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Category:Conference/Symposium/Workshop Paper
MONTHYEARML16209A3712016-08-17017 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) 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 ML11215A0562011-08-30030 August 2011 July 21, 2011, Summary of Conference Call Held Between the U.S. Nuclear Regulatory Commission and Entergy Nuclear Operations, Inc., Concerning Operating Experience at Indian Point Nuclear Generating Station, Units 2 and 3 ML0925707522009-09-22022 September 2009 & 08/19/09 Summary of Telephone Conference Calls Held Between NRC and Entergy Nuclear Operations, Inc., Concerning Impingement and Entrainment Data ML0907607482009-03-25025 March 2009 03/02/2009 Summary of Telephone Conference Call Held Between NRC and Entergy Nuclear Operations, Inc., Concerning Draft Request for Additional Information Pertaining to the Indian Point, Units 2 & 3, License Renewal Application - Open Items ML0903000332009-02-0404 February 2009 Summary of Tele Conference Call Held on, Between the U.S. NRC and Entergy Nuclear Operations, Inc., Concerning Draft Request for Additional Information Pertaining to the Iipng Unit Nos. 2 and 3, LRA-Open Items ML0829708102008-10-28028 October 2008 09/15/08 Summary of Conference Call Held Between NRC and Entergy Pertaining to the Indian Point, Units 2 and 3, License Renewal Application - Reactor Vessel Neutron Embrittlement ML0817703312008-06-27027 June 2008 Summary of Telephone Conference Call Held on May 19, 2008, Between the NRC and Entergy Nuclear Operations, Inc., Related to the Indian Point, Units 2 and 3, License Renewal Application - Submerged Cables ML0812805862008-05-0808 May 2008 Summary of Telephone Conference Call Held on 04/14/08, Between NRC and Entergy Nuclear Operations, Inc., Concerning Response to Audit Items Related to Indian Point, Units 2 &3, License Renewal Application- Submerged Cables ML0811900592008-05-0808 May 2008 Summary of Telephone Conference Call Held on 04/03/08, Between NRC and Entergy Nuclear Operations, Inc., Concerning Responses to Request for Additional Information Related to the Indian Point, Units 2 & 3, License Renewal Application Metal ML0808405682008-04-0202 April 2008 03/07/2008 - Summary of Telephone Conference Call, Between Us NRC and Entergy Nuclear Operations, Inc., Concerning Responses to Request for Additional Information Related to the Indian Point Nuclear Generating Units 2 & 3, License Renewal A ML0804204302008-02-13013 February 2008 02/07/2008,Summary of Telephone Conference Call Between NRC and Entergy Nuclear Operations, Inc., Concerning Responses to Request for Additional Information Pertaining to Indian Point Units 2 & 3, License Renewal Application-Containment Coa ML0727706052007-10-16016 October 2007 Summary of Telephone Conference Call Held Between the U.S. Nuclear Regulatory Commission and Entergy Nuclear Operations, Inc., Concerning Draft Requests for Additional Information Pertaining to Indian Point Generating Station. 2016-08-17
[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 ML14238A7262014-09-10010 September 2014 Summary of Conference Call Held on July 30, 2014, Between the U.S. Nuclear Regulatory Commission and Entergy Nuclear Operations Inc., Regarding a Draft Request for Additional Information on Removal of Certain Aging Management Review Items ML14219A6742014-08-14014 August 2014 July 15, 2014 Summary of Telephone Conference Call Held Between U.S. Nuclear Regulatory Commission and Entergy Nuclear Operations, Inc., Concerning the Environmental Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License R ML14206B1282014-08-0101 August 2014 June 19, 2014 & July 16, 2014 Summary of Conference Calls Held Between the U.S. Nuclear Regulatory Commission and Entergy Nuclear Operations, Inc., Regarding Entergy Response to a Request for Additional Information ML14178A8682014-06-25025 June 2014 Summary of Annual Assessment Meeting for Indian Point Energy Center on 6/4/2014 ML14136A0052014-05-27027 May 2014 Summary of Phone Call Between New York State Department of State and U.S. Nuclear Regulatory Commission on May 7, 2014, Regarding the Coastal Zone Management Act Consistency Review ML14105A3542014-04-24024 April 2014 Summary of Conference Call Held on March 26, 2014, Between the U.S. Nuclear Regulatory Commission and Entergy Nuclear Operations, Inc., Concerning a Draft Request for Additional Information on the Reactor Vessel Internals Program ML14078A3992014-03-21021 March 2014 Summary of Conference Call Held on February 20, 2014, Between the U.S. Nuclear Regulatory Commission and Entergy Nuclear Operations, Inc., Concerning a Draft Request for Additional Information on LR-ISG-2012-02 and Draft LR-ISG-2013-01 ML13256A0862013-09-24024 September 2013 Summary of Meeting with Entergy Nuclear Operations, Inc. and Netco on Indian Point Unit 2 Spent Fuel Pool Management 2022-12-12
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23171B0442023-06-23023 June 2023 Enclosure - Indian Point Energy Center - Request for Additional Information for Independent Spent Fuel Storage Installation Facility-Only Emergency Plan License Amendment ML22292A2402022-10-21021 October 2022 RAIs for Master Dtf Agreement on IP1 IP2 10 18 2022 ML22103A2442022-04-13013 April 2022 Attachment - Request for Additional Information - License Amendment Request to Revise Emergency Plan and Emergency Action Level Scheme for Permanently Defueled Condition for Indian Point Energy Center ML22104A0352022-04-13013 April 2022 Request for Additional Information Related to Exemption Request from Emergency Planning Holtec Decommissioning International, LLC Indian Point Energy Center ML22006A0452022-01-0505 January 2022 PSDAR RAIs Final ML21337A2952021-12-0303 December 2021 Subsequent Request for Additional Information License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device (E-mail Dated 12/3/2021) ML21183A1602021-06-30030 June 2021 Update Request for Additional Information - Indian Point Energy Center Quality Assurance Program Manual (06/30/2021 E-mail) ML21138A9412021-05-18018 May 2021 Request for Additional Information - Indian Point Energy Center Quality Assurance Program Manual (05/18/2021 E-mail) ML21112A2672021-04-22022 April 2021 Subsequent Request for Additional Information License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device (Public Redacted Version) ML21019A5672021-01-19019 January 2021 Second Round Request for Additional Information License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device ML21013A0152021-01-12012 January 2021 Draft Request for Additional Information (E-mail Dated 1/12/2021) License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device ML20268C2352020-09-24024 September 2020 Request for Additional Information (E-mail Dated 9/24/20) License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device ML20233B0152020-08-20020 August 2020 Request for Additional Information (E-mail Dated 8/20/20) License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device ML20190A2342020-07-0808 July 2020 Request for Additional Information - Application for Order Consenting to Transfers of Control of Licenses (07/08/2020 E-mail) ML20190A1502020-06-25025 June 2020 (06/25/2020 E-mail) Draft Request for Additional Information Application for Order Consenting to Transfers of Control of Licenses ML20106F2492020-04-15015 April 2020 E-mail (04/15/2020) Request for Additional Information Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic ML20070J7902020-03-10010 March 2020 Request for Information to Support Triennial Baseline Design-Basis Capability of Power-Operated Valves Inspection; Inspection Report 05000286/2020012 ML19045A6252019-02-14014 February 2019 Request for Additional Information - Proposed License Amendment Request Regarding Storage of Fresh and Spent Nuclear Fuel in the Spent Fuel Pool - 2/14/19 E-mail from R.Guzman to M.Mirzai NL-18-053, Response to Request for Additional Information Regarding Relief Request IP3-ISI-RR-11 for Reactor Vessel Weld Inservice Inspection Frequency Extension2018-07-18018 July 2018 Response to Request for Additional Information Regarding Relief Request IP3-ISI-RR-11 for Reactor Vessel Weld Inservice Inspection Frequency Extension ML18155A4842018-06-0404 June 2018 Request for Additional Information Regarding Relief Request IP3-ISI-RR-11, E-mail from R.Guzman to C.Mackaman ML18143B6792018-05-23023 May 2018 Request for Additional Information Regarding LAR for One-Time Extension of the Containment Leakage Rate Test - Email from R.Guzman to M.Mirzai ML18094B0922018-04-0505 April 2018 Enclosurequest for Additional Information (Letter to B. S. Ford RAI Regarding Entergy Operations, Inc.'S Decommissioning Funding Plan Update for ISFSI Docket Nos.: 72-43, 72-51, 72-1044, 72-07, 72-12, and 72-59) ML17296A2352017-10-23023 October 2017 Request for Additional Information -10/23/17 E-mail from R.Guzman to R.Louie Cyber Security Plan Milestone 8 Implementation Schedule (CAC Nos. MF9656, MF9657, MF9658; EPID: L-2017-LLA-0217) ML17277B5482017-10-0303 October 2017 Request for Additional Information - Relief Request IP2-ISI-RR-20 Regarding Weld Examination ML17219A1062017-08-10010 August 2017 Request for Additional Information Regarding Inter-Unit Transfer of Spent Fuel - Shielded Transfer Canister Requests for Additional Information ML17200A0852017-07-19019 July 2017 Request for Additional Information Regarding the Connection of Non-Seismic Boric Acid Recovery System to RWST Seismic Piping ML17197A0002017-07-17017 July 2017 Request for Additional Information Regarding Inter-Unit Transfer of Spent Fuel ML17170A2862017-06-27027 June 2017 RAI Set 2017-06 ML17103A4182017-04-25025 April 2017 Baffle Bolt Rais. Requests for Additional Information for the Review of the Indian Point License Renewal Application (TAC Nos. MD5407 and MD5408) ML17088A4052017-04-20020 April 2017 Requests for Additional Information for the Review of the Indian Point License Renewal Application RAI Set 2017-3 (CAC Nos. MD5407 and MD5408) ML17088A3272017-04-19019 April 2017 Requests for Additional Information for the Review of the Indian Point License Renewal Application RAI Set 2017-02 (CAC Nos. MD5407 and MD5408) ML17100A1282017-04-11011 April 2017 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment of Inter Unit Transfer of Spent Fuel ML17046A2312017-03-0808 March 2017 Request for Additional Information for the Review of the Indian Point License Renewal - Set 2017-01 ML16232A1192016-09-12012 September 2016 Request for Additional Information for the Review of the Indian Point Nuclear Generating Units Nos. 2 and 3, License Renewal Application Environmental Review - Severe Accident Mitigation Alternatives (CAC Nos. MD5411 and MD5412) ML16138A1942016-07-25025 July 2016 Request for Additional Information for the Review of License Renewal Application, Set 2016-01 ML16139A0302016-06-10010 June 2016 Request for Additional Information Regarding Conditional Exemption from End-of-Line Moderator Temperature Coefficient Measurement ML16112A2262016-04-26026 April 2016 Request for Additional Information Regarding Relief Request IP2-ISI-RR-02 Alternative Examination Volume Required by Code Case N-729-1 ML16041A5782016-02-18018 February 2016 Request for Additional Information Related to License Amendment Request Regarding Moderator Temperature Coefficient Measurement Change ML16005A6292016-01-14014 January 2016 Request for Additional Information Regarding Relief Request IP2-RR-19 ML16013A0642016-01-13013 January 2016 NRR E-mail Capture - Request for Additional Information Entergy CNRO-2015-00023 - Revision to Entergy Quality Assurance Program Manual (Fleet Submittal CAC Nos. MF7086-MF7097) ML15341A1662015-12-0707 December 2015 NRR E-mail Capture - Entergy Fleet RR-EN-15-1, Request for Additional Information (CACs MF6341-MF6349) ML15148A4032015-06-29029 June 2015 Request for Additional Information Regarding the Spent Fuel Pool Criticality Analysis ML15156B2742015-06-16016 June 2015 Request for Additional Information Regarding Request to Permanently Extend the Frequency of the Containment Integrated Leak Rate Test ML15125A0972015-05-0606 May 2015 Request for Additional Information Regarding License Amendment to Permanently Extend the Frequency of the Containment Integrated Leak Rate Test ML15071A1012015-05-0404 May 2015 Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application, Set 2015-01 (TAC Nos. MD5407 and MD5408) ML15103A2592015-04-28028 April 2015 Request for Additional Information Regarding the Proposed License Amendment to Extend the Containment Type a Leak Rate Testing Frequency to 15 Years ML15104A5412015-04-22022 April 2015 Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application Environmental Review (TAC Nos. MD5411 and MD5412) ML15072A4172015-03-17017 March 2015 Request for Additional Information Regarding Extension of the Containment Type a Leak Rate Testing Frequency to 15 Years ML14329B2452015-02-18018 February 2015 Request for Additional Information for the Review of the Indian Point Nuclear Generating Units 2 and 3, License Renewal Application Environmental Review (TAC Nos. MD5411 and MD5412) CNRO-2015-00008, Responses to NRC Request for Additional Information Regarding Change in Corporate Form of Entergy Nuclear Holding Company2015-02-18018 February 2015 Responses to NRC Request for Additional Information Regarding Change in Corporate Form of Entergy Nuclear Holding Company 2023-06-23
[Table view] |
Text
March 25, 2009 LICENSEE: Entergy Nuclear Operations, Inc.
FACILITY: Indian Point Nuclear Generating Unit Nos. 2 and 3
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON MARCH 2, 2009, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENTERGY NUCLEAR OPERATIONS, INC., CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO THE INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3, LICENSE RENEWAL APPLICATION - OPEN ITEMS The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Entergy Nuclear Operations, Inc., held a telephone conference call on March 2, 2009, to discuss and clarify the staffs draft request for additional information (D-RAI) concerning certain open items identified in the Safety Evaluation Report with Open Items Related to the License Renewal of Indian Point Nuclear Generating Unit Nos. 2 and 3. The telephone conference call was useful in clarifying the intent of the staffs D-RAI. provides a listing of the participants and Enclosure 2 contains a listing of the D-RAI items discussed with the applicant, including a brief description on the status of the items.
The applicant had an opportunity to comment on this summary.
/RA/
Kimberly Green, Safety Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-247 and 50-286
Enclosures:
- 1. List of Participants
- 2. List of Draft Request for Additional Information cc w/encls: See next page
ML090760748 OFFICE LA:DLR PM:RPB2:DLR BC:RPB2:DLR NAME IKing KGreen DWrona DATE / /09 / /09 / /09
Letter to Entergy Nuclear Operations, Inc. from K. Green, dated March 25, 2009 DISTRIBUTION:
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON MARCH 2, 2009, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENTERGY NUCLEAR OPERATIONS, INC., CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO THE INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3, LICENSE RENEWAL APPLICATION - OPEN ITEMS HARD COPY:
DLR RF E-MAIL:
PUBLIC RidsNrrDlr RidsNrrDlrRpb1 RidsNrrDlrRpb2 RidsNrrDlrRer1 RidsNrrDlrRer2 RidsNrrDlrRerb RidsNrrDlrRpob RidsNrrDciCvib RidsNrrDciCpnb RidsNrrDraAfpb RidsNrrDraAplb RidsNrrDeEmcb RidsNrrDeEeeb RidsNrrDssSrxb RidsNrrDssSbpb RidsNrrDssScvb RidsOgcMailCenter
DWrona EDacus, OCA BPham GMeyer, RI KGreen RConte, RI AStuyvenberg ECobey, RI JBoska NMcNamara, RI RAuluck DScrenci, RI OPA JDozier NSheehan, RI OPA MKowal PCataldo, RI STurk, OGC CHott, RI LSubin, OGC DJackson, RI BMizuno, OGC BWelling, RI SBurnell, OPA DMcIntyre, OPA UShoop, OEDO
Indian Point Nuclear Generating Unit Nos. 2 and 3 cc:
Senior Vice President Mr. John P. Spath Entergy Nuclear Operations, Inc. New York State Energy, Research, and P.O. Box 31995 Development Authority Jackson, MS 39286-1995 17 Columbia Circle Albany, NY 12203-6399 Vice President Oversight Entergy Nuclear Operations, Inc. Mr. Paul Eddy P.O. Box 31995 New York State Department Jackson, MS 39286-1995 of Public Service 3 Empire State Plaza Senior Manager, Nuclear Safety & Albany, NY 12223-1350 Licensing Entergy Nuclear Operations, Inc. Regional Administrator, Region I P.O. Box 31995 U.S. Nuclear Regulatory Commission Jackson, MS 39286-1995 475 Allendale Road King of Prussia, PA 19406 Senior Vice President and COO Entergy Nuclear Operations, Inc. Senior Resident Inspectors Office 440 Hamilton Avenue Indian Point 2 and 3 White Plains, NY 10601 U.S. Nuclear Regulatory Commission P.O. Box 59 Assistant General Counsel Buchanan, NY 10511 Entergy Nuclear Operations, Inc.
440 Hamilton Avenue Mr. Charles Donaldson, Esquire White Plains, NY 10601 Assistant Attorney General New York Department of Law Manager, Licensing 120 Broadway Entergy Nuclear Operations, Inc. New York, NY 10271 Indian Point Energy Center 450 Broadway, GSB Mr. Raymond L. Albanese P.O. Box 249 Four County Coordinator Buchanan, NY 10511-0249 200 Bradhurst Avenue Unit 4 Westchester County Mr. Paul D. Tonko Hawthorne, NY 10532 President and CEO New York State Energy, Research, and Mayor, Village of Buchanan Development Authority 236 Tate Avenue 17 Columbia Circle Buchanan, NY 10511 Albany, NY 12203-6399 Mr. William DiProfio PWR SRC Consultant 48 Bear Hill Road Newton, NH 03858
Indian Point Nuclear Generating Unit Nos. 2 and 3 cc:
Mr. Garry Randolph Mr. John Sipos PWR SRC Consultant Assistant Attorney General 1750 Ben Franklin Drive, 7E New York State Department of Law Sarasota, FL 34236 Environmental Protection Bureau The Capitol Mr. William T. Russell Albany, NY 12224 PWR SRC Consultant 400 Plantation Lane Robert Snook Stevensville, MD 21666-3232 Assistant Attorney General Office of the Attorney General Mr. Jim Riccio State of Connecticut Greenpeace 55 Elm Street 702 H Street, NW P.O. Box 120 Suite 300 Hartford, CT 06141-0120 Washington, DC 20001 Ms. Kathryn M. Sutton, Esq.
Mr. Phillip Musegaas Morgan, Lewis & Bockius, LLP Riverkeeper, Inc. 1111 Pennsylvania Avenue, NW 828 South Broadway Washington, DC 20004 Tarrytown, NY 10591 Mr. Paul M. Bessette, Esq.
Mr. Mark Jacobs Morgan, Lewis & Bockius, LLP IPSEC 1111 Pennsylvania Avenue, NW 46 Highland Drive Washington, DC 20004 Garrison, NY 10524 Mr. Martin J. ONeill, Esq.
Mr. R. M. Waters Morgan, Lewis & Bockius, LLP Technical Specialist Licensing 1111 Pennsylvania Avenue, NW 450 Broadway Washington, DC 20004 P.O. Box 0249 Buchanan, NY 10511-0249 The Honorable Nita Lowey 222 Mamaroneck Avenue, Suite 310 Mr. Sherwood Martinelli White Plains, NY 10605 351 Dyckman Street Peekskill, NY 10566 Ms. Joan Leary Matthews Senior Counsel for Special Projects Ms. Susan Shapiro, Esq. Office of General Counsel 21 Perlman Drive NYS Department of Environmental Spring Valley, NY 10977 Conservation 625 Broadway Ms. Jessica Steinberg, J.D. Albany, NY 12233-5500 Sive, Paget & Riesel, P.C.
460 Park Avenue New York, NY 10022
TELEPHONE CONFERENCE CALL INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS March 2, 2009 PARTICIPANTS AFFILIATIONS Kim Green U.S. Nuclear Regulatory Commission (NRC)
Raj Auluck NRC Hans Ashar NRC George Thomas NRC Bryce Lehman NRC Rich Morante Brookhaven National Laboratory Mike Stroud Entergy Nuclear Operations, Inc. (Entergy)
Alan Cox Entergy Rich Drake Entergy ENCLOSURE 1
DRAFT REQUEST FOR ADDITIONAL INFORMATION INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 LICENSE RENEWAL APPLICATION OPEN ITEMS MARCH 2, 2009 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Entergy Nuclear Operations, Inc., (Entergy or the applicant) held a telephone conference call on March 2, 2009, to discuss and clarify the following draft request for additional information (D-RAI) regarding certain open items identified in the Safety Evaluation Report with Open Items Related to the License Renewal of Indian Point Nuclear Generating Unit Nos. 2 and 3 (IP2 and IP3).
Follow-up D-RAI 1: Question 359 - Open Item 3.0.3.2.15-1 In Entergy Letter NL-08-169, dated November 6, 2008, Additional Information Regarding License Renewal Application- Operating Experience Clarification, the applicant submitted a supplemental clarification, describing its plan for implementing a permanent remediation of the Indian Point Nuclear Generating Unit No. 2 (IP2) refueling cavity leakage over the next three scheduled IP2 re-fueling outages (2010, 2012, 2014).
The transmittal letter NL-08-169, dated November 6, 2008, states: There are no new commitments identified in this submittal. The applicant has previously taken a bore sample in the region of the leak, and has committed to take another sample prior to entering the period of extended operation. In absence of a formal commitment to remedy the source of leakage, the applicants aging management program (AMP) should include a method to monitor for a degrading condition in the refueling cavity, and other structures affected by the leakage, during the period of extended operation, or the applicant should explain how the Structural Monitoring Program will adequately manage potential aging of this region during the period of extended operation.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
Follow-up D-RAI 2: Question 360 - Open Item 3.0.3.2.15-2 In Entergy Letter NL-08-169, dated November 6, 2008, the applicant submitted a supplemental clarification for the IP2 spent fuel pool pit walls, which provides a detailed description of (1) the design margins for the spent fuel pool concrete walls; and (2) the results of prior concrete core sample testing and rebar corrosion testing.
- a. In Commitment 25, the applicant commits to sample for tritium in groundwater wells in close proximity to the IP2 spent fuel pool at least every three months to assess for potential indications of spent fuel pool leakage. This commitment does not describe what actions will be taken if leakage continues. If sampling indicates continued leakage, the applicants AMP should include a method to determine if a degraded condition exists during the period of extended operation, or the applicant should explain how the Structural Monitoring Program will adequately manage potential aging of the ENCLOSURE 2
inaccessible concrete of the IP2 spent fuel pool due to borated water leakage during the period of extended operation.
- b. The second paragraph on page 2 of Attachment 1 of the clarification letter dated November 6, 2008, states in part: [l]ittle or no corrosion was observed in the rebar except at a location in the wall where spalling had occurred exposing rebar to the elements. Analysis of the rust particles showed high chloride content and low boron concentration indicating that rainwater was the primary cause of the observed corrosion. The staff requests the applicant to identify any Unit 2 and Unit 3 operating experience related to rebar corrosion, in light of the chloride content in rainwater, and identify the likely source for the high chloride content in the rainwater. Further the applicant is requested to explain whether and how the AMP is adequate to address this environment and the related potential aging effects to ensure there is no loss of intended function during the period of extended operation.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
Follow-up D-RAI 3: Question 361 - Open Item 3.0.3.3.2-1 In Entergy Letter NL-08-169, dated November 6, 2008, the applicant submitted a supplemental clarification for IP containment spalling, describing the design margins for the Indian Point (IP) containment structures at the locations of existing concrete degradation on the vertical wall.
Based on its review of the information, the staff identified areas that need further clarification and/or additional information to complete its review as described below:
- a. The clarification for the IP containment spalling states: As the surface concrete is not credited for tensile strength of the structure, the spalling has no impact on the available margins. The strength margins identified appear to be based on the nominal rebar dimensions, without any consideration for rebar degradation due to exposure and potential loss of bond between the concrete and the rebar. Explain whether, and if so how, the existing degradation and design margin will be considered in performing periodic inspections to monitor degradation, to ensure there is no loss of containment intended function during the period of extended operation.
- b. In the spent fuel pool discussion, in the letter dated November 6, 2008, the applicant stated: Little or no corrosion was observed in the rebar except at a location in the wall where spalling had occurred exposing rebar to the elements. Analysis of the rust particles showed high chloride content and low boron concentration indicating that rainwater was the primary cause of the observed corrosion. The applicant is requested to explain the adequacy of the 5-year IWL frequency of inspection of the degraded areas of the IP containments during the period of extended operation, considering the possibility of an increased site-specific corrosion rate of the exposed rebar on the containments.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
Follow-up D-RAI 4: Open Item 3.5-1 In Entergy Letter NL-08-169, dated November 6, 2008, the applicant submitted a supplemental clarification to LRA Section 3.5.2.2 related to the concrete mix design method and the durability of concrete used at IP. In the LRA the applicant claimed that concrete meets the specifications of ACI 318-63 and the intent of ACI 201.2R-77, Guide to Durable Concrete. As a result the applicant claimed that several aging effects were not applicable to inaccessible concrete. Based on its review of the information, the staff identified areas that need further clarification and/or additional information to determine that the applicant meets the cited ACI specifications such that further evaluation is not necessary as recommended by the GALL Report.
- a. In the clarification to LRA Section 3.5.2.2 (Part 1) on page 6 of Attachment 1 to letter NL-08-169, the applicant stated that it used Method 2 of Section 502 of ACI 318-63 by testing trial mixes to determine the water-cement ratios for the concrete mix design of the IP containments and other structures. In order for the staff to evaluate the quality of concrete in IP structures that may be subject to degradation during the period of extended operation, the staff requests the applicant to define the water-cement ratio that was specified at the time of construction. The applicant is requested to provide this information for the IP containments and other safety-related IP Unit 2 and 3 concrete structures, including the refueling cavities and the spent fuel pools.
- b. In order for the staff to understand the parameters related to concrete strength and durability during the period of extended operation, the applicant is requested to describe the methodology used to establish the required concrete compressive strength of 3000 psi for the containment and other safety-related concrete structures, in accordance with ACI 318-63, Method 2. The applicant is requested to provide a summary of the results of statistical analyses performed, if any, of the original concrete strength tests, including number of samples, raw strength values from the test, the mean, the standard deviation, and the original criterion (e.g., mean minus 1 standard deviation, coefficient of variation) used to confirm that the required compressive strength was achieved, and can be relied upon during the period of extended operation such that further evaluation is not necessary as recommended by the GALL Report.
- c. If the applicant is unable to provide the information requested in parts (a) and (b) above, the applicant is requested to explain how the aging effects on concrete will be adequately managed during the period of extended operation.
Discussion: With regard to part a of the question, during the telephone call, the applicant stated that because it used Method 2 of the ACI 318-63 standard to test the concrete mixtures, there is not one specific water-cement ratio that was specified at the time of construction.
Therefore, the applicant requested that the word specified in the sentence, the staff requests the applicant to define the water-cement ratio that was specified at the time of construction, be changed to used. The staff agreed that this would be a more appropriate term to use given the methodology used to test the concrete. Based on this discussion with the applicant, the staff agreed to revise this question as follows. The revised question will be sent as a formal RAI.
In the clarification to LRA Section 3.5.2.2 (Part 1) on page 6 of Attachment 1 to letter NL-08-169, the applicant stated that it used Method 2 of Section 502 of ACI 318-63 by testing trial mixes to determine the water-cement ratios for the concrete mix design of the IP containments and other structures. In order for the staff to evaluate the quality of concrete in IP structures that may be subject to degradation during the period of extended operation, the staff requests the applicant to define the water-cement ratio that was used at the time of construction. The applicant is requested to provide this information for the IP containments and other safety-related IP Unit 2 and 3 concrete structures, including the refueling cavities and the spent fuel pools.
Follow-up D-RAI 5: Open Item 3.5-2 In Entergy Letter NL-08-169, dated November 6, 2008, Additional Information Regarding License Renewal Application- Operating Experience Clarification, the applicant submitted a supplemental clarification to LRA Section 3.5.2.2 (Part 3) for IP2 containment concrete and its ability to withstand local area temperatures up to 250ºF. The staff has identified areas that need further clarification and/or additional information as discussed below:
- a. In the clarification to LRA Section 3.5.2.2 (Part 3) on page 7 of Attachment 1 to letter NL-08-169, the applicant stated that a 15% reduction of concrete strength could be expected when reaching temperatures of 250ºF and that concrete compressive strength tests showed an actual strength more than 15% higher than design strength. Please provide the methodology used to arrive at the conclusion that the actual concrete strength is more than 15% greater than 3000 psi, (i.e., greater than 3450 psi). Provide a summary of the results, including number of samples, raw strength values from the test, the mean, the standard deviation, and the original criterion (e.g., mean minus 1 standard deviation) used to confirm that the claimed strength was achieved.
- b. Please explain how consideration was given to the reduction in modulus of elasticity in the high temperature concrete evaluation.
- c. If the applicant is unable to provide the information requested in parts (a) and (b) above, the applicant is requested to explain how the aging effects on concrete, due to high temperatures, will be adequately managed during the period of extended operation.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
During the telephone call, the staff inquired about the 250ºF local area temperature in the adjoining concrete for penetrations for pipes carrying hot fluid, and whether the air-to-air heat exchangers are needed to maintain the temperature below 250ºF. The applicant stated that it will include information regarding the local area temperature for concrete in near these penetrations when it responds to the RAI.