Maintenance Outage
- Preliminary Root Cause
- Exigent Tech Spec Change
- Update and Actions Going Forward
- Channel Measurements
- Impacts on Compensatory Actions and MCPR SL
- Probable Root Cause
- Unit 1 Cycle 15 MCPR SL Tech Spec Change
- Unit 2 Status 12/08/05 Page 2
Susquehanna Steam Electric Station (SSES)
- "C" Lattice GE BWR 4
- 3489 MWth
- 764 Assemblies
- 185 Cruciform Blade Control Rods
- Full Core ATRIUM- I OTM (10 x 1O) Fuel 12108/05 Page 3 ppi *-
Overview of Channel Dimensional Measurements
- Purpose of Channel Measurements
- Characterize the amount of channel distortion in the Unit 1 Cycle 14 core.
- Determine the As-Left channel bow distribution in Unit 1 Cycle 14A core.
- Check measurement results against assumptions within MCPR SL.
- Confirm previously determined probable root cause.
Determine any possible trends.
- Material type (Zr-4 vs Zr-2)
- Neutronic parameters (e.g., controlled exposure, burnup) 12/08/05 Page 4 i.i
____Pp _ *v,*
UlC14 As-Found Channel Bow Results
- Compensatory Actions Implemented in July 2005
- Specific Analysis: MCPR OL increased by 0.04
- LHGR limit decreased by 3.9%
- Data taken for cells which experienced friction
- Represents upper end of the bow distribution
- Fresh fuel (SQA-13) mean bow within FANP database
- Once-Burned fuel (SQA-12) mean bow - double FANP database mean value
- Twice-Burned fuel (SQA-l 1) mean bow within FANP database
- UlC14 MCPR SL sensitivity analysis confirms MCPR OL increased < 0.04
- LHGR sensitivity analysis confirms that LHGR compensatory action conservative
Conclusion:
Compensatory Actions Conservative 12/08/05 Page 5 PPI
U1C14A As-Left Channel Bow Results
- Exigent Tech Spec Change Submitted
- U1C14A MCPR SL assumed Fresh Fuel (MCPR limiting fuel) and surrounding fuel had double the mean bow of the FANP database
- Measured bow distribution bounded by MCPR SL assumption
- Fresh Fuel (SQA-13) mean bow within the FANP database
- Once-Burned Fuel (SQA- 12) As-Left mean bow < 70% of the value used in MCPR SL (i.e., 2 x bow)
- 54 assemblies re-channeled 0 38 assemblies discharged
- Twice-Burned Fuel (SQA-l 1) & Thrice-Burned Fuel (SQA-IO) mean bow less than the value used in MCPR SL
Conclusion:
MCPR SL is valid for remainder of UIC14A 12108/05 Page 6 P____'
___ I___ 1.
Probable Root Cause
- Previously documented in our Corrective Action Process
- Probable Root Cause is Channel Deformation
- Shadow Corrosion induced bow
- Change from Zr-4 to Zr-2
- Visual inspections of Inoperable cells without fuel revealed no anomalies in control blade and fuel support piece
- Control Rod Drive testing showed normal drive performance without fuel in the cell
- Bow data substantiates our probable root cause
- Mean of Zr-4 channels was within FANP database
- Mean of Second Cycle Zr-2 channels was substantially higher than FANP database.
12/08/05 Page 7
UlC15 MCPR SL
- 1St application of SPCB CPR correlation at SSES
- Bow assumption is double FANP nominal mean value
- Fuel that contributes to pins in BT (fresh and once-burned) and the surrounding fuel are assumed to have double the mean bow of the FANP database
- Control cell friction monitoring as a part of channel management program will proactively identify MCPR SL issues during U1C15
- Evaluating U 1C 15 channel management strategy
- Potential re-channeling & channel measurements during Unit 1 14t Reload and Inspection Outage 12/08/05 Page 8
SSES Unit 2 Current Status
- Unit 2 is not currently showing signs of control cell friction
- Bow assumption already includes double FANP nominal mean value
- Core Loading Philosophy
- Channel Design and Material Composition
- Hot Excess Reactivity and Control History
- Unit 2 may follow a similar friction trend to that observed in Unit 1
- Based on Unit 1 experience, signs of friction would not develop until first quarter of 2006 12/08/05 Page 9
END 12V0805 Page 10 i___