Letter Sequence Other |
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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
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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-19-093, 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-19-084, 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-19-092, 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-19-080, .48(d)(2) Summary Report2019-09-26026 September 2019 .48(d)(2) Summary Report 2021-05-06
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML23024A0462023-01-17017 January 2023 License Amendment Request for the Independent Spent Fuel Storage Installation-Only Security, Training and Qualification, Safeguards Contingency Plan ML22332A0482022-11-22022 November 2022 New York State Alyse Peterson Comments on Completion of Emergency Planning Nd License Amendment Request Prior to Spent Fuel Transfer from Spent Fuel Pools to Casts (Dockets 50-003, 50-247, 50-286) ML22321A1482022-11-17017 November 2022 License Amendment Request to Approve the Independent Spent Fuel Storage Installation-Only Emergency Plan ML22306A1262022-11-0202 November 2022 License Amendment Request to Revise Indian Point Nuclear Generating Unit Nos. 2 and 3 Renewed Facility Licenses and Permanently Defueled Technical Specifications and IP3 Appendix C Technical Specifications to Reflect Permanent Removal of Sp ML22214A1282022-08-0202 August 2022 License Amendment Request to Revise Indian Point Nuclear Generating Unit No. 2 Permanently Defueled Technical Specifications to Modify Staffing Requirements Following Transfer of Spent Fuel to Dry Storage ML22140A1262022-05-20020 May 2022 License Amendment Request - Revise License Condition to Eliminate Cyber Security Plan Requirements ML22035A1212022-02-0404 February 2022 Revision to Holtec Decommissioning International, LLC, License Amendment Request to Revise the Emergency Plan and Emergency Action Level Scheme to Address the Permanently Defueled Condition ML21356B7042021-12-22022 December 2021 License Amendment Request to Revise the Emergency Plan and Emergency Action Level Scheme to Address the Permanently Defueled Condition ML21271A2592021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Copy of Calculations in Support of FCS LTP Chapter 6 Revision 0 ML21271A4082021-08-0303 August 2021 License Amendment Request (LAR) 21-01, FCS Buried Pipe Insitu Uncertainty Report Eu-152 ML21271A2692021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 6 19 E. A. Napier, Hanford Environmental Dosimetry Upgrade Project, Gen II the Hanford Environmental Radiation D-1 ML21271A2682021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 6 12 FC-20-006, Rev 0, End State Concrete Surface Areas Volumes, CAC2 ML21271A2672021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 6 3 Omaha Public Power District, Fort Calhoun Station Unit 1, Defueled Safety Analysis Report CAC2 ML21271A2652021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 6 7 FC-20-007, Fort Calhoun Station Potential Radionuclides of Concern CAC2 ML21271A2622021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 6 2 Radiation Safety and Control Services, Tsd 20-001, Historical Site Assessment for Fort Calhoun Station - F-1 ML21271A2612021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 6 1 Haley & Aldrich, Hydrogeological Conceptual Site Model, Rev. 2, Fort Calhoun Station, Blair, Ne, 2021 CAC2 ML21271A2582021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 6 8 Radiation Safety and Control Services, Tsd 21-043, Radionuclides of Concern in Support of the Fort Calhoun -1 ML21271A2192021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 5 12 FC-20-007, Fort Calhoun Station Potential Radionuclides of Concern CAC2 ML21271A5102021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Am-241 Soil Uncertainty Report ML21271A2142021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 5 17 Omaha Public Power District, NO-FC-10, Quality Assurance Topical Report CAC2 ML21271A2112021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 5 18 Radiation Safety and Control Services, Tsd 21-043, Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan ML21271A2102021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 4 3 Omaha Public Power District, Fort Calhoun Station Unit 1, Defueled Safety Analysis Report CAC 2 ML21271A2002021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 3 14 Backfill Attachment Final CAC 2 ML21271A1992021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 3 16 Omaha Public Power District, Offsite Dose Calculation Manual CAC 2 ML21271A1962021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 3, 1, Omaha Public Power District, Defueled Safety Analysis Report CAC 2 ML21271A1932021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 3 18 Omaha Public Power District, FC-20-012, Fort Calhoun Station Decommissioning Project Radiological Character 1 ML21271A5992021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 8, 12, Omaha Public Power District, FCS-SAF-103, FCS Deconstruction Health and Safety Plan CAC2 ML21271A1442021-08-0303 August 2021 License Amendment Request (LAR) 21-01, FCS LTP Rev 0. Final - All ML21271A4982021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Ce-144 Soil Uncertainty Report ML21271A1832021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 2 11 Omaha Public Power District, Fort Calhoun Station Unit 1, Defueled Safety Analysis Report cac2 ML21271A1802021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 2 19, Omaha Public Power District, FC-20-012, Fort Calhoun Station Decommissioning Project Radiological Characterization Report ML21271A1502021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Defueled Safety Analysis Report ML21271A4802021-08-0303 August 2021 License Amendment Request (LAR) 21-01, C-14 Soil Uncertainty Report ML21271A1762021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 2 5 Omaha Public Power District, FCSD-RA-LT-200, Characterization Survey Plan CAC2 ML21271A1732021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Omaha Public Power District, FCSD-RA-LT-100, Quality Assurance Project Plan for the License Termination Plan Development~1 ML21271A1432021-08-0303 August 2021 License Amendment Request (LAR) 21-01, LIC-21-0005 LTP Cover Letter Final Fisher Signature ML21271A1722021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 2 8 Omaha Public Power District, Offsite Dose Calculation Manual cac2 ML21271A1532021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Chapter 1 7 SUNSI EA 12-10, Flood Assessment HDR Report Placeholder Akb ML21271A5032021-08-0303 August 2021 License Amendment Request (LAR) 21-01, Ce-144 Soil Regression and Correlation Report ML21271A1752021-08-0202 August 2021 License Amendment Request (LAR) 21-01, Chapter 2 14 Radiation Safety and Control Services, Tsd 21-043, Radionuclides of Concern in Support of the Fort Calhoun License Termination Plan ML21271A1982021-07-24024 July 2021 License Amendment Request (LAR) 21-01, Chapter 3, 6, Omaha Public Power District, FC-21-002, Description of Embedded Piping, Penetrations, and Buried Pipe to Remain in Fort Calhoun End State ML21271A2082021-07-24024 July 2021 License Amendment Request (LAR) 21-01, Chapter 5, 10, Omaha Public Power District, FC-21-002, Description of Embedded Piping, Penetrations, and Buried Pipe to Remain in Fort Calhoun End State ML21271A2602021-07-24024 July 2021 License Amendment Request (LAR) 21-01, Chapter 6 4, Omaha Public Power District, FC-21-002, Description of Embedded Piping, Penetrations, and Buried Pipe to Remain in Fort Calhoun End State ML21271A2062021-07-23023 July 2021 License Amendment Request (LAR) 21-01, Chapter 4 10 Omaha Public Power District FC-20-006 - End State Concrete Surface Areas Volumes, Rev 0 CAC 2 ML21271A2132021-07-23023 July 2021 License Amendment Request (LAR) 21-01, Chapter 5 9 Oddp FC-20-006 - End State Concrete Surface Areas and Volumes Rev 0 CAC2 ML21271A4452021-06-0505 June 2021 License Amendment Request (LAR) 21-01, FCS Embedded Pipe Dsr ML21271A2882021-06-0202 June 2021 License Amendment Request (LAR) 21-01, FCS Bfm Insitu Regression and Correlation Report Cm-244 ML21271A4362021-05-17017 May 2021 License Amendment Request (LAR) 21-01, FCS Buried Pipe Insitu Regression and Correlation Report Pu-240 ML21271A3932021-05-16016 May 2021 License Amendment Request (LAR) 21-01, FCS Buried Pipe Insitu Uncertainty Report Pu-240 ML21271A4062021-05-15015 May 2021 License Amendment Request (LAR) 21-01, FCS Buried Pipe Insitu Uncertainty Report Cs-137 2023-01-17
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A Entergy Nuclear Northeast Indian Point Energy Center
-===* Entergx 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Tel (914) 254-2055 Anthony J Vitale Site Vice President NL-17-157 December 14, 2017 U.S. Nuclear Regulatory Commission Document Control Desk 11545 Rockville Pike, TWFN-2 F1 Rockville, MD 20852-2738
SUBJECT:
Amendment 19 to License Renewal Application (LRA)
Indian Point Nuclear Generating Unit Nos. 2 and 3 Docket Nos. 50-247 and 50-286 License Nos. DPR-26 and DPR-64
REFERENCES:
- 1. Entergy Letter dated April 23, 2007, F. R. Dacimo to Document Control Desk, "License Renewal Application" (NL-07-039)
- 2. Entergy Letter dated April 23, 2007, F. R. Dacimo to Document Control Desk, "License Renewal Application Boundary Drawings" (NL-07-040)
- 3. Entergy Letter dated April 23, 2007, F. R. Dacimo to Document Control Desk, "License Renewal Application Environmental Report References"
- 4. Entergy Letter dated October 11, 2007, F. R. Dacimo to Document Control Desk, "License Renewal Applicat'ion (LRA)" (NL-07-124)
- 5. Entergy Letter dated November 14, 2007, F. R. Dacimo to Document Control Desk, "Supplement to License Renewal Application (LRA)
Environmental Report References" (NL-07-133)
Dear Sir or Madam:
In accordance with 10 CFR 54.21 (b), each year following submittal of the license renewal application and at least 3 months before scheduled completion of the NRG review, an amendment to the renewal application must be submitted that identifies any change to the CLB of the facility that materially affects the contents of the license renewal application (LRA), including the FSAR supplement. In the referenced letters, Entergy Nuclear Operations, Inc. applied for ~enewal of the Indian Point Nuclear Generating Units 2 and 3 operating licenses. This letter provides Amendment 19 of the Indian Point Units 2 and 3 license renewal application.
There are no new commitments being made in this submittal.
Should you have any questions concerning this report, please contact Mr. Robert W. Walpole, Licensing Manager, at (914) 254-6710.
NL-17-157 Dockets 50-24 7 and 50-286 Page 2 of 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on 12..-11-r~ ,2011.
Sincerely, AJV/rl Attachment 1. Annual Update Amendment cc: Mr. David C. Lew, Regional Administrator, NRC Region I Mr. William Burton, Senior Project Manager, NRC DLR Mr. Richard V. Guzman, Senior Project Manager, NRC NRR DORL Ms. Bridget Frymire, New York State Department of Public Service Ms. Alicia Barton, President and CEO NYSERDA NRC Resident Inspector's Office
ATTACHMENT 1 TO NL-17-157 ANNUAL AMENDMENT ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 and 3 DOCKET NO. 50-247 and 50-286
NL-17-157 Page 1 of 16 Dockets 50-247 and 50-286 Attachment 1 INDIAN POINT NUCLEAR GENERATING UNIT Nos. 2 AND 3 LICENSE RENEWAL APPLICATION ANNUAL AMENDMENT In accordance with 10 CFR 54.21 (b), each year following submittal of the license renewal application and at least 3 months before scheduled completion of the NRC review, an amendment
- to the renewal application must be submitted that identifies any change to the CLB of the facility
Amendment 19 is based on a review of documents potentially affecting the Current Licensing Basis (CLB) during the periods of September 1, 2016 through August 31, 2017.
The review concluded that certain sections of the LRA are affected by changes to CLB documents and other related LRA reviews. The table below summarizes the changes listing the affected system (if applicable), an explanation of the change (including effect on the LRA), and the affected LRA section.
Affected LRA Sections Change LRA Section Affected IP2 - EC 38036 Table 3.3.2-19-4-IP2 Review ER IP2-05-15107 and develop new ECR/EC to install long radius coated elbows at the steam jet air ejector. REF ECR 13994 and TEMP MOD 37924 for work accomplished on 21 SJE A IP2 - EC 53505 Table 2.3.3-2-1P2 Table 3.3.2-2-IP2 Base EC for IP2 EOG cooler rupture disk installation IP2 - EC 53509 Table 2.3.3-2-IP3 Table 3.3.2-2-IP3 Base EC for IP3 EOG cooler rupture .
disk installation
NL-17-157 Page 2 of 16 Dockets 50-247 and 50-286 Attachment 1 Change LRA Section Affected IP3 - EC 59290 Table 2.4-4 Section 3.5.2.1.4 Evaluate the use of rubber lattice Section 3.5.2.2.2.6 supports as an equivalent to the Table 3.5.1 springs of existing vibrati.on isolators Table 3.5.2-4 underneath the PAB supply fan RA-17-089 A.3.1.17 B.1.18 The NRC staff approves use of the 2007 Edition through 2008 Addenda of the ASME Code,Section XI, for activities related to repair/replacement, pressure testing, and NOE of Class 1, 2, 3, MC, and CC components, component supports, and welds, for the remainder of the fourth 10-year ISi intervals at IP-3, which is scheduled*
to end on July 20, 2019. (Ref. Relief request EN-ISl-16-1).
NL-16-065
- A.2.1.17 B.1.18 Entergy notified the NRC staff of the application of the latest edition and addenda of the ASME Code (2007/2008 Addenda) for the fifth 120 month interval at IP-2 which began on June 1, 2016.
CR-IP2-2017-4851 Table 2.3.3-13 IP3 Table 3.3.2-13-IP3 Nl-12-190 added com12onents to Table 3.3.2-13-IP3 related to EC 38047 (IP2) instead of 3.3.2-t3-IP2.
NL-13-131 added these components to Table 3.3.2-13-IP2 but neglected to delete them from Table 3.3.2-13-IP3.
NL-13-152 determined that these components were not within the scope of license renewal, but did not delete them from Table 3.3.2-13-IP3.
NL-17-157 Page 3 of 16 Dockets 50-247 and 50-286 Attachment 1 Change LRA Section Affected Table 3.4.2-5-4-IP2 CR-IP2-2017-4851 8.1.27 8.1.29 During update of AMRRS and Annual A.2.1.28 Update preparation, it was noted that A.2.1.39 additional minor changes to the material content of the LRA were required for submittal to the NRC.
)
NL-17-157 Page 4 of 16 Dockets 50-247 and 50-286 Attachment 1 IPEC LRA changes are shown below.
(Changes are shown as strikethroughs for deletions and underlines for additions)
Table 3.3.2-19-4 Condensate System Nonsafety-Related Components Potentially Affecting Safety Functions Summary ofA. ,gmg Managemen tRev1ew .
Table 3.3.2-19-4-IP2: Condensate System Aging Effect Aging NUREG-Component Intended Table 1 Material Environment Requiring Management 1801 Vol. Notes Type Function Item Management Programs 2 Item Pressure Metal with Loss of coating Coating integrity --- --- E Piping internal Steam (int) integrity boundary coating Table 2.3.3-2-IP2 Service Water System Components Subject to Aging Management Review Component Type Intended Function(s)
Rupture disc Pressure boundary
NL-17-157 Page 5 of 16 Dockets 50-247 and 50-286 Attachment 1 Table 3.3.2-2-IP2 Service Water System Summary of Aging Management Review Table 3.3.2-2-IP2: Service Water System Aging Effect NUREG-Component Intended Aging Management Table 1 Material Environment Requiring 1801 Vol. 2 Notes Type Function Programs Item Management Item Rugture disc Pressure Nickel allo~ Raw water (int) Loss of material Service Water VII.C1-13 3.3.1-78 6 boundar~ lntegrit~ (AP-53)
Rugture disc Pressure Nickel allo~ Condensation Loss of material External Surfaces -- -- G boundar~ (ext) Monitoring Table 2.3.3-2-IP3 Service Water System Components Subject to Aging Management Review Component Type Intended Function(s)
Ru12ture disc Pressure boundary
NL-17-157 Page 6 of 16 Dockets 50-247 and 50-286 Attachment 1 Table 3.3.2-2-IP3 Service Water System Summary of Aging Management Review Table 3.3.2-2-IP3: Service Water System Aging Effect NUREG-Component Intended Aging Management Table 1 Material Environment Requiring 1801 Vol. 2 Notes Type Function Programs Item Management Item Rugture disc Pressure Nickel allo~ Raw water (int) Loss of material Service Water VII.C1-13 3.3.1-78 8.
boundar~ lntegrit~ (AP-53)
Rugture disc Pressure Nickel allo~ Condensation Loss of material External Surfaces -- -- G bounda!Y (ext) Monitoring Table 2.4-4 Bulk Commodities Com onents Sub*ect to A ement Review Component Other Materials Vibration isolators
- Support for Criterion (a)(3) equipment
NL-17-157 Page 7 of 16 Dockets 50-247 and 50-286 Attachment 1 3.5.2.1.4 Bulk Commodities Aging Effects Requiring Management The following aging effects associated with bulk commodities require management.
- change in material properties
- Reduction or loss of isolation function
- separation 3.5.2.2.2.6 Aging of Supports Not Covered by Structures Monitoring Program (3) Reduction/loss of isolation function due to degradation of vibration isolation elements for Group 84 supports The IPEC aging management review did not identify any eomponent support strueture/aging effeet eombination eorresponding to NUREG 1801 Volume 2 Item III.B4.2 a.
NUREG-1801 Item 111.84.2-a discusses vibration isolation elements and aging effect/mechanism: Reduction or Loss of Isolation Function due to Radiation Hardening, Temperature, Humidity, and Sustained Vibratory Loading. The IPEC Structural Monitoring Program manages reduction/loss of isolation function due to degradation of vibration isolation elements for Group 84 supports.
NL-17-157 Page 8 of 16 Dockets 50-247 and 50-286 Attachment 1 Table 3.5.1: Containment, Structures and Component Supports, NUREG-1801 Aging Further Item Aging Effect/
Component Management Evaluation Discussion Number Mechanism Programs Recommended 3.5.1-41 Vibration Reduction or loss Structures Yes, if not within Ne 11il3FatieR iselatieR isolation of isolation Monitoring the scope of the elemeRts at IPeG aFe iR elements function/ Program applicant's see13e aREl s1;11ajeet te agiRg radiation structures maRagemeRt r:eview. The hardening, monitoring Structures Monitoring*
temperature, program Program is used to manage C
humidity, the listed aging effects.
sustained vibratory loading
- Table 3.5.2-4: Bulk Commodities Structure and/or Aging Effect Aging Component or Intended Requiring Management NUREG- Table 1 Commodity Function Material Environment Management Program 1801 Item Item Notes Reduction or loss of isolation function/
radiation Vibration Air-indoor Structures 111.84-12 isolators SRE Elastomers uncontrolled hardening, Monitoring (T-31) 3.5.1-41 8.
tern 12erature, humidity, sustained vibratory loadina
NL-17-157 Page 9 of 16 Dockets 50-247 and 50-286 Attachment 1 B.1.18 INSERVICE INSPECTION Program Description The lnservice Inspection (ISi) Program is an existing program that en'compasses ASME Section XI, Subsections IWA, IWB, IWC, IWD and IWF requirements.
On March 1, 2007, IP2 entered the fourth ISi interval and on July 21, 2009 IP3 entered the fourth ISi interval. The ASME code edition and addenda used for the IP2 and IP3 fourth fifth interval is the 2004-7 Edition, 200~ Addenda. The ASME code edition and addenda used for the remainder of the IP3-fourth interval is the 2008 Edition, 2009 Addenda.
A.2.1.17 lnservice Inspection - lnservjce Inspection (ISi) Program On June 1, 2016March 1, 2007, IP2 entered the ~ fifth ISi interval. The ASME code edition and addenda used for the few:tR. fifth interval is the 2004-Z Edition with 200J§. addenda.
A.3.1.17 lnservice Inspection - lnservice Inspection (ISi) Program On July 21, 2009, IP3 entered the fourth ISi interval. The ASME code edition and addenda used for the fourth interval is the 2001 Edition 2003 Addenda.
The NRC staff approved use of the 2007 Edition through 2008 Addenda of the ASME Code,Section XI, for activities related to repair/
replacement, pressure testing, and NDE of Class 1, 2, 3, MC, and CC components, component supports, and welds, for the remainder of the fourth 10-year ISi interval at IP3, which is scheduled to end on July 20, 2019.
NL-17-157 Page 10 of 16 Dockets 50-247 and 50-286 Attachment 1 Table 2.3.3-13-IP3 Fuel Oil Components Subject to Aging Management Review Component Type Intended Function Fle*iele ee11e,<'1S PFess1:1re 13e1:1RaafY Fleat e*sl=laRgeF (13eRRet) PFeSSl:IFe 891:lRSaFy Fleat e*sl=laRgeF (t1:113es) PFeSSl:IFe Be1:1RaaFy Fleat tFaRSfeF SileRSeF PFeSSl:IFe 891:lRSafY
+l:IF89SRaFgeF PFeSSl:IFe 891:lRSaFy
NL-17-157 Page 11 of 16 Dockets 50-247 and 50-286 Attachment 1 Table 3.3.2-13-IP3 Fuel Oil Systems Summary of Aging Management Review Table 3.3.2-13-IP3: Fuel Oil Systems
-
Aging Effect Aging NUREG-Component Intended Table 1 Material Environment Requiring Management 1801 Vol. Notes Type Function Item Management Programs 2 Item Filter housing Pressure Carbon steel Air indoor (int) Loss of material External Surfaces "B Ir. 1 (E 3.2.1 32 e bounsary Monitoring 2at Flexible Pressure Stainless Air insoor (ext) Nooe Nooe VII.J 1§ 3.3.1 94 A bello\*.is bounsary steel- (AP 17)
Flexible Pressure Stainless Exhaust gas (int) Cracking fatigue Periosic Surveillance - - H bellows bounsary steel- ans Pre1.ienti1.ie Maintenance Flmcible Pressure Stainless Exhaust gas (int) Loss of material Periosic SuF\'eillance VII.H2 2 (A 3.3.1 18 e bellows bounsary
- steel- ans Preventive 2+t Maintenance Heat Pressure Carbon steel Air insoor (ext) Loss of material External Surfaces VII.I 8 (A 3.3.1 §8 A exchanger boundary Monitoring ~
(bonRet)
Heat Pressure CarboR steel Treates water Loss of material IJ\Jater Chemistry VII.C2 1 (A 3.3.1 48 g e:>cchaRger bOURSary ) fiRtt CoRtrol Closes ~
(bonRet) CooliRg \ft.later
NL-17-157 Page 12 of 16 Dockets 50-247 and 50-286 Attachment 1 Table 3.3.2-13-IP3: Fuel Oil Systems Aging Effect Aging NUREG-Component Intended Table 1 Material -Environment Requiring Management 1801 Vol. Notes Type,r Function Item Management Programs 2 Item Meat Heat transfer Go1313er alloy Air indoor (met) Fouling Per1odie Surveillanee - - G exohanger > 15% zn and Preventi,.*e (tubes) Maintenanee Meat Heat transfer Go1313er alloy Treated water Fouling \11..!ater Ghemistry VII.G22 3.3.1 52 g exehanger > 15% zn ~ Gontrol Glosed (AP 80)
(tubes) Gooling \II.tater I\.
Meat Pressure Go1313er alloy nlr indoor (ext) Nooe Nooe VF 3 (EP 32.1 53 G exehanger boundary > 15% zn 4-0}
(tubes)
-
Meat Pressure Go1313er alloy Treated 1.vater Loss of material Seleetive Leashing VII.H1 4 3.3.1 84 G exohanger boundary > 15% zn ~ (AP 43)
(tubes)
Meat Pressure Go1313er alloy Treated water Loss of material lJVater Ghemistry VII.E1 2 3.3.1 51 g exehanger boundary > 15% zn ~ Gontrol Glosed (AP 34)
(tubes) Gooling Water
~ Pressure Garbon steel Treated \Nater Loss of material lJVater Ghemist~* VII.H2 23 3.3.1 47 g boundary ~ Gontrol Glosed (Mat GooliRg VI.tater
~ Pressure Garbon steel Exhaust gas (int) Loss of material Periodie SuFVeillanee VII.H2 2 (A 3.3.1 18 E-boundary and Preventive 2+}
Maintenanee
NL-17-157 Page 13 of 16 Dockets 50-247 and 50-286 Attachment 1
,-,
Table 3.3.2-13-IP3: Fuel Oil Systems Aging Effect Aging NUREG-Component Intended Table 1 Material Environment Requiring Management 1801 Vol. Notes Type Function Item Management Programs 2 Item
~ Pi=ess1:1Fe CaFbon steel ,6",IF indooF (int) Loss of mateFial Extemal Sm:faees VJ\ 19(E 3.2.1 32 e bo1:1ndaFy MonitoFin§ 2-9*
~ PFess1:1Fe Al1:1min1:1m AiF indooF (ext) Nooe Nooe V.F 2 (EP 3.2.1 50 G bo1:1ndaicy ~
~ PFeSSl:IFe Al1:1min1:1m AiF indOOF (int) Nooe Nooe V.F 2 (EP 3.2.1 50 G bo1:1ndaicy ~
SileneeF PFeSSl:IFe CaFbon steel ,6",IF indooF (ext) Loss of mateFial External S1:1Ffaees VII.I 8 (A 3.3.1 58 A bo1:1ndaFy
SileneeF PFeSSl:IFe CaFbon steel Exha1:1st gas (int) Loss of mateFial PeFiodie S1:1FVeillanee VII.H2 2 (A 3.3.1 18 e bo1:1ndary and PFeventi1.ie 27t Maintenanee SileneeF PFeSSl:IFe CaFbon steel Exha1:1st gas (int) Craekin§ fati§1:1e PeFiodie S1:1FVeillanee - - M bo1:1ndaFy and Pi=eventive Maintenanee I\.
T1:1FboehaFgm PFeSSl:IFe Gray east nlF indooF (ext) Loss of mateFial Extemal S1:1Ffaees VII.I 8 (A 3.3.1 58 A bo1:1ndary ifon. MonitoFing ~
-
'
TmboehaFgeF PFeSSl:IFe Gray east AiF indooF (int) Loss of matmial Extemal S1:1Ffaees
~.
H,.,6' 19 (E 3.2.1 32 e bo1:1ndaicy ifon. MonitoFin§ ~
NL-17-157 Page 14 of 16 Dockets 50-247 and 50-286 Attachment 1 Table 3.3.2-13-IP3: Fuel Oil Systems Aging Effect Aging NUREG-Component Intended Table 1 Material Environment Requiring Management 1801 Vol. Notes Type Function Item Management Programs 2 Item A"
Turbocharger Pressure Aluminum nlr indoor (int) Nooe Nooe V.F 2 (EP 3.2.1 50 G boundary ~
Turbocharger Pressure Aluminum Exhaust gas (int) Loss of material Periodic Surveillance - - G boundary and Preventive Maintenance B.1.27 One-Time Inspection Program Description
-
- Internal surfaces of the IP2 instrument air system stainless steel or aluminum tubing and valve bodies containing condensation B.1.29 Periodic Surveillance and Preventive Maintenance Program Description Condensate system Use visual or NOE techniques to inspect a representative sample of the internal surfaces of the main condenser tubes exposed to raw water (internal) and expansion joints exposed to treated water and indoor air to manage cracking, loss of material, aREi change in materials properties, and fouling.
NL-17-157 Page 15 of 16 Dockets 50-247 and 50-286 Attachment 1 Table 3.4.2-5-4-IP2 City Water System Components Required to Support AFW Pump Room Fire Event Summary of Aging Management Review
-
rTable 3.4.2-5-4-IP2 City Water System (CYW)
, Aging Effect NUREG-Component Intended Aging Management Table 1 Material Environment Requiring 1801 Vol. 2 Notes Type Function Programs Item Management Item Copper ~ 3.2.1 53 G Pressure Strainer housing alloy >15% Air indoor (ext) Nooe Nooe (EP 10) eoundary iffi Copper Periodic - - G, 407 Pressure Treated water Surveillance and Strainer housing alloy >15% Loss of material eoundary iffi
~ Preventi11e Maintenance A.2.1.28 Periodic Surveilh:mce and Preventive Maintenance Program Surveillance testing and periodic inspections using visual or other non-destructive examination techniques verify that the following components are capable of performing their intended function.
o chlorination, circulating water, city water, intake structure system, emergency diesel generator, fresh water cooling, instrument air, integrated liquid waste handling, lube oil, miscellaneous, radiation monitoring, river water, station air, waste disposal, wash water, and water treatment plant system piping, piping components, and piping elements .---
NL-17-157 Page 16 of 16 Dockets 50-247 and 50-286 Attachment 1 A.2.1.39 Water Chemistry Control - Closed Cooling Water Program The Water Chemistry Control - Closed Cooling Water Program is an existing program that includes preventive measures that manage loss of material, cracking, or fouling for components in closed cooling water systems (component cooling water (CCW),
instrument air (IP2 only), fresh '1Jater cooling, conventional closed cooling (CCC), instrument air closed cooling (IACC), emergency.
diesel generator cooling, security generator cooling, station air (IP1) cooling and SBO/Appendix R diesel generator cooling). These chemistry activities provide for monitoring and controlling closed cooling water chemistry using procedures and processes based on EPRI guidance for closed cooling water chemistry.