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MONTHYEARML15203A5072015-07-28028 July 2015 July 28, 2015, Turbine Driven Auxiliary Feedwater Cross-tie License Amendment Request Project stage: Other ML15217A3312015-08-26026 August 2015 July 28, 2015, Summary of Ublic Meeting with NextEra Energy Point Beach, LLC, to Discuss a Proposed Licensing Basis Change for the Turbine-Driven Auxiliary Feedwater Pumps at the Point Beach Nuclear Plant, Units 1 and 2 Project stage: Meeting 2015-07-28
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Category:Slides and Viewgraphs
MONTHYEARML22181B0842022-06-30030 June 2022 2021 Point Beach Nuclear Plant End-of-Cycle Meeting Handout ML21336A7972021-12-0909 December 2021 GL 2004-02 Resolution Update - NextEra Energy Point Beach, LLC - December 9, 2021 (Slides) ML21335A0232021-12-0808 December 2021 Slides - Point Beach Nuclear Plant, Unit Nos. 1 and 2 December 8, 2021 Public Meeting Slides for the Draft Plant-Specific Supplement 23, Second Renewal Dseis Public Meeting ML21253A0152021-09-16016 September 2021 Pre-Submittal Meeting: LAR to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times -RITSTF Initiative 4b ML21162A2632021-06-11011 June 2021 2020 Point Beach Nuclear Plant End-of-Cycle Meeting Presentation ML21134A0232021-05-18018 May 2021 GL 2004-02 Resolution Update - NextEra Energy Point Beach, LLC (NextEra) ML21042B9452021-02-17017 February 2021 Scoping and Process Meeting - February 17, 2021 ML20240A2702020-08-27027 August 2020 2019 EOC Slide Presentation ML18121A3392018-05-0101 May 2018 Slides for Point Beach 2017 EOC Open House ML18108A0152018-05-0101 May 2018 NextEra Approach to Resolution of Tornado Missile Protection May 1, 2018 ML17310B2322017-11-0707 November 2017 Presentation Slides - NextEra Energy/Fpl - GSI-191 Issue Resolution, Pre-submittal Meeting, September 20, 2017 ML17205A0192017-07-17017 July 2017 Presentation for Point Beach 2016 EOC Open House ML17023A0652017-01-24024 January 2017 Pre-Submittal Call Regarding License Amendment Requests for Prairie Island Nuclear Generating Plant, Units 1 and 2 and Monticello Nuclear Generating Plant Emergency Action Level Scheme Changes ML16291A1772016-10-18018 October 2016 License Amendment Request Pre-Submittal Discussion October 18, 2016 ML15203A5072015-07-28028 July 2015 July 28, 2015, Turbine Driven Auxiliary Feedwater Cross-tie License Amendment Request ML15203A4982015-07-22022 July 2015 July 2015, Containment Dome Truss Seismic Analysis Methodology License Amendment Request ML15112A0672015-04-20020 April 2015 Annual Assessment Meeting Open House - Handout EOC 2014 Mtg ML15091A5172015-04-0606 April 2015 4/6/2015, Meeting Slide for Public Teleconference on Point Beach MCR Abandonment Analysis for Loss of Control Scenarios ML14112A4252014-04-0808 April 2014 Annual Assessment Meeting, 2013 Reactor Oversight Process - Slides ML13200A3962013-07-19019 July 2013 EA-13-125, Point Beach, Conference Slides ML13162A7902013-06-11011 June 2013 Meeting Slides ML1114603332011-05-25025 May 2011 EOC Licensee Presentation Slides ML1115400612011-05-25025 May 2011 Licensee Slides from 5/25/11 Public Meeting ML1107703492011-03-22022 March 2011 3/22/11 PRE-Application Meeting Slides Regarding NFPA 805 License Amendment Request ML1108206992011-03-22022 March 2011 3/22/11 Revised Pre-application Meeting Slides Regarding NFPA 805 License Amendment Request ML1013802102010-05-18018 May 2010 5/18/2010 Point Beach Public Meeting Slides ML1011304972010-04-22022 April 2010 NRC Slides for Point Beach End-of-Cycle Public Meeting ML1011304452010-04-22022 April 2010 FPL Energy Point Beach Handout from End-Of-Cycle Public Meeting ML0921107842009-07-29029 July 2009 Meeting Slides, Public Meeting with NRC Region III on Point Beach ML0912007342009-04-29029 April 2009 NRC Slides for Point Beach 2008 End-of-Cycle Public Meeting ML0912007042009-04-29029 April 2009 Presentation at 2008 End-of-Cycle Public Meeting ML0912007212009-04-29029 April 2009 NRC Presentation Handouts for Point Beach 2008 End-of-Cycle Public Meeting ML0828905272008-10-14014 October 2008 Meeting with NRC on AST ML0826819412008-09-24024 September 2008 Meeting Slides, FPL Energy Point Beach Public Meeting with NRC Region III ML0825401402008-09-16016 September 2008 Meeting Slides Point Beach Nuclear Plant Meeting with NRC on Epu. ML0819905262008-07-16016 July 2008 EOC Annual Assessment Meeting Slides ML0709403182007-03-28028 March 2007 EOC Summary Meeting Slides - 2007, Reactor Oversight Program - Cy 2006 ML0705106742007-02-21021 February 2007 NMC Slides for Public Meeting, Conduct of Operations Action Plan Update. ML0632601422006-11-21021 November 2006 11/21/2006 Informational Meeting Regarding Prairie Island License Renewal Application ML0615106012006-05-23023 May 2006 EPRI HRA Users Group Review of Draft NUREG-1842 ML0609307552006-04-0303 April 2006 Public Meeting Summary - Point Beach Safety Culture Meeting (Includes NMC Slides) ML0524903212005-08-25025 August 2005 Slides for Point Beach CAL Public Meeting Summary - August 25, 2005 ML0508304892005-03-14014 March 2005 Confirmatory Action Letter Public Meeting Slides ML0509200092005-03-0303 March 2005 3/3/05 - Preliminary Results of Environmental Review Point Beach Nuclear Plant, Units 1 and 2, Nuclear Regulatory Commission, March 3, 2005 ML0434900602004-11-30030 November 2004 NMC Slides for 11/30/04 Public Meeting ML0425404652004-08-18018 August 2004 Nuclear Management Co Confirmatory Action Letter Public Meeting Presentation Regarding Point Beach Nuclear Plant ML0508303502004-05-11011 May 2004 E-Mail B. Kemp, NMC, to H. Chernoff, NRR, May 11 Rev 2. Ppt W/Att Slides Conference Call, May 11, 2004 ML0508303302004-05-11011 May 2004 Slides: Point Beach Unit 1, Spring 2004 RPV Head Inspection Results Conference Call Tuesday, May 11, 2004 W/Handwritten Notes ML0412602942004-04-21021 April 2004 Public Meeting Slides, Point Beach 2003 End-of-Cycle Assessment ML0412602192004-04-21021 April 2004 Public Meeting Licensee Slides, Point Beach 2003 End - of - Cycle Assessment 2022-06-30
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Turbine Driven Auxiliary Feedwater Cross-tie License Amendment Request Point Beach Nuclear Plant Units 1 & 2 July 28, 2015
Agenda
- Beyond Design Basis Events
Purpose
- The purpose of the pre-submittal meeting is to:
- Provide an Overview of the Auxiliary Feedwater (AFW) System at Point Beach Nuclear Plant
- Review the AFW System Design Basis
- Discuss AFW System Cross-tie Considerations
- Highlight Beyond Design Basis Events Factors
- Licensing Basis Current Licensing Basis Proposed Licensing Basis
- Provide a proposed path forward 3
Auxiliary Feedwater System Design Basis
- one full-capacity Motor Driven Auxiliary Feedwater (MDAFW) pump system
- one full-capacity Turbine Driven Auxiliary Feedwater (TDAFW) pump system
- ensures adequate heat removal under all circumstances, including loss of offsite power and normal heat sink
- The MDAFW pump discharge piping for each unit can be cross-tied
- Current licensing basis (CLB)
- For plant fires, including those requiring evacuation of the control room
- AFW system can provide feedwater to a minimum of one steam generator per unit at sufficient flow and pressure to remove decay heat from the reactor coolant system Diverse Auxiliary Feedwater Design Basis 4
Auxiliary Feedwater System Design Basis
- Steam turbine-driven pump is capable of being supplied from either or both steam generators.
- For Station Blackout (SBO) event, only the turbine-driven pumps would be available for decay heat removal.
- System level Failure Modes and Effects Analysis for the AFW System has been performed.
Turbine Driven AFW Pumps Available for Decay Heat Removal During Station Blackout Event (SBO) 5
Auxiliary Feedwater Cross-tie
- MDAFW pump discharge piping for each unit can be cross-tied (in CLB)
- TDAFW suction is crosstied to a common suction from the condensate storage tanks
- TDAFW pump steam supply, exhaust, and water discharges are cross-tied
- TDAFW cross-tie has been implemented as part of Fukushima FLEX strategies for use in beyond design basis events AFW Pumps Can Feed Steam Generators on Opposite Unit 6
7 Beyond Design Basis Events
- TDAFW Pump Steam Supply and Discharge Cross-tie installed to meet NRC Order EA-12-049 for implementation of strategies for mitigating Beyond Design Basis Events
- Improves system redundancy and the capability to handle multiple failures
- Manual action required to align the TDAFW pump discharge and steam supply cross connects. Included in FLEX Support Guidelines (FSGs)
Turbine Driven AFW Pump Cross-tie Added for Implementation Strategies to Mitigate Fukushima Beyond Design Basis Events 8
Licensing Basis
- The Motor Driven AFW pump system includes a cross connect pipe between the units. Technical Specification 3.7.5 credits the availability of the MDAFW pump cross-tie capability
- Proposed License Amendment Request
- The TDAFW pump unit cross-tie is credited for the Fire PRA.
- Table S-2, Committed Modifications in NFPA 805 Application (MOD-2),
Cross tie TDAFW pump steam supplies and pump discharge(s) to allow opposite unit support Risk is reduced by having the cross-tie capability available to maintain Decay Heat Removal
- Cross-tie requires prior NRC approval Motor Driven AFW Cross-tie in CLB. Turbine Driven AFW Cross-tie to be added to CLB via License Amendment Request 9
Conclusions
- The Point Beach Nuclear Plant CLB contains a provision for cross-connecting a MDAFW pump to supply feedwater to both units
- The proposed licensing action would allow for cross-connecting a TDAFW pump to supply feedwater to both units like the MDAFW pump
- A single TDAFW pump is capable of supplying adequate AFW flow to remove the decay heat on two units via a single steam generator on each unit
- NRC approval is required for use of the TDAFW pump cross-tie prior to use 10
Path Forward
- A license amendment request (LAR) will be submitted requesting NRC approval to manually cross-tie the TDAFW steam supply and discharge during abnormal events
- An updated failure modes and effects analysis (FMEA) will be conducted to ensure that the condition associated with the affected unit will not propagate to the unaffected unit when the units are cross-tied
- Required Actions and Completion Times for LCO 3.7.5 will be included in the LAR submittal as applicable Failure Modes & Effects Analysis will be updated and Technical Specifications revised as applicable to reflect TDAFW cross-tie 11
Questions 12