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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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 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 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 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 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 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 ML13043A5272013-02-26026 February 2013 PM Change Letter - February 2013 Project stage: Other ML13077A2842013-03-0808 March 2013 Correction PM Letter Indian Point 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 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 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 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 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 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 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 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 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 ML14217A2062014-08-14014 August 2014 Respect for Withholding Information from Public Disclosure Project stage: Other 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 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 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 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 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: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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Text
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 staffs 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 staffs 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
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
TELEPHONE CONFERENCE CALL INDIAN POINT UNIT NOS. 2 AND 3 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS MAY 31, 2017 PARTICIPANTS AFFILIATIONS Brian Allik U.S. Nuclear Regulatory Commission (NRC)
William Burton NRC William Holston NRC Albert Wong NRC Charles Caputo Entergy Nuclear Operations, Inc. (Entergy)
Lina Cossio-Gonzalez Entergy Alan Cox Entergy John Favara Entergy David Lach Entergy Richard Louie Entergy Enclosure 1
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:
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.
Enclosure 2
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.