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| | document type = Meeting Summary, Meeting Briefing Package/Handouts, Slides and Viewgraphs | | | document type = Meeting Summary, Meeting Briefing Package/Handouts, Slides and Viewgraphs |
| | page count = 3 | | | page count = 3 |
| | project = TAC:ME1672, TAC:ME1671 | | | project = TAC:ME1671, TAC:ME1672 |
| | stage = Meeting | | | stage = Meeting |
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| =Text= | | =Text= |
| {{#Wiki_filter:}} | | {{#Wiki_filter:REGlI( UNITED "t;'01l NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 o iI: .fJ 't" May 9, 2011 ****.,. |
| | Entergy Nuclear Operations, Inc. |
| | Indian Point Nuclear Generating Unit Nos. 2 and 3 |
| | |
| | ==SUMMARY== |
| | OF APRIL 28, 2011, 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) On April 28, 2011, a Category 1 public meeting was held between the Nuclear Regulatory Commission (NRC) and representatives of Entergy Nuclear Operations, Inc. (the licensee) and Holtec International, Inc., one of the licensee's contractors, at the NRC's Executive Boulevard Building, 6003 Executive Boulevard, Rockville, Maryland. |
| | The purpose of the meeting was to discuss progress on the project and the NRC staffs request for additional information (RAI) dated March 16, 2011, which is publicly available in the NRC's Agencywide Documents Access and Management System (ADAMS) under Accession No. ML 110690446. |
| | The NRC's RAlletter was in response to Entergy's license amendment requests to authorize the transfer of spent fuel from the spent fuel pool at Indian Point Nuclear Generating Unit NO.3 (IP3) to the spent fuel pool at Indian Point Nuclear Generating Unit No.2 (IP2) using a newly designed shielded transfer canister (STC) and an external shield cask (the HI-TRAC). From there, Entergy intends to transfer the spent fuel to the independent spent fuel storage installation which already exists at the site. The licensee presented information on the scope of the project and methods they would use to respond to the RAI questions. |
| | Areas of discussion included the following: |
| | : 1) which section of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code would govern the design and fabrication of the STC; 2) which analysis methods and codes could be used for the criticality analyses; |
| | : 3) what are the expected doses to plant workers from handling the STC, and how can these doses be minimized; and 4) what methods can be used to prevent or detect the loading of fuel assemblies into the STC that do not meet the design requirements of the STC. A list of attendees is provided as Enclosure 1, but may not be all inclusive. |
| | The licensee's slide presentation is provided as Enclosure |
| | : 2. |
| | -2 No Public Meeting Feedback forms have been received. |
| | Please direct any inquiries to me at 301-415-2901, or by email to John.Boska@nrc.gov. J hn P. Boska, Senior Project Manager lant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-247 and 50-286 |
| | |
| | ==Enclosures:== |
| | : 1. List of Attendees |
| | : 2. Licensee Slides cc w/encls: Distribution via Listserv UNITED NUCLEAR REGULATORY MEETING ATTENDANCE FORM |
| | |
| | ==Subject:== |
| | Indian Point Fuel Transfer Amendments Date: April 28, 2011 Location: |
| | Executive Boulevard Building Room 1-B13 PLEASE PRINT LEGIBLY NAME ORGANIZATION Enclosure 1 |
| | UNITED STATES NUCLEAR REGULATORY COMMISSION MEETING ATTENDANCE FORM |
| | |
| | ==Subject:== |
| | Indian Point Fuel Transfer Amendments Date: April 28, 2011 Location: |
| | Executive Boulevard Building Room 1-B13 PLEASE PRINT LEGIBLY I ORGANIZATION NAME I M tlttl& !fa f+t i AJRR/IrSA C;+C:v*..- |
| | 1Ji22 /iJss )s.a?R IIJAI2 /]);//1 / AltlJJ:1 Le+a-lPr()Wh .-,-.k.' L, \l 014. (;/ AII'( '<:t:tUrS , Alfl 12/p 5S/Sf2Kt? |
| | Z/i/vn1 1-, |
| | / S"r>>I ,.., 1<.6/ tJl'-f.Sl |
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| | C Q) C()1i> o 0) 0) m T"""os..... s..... .C Q) I-N '+-Q)C_ex>.-W Q) N s..... CO C u:: "a. () *0 << |
| | Zcc.. men""OC") N <1> ::l C/) o u c w I ntrod uctions |
| | * Nuclear Regulatory Commission |
| | * Entergy -Indian Point Energy -Oscar Limpias (V.P. |
| | -John McCann (V.P. Nuclear Safety & |
| | -.Tom Orlando (Director of |
| | -Pat Conroy (Director Nuclear Safety |
| | -Ed Weinkam (Senior Manager |
| | -Bob Walpole (Manager |
| | -Tom McCaffrey (Manager Design |
| | -Joe De Francesco (Project |
| | -Richard Drake (Supervisor Design |
| | -Floyd Gumble (Supervisor Reactor |
| | -Roger Waters |
| | -John Skonieczny (Project |
| | -Dave Smith (Certified Health Project Transfer Spent Nuclear Fuel from IPEC Unit 3 Spent Fuel Pool to the Independent Spent Fuel Storage Installation (ISFSI) Restore Full Core Offload Capability for IP3 Reduce Spent Fuel Pool Inventory for IP3 Meeting Objectives Ensure a common understanding between Entergy and NRC of: |
| | * Fuel Transfer Operations |
| | * Licensing Approach |
| | * Schedule Need for Project Project Description Overview of Spent Fuel Transfer Project Fuel Transfer Operation |
| | * Transfer Schedule Licensing Summary -Submittals |
| | -Request For Additional Information (RAI's) Path Forward Closing and Q&A Project Qbtain License Amendment approvals Perform Site modifications Fabricate equipment to support the transfer of spent fuel from the Unit 3 Spent Fuel Pool to the Unit 2 Spent Fuel Pool Transfer Unit 3 Spent Fuel from Unit 2 to the ISFSI Fuel Transfer Operation Position HI-TRAC containing empty STC in Unit 3 Fuel Storage Building (FSB) Move Shielded Transfer canister (STC) into Unit 3 spent fuel pool Fuel loading, lid installation Remove STC from pool and place in Transfer Cask (HI-TRAC) Install STC lid bolting Perform leak testing of STC lid to shell area Perform STC Pressure Rise Test Perform leak testing of STC lid Vent & Drain ports Install H 1-TRAC solid Top Lid Perform pressure test of HI-TRAC sealing surfaces Using Air Pads, Move Hi-TRAC outside Unit 3 FSB . HI-TRAC moved with Vertical Cask Transporter (VCT) Move HI-TRAC/STC into Unit 2 FSB with existing Low Profile Transporter (LPT) Remove HI-TRAC Top Lid Using Unit 2 Gantry Crane lift STC and place in spent fuel pool cask handling area Remove STC Lid and move fuel to Unit 2 racks Dry cask and transfer Unit 3 fuel from Unit 2 to the ISFSI Fuel Transfer A HI-TRAC CONTAINING AN EMPTY SHIELDED TRANSFER CANISTER IS POSITIONED IN THE IP-3 CASK RECEIVING BAY HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL |
| | /// /' Fuel Transfer Sequence THE HI-TRAC TOP LID IS REMOVED AND THE SHIELDED TRANSFER CANISTER LID NUTS ARE REMOVED HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL Fuel Transfer Sequence THE SHIELDED TRANSFER CANISTER IS REMOVED FROM HI-TRAC HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL |
| | ......-.... C '-" Q) U Q) ::J Q) (f) s... C CO s... -Q) ::J LL Z 1-1 0 W Z 0 1-11-1 V)0 D. V) 1-10 a:: 1-1 W .... tiw 1-1::1: w3: "'" V)o Zo :!D. 1-.... OW w=>> 0"'" .... wZ .... W ::I:D.V) V) ww ::1:::1: << 2 UJ 0 UJ l-I 2 0 u << z: 0 z: ex: UJ I-z: ...... u 0 I Fuel Transfer Sequence THE SHIELDED TRANSFER CANISTER IS LOWERED INTO THE CASK LOADING AREA OF THE SPENT FUEL POOL HOl TEC INTERNATIONAL COPYRIGHTED MATERIAL Fuel Transfer Sequence THE SHIELDED TRANSFER CANISTER LID IS HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL Fuel Transfer Sequence SPENT FUEL ASSEMBLIES ARE LOADED INTO THE SHIELDED TRANSFER CANISTER HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL Fuel Transfer Sequence THE SHIELDED TRANSFER CANISTER IS FULLY LOADED WITH SPENT FUEL HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL Fuel Transfer Sequence THE SHIELDED TRANSFER CANISTER LID IS INSTALLED UNDERWATER HOl TEC INTERNATIONAL COPYRIGHTED MATERIAL Fuel Transfer Sequence THE SHIELDED TRANSFER CANISTER IS RAISED TO THE TOP OF THE SPENT FUEL POOL HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL Fuel Transfer Sequence THE SHIELDED TRANSFER CANISTER IS REMOVED FROM THE SPENT FUEL POOL AND PLACED DIRECTLY IN HI-TRAC HOl TEC INTERNATIONAL COPYRIGHTED MATERIAL Fuel Transfer Sequence THE SHIELDED TRANSFER CANISTER IS FULLY SEATED IN HI-TRAC, THE LID NUTS ARE TIGHTENED AND TESTING PERORMED PRIOR TO TRANSFER TO UNIT 2 HOl TEC INTERNATIONAL COPYRIGHTED MATERIAL Fuel Transfer Sequence ,/ /y /' THE HI-TRAC TOP LID IS INSTALLED, THE BOLTS ARE TIGHTENED AND HI-TRAC INTEGRITY TESTING PERFOMED PRIOR TO TRANSFER TO UNIT 2 HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL Fuel Transfer Sequence HI-TRAC IS MOVED FROM THE IP-3 FSB TRUCK BAY AREA TO THE AWAITING VERTICAL CASK TRANSPORTER HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL Fuel Transfer Sequence THE VERTICAL CASK TRANSPORTER LIFTS THE FROM THE AIR-PADS AND MOVES IT TO HOl TEC INTERNATIONAL COPYRIGHTED MATERIAL Project |
| | -Relocate Protected Area (PA) Fence to support fuel transfer inside PA at all times. -COMPLETED February 2011. -40 ton Crane Upgrade to single-failure-proof COMPLETED December 2010 -Facility and Transport Path Modifications 60% COMPLETE -Spent Fuel Transfer -To include the following: |
| | * Training |
| | * Procedures |
| | * Dry Runs 2012 2013 2014 Training Procedures Dry Runs Licensing |
| | * License Amendment Request (LAR) History -Public meetings/telecoms held: -March 6, 2009 -June 15, 2009 -June 11, 2010 -Submitted July 08, 2009, supplemented September 28, 2009 -1 st round RAls: -received April 20, 2010 -responses submitted October 5, 2010 -2 nd round -received March 16, -responses due May 15, Summary of Round 1 RAI -100 total Operating General Principal Design Criteria ProcedureslTS Inform ation (4) (9) (4)Materials Evaluation (11) --Criticality (33) Shielding Design (19) Structural Thermal Evaluation (7) Hydraulics (13) |
| | Summary of RAI's ROUND 1 Progress General Information Fully integrated response -revised licensing report Principal Design Criteria Criticality Tip-over analysis performed, FMEA, tornado missile NRC approved Part 71 methodology adopted for STC Thermal Hydraulics Operational changes to address detection of fuel misload -STC steam void, STC pressure rise LCO and SR I I I Structural Provided justifications and clarifications Shielding Design and ALARA Isolation zone adjacent to HI-TRAC haul path, Non Fuel Hardware analyzed I Materials Evaluation, etc STC use of ASME Code III NO I Operating ProcedureslTech. |
| | Specs NRC Control of CoC type information via Appendix C to the Technical Specifications. |
| | Captures both accident based and non accident based specifications Summary of Round 2 RAI -73 total Thermal General Information (2) Principal Operating Design Criteria Procedures/TS (0) (21 ) Criticality (18) Materials Hydraulics (10) Evaluation (4) Shielding Structural Design (17) Evaluation (1) |
| | Summary of RAI's ROUND 2 Progress General Information Fully integrated response -revised licensing report Principal Design Criteria -Criticality Justifications and clarifications provided for model assumptions and benchmarking Thermal Hydraulics Justification of thermal model and properties Severe thermal misload analyzed Structural Further justification of tipover analysis Shielding Design and ALARA Estimated doses reduced/ Model justifications I Credit for a "Leak Tight" confinement boundary Requested analyses performed to address Neutron Source Assemblies, Cobalt, Tipover I STC lid design change to address streaming Materials Evaluation, etc STC qualifies as a "Leak Tight" confinement boundary /ASME I Code NC/ND reconciliation Operating ProcedureslTech. |
| | Specs New TS proposed to isolate public/haul path New TS proposed to limit dose rates Summary of RAI's ROUND 2 Resolution Challenges General Information Per Thermal Hydraulics and TS below Principal Design Criteria -Criticality Some of the proposed RAI responses require further technical resolution Thermal Hydraulics Predicted hourly STC pressure rise Validation of no air in the vapor space Structural |
| | -Shielding Design and ALARA -Materials Evaluation, etc STC ASME Code NO Operating Procedures/Tech. |
| | Specs TS based on hourly STC pressure rise Adoption of a surface contamination LCO Path Forward Entergy to develop and submit RAI responses by 5/15/11 Entergy to provide continued support for RAI review process Continued Entergy / NRC Interface is essential Closing In order to meet Entergy's goals of: Transferring Spent Nuclear Fuel from IPEC Unit 3 Spent Fuel Pool to the ISFSI Restoring Full Core Offload Capability Reducing Spent Fuel Pool inventory The following items need to be accomplished: Continued Entergy/NRC Technical Review Interactions to Ensure Resolution of All outstanding Issues Continued Entergy/NRC Management Engagement at all levels to monitor progress and facilitate resolution of |
| | ....,.... ... |
| | :,..." ** |
| | --I ' |
| | -2 No Public Meeting Feedback forms have been received. |
| | Please direct any inquiries to me at 301-415-2901, or by email toJohn.Boska@nrc.gov. |
| | Docket Nos. 50-247 and 50-286 |
| | |
| | ==Enclosures:== |
| | : 1. List of Attendees |
| | : 2. Licensee Slides cc w/encls: Distribution via Listserv DISTRIBUTION: |
| | PUBLIC RidsNrrlndianPoint RidsOGCRp RidsRgn1 MailCenter MRahimi, NMSS DPickett, NRR DWeaver, NMSS ZLi, NMSS SJones, NRR JDavis, NMSS MCall, NMSS MKhanna, NRR TNakanishi, NRR /RAJ John P. Boska, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation LPL 1-1 R/F RidsNrrDorlLpl1-1 RidsNrrLASLittle MGray, RI RidsAcrsAcnw&mMailCenter RidsNrrOd JGoshen, NMSS RParkhill, NMSS SBurnell, OPA GCasto, NRR JParillo, NRR MYoder, NRR MHamm,NRR MSampson, NMSS DHoang, NRR NDay, NMSS EBenner, NMSS DTang, NMSS RNelson, NRR KWood, NRR RTemps, NMSS GHornseth, NMSS DPstrak, NMSS LBrown, NRR JSolis, I\IMSS JBoska 5/4/11 NSalgado 5/9/11}} |
Letter Sequence Meeting |
|---|
|
|
MONTHYEARML0919401782009-07-0101 July 2009
Rev. 1 to Holtec Report HI-2094289, Licensing Report on the Inter-Unit Transfer of Spent Nuclear Fuel at the Indian Point Energy Center.
Project stage: Request
NL-09-076, Application for Unit 2 Operating License Condition Change and Units 2 and 3 Technical Specification Changes to Add Inter-Unit Spent Fuel Transfer Requirements2009-07-0808 July 2009
Application for Unit 2 Operating License Condition Change and Units 2 and 3 Technical Specification Changes to Add Inter-Unit Spent Fuel Transfer Requirements
Project stage: Request
NL-09-100, Response to Request for Supplemental Information Regarding the Spent Fuel Transfer License Amendment Request2009-09-28028 September 2009
Response to Request for Supplemental Information Regarding the Spent Fuel Transfer License Amendment Request
Project stage: Supplement
NL-09-141, Submittal of Response to Request for Supplemental Information Regarding the Spent Fuel Transfer License Amendment2009-10-26026 October 2009
Submittal of Response to Request for Supplemental Information Regarding the Spent Fuel Transfer License Amendment
Project stage: Supplement
ML0930206032009-11-12012 November 2009
Request for Withholding Information from Public Disclosure
Project stage: Withholding Request Acceptance
ML0920902892010-01-0404 January 2010
Individual Notice of Consideration of Issuance of Amendment to Facility Operating License and Opportunity for Hearing, and Order Imposing Procedures for Access to SUNSI
Project stage: Other
ML1030801132010-10-0101 October 2010
Enclosure 1 to NL-10-122, Holtec International Licensing Report HI-2094289, Rev. 3, Licensing Report for Transfer of IP-3 Fuel to IP-2
Project stage: Other
NL-10-093, Response to Request for Additional Information Re Inter-Unit Spent Fuel Transfer License Amendment Request2010-10-0505 October 2010
Response to Request for Additional Information Re Inter-Unit Spent Fuel Transfer License Amendment Request
Project stage: Response to RAI
NL-10-122, Response to Request for Additional Information Regarding the Inter-Unit Spent Fuel Transfer License Amendment Request - Submittal of Non Proprietary Holtec Report HI-20942892010-10-28028 October 2010
Response to Request for Additional Information Regarding the Inter-Unit Spent Fuel Transfer License Amendment Request - Submittal of Non Proprietary Holtec Report HI-2094289
Project stage: Response to RAI
ML1029805382010-11-16016 November 2010
ME1671, ME1672, & L24299 - Proprietary Information Determination Letter for Withholding Information from Public Disclosure RAI Responses Dated October 5, 2010
Project stage: RAI
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)
Project stage: Meeting
NL-11-052, Response to Request for Additional Information Regarding the Inter-Unit Spent Fuel Transfer License Amendment Request (TAC Nos. ME1671, ME1672, and L24299)2011-07-28028 July 2011
Response to Request for Additional Information Regarding the Inter-Unit Spent Fuel Transfer License Amendment Request (TAC Nos. ME1671, ME1672, and L24299)
Project stage: Response to RAI
ML11243A1742011-08-23023 August 2011
Response to Request for Additional Information Regarding the Inter-Unit Spent Fuel Transfer License Amendment Request - Submittal of Non Proprietary Holtec Reports
Project stage: Response to RAI
NL-11-100, Request for Additional Information Regarding Spent Fuel Transfer2011-08-23023 August 2011
Request for Additional Information Regarding Spent Fuel Transfer
Project stage: Request
ML11243A2202011-08-23023 August 2011
HI-2094289, Revision 4, Licensing Report on the Inter-Unit Transfer of Spent Nuclear Fuel at the Indian Point Energy Center, Enclosure 2 to NL-11-100
Project stage: Other
ML1126506412011-09-28028 September 2011
Request for Additional Information Regarding Amendment Application for Inter-Unit Spent Fuel Transfer (TAC Nos. mE1671, ME1672, and L24299)
Project stage: RAI
NL-11-118, Response to Request for Additional Information Regarding the Inter-Unit Spent Fuel Transfer License Amendment Request2011-10-28028 October 2011
Response to Request for Additional Information Regarding the Inter-Unit Spent Fuel Transfer License Amendment Request
Project stage: Response to RAI
ML11327A0462011-10-28028 October 2011
Attachment 1 to NL-11-118 - Response to Request for Additional Information (Non-Proprietary)
Project stage: Response to RAI
ML1127701542011-10-31031 October 2011
Request for Withholding Information from Public Disclosure (TAC ME1671, ME1672, and L24299)
Project stage: Withholding Request Acceptance
ML1131301962011-11-0909 November 2011
Request for Additional Information Regarding Amendment Application for Inter-Unit Spent Fuel Transfer (TAC Nos. ME1671, ME1672, and L24299)
Project stage: RAI
ML1130703802011-12-0505 December 2011
Request for Withholding Information from Public Disclosure (TAC Nos. ME1671, ME1672, and L24299)
Project stage: Withholding Request Acceptance
NL-11-130, Response to Request for Additional Information Regarding the Inter-Unit Spent Fuel Transfer License Amendment Request (TAC Nos. ME1671, ME1672, and L24299)2011-12-15015 December 2011
Response to Request for Additional Information Regarding the Inter-Unit Spent Fuel Transfer License Amendment Request (TAC Nos. ME1671, ME1672, and L24299)
Project stage: Response to RAI
ML12040A3092012-01-11011 January 2012
Response to Request for Additional Information Regarding Inter-Unit Spent Fuel Transfer License Amendment Request - Submittal of Non-Proprietary Holtec Report
Project stage: Response to RAI
NL-12-007, Response to Request for Additional Information Regarding the Inter-Unit Spent Fuel Transfer License Amendment Request (TAC Nos. ME1671, ME1672, and L24299)2012-03-0202 March 2012
Response to Request for Additional Information Regarding the Inter-Unit Spent Fuel Transfer License Amendment Request (TAC Nos. ME1671, ME1672, and L24299)
Project stage: Response to RAI
NL-12-0471, Supplemental Information Regarding the Inter-Unit Spent Fuel Transfer License Amendment Request (TAC Nos. ME1671, ME1672, and L24299)2012-04-23023 April 2012
Supplemental Information Regarding the Inter-Unit Spent Fuel Transfer License Amendment Request (TAC Nos. ME1671, ME1672, and L24299)
Project stage: Supplement
NL-12-064, Supplemental Information Regarding the Inter-Unit Spent Fuel Transfer, License Amendment Request - Submittal of Non Proprietary Holtec Report2012-05-0707 May 2012
Supplemental Information Regarding the Inter-Unit Spent Fuel Transfer, License Amendment Request - Submittal of Non Proprietary Holtec Report
Project stage: Supplement
ML12137A2012012-05-0707 May 2012
Licensing Report on the Inter-Unit Transfer of Spent Nuclear Fuel at the Indian Point Energy Center, Enclosure 1 to NL-12-064
Project stage: Request
NL-12-074, Draft Safety Evaluation for License Amendment Request Inter-Unit Spent Fuel Transfer (TAC Nos. ME1671, ME1672, and L24299)2012-05-21021 May 2012
Draft Safety Evaluation for License Amendment Request Inter-Unit Spent Fuel Transfer (TAC Nos. ME1671, ME1672, and L24299)
Project stage: Draft Request
ML12150A3832012-06-25025 June 2012
Request for Withholding Information from Public Disclosure (TAC Nos. ME1671, ME1672, and L24299)
Project stage: Withholding Request Acceptance
ML12153A1962012-06-25025 June 2012
Request for Withholding Information from Public Disclosure
Project stage: Withholding Request Acceptance
ML1207405502012-07-0505 July 2012
Environmental Assessment and Finding of No Significant Impact (TAC Nos. ME1671, ME1672, and L24299)
Project stage: Other
2011-11-09
[Table View] |
|
|---|
Category:Meeting Summary
MONTHYEARML22309A0062022-12-12012 December 2022
Public Non-Sensitive Meeting Summary on Clarification Call with Holtec Regarding Request for Additional Information for Indian Point Unit 2 Master Decommissioning Trust Agreement as Per Indian Point Nuclear Generating Facility Unit 1 and 2
ML21342A1402021-12-0909 December 2021
Summary of Public Meeting in Tarrytown, Ny, to Discuss Indian Point Units 1, 2, and 3 (IPEC) Post-shutdown Decommissioning Activities Report
ML21055A9122021-02-24024 February 2021
(E-mail Dated 2/24/2021) Summary of Feb 8, 2021, Pre-submittal Meeting for Relief Request No. IP3-ISI-RR-16, Code Case N-513-4 Periodic Inspection Frequency Extension
ML20321A0002020-11-17017 November 2020
Summary of 9/30/20 Pre-Submittal Meeting with Entergy to Discuss Proposed One-Time Exemption Request - Biennial Emergency Preparedness Onsite Evaluated Exercise Requirements
ML20289A7322020-10-15015 October 2020
2020 Annual Assessment Meeting for Indian Point - Meeting Summary
ML20083F5962020-03-23023 March 2020
Summary of Teleconference with the National Marine Fisheries Service for Indian Point Biological Opinion
ML20059P1292020-03-0303 March 2020
Summary of Partially Closed Pre-submittal Public Meeting with Entergy Nuclear Operations, Inc. to Discuss the Proposed License Amendment Request to Replace the Indian Point Unit No. 3 Crane with a New Holtec High-Lift Crane (EPID L:2019-LRM
ML19330F5182019-11-29029 November 2019
Summary of Public Meeting Between the NRC and Entergy Regarding Pre-Submittal of a License Transfer Application to Holtec International for Indian Point Energy Center
ML19319A0242019-10-0202 October 2019
NEIMA Meeting - Courtney Williams Comments
ML19319A0282019-10-0202 October 2019
NEIMA Meeting - Marilyn Elie Comments
ML19319A0272019-10-0202 October 2019
NEIMA Meeting - Linda Puglisi Comments
ML19319A0252019-10-0202 October 2019
NEIMA Meeting - Jenean Eichenholtz Comments
ML19198A2392019-07-17017 July 2019
Annual Assessment Meeting for Indian Point Energy Center - Meeting Summary
ML18200A2722018-07-19019 July 2018
Summary of Annual Assessment Meeting for Indian Point Energy Center
ML18131A0572018-05-11011 May 2018
Summary of 04/12/2018 Meeting with the State of New York Regarding the Indian Point Generating Unit No. 2 Reactor Pressure Vessel Head Penetration Alternative Weld Repair
ML18117A3162018-04-30030 April 2018
Summary of 04/03/2018 Meeting with Entergy on Planned Submittal of Propose Alternative for Reactor Pressure Vessel Head Nozzle Weld Repair
ML18107A4972018-04-27027 April 2018
April 10, 2017, Summary of Public Meeting with Entergy Nuclear Operations, Inc. Regarding Upcoming License Amendment Request to Add Setpoint Verification Requirement to Technical Specification Surveillance Requirements
ML18099A0712018-04-16016 April 2018
March 20, 2018, Summary of Meeting with the Nuclear Energy Institute and Other Industry Representatives Regarding the Surveillance Frequency Control Program
ML18002A2562018-01-30030 January 2018
11/30/2017 and 12/19/2017 Summary Telephone Conference Calls with Entergy Nuclear Operations, Inc., Concerning Request for Additional Information Pertaining to the Indian Point License Renewal Application
ML17256A2862017-09-25025 September 2017
Summary of Telephone Call on 09/06/17, Between NRC and Entergy Concerning Next Steps from the Site Audit on 08/1-3/17
ML17180A5032017-09-21021 September 2017
04/19/2017 Summary of Teleconference with Entergy Nuclear Operations, Inc., Concerning Request for Additional Information Pertaining to the Indian Point Unit Nos. 2 and 3 License Renewal Application
ML17237A2132017-08-25025 August 2017
Memo E-mail to File -Summary of July 26, 2017, Meeting with Entergy to Discuss Proposed License Amendment Request, New Criticality Safety Analysis
ML17173A7672017-07-28028 July 2017
Summary of 6/20/2017 Meeting with Entergy to Discuss Plan for Decommissioning Licensing Actions of Palisades, Pilgrim, Indian Point, Units 2 and 3, and Vermont Yankee
ML17160A1652017-06-27027 June 2017
Summary of Telephone Conference Call Held on May 31,2017, Between the NRC and Entergy Nuclear Operations Inc. Concerning Requests for Additional Information Pertaining to the Indian Point, License Renewal Application (TAC Nos. MD5407/MD5408
ML17172A1972017-06-20020 June 2017
Summary of Annual Assessment Meeting for Indian Point Units 2 and 3
ML17157B5422017-06-20020 June 2017
Conference Call on 2nd Round RAIs - Final
ML17082A3112017-04-11011 April 2017
Summary of Clarification Call with Entergy Regarding Follow-Up RAIs on ISG-2012-02
ML16281A2162016-10-25025 October 2016
10/04/2016,Summary of Public Meeting with Entergy Nuclear Operations, Inc. Regarding Proposed Changes to the Service Water Integrity Program for the Indian Point Nuclear Generating, Units 2 and 3 (IP2 and IP3) License Renewal Application (LRA)
ML16209A3712016-08-17017 August 2016
July 21, 2016, Summary of Conference Call Held Between NRC and Entergy Nuclear Operations, Inc. Concerning the Draft RAI for the Review of the Indian Point, Units 2 & 3, License Renewal Application, Set 2016-01 (TAC Nos. MD5407 & MD5408)
ML16188A0202016-07-0505 July 2016
Summary of Annual Assessment Meeting for Indian Point Units 2 and 3
ML16133A4992016-06-21021 June 2016
Summary of Telephone Conference Call Held Between NRC and Entergy Concerning the Indian Point LRA Safety Review
ML16035A4802016-02-12012 February 2016
Jsc Meeting Summary Attachment
ML15351A2032015-12-30030 December 2015
Summary of Conference Call Held on December 9, 2015, Between the NRC and Entergy Nuclear Operations, Inc. Concerning the Draft Audit Plan for the Service Water Integrity and Fire Water System Aging Management Programs
ML15190A2912015-07-22022 July 2015
070115, Summary of Telephone Conference Call Held Between NRC and Entergy Concerning the RAIs Pertaining to the Indian Point LRA Safety Review
ML15152A0762015-05-29029 May 2015
Summary of Annual Assessment Meeting for Indian Point Units 2 and 3 on 5/20/2015
ML15120A6442015-05-0606 May 2015
Summary of Telephone Conference Call Held Between NRC and Entergy Concerning the RAIs Pertaining to the Indian Point LRA Safety Review
ML15107A1752015-04-28028 April 2015
041615, Summary of Telephone Conference Call Held Between NRC and Entergy Concerning the RAIs Pertaining to the Indian Point LRA Environmental Review
ML15093A5052015-04-14014 April 2015
Summary of Telephone Conference Call Held Between NRC and Entergy Concerning the Indian Point LRA Environmental Review
ML15051A5022015-03-10010 March 2015
Summary of Telephone Conference Call Held Between NRC and Entergy Concerning the RAIs Pertaining to the Indian Point LRA Environmental Review
ML15022A1602015-02-11011 February 2015
and 01/13/15, Summary of Telephone Conference Call Held Between NRC and Entergy Concerning the RAIs Pertaining to the Indian Point LRA Environmental Review
ML14197A5832014-09-18018 September 2014
Summary of the June 19, 2014, Category 1 Public Meeting with Entergy to Discuss Seismic Hazard Reevaluations Associated with Implementation of Japan Lessons-Learned Near-Tear Task Force Recommendation 2.1
ML14260A4312014-09-17017 September 2014
Revised Summary of Annual Assessment Meeting for Indian Point Energy Center on 6/4/2014
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Category:Slides and Viewgraphs
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[Table view] |
Text
REGlI( UNITED "t;'01l NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 o iI: .fJ 't" May 9, 2011 ****.,.
Entergy Nuclear Operations, Inc.
Indian Point Nuclear Generating Unit Nos. 2 and 3
SUMMARY
OF APRIL 28, 2011, 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) On April 28, 2011, a Category 1 public meeting was held between the Nuclear Regulatory Commission (NRC) and representatives of Entergy Nuclear Operations, Inc. (the licensee) and Holtec International, Inc., one of the licensee's contractors, at the NRC's Executive Boulevard Building, 6003 Executive Boulevard, Rockville, Maryland.
The purpose of the meeting was to discuss progress on the project and the NRC staffs request for additional information (RAI) dated March 16, 2011, which is publicly available in the NRC's Agencywide Documents Access and Management System (ADAMS) under Accession No. ML 110690446.
The NRC's RAlletter was in response to Entergy's license amendment requests to authorize the transfer of spent fuel from the spent fuel pool at Indian Point Nuclear Generating Unit NO.3 (IP3) to the spent fuel pool at Indian Point Nuclear Generating Unit No.2 (IP2) using a newly designed shielded transfer canister (STC) and an external shield cask (the HI-TRAC). From there, Entergy intends to transfer the spent fuel to the independent spent fuel storage installation which already exists at the site. The licensee presented information on the scope of the project and methods they would use to respond to the RAI questions.
Areas of discussion included the following:
- 1) which section of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code would govern the design and fabrication of the STC; 2) which analysis methods and codes could be used for the criticality analyses;
- 3) what are the expected doses to plant workers from handling the STC, and how can these doses be minimized; and 4) what methods can be used to prevent or detect the loading of fuel assemblies into the STC that do not meet the design requirements of the STC. A list of attendees is provided as Enclosure 1, but may not be all inclusive.
The licensee's slide presentation is provided as Enclosure
- 2.
-2 No Public Meeting Feedback forms have been received.
Please direct any inquiries to me at 301-415-2901, or by email to John.Boska@nrc.gov. J hn P. Boska, Senior Project Manager lant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-247 and 50-286
Enclosures:
- 1. List of Attendees
- 2. Licensee Slides cc w/encls: Distribution via Listserv UNITED NUCLEAR REGULATORY MEETING ATTENDANCE FORM
Subject:
Indian Point Fuel Transfer Amendments Date: April 28, 2011 Location:
Executive Boulevard Building Room 1-B13 PLEASE PRINT LEGIBLY NAME ORGANIZATION Enclosure 1
UNITED STATES NUCLEAR REGULATORY COMMISSION MEETING ATTENDANCE FORM
Subject:
Indian Point Fuel Transfer Amendments Date: April 28, 2011 Location:
Executive Boulevard Building Room 1-B13 PLEASE PRINT LEGIBLY I ORGANIZATION NAME I M tlttl& !fa f+t i AJRR/IrSA C;+C:v*..-
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Zcc.. men""OC") N <1> ::l C/) o u c w I ntrod uctions
- Nuclear Regulatory Commission
- Entergy -Indian Point Energy -Oscar Limpias (V.P.
-John McCann (V.P. Nuclear Safety &
-.Tom Orlando (Director of
-Pat Conroy (Director Nuclear Safety
-Ed Weinkam (Senior Manager
-Bob Walpole (Manager
-Tom McCaffrey (Manager Design
-Joe De Francesco (Project
-Richard Drake (Supervisor Design
-Floyd Gumble (Supervisor Reactor
-Roger Waters
-John Skonieczny (Project
-Dave Smith (Certified Health Project Transfer Spent Nuclear Fuel from IPEC Unit 3 Spent Fuel Pool to the Independent Spent Fuel Storage Installation (ISFSI) Restore Full Core Offload Capability for IP3 Reduce Spent Fuel Pool Inventory for IP3 Meeting Objectives Ensure a common understanding between Entergy and NRC of:
- Schedule Need for Project Project Description Overview of Spent Fuel Transfer Project Fuel Transfer Operation
- Transfer Schedule Licensing Summary -Submittals
-Request For Additional Information (RAI's) Path Forward Closing and Q&A Project Qbtain License Amendment approvals Perform Site modifications Fabricate equipment to support the transfer of spent fuel from the Unit 3 Spent Fuel Pool to the Unit 2 Spent Fuel Pool Transfer Unit 3 Spent Fuel from Unit 2 to the ISFSI Fuel Transfer Operation Position HI-TRAC containing empty STC in Unit 3 Fuel Storage Building (FSB) Move Shielded Transfer canister (STC) into Unit 3 spent fuel pool Fuel loading, lid installation Remove STC from pool and place in Transfer Cask (HI-TRAC) Install STC lid bolting Perform leak testing of STC lid to shell area Perform STC Pressure Rise Test Perform leak testing of STC lid Vent & Drain ports Install H 1-TRAC solid Top Lid Perform pressure test of HI-TRAC sealing surfaces Using Air Pads, Move Hi-TRAC outside Unit 3 FSB . HI-TRAC moved with Vertical Cask Transporter (VCT) Move HI-TRAC/STC into Unit 2 FSB with existing Low Profile Transporter (LPT) Remove HI-TRAC Top Lid Using Unit 2 Gantry Crane lift STC and place in spent fuel pool cask handling area Remove STC Lid and move fuel to Unit 2 racks Dry cask and transfer Unit 3 fuel from Unit 2 to the ISFSI Fuel Transfer A HI-TRAC CONTAINING AN EMPTY SHIELDED TRANSFER CANISTER IS POSITIONED IN THE IP-3 CASK RECEIVING BAY HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL
/// /' Fuel Transfer Sequence THE HI-TRAC TOP LID IS REMOVED AND THE SHIELDED TRANSFER CANISTER LID NUTS ARE REMOVED HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL Fuel Transfer Sequence THE SHIELDED TRANSFER CANISTER IS REMOVED FROM HI-TRAC HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL
......-.... C '-" Q) U Q) ::J Q) (f) s... C CO s... -Q) ::J LL Z 1-1 0 W Z 0 1-11-1 V)0 D. V) 1-10 a:: 1-1 W .... tiw 1-1::1: w3: "'" V)o Zo :!D. 1-.... OW w=>> 0"'" .... wZ .... W ::I:D.V) V) ww ::1:::1: << 2 UJ 0 UJ l-I 2 0 u << z: 0 z: ex: UJ I-z: ...... u 0 I Fuel Transfer Sequence THE SHIELDED TRANSFER CANISTER IS LOWERED INTO THE CASK LOADING AREA OF THE SPENT FUEL POOL HOl TEC INTERNATIONAL COPYRIGHTED MATERIAL Fuel Transfer Sequence THE SHIELDED TRANSFER CANISTER LID IS HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL Fuel Transfer Sequence SPENT FUEL ASSEMBLIES ARE LOADED INTO THE SHIELDED TRANSFER CANISTER HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL Fuel Transfer Sequence THE SHIELDED TRANSFER CANISTER IS FULLY LOADED WITH SPENT FUEL HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL Fuel Transfer Sequence THE SHIELDED TRANSFER CANISTER LID IS INSTALLED UNDERWATER HOl TEC INTERNATIONAL COPYRIGHTED MATERIAL Fuel Transfer Sequence THE SHIELDED TRANSFER CANISTER IS RAISED TO THE TOP OF THE SPENT FUEL POOL HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL Fuel Transfer Sequence THE SHIELDED TRANSFER CANISTER IS REMOVED FROM THE SPENT FUEL POOL AND PLACED DIRECTLY IN HI-TRAC HOl TEC INTERNATIONAL COPYRIGHTED MATERIAL Fuel Transfer Sequence THE SHIELDED TRANSFER CANISTER IS FULLY SEATED IN HI-TRAC, THE LID NUTS ARE TIGHTENED AND TESTING PERORMED PRIOR TO TRANSFER TO UNIT 2 HOl TEC INTERNATIONAL COPYRIGHTED MATERIAL Fuel Transfer Sequence ,/ /y /' THE HI-TRAC TOP LID IS INSTALLED, THE BOLTS ARE TIGHTENED AND HI-TRAC INTEGRITY TESTING PERFOMED PRIOR TO TRANSFER TO UNIT 2 HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL Fuel Transfer Sequence HI-TRAC IS MOVED FROM THE IP-3 FSB TRUCK BAY AREA TO THE AWAITING VERTICAL CASK TRANSPORTER HOLTEC INTERNATIONAL COPYRIGHTED MATERIAL Fuel Transfer Sequence THE VERTICAL CASK TRANSPORTER LIFTS THE FROM THE AIR-PADS AND MOVES IT TO HOl TEC INTERNATIONAL COPYRIGHTED MATERIAL Project
-Relocate Protected Area (PA) Fence to support fuel transfer inside PA at all times. -COMPLETED February 2011. -40 ton Crane Upgrade to single-failure-proof COMPLETED December 2010 -Facility and Transport Path Modifications 60% COMPLETE -Spent Fuel Transfer -To include the following:
- Dry Runs 2012 2013 2014 Training Procedures Dry Runs Licensing
- License Amendment Request (LAR) History -Public meetings/telecoms held: -March 6, 2009 -June 15, 2009 -June 11, 2010 -Submitted July 08, 2009, supplemented September 28, 2009 -1 st round RAls: -received April 20, 2010 -responses submitted October 5, 2010 -2 nd round -received March 16, -responses due May 15, Summary of Round 1 RAI -100 total Operating General Principal Design Criteria ProcedureslTS Inform ation (4) (9) (4)Materials Evaluation (11) --Criticality (33) Shielding Design (19) Structural Thermal Evaluation (7) Hydraulics (13)
Summary of RAI's ROUND 1 Progress General Information Fully integrated response -revised licensing report Principal Design Criteria Criticality Tip-over analysis performed, FMEA, tornado missile NRC approved Part 71 methodology adopted for STC Thermal Hydraulics Operational changes to address detection of fuel misload -STC steam void, STC pressure rise LCO and SR I I I Structural Provided justifications and clarifications Shielding Design and ALARA Isolation zone adjacent to HI-TRAC haul path, Non Fuel Hardware analyzed I Materials Evaluation, etc STC use of ASME Code III NO I Operating ProcedureslTech.
Specs NRC Control of CoC type information via Appendix C to the Technical Specifications.
Captures both accident based and non accident based specifications Summary of Round 2 RAI -73 total Thermal General Information (2) Principal Operating Design Criteria Procedures/TS (0) (21 ) Criticality (18) Materials Hydraulics (10) Evaluation (4) Shielding Structural Design (17) Evaluation (1)
Summary of RAI's ROUND 2 Progress General Information Fully integrated response -revised licensing report Principal Design Criteria -Criticality Justifications and clarifications provided for model assumptions and benchmarking Thermal Hydraulics Justification of thermal model and properties Severe thermal misload analyzed Structural Further justification of tipover analysis Shielding Design and ALARA Estimated doses reduced/ Model justifications I Credit for a "Leak Tight" confinement boundary Requested analyses performed to address Neutron Source Assemblies, Cobalt, Tipover I STC lid design change to address streaming Materials Evaluation, etc STC qualifies as a "Leak Tight" confinement boundary /ASME I Code NC/ND reconciliation Operating ProcedureslTech.
Specs New TS proposed to isolate public/haul path New TS proposed to limit dose rates Summary of RAI's ROUND 2 Resolution Challenges General Information Per Thermal Hydraulics and TS below Principal Design Criteria -Criticality Some of the proposed RAI responses require further technical resolution Thermal Hydraulics Predicted hourly STC pressure rise Validation of no air in the vapor space Structural
-Shielding Design and ALARA -Materials Evaluation, etc STC ASME Code NO Operating Procedures/Tech.
Specs TS based on hourly STC pressure rise Adoption of a surface contamination LCO Path Forward Entergy to develop and submit RAI responses by 5/15/11 Entergy to provide continued support for RAI review process Continued Entergy / NRC Interface is essential Closing In order to meet Entergy's goals of: Transferring Spent Nuclear Fuel from IPEC Unit 3 Spent Fuel Pool to the ISFSI Restoring Full Core Offload Capability Reducing Spent Fuel Pool inventory The following items need to be accomplished: Continued Entergy/NRC Technical Review Interactions to Ensure Resolution of All outstanding Issues Continued Entergy/NRC Management Engagement at all levels to monitor progress and facilitate resolution of
....,.... ...
- ,..." **
--I '
-2 No Public Meeting Feedback forms have been received.
Please direct any inquiries to me at 301-415-2901, or by email toJohn.Boska@nrc.gov.
Docket Nos. 50-247 and 50-286
Enclosures:
- 1. List of Attendees
- 2. Licensee Slides cc w/encls: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsNrrlndianPoint RidsOGCRp RidsRgn1 MailCenter MRahimi, NMSS DPickett, NRR DWeaver, NMSS ZLi, NMSS SJones, NRR JDavis, NMSS MCall, NMSS MKhanna, NRR TNakanishi, NRR /RAJ John P. Boska, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation LPL 1-1 R/F RidsNrrDorlLpl1-1 RidsNrrLASLittle MGray, RI RidsAcrsAcnw&mMailCenter RidsNrrOd JGoshen, NMSS RParkhill, NMSS SBurnell, OPA GCasto, NRR JParillo, NRR MYoder, NRR MHamm,NRR MSampson, NMSS DHoang, NRR NDay, NMSS EBenner, NMSS DTang, NMSS RNelson, NRR KWood, NRR RTemps, NMSS GHornseth, NMSS DPstrak, NMSS LBrown, NRR JSolis, I\IMSS JBoska 5/4/11 NSalgado 5/9/11
