Letter Sequence Draft RAI |
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Results
Other: ML071900365, ML11109A067, ML13043A527, ML13067A315, ML13077A284, ML14217A206, ML15007A430, ML15055A004, ML15055A014, ML15268A128, NL-07-078, Station Blackout (SBO) / Appendix R Diesel Generator Commitment, Response to NRC Review Status of License Renewal Application, NL-10-054, Correction to License Renewal Application, NL-12-037, License Renewal Application - Revised Reactor Vessel Internals Program and Inspection Plan Compliant with MRP-227-A, NL-14-013, Additional Information Regarding the License Renewal Application - Action Item 7 from MRP-227-A
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MONTHYEARNL-07-056, Supplement to License Renewal Application2007-05-0303 May 2007 Supplement to License Renewal Application Project stage: Supplement NL-07-078, Station Blackout (SBO) / Appendix R Diesel Generator Commitment, Response to NRC Review Status of License Renewal Application2007-06-21021 June 2007 Station Blackout (SBO) / Appendix R Diesel Generator Commitment, Response to NRC Review Status of License Renewal Application Project stage: Other ML0719003652007-07-25025 July 2007 Determination of Acceptability and Sufficiency for Docketing, Proposed Review Schedule, and Opportunity for a Hearing Regarding the Application from ENO, Inc. for Renewal of the Operating License for the Indian Point Nuclear Generating Unit Project stage: Other ML0727804392007-10-16016 October 2007 Summary of Telephone Conference Call with Entergy Nuclear Operations, Inc., Requests for Additional Information Project stage: RAI NL-10-054, Correction to License Renewal Application2010-05-27027 May 2010 Correction to License Renewal Application Project stage: Other ML11109A0672011-04-19019 April 2011 2011/04/19 Indian Point Lr Hearing - FW: OAR - Safety PM Change for the License Renewal Project for Indian Point...(Tac Nos. MD5407 & MD5408) Project stage: Other NL-12-037, License Renewal Application - Revised Reactor Vessel Internals Program and Inspection Plan Compliant with MRP-227-A2012-02-17017 February 2012 License Renewal Application - Revised Reactor Vessel Internals Program and Inspection Plan Compliant with MRP-227-A Project stage: Other ML12223A3882012-09-10010 September 2012 RAI for the Review of the Indian Pont Nuclear Generating Unit Nos. 2 and 3, LRA Set 2012-02 Project stage: RAI ML12223A3672012-09-12012 September 2012 08/08/2012 Summary of Telephone Conference Call Held Between NRC and Entergy Nuclear Operations, Inc., Concerning RAI Set 2012-02, Reactor Vessel Internals Program Pertaining to the Indian Point, Units 2 & 3, License Renewal Application Project stage: RAI ML12278A0772012-10-16016 October 2012 Request for Additional Information for the Review of the Indian Point Nuclear Generating Units 2 and 3, License Renewal Application, Set 2012-03 (TAC Nos. MD5407 and MD5408) Project stage: RAI NL-12-140, Reply to Request for Additional Information Regarding the License Renewal Application2012-10-17017 October 2012 Reply to Request for Additional Information Regarding the License Renewal Application Project stage: Response to RAI NL-12-166, Reply to Request for Additional Information Regarding the License Renewal Application2012-11-20020 November 2012 Reply to Request for Additional Information Regarding the License Renewal Application Project stage: Response to RAI ML15334A2562013-02-0606 February 2013 Official Exhibit - ENT000660-00-BD01 - Letter from J. Daly, NRC, to Vice President, Operations, Entergy, Request for Additional Information for the Review of the IP Nuclear Generating Unit Nos. 2 and 3 LRA, Set 2013-01 (TAC Nos. MD5407 and Project stage: Request ML15335A2722013-02-0606 February 2013 Official Exhibit - NRC000187-00-BD01 - Letter from John Daily, NRC, to Entergy, Request for Additional Information for the Review of the IP Nuclear Generating Unit Nos. 2 and 3, License Renewal Application, Set 2013-01 (TAC Nos. MD5407 and Project stage: RAI ML13015A1752013-02-0606 February 2013 Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, LRA, Set 2013-01 Project stage: RAI ML15222A8962013-02-0606 February 2013 ENT000660 - Letter from J. Daly, NRC, to Vice President, Operations, Entergy, Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3 License Renewal Application, Set 2013-01 (TAC Nos. MD54 Project stage: Request ML15223A2632013-02-0606 February 2013 NRC000187 - Letter from John Daily, NRC, to Entergy, Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application, Set 2013-01 (TAC Nos. MD5407 and MD5408) Feb. 6, Project stage: RAI ML13043A5272013-02-26026 February 2013 PM Change Letter - February 2013 Project stage: Other ML13067A3152013-03-0808 March 2013 Correction to Project Manager Change for the License Renewal of Indian Point, Units 2 and 3 (TAC Nos. MD5407 & MD5408) Project stage: Other ML13077A2842013-03-0808 March 2013 Correction PM Letter Indian Point Project stage: Other NL-13-052, Reply to Request for Additional Information Regarding the License Renewal Application2013-05-0707 May 2013 Reply to Request for Additional Information Regarding the License Renewal Application Project stage: Response to RAI ML13162A6062013-06-12012 June 2013 Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application, Set 2013-02 (TAC Nos. MD5407 and MD5408) Project stage: RAI ML13186A1692013-07-17017 July 2013 Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application, Set 2013 03 (TAC Nos. MD5407 and MD5408) Project stage: RAI ML15222A8982013-07-26026 July 2013 ENT000661 - Letter from K. Green, NRC, to Vice President, Operations, Entergy, Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3 License Renewal Application, Set 2013-04 (TAC Nos. MD5 Project stage: Request ML15334A2572013-07-26026 July 2013 Official Exhibit - ENT000661-00-BD01 - Letter from K. Green, NRC, to Vice President, Operations, Entergy, Request for Additional Information for the Review of the IP Nuclear Generating Unit Nos. 2 and 3 Lr Application, Set 2013-04 (TAC Nos Project stage: Request ML13204A1992013-07-26026 July 2013 RAI for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application, Set 2013-04 (TAC Nos. MD5407 and MD5408) Project stage: RAI ML13240A0762013-09-0303 September 2013 RAI Set 2013-5 follow-up RAI on CP Project stage: RAI ML13318A4502013-11-19019 November 2013 Request for Additional Information for the Review of the Indian Point Nuclear Generating, Units 2 and 3, License Renewal Application, Set 2013-06 (TAC Nos. MD5407 and MD5408) Project stage: RAI ML14027A4152014-01-16016 January 2014 Enclosure 2 to NL-14-010, Attachment 2, Final Response to U.S. NRC RAI 6-A Items 1 and 2 on the Rvi Program and Rvi Inspection Plan Project stage: Request NL-14-010, Units, 2 & 3 - Reply to Request for Additional Information Regarding the License Renewal Application2014-01-16016 January 2014 Units, 2 & 3 - Reply to Request for Additional Information Regarding the License Renewal Application Project stage: Response to RAI NL-14-013, Additional Information Regarding the License Renewal Application - Action Item 7 from MRP-227-A2014-01-28028 January 2014 Additional Information Regarding the License Renewal Application - Action Item 7 from MRP-227-A Project stage: Other ML14084A3872014-04-0101 April 2014 Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application, Set 2014-01 (TAC Nos. MD5407 and MD5408) Project stage: RAI ML15334A2582014-04-0909 April 2014 Official Exhibit - ENT000662-00-BD01 - Letter from K. Green, NRC, to Vice President, Operations, Entergy, Request for Additional Information for the Review of the IP Nuclear Generating Unit Nos. 2 and 3 LRA, Set 2014-02 (TAC Nos. MD5407 and Project stage: Request ML15222A9012014-04-0909 April 2014 ENT000662 - Letter from K. Green, NRC, to Vice President, Operations, Entergy, Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3 License Renewal Application, Set 2014-02 (TAC Nos. MD5 Project stage: Request ML14094A1732014-04-0909 April 2014 Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application, Set 2014-02 Project stage: RAI NL-14-093, Reply to Request for Additional Information Regarding License Renewal Application2014-08-0505 August 2014 Reply to Request for Additional Information Regarding License Renewal Application Project stage: Response to RAI ML14217A2062014-08-14014 August 2014 Respect for Withholding Information from Public Disclosure Project stage: Other ML14206B1742014-08-14014 August 2014 Review of Draft Audit Report Regarding Indian Point Nuclear Generating Unit Nos 2 and 3, License Renewal Application Project stage: Draft Approval ML14259A1152014-09-0909 September 2014 Submittal of Westinghouse Review of Draft NRC Audit Report Regarding Indian Point Nuclear Generating Units Nos. 2 and 3 Project stage: Request ML14265A2262014-09-25025 September 2014 Request for Withholding Information from Public Disclosure Regarding the Aging Management Audit Report Associated with Indian Point, Units 2 and 3 License Renewal Application (TACs MD5407 and MD5408) Project stage: Withholding Request Acceptance ML15007A4302015-01-0909 January 2015 Project Manager Change for the License Renewal of Indian Point Nuclear Generating Unit Nos. 2 and 3 (TAC Nos. MD5407 and MD5408) Project stage: Other ML15055A0042015-02-17017 February 2015 Lr Hearing - Indian Point: Reissue of RAI 3.0.3-2 from Set 2014-01 for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, LRA Project stage: Other ML15055A0142015-02-18018 February 2015 Lr Hearing - Reissue of RAI 3.0.3-2 from Set 2014-01 for Review of Indian Point, Units 2 and 3, LRA Project stage: Other ML15055A0082015-02-18018 February 2015 Lr Hearing - Indian Point: Reissue of RAI 3.0.3-2 from Set 2014-01 for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, LRA Project stage: RAI ML15055A0122015-02-18018 February 2015 Lr Hearing - Indian Point: Reissue of RAI 3.0.3-2 from Set 2014-01 for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, LRA (Tac Nos. MD5407 and MD5408) Project stage: RAI NL-15-019, Reply to Request for Additional Information 3.0.3-2 from Set 2014-01 for the Review of the License Renewal Application2015-03-10010 March 2015 Reply to Request for Additional Information 3.0.3-2 from Set 2014-01 for the Review of the License Renewal Application Project stage: Response to RAI 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) Project stage: RAI ML15170A4562015-07-0707 July 2015 RAI for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application, Set 2015-02 Project stage: RAI 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 Project stage: RAI NL-15-092, Reply to 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)2015-08-18018 August 2015 Reply to 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) Project stage: Response to RAI 2013-07-17
[Table View] |
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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
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 17, 2016 LICENSEE: Entergy Nuclear Operations, Inc.
FACILITY: Indian Point Nuclear Generating Unit Nos. 2 and 3
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON JULY 21, 2016, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENTERGY NUCLEAR OPERATIONS, INC. CONCERNING THE DRAFT REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3, LICENSE RENEWAL APPLICATION, SET 2016-01 (TAC NOS. MD5407 AND MD5408)
The U.S. Nuclear Regulatory Commission (NRC) staff and representatives of Entergy Nuclear Operations, Inc. (Entergy), held a telephone conference call on July 21, 2016, to discuss and clarify the NRC staffs request for additional information (RAI) concerning the Indian Point Nuclear Generating Unit Nos. 2 and 3 license renewal application safety review. provides a listing of the participants and Enclosure 2 contains a listing of the RAIs discussed with Entergy, including a brief description of the status.
Entergy had an opportunity to comment on this summary.
/RA/
Michael Wentzel, Project Manager Environmental Review and Projects Branch Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-247 and 50-286
Enclosure:
As stated cc w/encl: Listserv
ML16209A371 *concurrence via e-mail OFFICE LA:DLR PM:RERP:DLR BC:RPB1:DLR PM:RERP:DLR NAME IBetts MWentzel YDiaz (LJames for) MWentzel DATE 8/8/16 8/10/2016 8/16/2016 8/17/2016
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON JULY 21, 2016, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENTERGY NUCLEAR OPERATIONS, INC. CONCERNING THE DRAFT REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3, LICENSE RENEWAL APPLICATION, SET 2016-01 (TAC NOS. MD5407 AND MD5408)
DISTRIBUTION:
HARD COPY:
DLR RF E-MAIL:
PUBLIC RidsNrrDlrRpb1 Resource RidsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsNrrDlrRerp Resource RidsNrrDlrRsrg Resource RidsOgcMailCenter Resource
YDiaz MWentzel WHolston JGavula BAllik DPickett STurk, OGC DRoth, OGC BHarris, OGC SBurnell, OPA DMcIntyre, OPA JWeil, OCA MGray, RI GDentel, RI DonaldJackson, RI MModes, RI NSheehan, RI OPA DScrenci, RI OPA DTifft, RI NMcNamara, RI BHaagensen, RI GNewman, RI SRich, RI
TELEPHONE CONFERENCE CALL INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS JULY 21, 2016 PARTICIPANTS: AFFILIATIONS:
Brian Allik U.S. Nuclear Regulatory Commission (NRC)
Jim Gavula NRC Bill Holsten NRC Michael Wentzel NRC Charlie Caputo Entergy Nuclear Operations, Inc. (Entergy)
Alan Cox Entergy Peter Guglielmino Entergy Dave Lach Entergy Rich Louie Entergy Tom Orlando Entergy Dennis Pennino Entergy Andy Taylor Entergy Mike Troy Entergy Sal Zulla Entergy ENCLOSURE 1
TELEPHONE CONFERENCE CALL CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION (RAI), SET 2016-01 RELATED TO INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 (IP2 and IP3)
LICENSE RENEWAL APPLICATION DOCKET NOS. 50-247 AND 50-286 REGARDING LR-ISG-2012-02 JULY 21, 2016 The U.S. Nuclear Regulatory Commission (NRC) staff and representatives of Entergy Nuclear Operations, Inc. (Entergy), held a telephone conference call on July 21, 2016, to discuss and clarify the following requests for additional information (RAIs) concerning the license renewal application safety review.
RAI 3.0.3-9
Background
By letter dated December 16, 2014 (ML14365A069), Entergy Nuclear Operations, Inc.
(Entergy), stated the following:
- The Fire Water System Program includes volumetric wall thickness measurements used to ensure that wall thickness is within required structural limits. Entergy also stated that wall thickness measurements conducted for IP2 prior to the end of its original operating term did not identify any unacceptable wall thinning. Entergy also stated that,
[l]ocalized corrosion has resulted in minor through-wall leaks that have no impact on system performance and do not threaten the structural integrity of the piping or the safety function of nearby equipment. Entergy did not propose any changes to its Fire Water System Program to address recurring internal corrosion (RIC).
- Loss of material in the city water system is managed by the Periodic Surveillance and Preventive Maintenance Program. Entergy also stated that, [h]owever, based on past operating experience, they [through-wall leaks] do not compromise the intended functions of these or any other system, and do not warrant aging management program activities beyond those provided by established aging management programs and the corrective action program. In its letter dated September 26, 2012 (ML12285A084),
Entergy stated that visual inspection or other NDE techniques will be used to inspect a representative sample of the internals of city water piping, and piping components to manage loss of material. Entergy did not propose any changes to its Periodic Surveillance and Preventive Maintenance Program to address RIC.
It appears that two events have impacted the performance of the fire water system.
- IP2 - NRC Integrated Inspection Report 050000247/2003011 (ML033140584) documents a September 10, 2003, 80 gallon per minute leak that resulted in the fire water header not being available to perform its intended function for approximately three hours. The apparent cause for this leak states, [t]he apparent cause for the pin-hole leak is age related corrosion degradation of the piping, specifically, high-oxygenation pitting corrosion. The piping is original Unit 1 equipment, schedule 40 un-lined black steel pipe that is approximately 45 years old. The follow-up UT inspections indicated that the corrosion mechanism that resulted in the pinhole was not general pipe corrosion but ENCLOSURE 2
was localized in the pinhole. The periodic testing of the system introduces fresh oxygen to the system and such cyclic re-oxygenation results in pits caused by 'high-oxygenation corrosion.' These pits then grow to become thru wall pinhole leaks in the piping. Portions not subject to periodic flow are not subject to this corrosion mechanism.
- IP2 - NRC Integrated Inspection Report 05000247/2015001 and 05000286/2015001 (ML15133A264) documents a December 29, 2014, failure of a 10-inch piping spool piece in the IP1 high pressure fire protection header that resulted in the fire water header to IP2 not being available to perform its intended function for about two hours. The failure was as a result of a crack opening up along the longitudinal seam weld along the bottom of the pipe. Three previously identified pinhole leaks were located along the length of the cracked region.
Issue During the supplemental audit conducted on February 23-25, 2016, the U.S. Nuclear Regulatory Commission (NRC) staff reviewed a list of leaks in the fire water and city water systems provided by Entergy. These leaks encompassed those occurring from 2007 through 2015.
During this timeframe, there were approximately 42 leaks in the fire water system and 14 in the city water system. Sixteen of the fire water leaks were inspected using ultrasonic thickness techniques. Ultrasonic inspections were conducted on an additional 14 locations at IP2. Based on Entergys evaluation of all of the thickness measurements, structural integrity requirements were met. The NRC staff reviewed Entergys analytical techniques. Entergy has generated a preventive maintenance activity to perform ultrasonic inspections at the additional 14 locations by 2023. The NRC staff reviewed the ultrasonic thickness reports for two of the leaks associated with the December 29, 2014 failure. The NRC staff projected potential loss of material based on corrosion rates documented in Entergys calculations. It would appear that structural integrity requirements would have been met on the day of the failure. Based on its review of documents during the audit, the NRC staff concluded that conducting ultrasonic wall thickness examinations will not provide sufficient information to result in prevention of potential future losses of intended function of the fire water and city water system.
The cause evaluation for the September 10, 2003, failure did not provide an explanation as to why the pinhole leak, unlike the numerous other pinhole leaks, resulted in a temporary loss of intended function of the fire water header. Entergy does not have or did not provide an apparent cause report for the December 29, 2014 failure.
Lacking an apparent cause of the failure on December 29, 2014, and the limited causal analysis of the failure on September 10, 2003, the NRC staff lacks sufficient information to conclude that Entergy has implemented effective means to provide reasonable assurance that future losses of intended function of the fire water and city water system will not occur.
Request
- 1) State the cause of the failure on December 29, 2014. If possible, provide additional information related to the cause of the failure on September 10, 2003. In particular, if possible, provide information related to why the pinhole leak, unlike numerous other pinhole leaks, resulted in a temporary loss of intended function of the fire water header during the September 10, 2003, failure.
- 2) State how these causes of failure are related to age-related degradation.
- 3) Propose changes to the Fire Water System Program and Periodic Surveillance and Preventive Maintenance Program to address recurring internal corrosion in the fire water and city water systems or provide the basis as to why changes are not necessary.
Discussion: Entergy requested that the wording in Request 3 be revised from Fire Water System Program and Periodic Surveillance and Preventive Maintenance Program to aging management programs. Entergy stated that changes may be needed in programs other than the ones identified in the draft request. As a result, the NRC staff changed the request to state:
Propose changes to aging management programs, as appropriate, to address recurring internal corrosion in the fire water and city water systems or provide the basis as to why changes are not necessary.
RAI 3.0.3-10
Background
The NRC staff issued the Safety Evaluation Report (SER) for License Renewal of Indian Point Energy Center (IPEC) in August 2009. As documented in the SER, the NRC staff concluded that the Service Water Integrity Program was shown to adequately manage the effects of aging.
Since the completion of its initial reviews for the SER, as part of its efforts to evaluate information for interim staff guidance in LR-ISG-2012-02, Aging Management of Internal Surfaces, Fire Water Systems, Atmospheric Storage Tanks, and Corrosion Under Insulation, the NRC staff identified operating experience at IP2 and IP3 during the intervening years (i.e.,
after 2009) where, as a result of aging effects, licensing basis functions may have been impacted by certain service water system components or components supported by the service water system. In addition, during its reviews of the more recent events, the NRC staff identified another historical event in 2002 that was not previously described. Based on this recently identified operating experience, the NRC staff needs additional information to evaluate the adequacy of Entergys Service Water Integrity Program in addressing recurring internal corrosion.
Issue
- 1) Licensee Event Report (LER) 286/2002-001 documents corrosion in an 18-inch service water pipe where the remaining wall thickness did not provide sufficient structural integrity. The cement-lined pipe configuration did not appear to be unique, the prior visual inspections did not reveal any missing cement liner or biological growth that are precursors to corrosion of the pipe; however, the existing Generic Letter (GL) 89-13 program did not prevent a loss of pressure boundary due to a known degradation mechanism. It is unclear to the NRC staff that effective changes have been made to ensure that future, similar losses of pressure boundary will not occur in other cement-lined piping
- 2) LER 286/2011-003 documents corrosion in a 10-inch service water pipe involving a prior repair that caused a safety system functional failure due to flooding. Entergys August 18, 2015, letter states that the through-wall failure of the piping was not considered to be due to the effects of aging because the loss of material occurred due to an inadequate repair of the concrete lining. It is unclear to the NRC staff that effective changes have been made to ensure that future, similar loss of intended function involving flooding or prior repairs will not occur in other cement-lined piping.
- 3) LER 247/2011-003 documents inoperable containment fan cooler units due to silt in the service water intake bay and notes that similar silt levels had caused similar issues in 2007. According to Entergys August 2015 letter, the associated changes to the Service Water Integrity Program were not made to manage the effects of aging, but instead were made to manage the effects of weather-related events. In addition, as a separate action, Entergy changed its associated GL 89-13 program commitment, which potentially allows the service water intake bay silting inspections to be conducted less frequently than given in GL 89-13. Given the distinction made between age-related silting and event-driven silting, and the change to GL 89-13 commitment, it is unclear to the NRC staff that effective changes have been made to ensure that the effects of aging associated with silting in the service water intake bay are adequately managed.
- 4) LER 247/2013-004 documents inoperable service water piping that rendered radiation monitors R-49, R-46, and R-53 non-functional, requiring compensatory action to be taken. The NRC staff identified four subsequent condition reports (CR-IP2-2013-5053, CR-IP2-2014-1179, CR-IP2-2014-6504, and CR-IP2-2015-3500) documenting additional leaks with the same consequence. The LER states that full piping replacement was planned for the 2014 refueling outage, and Entergys August 2015 letter states that 200 feet of this piping was replaced in 2014. Given that leakage has occurred subsequent to the piping replacement, it is unclear to the NRC staff that effective changes have been made to the program to ensure that future, similar recurring leaks will not adversely impact the intended function(s) of the radiation monitors.
- 5) LER 286/2014-002 documents a leak in a socket welded service water pipe that resulted in an essential service water header being declared inoperable because the leak location did not meet the ASME Code Case N-513-3 criteria. The LER states that the service water piping and valve flush procedure, 3-PT-R185B, was specifically developed to address recurring leaks in stagnant vent and drain piping, and the procedure is the main barrier for preventing future leaks in carbon steel socket welded piping. In its August 2015 letter, Entergy states that a section was added to the Program governing procedure in July 2011, after Entergy identified that IP2 did not have an equivalent flushing procedure as IP3. Entergy also states that the IP3 flushing procedure has been effective since being instituted in 2001. It is unclear to the NRC staff that effective changes have been made to the program because the procedure for preventing leaks apparently does not prevent recurring leaks. It is also unclear whether a comprehensive review has been performed to identify other missing unit-specific procedures for managing the effects of aging.
- 6) The August 2015 response to RAI 3.0.3-4 states more than 600 weld examinations have been performed since 1997 with more than 90 percent of the welds meeting acceptance criteria. The approximately 10 percent of welds that did not meet acceptance criteria can be viewed as the program having prevented about 60 leaks over the span of 18 years. In contrast, the listing for the number of leaks in the response indicates there have been over 90 leaks that the program did not prevent in 11 years. Although Entergy has made efforts to manage the effects of aging associated with recurring leaks, it is unclear whether the significance (i.e., multiple instances of loss of intended function) of these leaks will be limited as ongoing corrosion occurs.
- 7) Entergys December 2014 letter included an enhancement to the Service Water Integrity Program to evaluate through-wall leakage using the corrective action program. Although all conditions adverse to quality should be entered into the corrective action program and
evaluated, given the need for this enhancement, it is unclear to the NRC staff whether previous leaks were evaluated under the corrective action program and, consequently, considered during previous operating experience reviews of corrective action documents. In addition, the basis for the December 31, 2019, completion date for this enhancement is unclear.
Request
- 1) Regarding the issues discussed above in LER 286/2002-001, provide information to show that changes made to the program (since that time) provide reasonable assurance that recurrence of the loss of function in other cement-lined piping is unlikely.
- 2) For LER 286/2011-003:
a) Provide the bases for reasonable assurance that the Service Water Integrity Program compensates for all past liner repairs such that this degradation mechanism will not result in a loss of intended function of the service water system. Also, provide the bases for reasonable assurance that all locations where flooding due to system leakage could cause loss of intended function have been identified and evaluated for probable leak rates.
b) For the previous operating experience reviews for license renewal, identify past degradation involving loss of material that was not considered to be due to the effects of aging, and provide the bases to demonstrate that the cause of loss of material has been adequately addressed to prevent a recurrence of a loss of safety function.
- 3) For LER 247/2011-003, clarify whether silt monitoring of the intake bays is included as an aging management activity. Provide the basis to demonstrate that the Service Water Integrity program, as modified by the December 2010 commitment changes, provides reasonable assurance that silting cannot result in a loss of intended function of the service water system.
- 4) For LER 247/2013-004, and subsequently issued condition reports CR-IP2-2013-5053, CR-IP2-2014-1179, CR-IP2-2014-6504, and CR-IP2-2015-3500:
a) Describe what aspects of the Service Water Integrity Program will provide reasonable assurance that the intended function of these in-scope components will not be lost during the period of extended operation.
b) Provide an explanation for the continuing non-functionality of the radiation monitoring system given that 200 feet of the associated piping was replaced in 2014.
- 5) As it pertains to LER 286/2014-002:
a) State the basis for why the current Service Water Piping and Valve Flush procedure will provide reasonable assurance that the intended function of the service water system will be met. Address the effectiveness of the procedure in mitigating the leaks that it is intended to prevent, and discuss the basis for not needing to change the procedure to address recurring leaks in stagnant vent and drain piping.
b) Provide the bases establishing reasonable assurance that there are no other missing unit-specific aging management procedures being credited in the Service Water Integrity Program.
- 6) For the specific recurring internal corrosion category of cement-lined piping, state the minimum number of augmented inspections that will be performed in response to any identified leakage associated with corrosion. If augmented inspections will not be performed, provide an assessment based on observed corrosion rate ranges to provide reasonable assurance that structural integrity of the service water piping will be maintained throughout the period of extended operation.
- 7) For components managed by the Service Water Integrity Program:
a) List the past degradation due to loss of material issues that have not been evaluated under the corrective action program. Within the list provide the date, description of the issue, the basis for why it was not addressed in the corrective action program, and whether the issue was considered during the development of the program elements of the Service Water Integrity Program.
b) Provide the basis to justify the December 31, 2019 implementation date of this enhancement.
Discussion: Entergy requested that loss of material in Requests 2b and 7a be changed to state through-wall leakage. Entergy stated that the wording change would allow them to provide a more meaningful response by filtering out extraneous information. The NRC staff agreed to the request, noting that sufficient information should still be available to allow the staff to make its determination, even with the requested wording change.