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MONTHYEARML0603800992006-02-0909 February 2006 Request for Additional Information Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-Water Reactors (TAC MC4689 & MC4690) Project stage: RAI ML0705104762007-02-0909 February 2007 Licensee Slides 2-9-07 Project stage: Other ML0704701232007-02-26026 February 2007 Summary of February 9, 2007, Meeting with Entergy on the Response to Generic Letter 2004-02 for Indian Point Nuclear Generating Unit Nos. 2 and 3 Project stage: Meeting NL-07-098, Request for Extension of Completion Date for Indian Point Unit 3 Corrective Actions and Modifications Required by Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Press2007-10-24024 October 2007 Request for Extension of Completion Date for Indian Point Unit 3 Corrective Actions and Modifications Required by Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressu Project stage: Request ML0732301582007-11-20020 November 2007 Unit No.3 - Denial of Extension Request for Corrective Actions Required by Generic Letter 2004-02 Project stage: Other ML0732301692007-11-20020 November 2007 Approval of Extension Request for Corrective Actions Required by Generic Letter 2004-02 Project stage: Other NL-05-0133, Revised Request for Extension of Completion Date for Indian Point Unit 3 Corrective Actions & Modifications Required by Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents a2007-12-0303 December 2007 Revised Request for Extension of Completion Date for Indian Point Unit 3 Corrective Actions & Modifications Required by Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Project stage: Request ML0735102422007-12-20020 December 2007 Approval of Revised Extension Request for Corrective Actions Required by Generic Letter 2004-02 Project stage: Other NL-08-054, Request for Extension of Completion Dates for Indian Point, Units 2 & 3, Corrective Actions Required by Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Wat2008-03-28028 March 2008 Request for Extension of Completion Dates for Indian Point, Units 2 & 3, Corrective Actions Required by Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Wate Project stage: Request NL-08-119, Proprietary Review of Audit Report for the Corrective Actions Associated with Generic Letter 2004-022008-07-21021 July 2008 Proprietary Review of Audit Report for the Corrective Actions Associated with Generic Letter 2004-02 Project stage: Other NL-08-153, Request for Extension of Completion Dates for Indian Point Units 2 and 3 Corrective Actions Required by Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Wat2008-10-17017 October 2008 Request for Extension of Completion Dates for Indian Point Units 2 and 3 Corrective Actions Required by Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Wate Project stage: Request NL-08-171, Planned Replacement of Internal Recirculation Pump Bearings in Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2008-12-0101 December 2008 Planned Replacement of Internal Recirculation Pump Bearings in Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other NL-09-021, Response to Request for Additional Information Regarding Generic Letter 2004-022009-02-0202 February 2009 Response to Request for Additional Information Regarding Generic Letter 2004-02 Project stage: Response to RAI ML0926400612009-09-24024 September 2009 Summary of Conference Call with Entergy on Proposed Response to a Request for Additional Information on Generic Letter 2004-02 Project stage: RAI 2007-02-09
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MONTHYEARML24173A2132024-06-13013 June 2024 NRC Presentation; Indian Point Decommissioning Oversight Board, Dated June 13, 2024 ML23031A2532022-12-0707 December 2022 NRC Presentation at New York State Decommissioning Oversight Board on December 7, 2022 in Cortlandt, New York (Dockets 50-003, 247, 286) ML21217A1992021-08-18018 August 2021 Virtual Public Meeting Presentation Slides - Post Shutdown Decommissioning Activities Report, 08/15/2021 PSDAR Public Webinar Meeting ML21207A0262021-07-29029 July 2021 Public Meeting Presentation Slides - Post Shutdown Decommissioning Activities Report, 07/29/2021 PSDAR Public Meeting ML21214A1402021-07-29029 July 2021 Updated Indian Point Public Meeting Presentation Slides - Post Shutdown Decommissioning Activities Report, 07/29/2021 PSDAR Public Meeting ML21036A0382021-02-0808 February 2021 Pre-submittal Meeting Presentation (02/08/2021) Relief Request No. IP3-ISI-RR-16 ML20269A1722020-09-30030 September 2020 Presentation Material for 9/30/2020 Pre-Submittal Meeting Request for One-Time Exemption from 10 CFR 50, Appendix E Biennial Emergency Preparedness Evaluated Onsite Exercise Requirements ML20269A3452020-09-28028 September 2020 Pre-submittal Meeting for Request for One-Time Exemption from 10 CFR Part 50, Appendix E, Biennial EP Exercise (Offsite) Due to COVID-19- Entergy Presentation Slides ML20265A2842020-09-22022 September 2020 Annual Assessment Meeting - Webinar Presentation NL-20-008, Transmittal of Presentation Slides for Partially Closed Pre-Submittal Meeting to Discuss a Planned License Amendment Request to Replace the Fuel Handling Building Crane2020-01-0606 January 2020 Transmittal of Presentation Slides for Partially Closed Pre-Submittal Meeting to Discuss a Planned License Amendment Request to Replace the Fuel Handling Building Crane ML19289A0042019-10-17017 October 2019 Presentation Material for 10/17/19 Pre-Submittal Meeting Entergy to Holtec Proposed License Transfer Application ML19269B6832019-10-0202 October 2019 NEIMA Section 108 Public Meeting Slides - Indian Point - October 2, 2019 ML19198A2392019-07-17017 July 2019 Annual Assessment Meeting for Indian Point Energy Center - Meeting Summary ML18107A3342018-04-10010 April 2018 Tech Spec 3.3.5.2a Change Pre-Submittal Meeting Presentation Slides ML18075A1232018-03-20020 March 2018 Entergy Nuclear Operations - March 20, 2018, Presentation Slides for Surveillance Frequency Control Program, UFSAR Change Considerations ML17200C9272017-07-0606 July 2017 07/26/2017 Entergy Presentation Slides for Public Meeting Regarding Spent Fuel Pool Management Project, New Criticality Analysis ML17171A1982017-06-20020 June 2017 Presentations by Members of the Public - Indian Point Annual Assessment Meeting ML17171A1922017-06-14014 June 2017 NRC Staff Presentation - Power Reactor Decommissioning Program ML17171A1872017-06-14014 June 2017 NRC Staff Presentation - Baffle-Former Bolt Inspections at Indian Point ML17160A1952017-06-12012 June 2017 Meeting Slides for Pre-Submittal Meeting with Entergy Regarding the Plan for Decommissioning Licensing Actions ML16182A1022016-06-30030 June 2016 6/8/2016 - Indian Point Units 2 & 3 Annual Assessment Meeting - Presentations from the Public ML16182A0672016-06-30030 June 2016 6/8/2016 - Indian Point Units 2 & 3 Annual Assessment Meeting - NRC Presentation Slides ML16166A2812016-06-0606 June 2016 Media Briefing Slides June 6, 2016 IR 05000247/20130112014-04-29029 April 2014 IR 05000247-13-011 & 05000286-13-011, and Notice of Violation, Indian Point Energy Center Units 2 & 3, and Office of Investigations Report No. 1-2012-036 ML12361A1552012-12-26026 December 2012 Summary of Entergy Drop-In on December 19, 2012 ML12130A1312012-05-0909 May 2012 Annual Assessment Posterboard Slides 2012 ML1116801732011-06-17017 June 2011 Annual Assessment Meeting - Written Statements from the Public ML1116721212011-06-16016 June 2011 Annual Assessment Meeting Slides ML1112502382011-05-0909 May 2011 Summary of Category 1 Public Meeting with Entergy on the Transfer of Spent Fuel from Unit 3 to Unit 2 at Indian Point Nuclear Generating Unit Nos. 2 and 3 (TAC Nos. ME1671, ME1672, and L24299) ML1011303462010-04-22022 April 2010 Annual Assessment Meeting Slides - Entergy Presentation ML1011303362010-04-22022 April 2010 Annual Assessment Meeting - NRC Slides ML0926400612009-09-24024 September 2009 Summary of Conference Call with Entergy on Proposed Response to a Request for Additional Information on Generic Letter 2004-02 ML0926401682009-08-28028 August 2009 Diffusion Models ML0913906312009-06-0404 June 2009 ACRS Meeting with the U.S. Nuclear Regulatory Commission, - June 4, 2009, Slides ML0914700162009-05-26026 May 2009 NRC Slides for Indian Point Units 2 & 3, Annual Assessment Meeting ML0914700132009-05-26026 May 2009 Meeting Slides, Plant Performance Review Indian Point Energy Center, Entergy NRC Annual Assessment Meeting ML0913804362009-04-15015 April 2009 Meeting Slides, Teleperm Xs Permissions and Operating Modes ML11083A0542009-03-0606 March 2009 Lr Hearing - Slides from ACRS Subcommittee Meeting on March 4, 2009 ML11083A0252009-03-0303 March 2009 Lr Hearing - Latest Slides ML11077A0332009-02-24024 February 2009 Lr Hearing - Draft Slides ML0823107362008-08-0808 August 2008 IPEC ANS Public Meeting - Entergy Slides ML0823107202008-08-0808 August 2008 IP ANS Public Meeting - August 8, 2008; NRC Slides ML0819303272008-07-11011 July 2008 NRC Annual Performance Assessment of Indian Point, Units 2 & 3, Reactor Oversight Program, Meeting Slides ML0819605452008-07-0202 July 2008 Entergy End of Cycle Plant Performance Review Slides, 7/2/08 ML0818404872008-07-0202 July 2008 NRC/DRS/EB1 Slides for Indian Point License Renewal Exit Meeting, June 18, 2008 ML0904102282008-07-0101 July 2008 2 SBO DG PM003.png; Develop Annual PM for Sbo/App R DG Swgr/Sfmrs Space Heaters ML0821305302008-06-18018 June 2008 License Renewal, Slides ML0904102082008-06-0505 June 2008 2 SBO DG PM001.png; Develop PM for Sbo/App R DG Battery ML0905401612008-05-31031 May 2008 NRC Slides for Public Meeting, Assessment: Indian Point Contaminated Groundwater ML0905401622008-05-31031 May 2008 NRC Government to Government Meeting Slides - NRC Assessment: Indian Point Contaminated Groundwater 2024-06-13
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Text
IPEC GSI-191 STATUS AND STRATEGY Presentation to the NRC February 9, 2007 1
ENERCON
AGENDA
- Design Basis and Pool Turnover
- Alternate Break Methodology
- License Amendments ENERCON
GSI-191 Project Team
- Project Management, Engineering, Licensing, Nuclear Engineering Analysis, Construction Services
- Enercon
- Alion
- Transco
- Westinghouse 3
ENERCON
IP2/IP3 Sump Layout
- Two Independent and Redundant Sumps
- Internal Recirculation (IR) Sump - primary means of recirculation
- Vapor Containment (VC) Sump - backup to IR sump in case of loss of flow path
- IR Sump served by two IR pumps
- VC Sump served by two RHR pumps 4
ENERCON
Plan View of lower containment IR SUMP VC SUMP 5
ENERCON
Simplified ECCS Configuration RHR RHR PUMP PUMP IR IR PUMP PUMP M Valve IR SUMP VC SUMP 6
ENERCON
Sump Strainer Design
- Double Top Hat Strainer Module with Bypass Eliminator
- Perforated plate with 3/32 diameter hole
- Fiber Bypass expected to be less than 1 ft3 7
ENERCON
Top Hat Strainer Module 8
ENERCON
Debris Bypass Eliminator 9
ENERCON
Debris Bypass Eliminator Since most of the fiber is captured near the surface of the wire mesh material, very little fiber is observed at the ends of the mesh material exiting the strainer Top Hat modules 10 ENERCON
IP2 GSI-191 Modifications
- 2R17 Spring 2006 Refueling Outage
- Installation of Sump Strainers
- ~3200 ft2 Installed in IR Sump (original 48 ft2)
- ~440 ft2 Installed in VC Sump (original 14 ft2)
- Maximized surface area in sumps 11 ENERCON
IP2 IR Sump Strainer 12 ENERCON
IP2 IR Sump Strainer 13 ENERCON
IP2 VC Sump Strainer 14 ENERCON
IP2 VC Sump Strainer 15 ENERCON
IP2 GSI-191 Modifications (Contd)
Installation of Flow Channeling Modifications
- Gates and barriers 16 ENERCON
Flow Channeling Concept Debris Transport is Reduced by Flow Channeling Concept
- Step 1: Water inside the crane wall flows to the Reactor Cavity
- Step 2: Water travels through the Incore Instrumentation Tunnel where a majority of the debris settles
- Step 3: Relatively clean water travels to the sumps 17 ENERCON
Flow Channeling Concept 18 ENERCON
Flow Channeling Concept IP2 North Incore Tunnel Exit Flow Barrier 19 ENERCON
IP3 GSI-191 Planned Modifications
- 3R14 Spring 2007 Refueling Outage
- Installation of Sump Strainers
- ~3200 ft2 Installed in IR Sump (original 48 ft2)
- ~1000 ft2 Installed in VC Sump (original 32 ft2)
- Maximized surface area in sumps
- Installation of Flow Channeling Modifications
- Screens on penetrations ENERCON
IP3 IR Sump Strainer IP2 and IP3 IR Sump Strainers are Virtually Identical 21 ENERCON
IP3 VC Sump Strainer 22 ENERCON
OVERALL METHODOLOGY
- Debris Identification
- Debris Generation
- Debris Transport
- Downstream Effects
- Testing 23 ENERCON
Debris Identification
- Calsil/Asbestos, Temp-Mat, Nukon, Transco blanket, RMI, Mineral Wool, Kaowool
- Epoxy, Inorganic zinc, Enamel, High temperature aluminum, Phenoline
- Tape & Equipment labels, Tie wraps, Fiber board tags, Dirt & Dust, Latent Fiber 24 ENERCON
Debris Generation 25 ENERCON
Debris Transport Vectors showing pool flow direction on the floor 26 ENERCON
Debris Transport Vectors of pool flow direction in the Incore Tunnel 27 ENERCON
Debris Transport Determination
- The turbulence and vertical velocity are compared to the turbulent kinetic energy (TKE) and velocity metrics to suspend each kind of debris
- 3-D CFD plots show the turbulence and z velocities
- If TKE or vertical velocities not high enough - the debris would settle in tunnel
- Results show that most debris settles in the tunnel 28 ENERCON
Downstream Effects
- Blockage of small flow paths
- Seizure of rotating components
- Wear and abrasion of surfaces
- Evaluation of Reactor Vessel and Fuel
- Reactor vessel flow paths
- Nuclear fuel
- No Downstream Effects Concerns Identified to Date 29 ENERCON
Testing
- Dissolution / Erosion Measurement of Cal-Sil
- Array Head Loss for Debris
- Fiber Bypass testing of a prototypical module
- Bypass material characterization 30 ENERCON
Current Design Basis
- Indian Points ECCS configuration is unique in that it has two independent and redundant sumps
- No single active failure will disable the IR Sump and only a passive failure will require the use of the VC Sump
- The VC Sump is not in itself single active failure protected, however, once a passive failure has occurred no more active failures would need to be considered 31 ENERCON
Current Design Basis No single active failure will disable the IR Sump RHR RHR PUMP PUMP IR IR PUMP PUMP M Valve IR SUMP VC SUMP 32 ENERCON
Current Design Basis Only a passive failure will require the use of the VC Sump RHR RHR PUMP PUMP IR IR PUMP PUMP M Valve IR SUMP VC SUMP 33 ENERCON
Current Design Basis The VC Sump is not in itself single active failure protected RHR RHR PUMP PUMP IR IR PUMP PUMP M Valve IR SUMP VC SUMP 34 ENERCON
Alternate Break
- The Alternate Break Methodology as accepted by the SER allows no single failure for breaks larger than 14 (Large Break, LBLOCA) but requires design basis rules for breaks smaller than 14 (Alternate Break, ABLOCA)
- This approach allows the VC Sump design to be limited to ABLOCA debris loads with credit for Pool Turnover 35 ENERCON
Pool Turnover Strategy
- At start of recirculation the IR Sump will be in operation. VC Sump will be in stand-by
- A passive failure of the IR Sump is postulated to occur no earlier than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the start of recirculation
- Greater than 95% of the transportable debris would be collected at the IR Sump strainer
- The VC sump strainer would be essentially clean at this time and would provide necessary recirculation cooling 36 ENERCON
37 ENERCON
Alternate Break Methodology IP2/3 (Without Chemical Effects)
- LBLOCA (no single failure required to be assumed)
- IR Sump can handle LBLOCA debris load (including a single active failure)
- VC Sump can handle LBLOCA debris load after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of IR Sump recirculation
- ABLOCA (single failure required to be assumed)
- IR Sump can handle ABLOCA debris load including a single active failure
- VC Sump can handle ABLOCA debris load following 24 hrs of IR Sump recirculation assuming a passive failure of IR system 38 ENERCON
Chemical Effects
- TSP (IP2 only) and Cal-Sil
- Results in Calcium Phosphate formation
- Results in Sodium Aluminum Silicate formation 39 ENERCON
Chemical Effects with Alternate Break Methodology
- LBLOCA (no single failure required to be assumed)
- IR sump will handle debris + chemical loads for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (including a single active failure)
- VC sump will handle residual debris + chemical loads following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of IR Sump recirculation
- ABLOCA (single failure required to be assumed)
- IR Sump will handle debris + chemical loads for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> including a single active failure
- VC sump will handle residual debris + chemical loads following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of IR sump operation with a postulated passive failure of IR system.
- If IR sump cannot survive long term with debris + chemical loads, then VC sump must be utilized. 40 ENERCON
Chemical Effects Options
- Reduce debris amounts such that chemical precipitants may pass through the strainer
- Reduce precipitate formation by PWROG WCAP model refinement
- Reduce Aluminum quantity exposed to spray
- Autoclave Testing to determine precipitate formation as function of time
- Replace buffer
- Batch buffer 41 ENERCON
Path Forward
- ZOI Refinements for Nukon, Temp Mat, Mineral Wool
- Coatings fail as chips
- Remove Kaowool (IP3)
- Extension Requests and License Amendments 42 ENERCON
GL 2004-02 Extension Request
- 2R18 Spring 2008 Refueling Modifications
- Buffer replacement or batching
- Screens on crane wall penetrations
- None required (Pending Chemical Refinements) 43 ENERCON
License Amendments
- Buffer replacement/batching
- Alternate Break
- 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> delay time for passive failure
- Buffer replacement/batching
- Alternate Break
- 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> delay time for passive failure
- RWST switchover level TS change 44 ENERCON
End of Presentation 45 ENERCON