Letter Sequence Other |
---|
|
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
|
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] |
|
---|
Category:Letter type:NL
MONTHYEARNL-21-034, Notification of Expected Date of Transfer of Ownership of Nuclear Units to Holtec Indian Point 2, LLC and Holtec Indian Point 3, LLC; and Notification of Receipt of All Required Regulatory Approvals2021-05-26026 May 2021 Notification of Expected Date of Transfer of Ownership of Nuclear Units to Holtec Indian Point 2, LLC and Holtec Indian Point 3, LLC; and Notification of Receipt of All Required Regulatory Approvals NL-21-039, Response to Request for Additional Information - License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary2021-05-20020 May 2021 Response to Request for Additional Information - License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary NL-21-033, Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel2021-05-11011 May 2021 Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel NL-21-032, Termination of Emergency Response Data System Feed to the U.S. Nuclear Regulatory Commission at Indian Point Energy Center2021-05-11011 May 2021 Termination of Emergency Response Data System Feed to the U.S. Nuclear Regulatory Commission at Indian Point Energy Center NL-21-005, Cancellation of Commitments Related to Beyond-Design-Basis External Events Seismic and Flooding Actions2021-05-11011 May 2021 Cancellation of Commitments Related to Beyond-Design-Basis External Events Seismic and Flooding Actions NL-21-030, Submittal of 2020 Annual Radiological Environmental Operating Report2021-05-0606 May 2021 Submittal of 2020 Annual Radiological Environmental Operating Report NL-21-027, Registration of Spent Fuel Cask Use2021-04-20020 April 2021 Registration of Spent Fuel Cask Use NL-21-021, Registration of Spent Fuel Cask Use2021-04-19019 April 2021 Registration of Spent Fuel Cask Use NL-21-017, Pre-Notice of Disbursement from Decommissioning Trusts2021-04-0808 April 2021 Pre-Notice of Disbursement from Decommissioning Trusts NL-21-010, Submittal of 2020 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report2021-02-17017 February 2021 Submittal of 2020 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report NL-21-006, Relief Request IP3-ISI-RR-16, Proposed Alternative to American Society of Mechanical Engineers Code Case N-513-4 Inspection Requirement2021-02-10010 February 2021 Relief Request IP3-ISI-RR-16, Proposed Alternative to American Society of Mechanical Engineers Code Case N-513-4 Inspection Requirement NL-21-014, Response to 2nd Round Request for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2021-01-26026 January 2021 Response to 2nd Round Request for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device NL-20-082, Notice of Planned Transfer of Decommissioning Funds2020-12-14014 December 2020 Notice of Planned Transfer of Decommissioning Funds NL-20-081, Pre-Notice of Disbursement from Decommissioning Trusts2020-12-0909 December 2020 Pre-Notice of Disbursement from Decommissioning Trusts NL-20-080, Report in Accordance with 10 CFR 71.95(a) for Failure to Comply with Certificate of Compliance No. 71-93212020-11-19019 November 2020 Report in Accordance with 10 CFR 71.95(a) for Failure to Comply with Certificate of Compliance No. 71-9321 NL-20-079, (IP2 and IP3) - Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic2020-11-12012 November 2020 (IP2 and IP3) - Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic NL-20-077, Submittal of Quality Assurance Program Manual Revision 22020-11-0909 November 2020 Submittal of Quality Assurance Program Manual Revision 2 NL-20-078, Response to Requests for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2020-11-0909 November 2020 Response to Requests for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device NL-20-076, Revision of Commitment Related to Nuclear Reactor Safeguards Interim Compensatory Measure - Section B.5.b Issue Regarding Spent Fuel Dispersal2020-11-0202 November 2020 Revision of Commitment Related to Nuclear Reactor Safeguards Interim Compensatory Measure - Section B.5.b Issue Regarding Spent Fuel Dispersal NL-20-069, One-time Scheduler Exemption Request from 10 CFR 50, Appendix E Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Public Health Emergency2020-10-0808 October 2020 One-time Scheduler Exemption Request from 10 CFR 50, Appendix E Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Public Health Emergency NL-20-070, Response to Requests for Additional Information, License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2020-10-0202 October 2020 Response to Requests for Additional Information, License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device NL-20-067, Redacted Version of Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline2020-09-16016 September 2020 Redacted Version of Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline NL-20-064, 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments2020-09-0101 September 2020 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments NL-20-060, Status of Remaining Actions for Generic Letter 2004-022020-08-11011 August 2020 Status of Remaining Actions for Generic Letter 2004-02 NL-20-057, Cancellation of Commitment Related to Large Break LOCA Reanalysis2020-07-30030 July 2020 Cancellation of Commitment Related to Large Break LOCA Reanalysis NL-20-0851, 30-Day 10 CFR 21 Notification - Continuously Energized Eaton D26 Relays Could Fail to Deenergize Because of an Organic C3 Insulating Material2020-07-22022 July 2020 30-Day 10 CFR 21 Notification - Continuously Energized Eaton D26 Relays Could Fail to Deenergize Because of an Organic C3 Insulating Material NL-20-051, Submittal of Quality Assurance Program Manual, Revision 1 for the Indian Point Energy Center2020-07-0707 July 2020 Submittal of Quality Assurance Program Manual, Revision 1 for the Indian Point Energy Center NL-20-052, Unsatisfactory 10 CFR 26 Fitness-For-Duty Blind Performance Testing Results2020-07-0707 July 2020 Unsatisfactory 10 CFR 26 Fitness-For-Duty Blind Performance Testing Results NL-20-012, Application to Revise Provisional Operating License and Technical Specifications2020-06-30030 June 2020 Application to Revise Provisional Operating License and Technical Specifications NL-20-050, Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline2020-06-24024 June 2020 Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline NL-20-041, Registration of Unit 3 Spent Fuel Cask Use2020-05-13013 May 2020 Registration of Unit 3 Spent Fuel Cask Use NL-20-042, Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel2020-05-12012 May 2020 Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel NL-20-033, Technical Specifications Proposed Change - Permanently Defueled Technical Specifications2020-04-28028 April 2020 Technical Specifications Proposed Change - Permanently Defueled Technical Specifications NL-20-038, Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline2020-04-23023 April 2020 Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline NL-20-035, Response to Request for Additional Information - Temporary Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic2020-04-16016 April 2020 Response to Request for Additional Information - Temporary Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic NL-20-034, Temporary Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic2020-04-13013 April 2020 Temporary Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic NL-20-021, Proposed License Amendment to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2020-03-24024 March 2020 Proposed License Amendment to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device NL-20-020, Submittal of 2019 Annual Fitness for Duty Performance Data Report Update2020-02-26026 February 2020 Submittal of 2019 Annual Fitness for Duty Performance Data Report Update NL-20-015, Submittal of 2019 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report2020-02-10010 February 2020 Submittal of 2019 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report NL-20-008, Transmittal of Presentation Slides for Partially Closed Pre-Submittal Meeting to Discuss a Planned License Amendment Request to Replace the Fuel Handling Building Crane2020-01-0606 January 2020 Transmittal of Presentation Slides for Partially Closed Pre-Submittal Meeting to Discuss a Planned License Amendment Request to Replace the Fuel Handling Building Crane NL-19-094, 2018 Annual 10 CFR 50.46 Emergency Core Cooling System Evaluation Changes Report2019-12-16016 December 2019 2018 Annual 10 CFR 50.46 Emergency Core Cooling System Evaluation Changes Report NL-19-084, Application for Order Consenting to Transfers of Control of Licenses and Approving Conforming License Amendments2019-11-21021 November 2019 Application for Order Consenting to Transfers of Control of Licenses and Approving Conforming License Amendments NL-19-093, Proposed Technical Specifications (TS) Changes - Indian Point Nuclear Generating Unit 3 TS SR 3.7.7.2 and TS 3.7.6, Required Action A.12019-11-21021 November 2019 Proposed Technical Specifications (TS) Changes - Indian Point Nuclear Generating Unit 3 TS SR 3.7.7.2 and TS 3.7.6, Required Action A.1 NL-19-092, Request for Rescission of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2019-11-20020 November 2019 Request for Rescission of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) NL-19-043, Request for Partial Exemption from Record Retention Requirements in 10 CFR 50.122019-10-22022 October 2019 Request for Partial Exemption from Record Retention Requirements in 10 CFR 50.12 NL-19-073, Request for Relaxation of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2019-10-22022 October 2019 Request for Relaxation of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) NL-19-078, Supplement to Technical Specifications Proposed Change - Permanently Defueled Technical Specifications2019-10-22022 October 2019 Supplement to Technical Specifications Proposed Change - Permanently Defueled Technical Specifications NL-19-091, Independent Spent Fuel Storage Installation (Isfsi), Registration of Spent Fuel Cask Use2019-10-17017 October 2019 Independent Spent Fuel Storage Installation (Isfsi), Registration of Spent Fuel Cask Use NL-19-090, Registration of Unit 2 Spent Fuel Cask Use2019-10-0909 October 2019 Registration of Unit 2 Spent Fuel Cask Use NL-19-079, 50.59(d)(2) Summary Report of Changes, Tests and Experiments2019-09-26026 September 2019 50.59(d)(2) Summary Report of Changes, Tests and Experiments 2021-05-06
[Table view] |
Text
Enterav Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Tel (914) 254-2055 Fred Dacimo Vice President Operations License Renewal NL-14-013 January 28, 2014 U.S. Nuclear Regulatory Commission Document Control Desk 11545 Rockville Pike, TWFN-2 F1 Rockville, MD 20852-2738
SUBJECT:
Additional Information Regarding the License Renewal Application -
Action Item 7 from MRP-227-A Indian Point Nuclear Generating Unit Nos. 2 & 3 Docket Nos. 50-247 and 50-286 License Nos. DPR-26 and DPR-64
REFERENCES:
- 1. NRC letter, "Summary of Conference Call held on December 18, 2013, between the U.S. Nuclear Regulatory Commission and Entergy Nuclear Operations, Inc., Concerning Applicant/Licensee Action Item 7 from MRP-227-A" dated January 9, 2014.
- 2. Entergy letter, NL-13-122, "Reply to Request for Additional Information Regarding the License Renewal Application" dated September 27, 2013.
Dear Sir or Madam:
Entergy Nuclear Operations, Inc is providing, in the enclosure, additional information pertaining to NRC review of the License Renewal Application (LRA) for Indian Point 2 (IP2) and Indian Point 3 (IP3). The additional information is being provided as a follow up to a recent conference call between Entergy and the NRC regarding Action Item 7 from MRP-227-A, as documented in Reference 1. The NRC letter notes that the NRC is considering an alternative approach for cast austenitic stainless steel (CASS) components that may impact Commitment 47. This alternative approach would be based on ferrite content derived from certified material test reports (CMTRs) for CASS components. There are 96 columns with CASS caps in the lower internals assembly of each Indian Point unit. As noted on the call, CMTRs are available for all of the IP3 CASS caps. As documented in the enclosure attached to this letter, Entergy can now confirm that CMTRs are also available for all of the IP2 CASS caps, and that the IP2 and IP3 column caps are of low molybdenum CF8 material. As noted in Reference 2, no special casting processes were designated; thus, it was conservatively assumed that the lower core support column caps were statically cast.
Docket Nos. 50-247 & 50-286 NL-14-013 Page 2 of 2 There are no new regulatory commitments in this submittal.
I declare Ondeq penalty of perjury that the foregoing is true and correct. Executed on 2014.
Since FRD/rw
Enclosure:
LTR-RIAM-14-2, Revision 0, Attachment 1, "Summary of the Evaluation of Indian Point Units 2 and 3, Lower Internals Assembly, Column Caps - Ferrite Content and Susceptibility to Thermal Embrittlement" cc: Mr. William Dean, Regional Administrator, NRC Region I Mr. Sherwin E. Turk, NRC Office of General Counsel, Special Counsel Mr. Dave Wrona, NRC Branch Chief, Engineering Review Branch I Ms. Kimberly Green, NRC Sr. Project Manager, Division of License Renewal Mr. Douglas Pickett, NRR Senior Project Manager Ms. Bridget Frymire, New York State Department of Public Service NRC Resident Inspector's Office Mr. Francis J. Murray, Jr., President and CEO NYSERDA
ENCLOSURE TO NL-14-013 LTR-RIAM-14-2, Revision 0, Attachment 1, "Summary of the Evaluation of Indian Point Units 2 and 3, Lower Internals Assembly, Column Caps - Ferrite Content and Susceptibility to Thermal Embrittlement" ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 & 3 DOCKET NOS. 50-247 AND 50-286
Westinghouse Non-Proprietary Class 3 Attachment I Page 1 of 5 Our ref: LTR-RIAM-14-2, Rev. 0 January 10, 2014 : Summary of the Evaluation of Indian Point Units 2 and 3, Lower Internals Assembly, Column Caps - Ferrite Content and Susceptibility to Thermal Embrittlement
© 2014 Westinghouse Electric Company LLC All Rights Reserved
Westinghouse Non-Proprietary Class 3 Attachment I Page 2 of 5 Our ref: LTR-RIAM- 14-2, Rev. 0 January 10, 2014 Summary of the Evaluation of Indian Point Units 2 and 3, Lower Internals Assembly, Column Caps - Ferrite Content and Susceptibility to Thermal Embrittlement Background and Purpose The Reactor Vessel Internals (RVI) Program at Indian Point Units 2 and 3 is based on MRP-227-A (Reference 1) and is the base program that addresses the RVI components that require aging management and it specifies inspection requirements. The Thermal Aging and Neutron Irradiation Embrittlement of Cast Austenitic Stainless Steel (CASS) Program at Indian Point (IPEC LRA (Reference 2) augments the RVI program by evaluating the potential susceptibility to thermal embrittlement (TE) of plant-specific CASS components.
The delta ferrite content of the CASS component is calculated using Hull's formula (as applied to CASS material in Reference 3) with input of element percentages from the component-specific chemistry from either the material specification or from the certified material test report (CMTR) for the material. The NRC screening criteria for TE (Reference 4, Table 2) is based on chemistry, casting method, and the delta-ferrite content.
This is an evaluation of the susceptibility to TE of the Indian Point Units 2 and 3 CASS column caps.
These CASS column caps are part of the support columns in the lower internals assembly. There are 96 columns with CASS caps in the lower internals assembly of each Indian Point Unit. Figure 1 is an illustration of the column with its CASS cap. This Indian Point-specific component, lower internals assembly - column cap, correlates to the MRP-227-A, lower support assembly, lower support column bodies (cast) component.
- Figure 1 Support Column with CASS Cap (cast cap is shown as shaded)
Westinghouse Non-Proprietary Class 3 Attachment I Page 3 of 5 Our ref: LTR-RIAM-14-2, Rev. 0 January 10, 2014 Indian Point Unit 2. Lower Internals Assembly Column Cap - Ferrite Content and Thermal Embrittlement Evaluation The Indian Point Unit 2 lower internals assembly - column caps were cast from ASTM A296, Grade CF8 material (Reference 5). The elemental percentages from the CMTRs, for the Indian Point Unit 2, CASS column caps, are input into Hull's formula (per Reference 3 guidance) to calculate the delta ferrite content of the CASS material. The Indian Point Unit 2 CMTRs do not list the element percentage for nitrogen; thus, per the guidance of Reference 3, nitrogen is assumed to be 0.04 percent. The CMTRs do not list an elemental percentage for molybdenum. ASTM A296, Grade CF8 did not have a requirement for percent molybdenum and that specification was withdrawn in 1977. The current ASTM A351-13, Grade CF8 chemistry requirements specify a maximum of 0.5 percent molybdenum; thus, this maximum value is input into Hull's formula.
The Westinghouse records show that six different heats of material were used to produce 97 CASS caps that were released for use in the fabrication of the 96 Indian Point Unit 2 columns in the lower internals assembly columns. The records do not show exactly which cast cap, out of the 97, was used on each of the 96 columns. The calculated ferrite contents are listed in Table 1. The maximum ferrite content is 14.6 percent, the minimum is 6.4 percent, and the mean ferrite content is 10.5 percent.
The TE screening of Indian Point Unit 2, CASS column caps is shown in Table 2. The Indian Point Unit 2 column caps are of low molybdenum CF8 material, are assumed static cast, and have maximum ferrite content 14.6 percent which is less than the 20 percent screening level. Therefore, consistent with the NRC criteria of Reference 4, it is concluded that the Indian Point Unit 2 lower internals assembly, column caps are not susceptible to TE.
Table 1 Indian Point Unit 2 Lower Internals Assembly - Column Caps Heat and Ferrite Content Quantity of Calculated Ferrite Content Supplier Heat Number CASS Caps (Percent)
L14 23 8.1 L25 25 12.4 L35 20 14.6 L54 14 6.4 L60 7 10.3 L217 8 7.8 Table 2 TE Screening of Indian Point Unit 2 Lower Internals Assembly -
Column Cans
Westinghouse Non-Proprietary Class 3 Attachment I Page 4 of 5 Our ref: LTR-RIAM-14-2, Rev. 0 January 10, 2014 Indian Point Unit 3. Lower Internals Assembly Column Cap - Ferrite Content and Thermal Embrittlement Evaluation The Indian Point Unit 3 lower internals assembly - column caps were cast from ASTM A296 Grade CF8 material (Reference 6). The elemental percentages from the CMTRs, for the Indian Point Unit 3, CASS column caps, are input into Hull's formula (per Reference 3 guidance) to calculate the delta ferrite content of the CASS material. The Indian Point Unit 3 CMTRs do not list the element percentage for nitrogen; thus, per the guidance of Reference 3, nitrogen is assumed to be 0.04 percent. The CMTRs typically do not list an elemental percentage for molybdenum. There are isolated cases where the Indian Point Unit 3 records do list the molybdenum percentage, which ranges from 0.14 to 0.36 percent, depending on the material heat. Where the CMTRs do list the molybdenum percentage, the listed value is used in the calculation of ferrite content. ASTM A296, Grade CF8 did not have a requirement for percent molybdenum and the specification was withdrawn in 1977; thus, where the CMTRs do not list molybdenum, the current ASTM A351-13, Grade CF8 chemistry requirement of maximum 0.5 percent molybdenum is input into Hull's formula.
The Westinghouse records show that seven different heats of material were used to produce 97 CASS caps that were released for use in the fabrication of the 96 Indian Point Unit 3 lower internals assembly columns. The records do not show exactly which cast cap, out of the 97, was used on each of the 96 columns. The calculated ferrite contents are listed in Table 3. The maximum ferrite content is 11.8 percent, the minimum is 5.2 percent, and the mean ferrite content is 8.3 percent.
The TE screening of Indian Point Unit 3, CASS column caps is shown in Table 4. The Indian Point Unit 3, column caps are of low molybdenum CF8 material, are assumed static cast, and have maximum ferrite content 11.8 percent which is less than the 20 percent screening level. Therefore, consistent with the NRC criteria of Reference 4, it is concluded that the Indian Point Unit 3 lower internals assembly, column caps are not susceptible to TE.
Table 3 Indian Point Unit 3 Lower Internals Assembly - Column Caps Heat and Ferrite Content Supplier Heat Number Quantity of CASS Calculated Ferrite Content Caps (Percent)
L335 13 8.9 L347 21 7.7 L353 18 11.8 L355 6 7.9 L364 22 5.2 L370 4 5.3 L373 13 10.0 Table 4 TE Screening of Indian Point Unit 3 Lower Internals Assembly -
Column Caps
Westinghouse Non-Proprietary Class 3 Attachment I Page 5 of 5 Our ref: LTR-RIAM-14-2, Rev. 0 January 10, 2014 References
- 1. Materials Reliability Program. PressurizedWater ReactorInternals Inspection and Evaluation Guidelines (MRP-227-A). EPRI, Palo Alto, CA: 2011. 1022863.
- 2. Entergy Letter, NL-12-037, "License Renewal Application - Revised Reactor Vessel Internals Program and Inspection Plan Complaint with MRP-227-A, Indian Point Nuclear Generating Unit Nos. 2 and 3, Docket Nos. 50-247 and 50-286, License Nos. DPR-26 and DPR-64," February 17, 2012.
- 3. U.S. Nuclear Regulatory Commission NUREG/CR-4513, "Estimation of Fracture Toughness of Cast Stainless Steels During Thermal Aging in LWR Systems," August 1994. (Available NRC ADAMS Accession No. ML052360554).
- 4. U.S. Nuclear Regulatory Commission License Renewal Issue No. 98-0030, "Thermal Aging Embrittlement of Cast Austenitic Stainless Steel Components," May 19, 2000. (Available NRC ADAMS Accession No. ML003717179).
- 5. Westinghouse Letter IPP-1 3-44, "Support for Reactor Vessel Internals Aging Management RAI Project Final Response to RAI 1 B Items 1, 2 and 3," October 16, 2013.
- 6. Westinghouse Letter INT-13-51, "Support for Reactor Vessel Internals Aging Management RAI Project Final Response to RAI 1 B Items 1, 2 and 3," October 16, 2013.