Letter Sequence Other |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
Results
Other: ML070510476, ML073230158, ML073230169, ML073510242, ML081000213, ML082050406, ML082050433, ML082070154, ML083010366, ML083570153, ML091130122, ML092330075, NL-08-119, Proprietary Review of Audit Report for the Corrective Actions Associated with Generic Letter 2004-02, 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 Reactors
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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 ML0726808352007-09-17017 September 2007 Request for Extension of Completion Date for Corrective Actions and Modifications Required by GL-2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request ML0730402912007-10-24024 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 ML0732301692007-11-20020 November 2007 Approval of Extension Request for Corrective Actions Required by Generic Letter 2004-02 Project stage: Other ML0732301582007-11-20020 November 2007 Unit No.3 - Denial 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 ML0733800442007-12-0303 December 2007 LB Order (Censure of Sherwood Martinelli) Project stage: Request ML0734600422007-12-0303 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 ML0802900972008-01-31031 January 2008 Draft Open Items from Staff Audit of Corrective Actions to Address Generic Letter 2004 02 Project stage: Draft Other ML0806701352008-02-28028 February 2008 Supplemental Response to GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request ML0808801782008-03-27027 March 2008 Summary of February 28, 2008, 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-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 ML0809900852008-03-28028 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 ML0810002132008-04-10010 April 2008 Approval of Revised Extension Request for Corrective Actions Required by Generic Letter 2004-02 Project stage: Other ML0818200362008-07-10010 July 2008 Draft Audit Report for the Corrective Actions Associated with Generic Letter 2004-02 Project stage: Draft Other 05000003/LER-2008-001, Attempted Introduction of Contraband Into the Plant Protected Area Due to Personnel Error2008-07-21021 July 2008 Attempted Introduction of Contraband Into the Plant Protected Area Due to Personnel Error Project stage: Request ML0820701542008-07-21021 July 2008 Proprietary Review of Audit Report for the Corrective Actions Associated with Generic Letter 2004-02 Project stage: Other 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 ML0820504062008-07-29029 July 2008 Report on Results of Staff Audit of Corrective Actions Address Generic Letter 2004-02 Project stage: Other ML0820504332008-07-29029 July 2008 Audit Report-Indian Point Nuclear Generating Unit Nos. 2 and 3 - Report on Result of Staff Audit of Corrective Actions to Address Generic Letter 2004-02 Project stage: Other ML0825505742008-09-17017 September 2008 Summary of Telephone Conference Call Held on August 7, 2008, Between the U.S. Nuclear Regulatory Commission and Entergy Nuclear Operations, Inc., Pertaining to the Indian Point Nuclear Generating Unit Nos. 2 and 3 (IP2 and IP3), License Project stage: Request ML0825902152008-09-17017 September 2008 Request for Additional Information Regarding Responses to Generic Letter 2004 - 02 Project stage: RAI ML0829105722008-10-17017 October 2008 Lr Hearing - Draft Telecon Summary of September 15, 2008 Re Reactor Vessel Neutron Embrittlement Project stage: Request ML0830102392008-10-17017 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-08-153, 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 ML0830103662008-10-30030 October 2008 Approval of Revised Extension Request for Corrective Actions Required by Generic Letter 2004-02 Project stage: Other ML0832300542008-11-19019 November 2008 Request for Additional Information Regarding Generic Letter 2004-02 Project stage: RAI ML0835701532008-12-0101 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-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 ML0911301222009-04-28028 April 2009 Telcom with Entergy on April 16, 2009, on Chemical Effects Testing for Generic Letter 2004-02 Project stage: Other ML0921903102009-07-29029 July 2009 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-Wat Project stage: Request ML0923300752009-08-25025 August 2009 Approval of Revised Extension Request for Corrective Actions Required by Generic Letter 2004-02 Project stage: Other 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 ML0932903162009-11-19019 November 2009 Updated Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request ML1011702372010-04-29029 April 2010 Request for Additional Information Regarding Generic Letter 2004-02 Project stage: RAI ML1016501692010-06-18018 June 2010 June 9, 2010 Summary of Conference Call with Entergy on Proposed Response to Request for Additional Information on Generic Letter 2004-02 Project stage: RAI 2008-03-27
[Table View] |
Text
1 ENERCON IPEC GSI-191 STATUS AND STRATEGY Presentation to the NRC February 9, 2007
2 ENERCON AGENDA
- Design Basis and Pool Turnover
- Alternate Break Methodology
3 ENERCON GSI-191 Project Team
- Project Management, Engineering, Licensing, Nuclear Engineering Analysis, Construction Services
- Enercon
- Alion
- Transco
- Westinghouse
4 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
5 ENERCON Plan View of lower containment IR SUMP VC SUMP
6 ENERCON Simplified ECCS Configuration IR PUMP IR PUMP IR SUMP VC SUMP RHR PUMP RHR PUMP Valve M
7 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
8 ENERCON Top Hat Strainer Module
9 ENERCON Debris Bypass Eliminator
10 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
11 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
12 ENERCON IP2 IR Sump Strainer
13 ENERCON IP2 IR Sump Strainer
14 ENERCON IP2 VC Sump Strainer
15 ENERCON IP2 VC Sump Strainer
16 ENERCON IP2 GSI-191 Modifications (Contd)
Installation of Flow Channeling Modifications
17 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
18 ENERCON Flow Channeling Concept
19 ENERCON Flow Channeling Concept IP2 North Incore Tunnel Exit Flow Barrier
20 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
21 ENERCON IP3 IR Sump Strainer IP2 and IP3 IR Sump Strainers are Virtually Identical
22 ENERCON IP3 VC Sump Strainer
23 ENERCON OVERALL METHODOLOGY
- Debris Identification
- Debris Generation
- Debris Transport
- Downstream Effects
- Testing
24 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
25 ENERCON Debris Generation
26 ENERCON Debris Transport Vectors showing pool flow direction on the floor
27 ENERCON Debris Transport Vectors of pool flow direction in the Incore Tunnel
28 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
29 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
30 ENERCON Testing
- Dissolution / Erosion Measurement of Cal-Sil
- Array Head Loss for Debris
- Fiber Bypass testing of a prototypical module
- Bypass material characterization
31 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
32 ENERCON Current Design Basis No single active failure will disable the IR Sump IR PUMP IR PUMP IR SUMP VC SUMP RHR PUMP RHR PUMP Valve M
33 ENERCON Current Design Basis Only a passive failure will require the use of the VC Sump IR PUMP IR PUMP IR SUMP VC SUMP RHR PUMP RHR PUMP Valve M
34 ENERCON Current Design Basis The VC Sump is not in itself single active failure protected IR PUMP IR PUMP IR SUMP VC SUMP RHR PUMP RHR PUMP Valve M
35 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
36 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
37 ENERCON
38 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
39 ENERCON Chemical Effects
- TSP (IP2 only) and Cal-Sil
- Results in Calcium Phosphate formation
- Results in Sodium Aluminum Silicate formation
40 ENERCON
- 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.
Chemical Effects with Alternate Break Methodology
41 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
42 ENERCON Path Forward
- ZOI Refinements for Nukon, Temp Mat, Mineral Wool
- Coatings fail as chips
- Remove Kaowool (IP3)
- Extension Requests and License Amendments
43 ENERCON GL 2004-02 Extension Request
- 2R18 Spring 2008 Refueling Modifications
- Buffer replacement or batching
- None required (Pending Chemical Refinements)
44 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
45 ENERCON End of Presentation