Letter Sequence RAI |
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Initiation
- Request, Request, Request
- Acceptance, Acceptance, Acceptance, Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Results
Other: ML15327A213, ML16133A459, ML16133A499, ML17101A697, ML17207A165, ML17256A286, ML18212A032, ML18212A185, NL-16-138, Amendment 18 to License Renewal Application, NL-17-005, Actions Concerning License Renewal Commitments 41 and 42 in Response to LR-ISG-2016-01, Changes to Aging Management Guidance for Various Steam Generator Components., NL-17-019, Amendment to License Renewal Application - Reflecting Shortened License Renewal Terms, NL-17-157, Amendment 19 to License Renewal Application (LRA)
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MONTHYEARML15344A4362015-12-10010 December 2015 Lr Hearing - (External_Sender) Draft Audit Plan Edits Project stage: Request ML15327A2132015-12-21021 December 2015 Plan for the Regulatory Audit of the Service Water Integrity and Fire Water System Aging Management Programs Pertaining to the Indian Point Nuclear Generating Unit Nos. 2 and 3 LRA Project stage: Other 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 Project stage: Draft Other ML16133A4592016-06-15015 June 2016 Service Water and Fire Water Systems Aging Management Programs Audit Report for the Indian Point Nuclear Generating Unit Nos. 2 and 3 License Renewal Application Project stage: Other ML16133A4992016-06-21021 June 2016 Summary of Telephone Conference Call Held Between NRC and Entergy Concerning the Indian Point LRA Safety Review Project stage: Other ML16138A1942016-07-25025 July 2016 Request for Additional Information for the Review of License Renewal Application, Set 2016-01 Project stage: RAI ML16208A2772016-07-26026 July 2016 Lr Hearing - RAI Set 2016-01 Project stage: Request NL-16-122, Reply to Request for Additional Information for the Review of License Renewal Application, Set 2016-01 (CAC Nos. MD5407 and MD5408)2016-12-0202 December 2016 Reply to Request for Additional Information for the Review of License Renewal Application, Set 2016-01 (CAC Nos. MD5407 and MD5408) Project stage: Response to RAI NL-16-138, Amendment 18 to License Renewal Application2016-12-15015 December 2016 Amendment 18 to License Renewal Application Project stage: Other NL-17-005, Actions Concerning License Renewal Commitments 41 and 42 in Response to LR-ISG-2016-01, Changes to Aging Management Guidance for Various Steam Generator Components.2017-01-17017 January 2017 Actions Concerning License Renewal Commitments 41 and 42 in Response to LR-ISG-2016-01, Changes to Aging Management Guidance for Various Steam Generator Components. Project stage: Other NL-17-019, Amendment to License Renewal Application - Reflecting Shortened License Renewal Terms2017-02-0808 February 2017 Amendment to License Renewal Application - Reflecting Shortened License Renewal Terms Project stage: Other ML17046A2312017-03-0808 March 2017 Request for Additional Information for the Review of the Indian Point License Renewal - Set 2017-01 Project stage: RAI ML17082A3112017-04-11011 April 2017 Summary of Clarification Call with Entergy Regarding Follow-Up RAIs on ISG-2012-02 Project stage: RAI 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) Project stage: RAI 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) Project stage: RAI ML17101A6972017-04-25025 April 2017 License Renewal Clarification Call on Baffle Bolt Rai'S Project stage: Other NL-17-052, Reply to Request for Additional Information for the Review of the License Renewal Application, Set 2017-012017-05-0808 May 2017 Reply to Request for Additional Information for the Review of the License Renewal Application, Set 2017-01 Project stage: Response to RAI NL-17-053, Reply to Request for Additional Information for the Review of the Indian Point License Renewal Application RAI Set 2017-03 (CAC Nos. MD5407 and MD5408)2017-05-18018 May 2017 Reply to Request for Additional Information for the Review of the Indian Point License Renewal Application RAI Set 2017-03 (CAC Nos. MD5407 and MD5408) Project stage: Response to RAI NL-17-060, Reply to Requests for Additional Information for the Review of the Indian Point License Renewal Application RAI Set 2017-02 (CAC Nos. MD5407 and MD5408)2017-05-19019 May 2017 Reply to Requests for Additional Information for the Review of the Indian Point License Renewal Application RAI Set 2017-02 (CAC Nos. MD5407 and MD5408) Project stage: Response to RAI ML17128A3352017-05-23023 May 2017 Summary of Telephone Conference Call Between the NRC and Entergy Concerning RAIs Pertaining to IP2 and IP3 Project stage: RAI NL-17-061, Reply to Requests for Additional Information for the Review of the License Renewal Application RAI Set 2017-042017-05-24024 May 2017 Reply to Requests for Additional Information for the Review of the License Renewal Application RAI Set 2017-04 Project stage: Response to RAI NL-17-069, Reply to Requests for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application RAI Set 2017-05 (CAC Nos. MD5407 and MD5408)2017-06-0808 June 2017 Reply to Requests for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application RAI Set 2017-05 (CAC Nos. MD5407 and MD5408) Project stage: Response to RAI NL-17-074, Supplemental Information Regarding Reply to Request for Additional Information Set 2017-01 for the Review of the License Renewal Application (LRA)2017-06-27027 June 2017 Supplemental Information Regarding Reply to Request for Additional Information Set 2017-01 for the Review of the License Renewal Application (LRA) Project stage: Response to RAI ML17170A2862017-06-27027 June 2017 RAI Set 2017-06 Project stage: RAI 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 Project stage: RAI NL-17-084, Reply to Requests for Additional Information for the Review of the License Renewal Application. Re RAI Set 2017-062017-07-27027 July 2017 Reply to Requests for Additional Information for the Review of the License Renewal Application. Re RAI Set 2017-06 Project stage: Response to RAI NL-17-092, Amended Response to Request for Additional Information Question RAI 3.3.2-17-IP3-1 Re License Renewal Application RAI Set 2017-052017-07-27027 July 2017 Amended Response to Request for Additional Information Question RAI 3.3.2-17-IP3-1 Re License Renewal Application RAI Set 2017-05 Project stage: Response to RAI ML17207A1652017-09-0101 September 2017 License Renewal Audit Plan Regarding the Service Water Integrity Program Project stage: Other ML17250A2442017-09-20020 September 2017 Audit Report for IP Swi - Aug 2017 Project stage: Acceptance Review ML17191A4562017-09-20020 September 2017 06/08/2017 Telecon Summary Related to Indian Point License Renewal RAIs Associated with ISG-2016-01 Project stage: RAI 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 Project stage: RAI 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 Project stage: Other NL-17-127, Supplemental Information Regarding the Service Water Integrity Aging Management Program for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3 License Renewal Application (LRA) (CAC Nos. MD5407 and MD5408)2017-11-0808 November 2017 Supplemental Information Regarding the Service Water Integrity Aging Management Program for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3 License Renewal Application (LRA) (CAC Nos. MD5407 and MD5408) Project stage: Supplement NL-17-155, Re-Submittal of Supplemental Information Regarding the Service Water Integrity Aging Management Program for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3 License Renewal Application (LRA)2017-12-14014 December 2017 Re-Submittal of Supplemental Information Regarding the Service Water Integrity Aging Management Program for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3 License Renewal Application (LRA) Project stage: Supplement NL-17-157, Amendment 19 to License Renewal Application (LRA)2017-12-14014 December 2017 Amendment 19 to License Renewal Application (LRA) Project stage: Other NL-17-161, Supplemental Information Regarding the Service Water Integrity Aging Management Program for the Review of the Indian Point Nuclear Generating Units 2 and 3 License Renewal Application (LRA) (CAC Nos. MD5407 and MD5408)2017-12-21021 December 2017 Supplemental Information Regarding the Service Water Integrity Aging Management Program for the Review of the Indian Point Nuclear Generating Units 2 and 3 License Renewal Application (LRA) (CAC Nos. MD5407 and MD5408) Project stage: Supplement NL-18-010, Supplemental Information Regarding the Review of the License Renewal Application2018-02-26026 February 2018 Supplemental Information Regarding the Review of the License Renewal Application Project stage: Supplement ML18107A7592018-04-30030 April 2018 NUREG-1437, Suppl. 38, Vol. 5, Generic Environmental Impact Statement for License Renewal of Nuclear Plants Supplement 38 Regarding Indian Port Nuclear Generating Unit Nos. 2 and 3 Final. Project stage: Acceptance Review NL-18-030, Supplemental Information Associated with Amendment 19 to the License Renewal Application (LRA)2018-05-0808 May 2018 Supplemental Information Associated with Amendment 19 to the License Renewal Application (LRA) Project stage: Supplement NL-18-044, Supplemental Information Regarding the Review of the License Renewal Application2018-06-25025 June 2018 Supplemental Information Regarding the Review of the License Renewal Application Project stage: Supplement ML18200A3332018-08-0101 August 2018 NUREG-1930, Supp 3, Safety Evaluation Report Related to the License Renewal of Indian Point Nuclear Generating Plant, Units 2 and 3. Project stage: Approval ML18211A4842018-08-0707 August 2018 to NUREG-1930, Safety Evaluation Report Related to the License Renewal of Indian Point Nuclear Generating Plant, Units 2 and 3. Project stage: Approval ML18211A5842018-09-17017 September 2018 Issuance of Renewed Facility Operating License Nos. DPR 26 and DPR-64 for Indian Point Nuclear Generating Unit Nos. 2 and 3 (CAC Nos. MD5407 and MD5408) Project stage: Request ML18212A1882018-09-17017 September 2018 Renewed License Appendix C Project stage: Acceptance Review ML18212A1852018-09-17017 September 2018 Renewed Facility Operating License DPR-26, Technical Specifications, Appendix B Project stage: Other ML18212A1812018-09-17017 September 2018 Renewed Facility Operating License DPR-26, Technical Specifications, Appendix a Project stage: Acceptance Review ML18212A0322018-09-17017 September 2018 Records of Decision for the Indian Point Renewed Licenses Project stage: Other ML18211A5962018-09-17017 September 2018 Transmittal Letter - Issuance of Renewed Facility Operating License Nos. DPR-26 and DPR-64 for Indian Point Nuclear Generating Unit Nos. 2 and 3 (CAC Nos. MD5407 and MD5408) Project stage: Approval ML18211A5782018-09-17017 September 2018 Federal Register Notice - Announcing the Issuance of the Indian Point Renewed Licenses Project stage: Approval ML18213A1142018-09-17017 September 2018 Renewed Facility Operating License Project stage: Other 2017-04-25
[Table View] |
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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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1 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 27, 2017 LICENSEE: Entergy Nuclear Operations, Inc. (Entergy)
FACILITY: Indian Point Unit Nos. 2 and 3 (IP2 and IP3)
SUBJECT:
SUMMARY OF TELEPHONE CONFERENCE CALL HELD ON MAY 31, 2017 BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENTERGY NUCLEAR OPERATIONS, INC., CONCERNING REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE INDIAN POINT UNIT NOS. 2 AND 3, LICENSE RENEWAL APPLICATION (CAC. NOS. MD5407 AND MD5408) The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Entergy Nuclear Operations, Inc., held a telephone conference call on May 31, 2017, to discuss and clarify the staff's requests for additional information (RAIs) concerning the (IP2 and IP3) license renewal application to ensure compliance with 10 CFR Part 54. The telephone conference call was useful in clarifying the intent of the staff's RAIs. provides a listing of the participants and Enclosure 2 provides a listing of the RAIs discussed with the applicant.
The applicant had an opportunity to comment on this summary. Sincerely,
/RA/ William Burton, Senior Project Manager Project Management and Guidance Branch Division of Materials and License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-247 and 50-286
Enclosures:
- 1. List of Participants
- 2. List of Requests for Additional Information cc w/encls: Listserv
SUBJECT:
SUMMARY OF TELEPHONE CONFERENCE CALL HELD ON MAY 31, 2017 BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENTERGY NUCLEAR OPERATIONS, INC., CONCERNING REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE INDIAN POINT UNIT NOS. 2 AND 3, LICENSE RENEWAL APPLICATION (CAC. NOS. MD5407 AND MD5408)
DISTRIBUTION:
E-MAIL: PUBLIC RidsNrrDlmr Resource RidsNrrDlmrMrpb Resource RidsNrrDlmrRerp Resource RidsNrrDlmrRarb Resource RidsNrrDlmrMccb Resource RidsOgcMailCenter Resource RidsNrrPMIndianPoint Resource
SStuchell SBllom WBurton WHolston BAllik RGuzman STurk, OGC DRoth, OGC BHarris, OGC SBurnell, OPA DMcIntyre, OPA JWeil, OPA MGray, RI GDentel, RI DJackson, RI MModes, RI NSheehan, RI OPA DScrenci, RI OPA DTifft, RI NMcnamara, RI BHaagensen, RI GNewman, RI SRich, RI rlouie@entergy.com rburron@entergy.com avitale@entergy.com rwalpol@entergy.com
ADAMS Accession No: ML17160A165 OFFICE LA:DLMR PM:MRPB:DLMR BC:MRPB:DLMR PM:MRPB:DLMR NAME YEdmonds W Burton S Stuchell W Burton DATE 6/22/2017 6/26/2017 6/27/2017 6/27/2017 OFFICIAL RECORD COPY Enclosure 1 TELEPHONE CONFERENCE CALL INDIAN POINT UNIT NOS. 2 AND 3 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS MAY 31, 2017 PARTICIPANTS AFFILIATIONSBrian Allik U.S. Nuclear Regulatory Commission (NRC)William Burton NRCWilliam Holston NRCAlbert Wong NRCCharles Caputo Entergy Nuclear Operations, Inc. (Entergy)Lina Cossio-Gonzalez EntergyAlan Cox EntergyJohn Favara EntergyDavid Lach EntergyRichard Louie Entergy
Enclosure 2 REQUESTS FOR ADDITIONAL INFORMATION LICENSE RENEWAL APPLICATION MAY 31, 2017 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Entergy Nuclear Operations, Inc., (Entergy) held a telephone conference call on May 31, 2017, to discuss and clarify the following requests for additional information (RAIs) concerning the license renewal application (LRA) to ensure compliance with 10 CFR Part 54. RAI 3.0.3.1.2-1
Background:
GALL Report AMP XI.M41, "Buried and Underground Piping and Tanks," as modified by LR-ISG-2015-01, "Changes to Buried and Underground Piping and Tank Recommendations,"
includes the following recommendations to ensure compliance with 10 CFR Part 54.
1. The "preventive actions" program element recommends that coatings are provided for buried stainless steel or the applicant provides justification when coatings are not provided. 2. Table XI.M41-2, "Inspection of Buried and Underground Piping and Tanks," recommends one inspection of buried stainless steel piping during each 10-year period, commencing 10 years prior to the period of extended operation.
Issue:
The number of recommended inspections for buried stainless steel in GALL Report AMP XI.M41, as modified by LR-ISG-2015-01, is based on coatings being provided or adequate justification when coatings are not provided. It is unclear to the staff if buried stainless steel piping is coated, and if it is not coated, the justification for why coatings do not need to be provided. Request:
State if buried stainless steel piping is coated. If buried stainless steel piping is not coated, provide justification (e.g., increased extent or frequency of inspections, soil parameters) for why coatings do not need to be provided.
Discussion Entergy had no questions and understands what the staff expects.
RAI 3.0.3.1.2-2
Background:
Attachment 1 of letter dated April 28, 2017, states that polyvinyl chloride (PVC) piping exposed to soil has no aging effects due to the lack of stressors in a soil environment and non-aggressive soil as confirmed by soil samples.
GALL Report AMP XI.M41, as modified by LR-ISG-2015-01, includes the following recommendations:
1. The "parameters monitored or inspected" program element recommends visual inspections of the external surface condition of polymeric materials to detect loss of material due to wear. 2. Table XI.M41-2, "Inspection of Buried and Underground Piping and Tanks," recommends one inspection of buried polymeric piping when backfill is in accordance with the "preventive actions" program element, and the smaller of one percent of the length of the pipe or two inspections when backfill is not in accordance with the "preventive actions" program element. Issue: As noted above, GALL Report AMP XI.M41, as modified by LR-ISG-2015-01, recommends reducing the number of inspections for polymeric piping based on backfill quality, but does not recommend eliminating inspections based on soil aggressiveness. It is unclear to the staff how lack of stressors in a soil environment and non-aggressive soil as confirmed by soil samples precludes the need to perform visual inspections to detect loss of material due to wear.
Request: State the basis for why loss of material due to wear is not an aging effect requiring management for PVC piping exposed to soil. Alternatively, revise the program to address loss of material due to wear for buried PVC piping. Discussion Entergy had no questions and understands what the staff expects.
RAI 3.0.3.1.2-3
Background:
of letter dated April 28, 2017, states "[c]athodic protection levels are maintained as described in NL-13-132 [response to RAI 3.0.3.1.2-4a dated October 3, 2013] and soil conditions are not aggressive such that cracking is not an aging effect requiring management. In addition, the stainless steel piping in the program operates at temperatures below 140°F, which is the threshold for stress corrosion cracking in stainless steel."
GALL Report AMP XI.M41, as modified by LR-ISG-2015-01, provides the following recommendations: 1. Stainless steel components can experience stress corrosion cracking when exposed to soil due to the potential presence of halides. 2. Steel components can experience stress corrosion cracking when exposed to a carbonate/bicarbonate environment depending on cathodic polarization level, temperature, and pH. See NACE SP0169-2013, "Control of External Corrosion on Underground or Submerged Metallic Piping Systems," Figure 2, "SCC [stress corrosion cracking] Range of Pipe Steel in Carbonate/Bicarbonate Environments." Issue: 1. The threshold temperature for SCC of stainless steel in a treated water environment (i.e., water whose chemistry has been altered and is maintained) is 140°F; however, due to the potential presence of halides, SCC is an applicable aging effect for stainless steel piping exposed to soil. 2. The subject letter does not address cracking of steel exposed to soil, which can occur in a carbonate/bicarbonate environment depending on cathodic polarization level, temperature, and pH. It is unclear to the staff if steel piping is exposed to a carbonate/bicarbonate environment, and if it is, how factors such as cathodic polarization level, temperature, and pH preclude the need to manage steel piping for cracking.
Request: 1. For buried stainless steel components, state the specific soil parameters (e.g., bacteria, presence of halogens) and results that demonstrate that cracking will not occur.
Alternatively, revise the program to address cracking of buried stainless steel piping.
2. State the basis for why cracking is not an aging effect requiring management for steel piping exposed to soil. Alternatively, revise the program to address cracking of buried steel piping.
Discussion Entergy had a question regarding the background section of the draft RAI which stated that steel and stainless steel components can experience stress corrosion cracking dependent on the cathodic protection polarization level, temperature, pH, etc. Entergy noted that it was unclear which parameters (i.e., cathodic protection polarization level, temperature, pH ) were applicable for stainless steel and which parameters were applicable for steel. The staff agreed to clarify the conditions where steel and stainless steel components can experience stress corrosion cracking as shown in the background section above. Entergy had no additional questions and understands what the staff expects. RAI 3.0.3.1.2-4
Background:
As amended by letter dated April 28, 2017, LRA Section B.1.6, "Buried Piping and Tanks Inspection," states "[i]f future inspections reveal significant coating damage caused by non-conforming backfill, then Entergy will double the inspection sample size up to an increase of five (5) inspections."
GALL Report AMP XI.M41, as modified by LR-ISG-2015-01, states that where the coatings, backfill or the condition of exposed piping does not meet acceptance criteria such that the depth or extent of degradation of the base metal could have resulted in a loss of pressure boundary function when the loss of material rate is extrapolated to the end of the period of extended operation, an increase in the sample size is conducted.
Issue: The staff noted that degradation of the base metal could occur for reasons besides significant coating damage caused by non-conforming backfill (e.g., coating degradation based on coating service life). Significant coating damage caused by non-conforming backfill is only an example of how degradation of the base metal could occur. In addition, in contrast to AMP XI.M41, which defines the degree of degradation (i.e., loss of pressure boundary function), "significant coating damage" is not defined.
Request: State the basis for why an increase in inspection sample size will only occur when significant coating damage caused by non-conforming backfill is revealed. Alternatively, revise the program to be consistent with LR-ISG-2015-01 regarding criteria for increasing inspection sample size.
Discussion Entergy had no questions and understands what the staff expects.
RAI 3.0.3.1.2-5
Background:
As amended by letter dated April 28, 2017, LRA Sections A.2.1.5 and A.3.1.5 (Buried Piping and Tanks Inspection program (UFSAR) summary descriptions for Units 2 and 3, respectively) were revised in response to the issuance of LR-ISG-2015-01. The UFSAR summary description issued in LR-ISG-2015-01 includes the following recommendations:
1. This program manages the aging effects of cracking. 2. Inspections are conducted by qualified individuals. 3. Where the coatings, backfill or the condition of exposed piping does not meet acceptance criteria such that the depth or extent of degradation of the base metal could have resulted in a loss of pressure boundary function when the loss of material rate is extrapolated to the end of the period of extended operation, an increase in the sample size is conducted.
Issue: The staff noted that aspects of the UFSAR summary description issued in LR-ISG-2015-01 (bulletized above) were not included in the revised LRA Sections A.2.1.5 and A.3.1.5. The licensing basis for this program for the period of extended operation may not be adequate if the applicant does not incorporate this information in its UFSAR supplement.
Request: State the basis for not including aspects of the UFSAR Summary Description issued in LR-ISG-2015-01 (bulletized above) in the revised LRA Sections A.2.1.5 and A.3.1.5. Alternatively, revise LRA Sections A.2.1.5 and A.3.1.5 to be consistent with LR-ISG-2015-01.
Discussion Entergy had no questions and understands what the staff expects.