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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-19-084, 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] 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 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 ML20078L1402020-04-15015 April 2020 Issuance of Amendment Nos. 62, 293, and 268 Changes to Emergency Plan for Post-Shutdown and Permanently Defueled Condition ML20017A2902020-01-17017 January 2020 Supplement to 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-19-084, 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-19-053, Request for Rescission of Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA-12-051)2019-06-0606 June 2019 Request for Rescission of Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA-12-051) NL-19-013, Proposed Technical Specifications Change - Administrative Controls for Permanently Defueled Condition2019-04-15015 April 2019 Proposed Technical Specifications Change - Administrative Controls for Permanently Defueled Condition NL-19-026, Technical Specifications Proposed Change - Permanently Defueled Technical Specifications2019-04-15015 April 2019 Technical Specifications Proposed Change - Permanently Defueled Technical Specifications NL-19-001, License Amendment Request to Revise the Indian Point Energy Center Site Emergency Plan to Address the Permanently Shut Down and Defueled Condition2019-04-15015 April 2019 License Amendment Request to Revise the Indian Point Energy Center Site Emergency Plan to Address the Permanently Shut Down and Defueled Condition CNRO-2019-00003, Application to Revise Technical Specifications to Adopt TSTF-529 11 Clarify Use and Application Rules, 11 Revision 42019-01-31031 January 2019 Application to Revise Technical Specifications to Adopt TSTF-529 11 Clarify Use and Application Rules, 11 Revision 4 NL-18-034, License Amendment Request- Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions2018-06-20020 June 2018 License Amendment Request- Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions NL-17-157, Amendment 19 to License Renewal Application (LRA)2017-12-14014 December 2017 Amendment 19 to License Renewal Application (LRA) NL-17-070, Additional Information for the Review of the Plants License Renewal Application (LRA) Regarding the Containment Leak Rate Program2017-05-31031 May 2017 Additional Information for the Review of the Plants License Renewal Application (LRA) Regarding the Containment Leak Rate Program NL-17-049, Unit Nos., 1, 2, and 3, License Amendment Request - Cyber Security Plan Implementation Schedule2017-04-28028 April 2017 Unit Nos., 1, 2, and 3, License Amendment Request - Cyber Security Plan Implementation Schedule NL-17-035, Proposed License Amendment Regarding Connection of Non-Seismic Boric Acid Recovery System to the Refueling Water Storage Tank2017-04-0707 April 2017 Proposed License Amendment Regarding Connection of Non-Seismic Boric Acid Recovery System to the Refueling Water Storage Tank NL-17-018, Consistency Certification for Entergy Nuclear Indian Point 2 and Entergy Nuclear Indian Point 3 License Renewal Application2017-01-31031 January 2017 Consistency Certification for Entergy Nuclear Indian Point 2 and Entergy Nuclear Indian Point 3 License Renewal Application NL-16-138, Amendment 18 to License Renewal Application2016-12-15015 December 2016 Amendment 18 to License Renewal Application NL-16-118, Indian Point Nuclear Power Plant, Units 2 & 3, Proposed License Amendment Regarding the Inter-Unit Transfer of Spent Fuel2016-12-14014 December 2016 Indian Point Nuclear Power Plant, Units 2 & 3, Proposed License Amendment Regarding the Inter-Unit Transfer of Spent Fuel ML16355A0682016-12-14014 December 2016 Licensing Report on the Inter-Unit Transfer of Spent Nuclear Fuel NL-16-118, Proposed License Amendment Regarding the Inter-Unit Transfer of Spent Fuel2016-12-14014 December 2016 Proposed License Amendment Regarding the Inter-Unit Transfer of Spent Fuel CNRO-2016-00020, Application for Order to Transfer Master Decommissioning Trust from PASNY to ENO, Consenting to Amendments to Trust Agreement, and Approving Proposed License Amendments to Modify and Delete Decommissioning .2016-08-16016 August 2016 Application for Order to Transfer Master Decommissioning Trust from PASNY to ENO, Consenting to Amendments to Trust Agreement, and Approving Proposed License Amendments to Modify and Delete Decommissioning . NL-15-148, Amendment 17 to License Renewal Application (LRA)2015-12-14014 December 2015 Amendment 17 to License Renewal Application (LRA) NL-15-144, License Amendment Request - Conditional Exemption from End-of-Life (Eol) Moderator Temperature Coefficient (Mtc) Measurement2015-12-10010 December 2015 License Amendment Request - Conditional Exemption from End-of-Life (Eol) Moderator Temperature Coefficient (Mtc) Measurement NL-15-144, Indian Point, Units 2 and 3 - License Amendment Request - Conditional Exemption from End-of-Life (Eol) Moderator Temperature Coefficient (Mtc) Measurement2015-12-10010 December 2015 Indian Point, Units 2 and 3 - License Amendment Request - Conditional Exemption from End-of-Life (Eol) Moderator Temperature Coefficient (Mtc) Measurement NL-15-109, Reply to Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application, Set 2015-022015-09-0101 September 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 2015-02 NL-15-067, License Amendment Request - Cyber Security Plan Implementation Schedule2015-06-16016 June 2015 License Amendment Request - Cyber Security Plan Implementation Schedule NL-15-021, Proposed License Amendment Regarding a Change to Technical Specification 3.1.4 Reactivity Control Systems Indian Point Unit Number 22015-02-12012 February 2015 Proposed License Amendment Regarding a Change to Technical Specification 3.1.4 Reactivity Control Systems Indian Point Unit Number 2 NL-14-146, Amendment 16 to License Renewal Application (LRA)2014-12-15015 December 2014 Amendment 16 to License Renewal Application (LRA) NL-14-128, Proposed License Amendment Regarding Extending the Containment Type a Leak Rate Testing Frequency to 15 Years2014-12-0909 December 2014 Proposed License Amendment Regarding Extending the Containment Type a Leak Rate Testing Frequency to 15 Years ML14304A7002014-04-30030 April 2014 Annual Energy Outlook 2014 NL-13-145, Proposed License Amendment to Adopt TSTF-510, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection Indian Point Unit Nuclear Generating Unit Nos. 2 and 32014-04-0101 April 2014 Proposed License Amendment to Adopt TSTF-510, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection Indian Point Unit Nuclear Generating Unit Nos. 2 and 3 NL-14-035, Proposed Changes to Technical Specifications Regarding Reactor Vessel Pressure/Temperature Limit Curves2014-04-0101 April 2014 Proposed Changes to Technical Specifications Regarding Reactor Vessel Pressure/Temperature Limit Curves NL-14-016, License Amendment Request - Cyber Security Plan Implementation Schedule2014-01-30030 January 2014 License Amendment Request - Cyber Security Plan Implementation Schedule NL-13-131, Amendment 14 to License Renewal Application (LRA)2013-09-26026 September 2013 Amendment 14 to License Renewal Application (LRA) NL-13-077, License Renewal Application-Update to Electrical Meb and Structures Monitoring Program Scope, Aging Management Programs2013-05-0606 May 2013 License Renewal Application-Update to Electrical Meb and Structures Monitoring Program Scope, Aging Management Programs NL-13-015, Proposed License Amendment Regarding Connection of Non Seismic Boric Acid Recovery System to the Refueling Water Storage Tank2013-04-15015 April 2013 Proposed License Amendment Regarding Connection of Non Seismic Boric Acid Recovery System to the Refueling Water Storage Tank ML13116A0082013-04-0909 April 2013 Engineering Evaluation of Postulated RWST Inventory Loss During the Reverse Osmosis Clean-up Skid Process in Accordance to 2-TAP-001-ROS Due to Seismic Event NL-13-046, Amendment 13 to License Renewal Application (LRA) Pertaining to One-Time Inspection and Selective Leaching Programs2013-03-18018 March 2013 Amendment 13 to License Renewal Application (LRA) Pertaining to One-Time Inspection and Selective Leaching Programs ML13046A1662013-02-22022 February 2013 Issuance of Amendment Connecting Non-Seismic Purification System Piping to the Refueling Water Storage Tank NL-12-190, Amendment 12 to License Renewal Application (LRA)2012-12-27027 December 2012 Amendment 12 to License Renewal Application (LRA) NL-12-090, Proposed License Amendment Regarding Connection of Non Seismic Purification Line to Refuel Water Storage Tank2012-08-14014 August 2012 Proposed License Amendment Regarding Connection of Non Seismic Purification Line to Refuel Water Storage Tank NL-12-107, Application to Renew Operating Licenses for Indian Point Nuclear Power Reactors Unit 2 and Unit 3, General Correspondence - NL-12-1072012-08-0808 August 2012 Application to Renew Operating Licenses for Indian Point Nuclear Power Reactors Unit 2 and Unit 3, General Correspondence - NL-12-107 2023-01-17
[Table view] Category:Technical Specification
MONTHYEARML21091A3052022-02-28028 February 2022 Issuance of Amendment No. 272 Revision to Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device (EPID L-2020-LLA-0051) (Non-Proprietary) ML21074A0002021-04-22022 April 2021 Issuance of Amendment No. 270 Permanently Defueled Technical Specifications ML21083A0002021-04-14014 April 2021 Issuance of Amendment No. 63 Permanently Defueled Technical Specifications ML20259A2162020-09-14014 September 2020 Defueled Safety Analysis Report, Appendix a, Permanently Defueled Technical Specifications Bases NL-20-033, Technical Specifications Proposed Change - Permanently Defueled Technical Specifications2020-04-28028 April 2020 Technical Specifications Proposed Change - Permanently Defueled Technical Specifications 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-17-137, License Amendment Request (LAR) for One-Time Extension of the Containment Type a Leak Rate Testing Frequency from 15 to 16 Years2017-12-0808 December 2017 License Amendment Request (LAR) for One-Time Extension of the Containment Type a Leak Rate Testing Frequency from 15 to 16 Years NL-17-137, Indian Point Unit No. 3 - License Amendment Request (LAR) for One-Time Extension of the Containment Type a Leak Rate Testing Frequency from 15 to 16 Years2017-12-0808 December 2017 Indian Point Unit No. 3 - License Amendment Request (LAR) for One-Time Extension of the Containment Type a Leak Rate Testing Frequency from 15 to 16 Years ML16280A2292016-09-19019 September 2016 Indian Point 2 Improved Technical Specifications Bases NL-16-109, Indian Point 2 Improved Technical Specifications Bases2016-09-19019 September 2016 Indian Point 2 Improved Technical Specifications Bases NL-15-094, Proposed Changes to Technical Specifications Regarding Reactor Vessel Heatup and Cooldown Curves and Low Temperature Overpressure Protection System Requirements2015-08-11011 August 2015 Proposed Changes to Technical Specifications Regarding Reactor Vessel Heatup and Cooldown Curves and Low Temperature Overpressure Protection System Requirements NL-15-021, Proposed License Amendment Regarding a Change to Technical Specification 3.1.4 Reactivity Control Systems Indian Point Unit Number 22015-02-12012 February 2015 Proposed License Amendment Regarding a Change to Technical Specification 3.1.4 Reactivity Control Systems Indian Point Unit Number 2 NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Specification Bases List of Effective Sections2014-09-17017 September 2014 Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Specification Bases List of Effective Sections ML14287A3002014-09-17017 September 2014 Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Specification Bases List of Effective Sections NL-14-122, Indian Point, Unit 2 - Proposed License Amendment Re an Exigent Change to Technical Specification 3.8.6, Station Battery Surveillance2014-09-15015 September 2014 Indian Point, Unit 2 - Proposed License Amendment Re an Exigent Change to Technical Specification 3.8.6, Station Battery Surveillance ML14268A3532014-09-15015 September 2014 Proposed License Amendment Re an Exigent Change to Technical Specification 3.8.6, Station Battery Surveillance NL-13-145, Proposed License Amendment to Adopt TSTF-510, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection Indian Point Unit Nuclear Generating Unit Nos. 2 and 32014-04-0101 April 2014 Proposed License Amendment to Adopt TSTF-510, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection Indian Point Unit Nuclear Generating Unit Nos. 2 and 3 NL-11-119, Proposed Change to the Technical Specification Requirement for Containment Sump Level Indication2011-10-18018 October 2011 Proposed Change to the Technical Specification Requirement for Containment Sump Level Indication NL-10-133, Supplement to Proposed License Amendment to Change Technical Specifications Regarding Surveillance Requirements for AC and DC Sources2010-12-16016 December 2010 Supplement to Proposed License Amendment to Change Technical Specifications Regarding Surveillance Requirements for AC and DC Sources ML1015506572010-06-28028 June 2010 Issuance of Amendment Refueling Water Storage Tank Level Instrumentation ML0934307192009-10-13013 October 2009 2009 Amendment Update to the Final Safety Analysis Report (Fsar), Revision 03, Technical Specification Bases, November 2009, Appendix a, B.2.0 Through B.3.9.6 NL-09-062, Proposed Technical Specification Change Regarding RWST Surveillance Requirement2009-07-23023 July 2009 Proposed Technical Specification Change Regarding RWST Surveillance Requirement ENOC-09-00009, Entergy Nuclear Operations, Inc. - License Amendment Request; Proposed Adoption of TSTF-511 Regarding Elimination of Technical Specification Work Hour Restrictions2009-04-27027 April 2009 Entergy Nuclear Operations, Inc. - License Amendment Request; Proposed Adoption of TSTF-511 Regarding Elimination of Technical Specification Work Hour Restrictions NL-09-004, License Amendment Request Regarding Surveillance Requirements for ECCS Valves Required to Be in Position with Power to the Valve Operator Removed2009-03-25025 March 2009 License Amendment Request Regarding Surveillance Requirements for ECCS Valves Required to Be in Position with Power to the Valve Operator Removed NL-08-158, Additional Information Regarding Amendment Application on Control Room Envelope Habitability2008-10-28028 October 2008 Additional Information Regarding Amendment Application on Control Room Envelope Habitability NL-08-163, (IP2) - Transmittal of Amendment Update to the Final Safety Analysis Report (Fsar), Revision 212008-10-20020 October 2008 (IP2) - Transmittal of Amendment Update to the Final Safety Analysis Report (Fsar), Revision 21 NL-08-101, Proposed Changes to Technical Specifications Regarding Diesel Generator Endurance Test Surveillance2008-07-0909 July 2008 Proposed Changes to Technical Specifications Regarding Diesel Generator Endurance Test Surveillance ML0820701552008-06-26026 June 2008 Distribution of IP3 Technical Specification Amendment 236 ML0729102922007-10-0101 October 2007 Technical Specification Bases Change ML0724801632007-07-0606 July 2007 Revision 0 to IPEC Site Management Manual, IP-SMM-AD-103, IP3 Its/Bases ML0715003222007-03-29029 March 2007 IPEC Site Management Manual, Technical Specification Bases Update 23-05/16/07 ML0711402032007-03-29029 March 2007 Technical Specification Bases ML0707205372007-02-26026 February 2007 Improved Technical Specifications, Amendment 233 ML0702903522007-01-19019 January 2007 Revision 0 to IPEC Site Management Manual, IP-SMM-AD-103, IP3 Its/Bases NL-06-099, Units, 2 and 3 - Proposed Changes to Technical Specifications: Miscellaneous Editorial Changes, Including TSTF-4852006-09-25025 September 2006 Units, 2 and 3 - Proposed Changes to Technical Specifications: Miscellaneous Editorial Changes, Including TSTF-485 ML0620003692006-04-19019 April 2006 Update to IP3 Technical Specifications Bases ML0631905242006-04-19019 April 2006 Technical Specification Bases Manual, IP-SMM-AD-103 ML0604505332006-02-13013 February 2006 Tech Spec Pages for Amendments 245 and 229 Inoperability of Snubbers ML0532004452005-10-28028 October 2005 Technical Specification Bases Changes NL-05-105, Proposed Change to Technical Specifications Regarding Emergency Core Cooling System Throttle Valve Surveillance Requirements2005-10-0303 October 2005 Proposed Change to Technical Specifications Regarding Emergency Core Cooling System Throttle Valve Surveillance Requirements NL-05-107, Proposed Change to Indian Point 2 Technical Specifications Regarding LBLOCA Analysis Methodology2005-09-26026 September 2005 Proposed Change to Indian Point 2 Technical Specifications Regarding LBLOCA Analysis Methodology ML0523702312005-08-0808 August 2005 Technical Specification Bases NL-05-065, Application for a Technical Specification Change to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process (TSTF-372)2005-06-0808 June 2005 Application for a Technical Specification Change to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process (TSTF-372) NL-05-062, Proposed Change to IP2 Technical Specifications Regarding Pressurizer Water Level Requirements, Indian Point Unit No. 22005-05-25025 May 2005 Proposed Change to IP2 Technical Specifications Regarding Pressurizer Water Level Requirements, Indian Point Unit No. 2 ML0510800342005-04-14014 April 2005 Tech Spec Pages for Amendment 242 Reporting Requirements for Annual Radiological Environmental Operating Report ML0510903802005-03-31031 March 2005 Technical Specification Bases ML0509600592005-03-25025 March 2005 Distribution of IP3 Technical Specification Amendment 224 and 225 ML0508703842005-03-24024 March 2005 Technical Specification Pages Re 4.85 Percent Stretch Power Uprate & Relocation of Cycle-Specific Parameters ML0507500422005-02-0303 February 2005 Technical Specification Bases ML0506705222005-02-0303 February 2005 Technical Specification Bases 2022-02-28
[Table view] Category:Amendment
MONTHYEARML21091A3052022-02-28028 February 2022 Issuance of Amendment No. 272 Revision to Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device (EPID L-2020-LLA-0051) (Non-Proprietary) ML21074A0002021-04-22022 April 2021 Issuance of Amendment No. 270 Permanently Defueled Technical Specifications ML21083A0002021-04-14014 April 2021 Issuance of Amendment No. 63 Permanently Defueled Technical Specifications 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-17-137, Indian Point Unit No. 3 - License Amendment Request (LAR) for One-Time Extension of the Containment Type a Leak Rate Testing Frequency from 15 to 16 Years2017-12-0808 December 2017 Indian Point Unit No. 3 - License Amendment Request (LAR) for One-Time Extension of the Containment Type a Leak Rate Testing Frequency from 15 to 16 Years NL-17-137, License Amendment Request (LAR) for One-Time Extension of the Containment Type a Leak Rate Testing Frequency from 15 to 16 Years2017-12-0808 December 2017 License Amendment Request (LAR) for One-Time Extension of the Containment Type a Leak Rate Testing Frequency from 15 to 16 Years ML1015506572010-06-28028 June 2010 Issuance of Amendment Refueling Water Storage Tank Level Instrumentation ENOC-09-00009, Entergy Nuclear Operations, Inc. - License Amendment Request; Proposed Adoption of TSTF-511 Regarding Elimination of Technical Specification Work Hour Restrictions2009-04-27027 April 2009 Entergy Nuclear Operations, Inc. - License Amendment Request; Proposed Adoption of TSTF-511 Regarding Elimination of Technical Specification Work Hour Restrictions NL-09-004, License Amendment Request Regarding Surveillance Requirements for ECCS Valves Required to Be in Position with Power to the Valve Operator Removed2009-03-25025 March 2009 License Amendment Request Regarding Surveillance Requirements for ECCS Valves Required to Be in Position with Power to the Valve Operator Removed NL-08-101, Proposed Changes to Technical Specifications Regarding Diesel Generator Endurance Test Surveillance2008-07-0909 July 2008 Proposed Changes to Technical Specifications Regarding Diesel Generator Endurance Test Surveillance ML0707205372007-02-26026 February 2007 Improved Technical Specifications, Amendment 233 NL-06-099, Units, 2 and 3 - Proposed Changes to Technical Specifications: Miscellaneous Editorial Changes, Including TSTF-4852006-09-25025 September 2006 Units, 2 and 3 - Proposed Changes to Technical Specifications: Miscellaneous Editorial Changes, Including TSTF-485 ML0604505332006-02-13013 February 2006 Tech Spec Pages for Amendments 245 and 229 Inoperability of Snubbers NL-05-105, Proposed Change to Technical Specifications Regarding Emergency Core Cooling System Throttle Valve Surveillance Requirements2005-10-0303 October 2005 Proposed Change to Technical Specifications Regarding Emergency Core Cooling System Throttle Valve Surveillance Requirements NL-05-107, Proposed Change to Indian Point 2 Technical Specifications Regarding LBLOCA Analysis Methodology2005-09-26026 September 2005 Proposed Change to Indian Point 2 Technical Specifications Regarding LBLOCA Analysis Methodology NL-05-065, Application for a Technical Specification Change to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process (TSTF-372)2005-06-0808 June 2005 Application for a Technical Specification Change to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process (TSTF-372) NL-05-062, Proposed Change to IP2 Technical Specifications Regarding Pressurizer Water Level Requirements, Indian Point Unit No. 22005-05-25025 May 2005 Proposed Change to IP2 Technical Specifications Regarding Pressurizer Water Level Requirements, Indian Point Unit No. 2 ML0510800342005-04-14014 April 2005 Tech Spec Pages for Amendment 242 Reporting Requirements for Annual Radiological Environmental Operating Report ML0509600592005-03-25025 March 2005 Distribution of IP3 Technical Specification Amendment 224 and 225 ML0508703842005-03-24024 March 2005 Technical Specification Pages Re 4.85 Percent Stretch Power Uprate & Relocation of Cycle-Specific Parameters NL-04-025, Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2004-03-0909 March 2004 Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process NL-04-022, Proposed Change to Technical Specifications Regarding Reactor Coolant Pump Flywheel Inspection Interval (TSTF-421)2004-03-0303 March 2004 Proposed Change to Technical Specifications Regarding Reactor Coolant Pump Flywheel Inspection Interval (TSTF-421) ML0330904272003-10-30030 October 2003 Tech Spec Page for Amendment No. 219, Revising TS 5.5.10 to Adopt the Requirements of the American Society for Testing and Materials Standard D3803-1989 ML0325213882003-08-28028 August 2003 Transmittal of IP3 Technical Specification Amendment 218 ML0311403682003-03-26026 March 2003 Transmittal of Technical Specification Amendment 216 ML0221202052002-07-30030 July 2002 Technical Specifications, Amendment Reactor Vessel Material Surveillance Program (Tac No. MB3917) NL-02-082, License Amendment Request (LAR No. 02-010) - Regarding Indian Point Energy Center, Unit No. 2 Technical Specifications Requirements for Control Rod Misalignment & Rod Position Indication2002-07-0909 July 2002 License Amendment Request (LAR No. 02-010) - Regarding Indian Point Energy Center, Unit No. 2 Technical Specifications Requirements for Control Rod Misalignment & Rod Position Indication ML0215505332002-05-29029 May 2002 List of Figures for Amendment No. 227, Indian Point, Unit 2 ML0211905422002-04-25025 April 2002 No. 2 - Technical Specifications - Changes to Technical Specifications Bases ML0210103892002-04-11011 April 2002 Correction of Technical Specification Page Issued by Amendment No. 225 (Tac No. MB2990) ML0209400142002-04-0202 April 2002 Technical Specification, Amendment Technical Specification Changes to Secondary Leakage Limits and Steam Generator Tube Inservice Surveillance Requirements (Tac No. MB0770) ML0209101122002-03-27027 March 2002 Technical Specification Pages for Amendment No. 225 ML0205004982002-02-15015 February 2002 TS, Amendment Updated Pressure-Temperature Limit Curves (Tac No. MB2419) ML0204403322002-02-12012 February 2002 Technical Specification Amendment No. 223, Re Removal of Containment Isolation Valve Lists from Technical Specifications ML0037781142000-12-12012 December 2000 Transfer of Facility Operating Licenses and Proposed License Amendments. Consolidated Edison Co. of New York, Inc, Entergy Nuclear Indian Point 2, LLC, and Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Unit Nos. 1 and 2 2022-02-28
[Table view] |
Text
Entergy Nuclear Northeast Indian Point Energy Center Entergy 450 Broadway, GSB PO. Box 249 Buchanan, NY 10511-0249 Tel 914 734 6700 Fred Dacimo Site Vice President Administration September 26, 2005 Re: Indian Point Unit 2 Docket 50-247 NL-05-107 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Proposed Change to Indian Point 2 Technical Specifications Regarding LBLOCA Analysis Methodology
REFERENCE:
- 1. Entergy letter (NL-05-058) to NRC; "Reanalysis of Large Break Loss of Coolant Accident Using ASTRUM", dated April 22, 2005.
Dear Sir:
Pursuant to 10 CFR 50.90, Entergy Nuclear Operations, Inc, (Entergy) hereby requests an amendment to the Operating License for Indian Point Nuclear Generating Unit 2 (IP2) to adopt the use of ASTRUM for the licensing basis analysis of the Large Break Loss of Coolant Accident (LBLOCA), as stated in Reference 1.
Entergy has evaluated the proposed change in accordance with 10 CFR 50.91 (a)(1) using the criteria of 10 CFR 50.92 (c) and Entergy has determined that this proposed change involves no significant hazards considerations, as described in Attachment 1. The proposed changes to the Technical Specifications are shown in Attachment 2.
A copy of this application and the associated attachments are being submitted to the designated New York State official.
Entergy requests approval of the proposed amendment by June 2006, to be implemented within 60 days. There are no new commitments being made in this submittal. If you have any questions or require additional information, please contact Mr. Kevin Kingsley at 914-734-6695.
I declare under penalty of perjury that the foregoing is true and correct. Executed on 4!/ '
Fred R. Dacimo Site Vice President Indian Point Energy Center A.~
NL-05-107 Docket No. 50-247 Page 2 of 2 Attachments:
- 1. Analysis of Proposed Technical Specification Change
- 2. Proposed Technical Specification Change (markup) cc: Mr. John P. Boska, Senior Project Manager, NRC NRR Mr. Samuel J. Collins, Regional Administrator, NRC Region 1 NRC Resident Inspector's Office, Indian Point Unit 2 Mr. Peter R. Smith, President, NYSERDA Mr. Paul Eddy, New York State Dept. of Public Service
ATTACHMENT 1 TO NL-05-107 ANALYSIS OF PROPOSED TECHNICAL SPECIFICATION CHANGE REGARDING USE OF ASTRUM FOR LBLOCA ANALYSIS ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 DOCKET NO. 50-247
NL-05-1 07 Docket No. 50-247 Attachment 1 Page 1 of 11
1.0 DESCRIPTION
This letter requests an amendment to Operating License DPR-26, Docket No. 50-247 for Indian Point Nuclear Generating Unit No. 2 (IP2).
The proposed amendment will revise the analysis method used for the Large Break Loss of Coolant Accident (LBLOCA) by incorporating the use of a new approach (ASTRUM) for the treatment of parameter uncertainties. The new approach is described in Westinghouse Topical Report WCAP-1 6009-P-A, approved by NRC in Reference 1.
Changes to the Technical Specifications to reflect the proposed use of ASTRUM in LBLOCA analyses consist of revisions to the list of references provided in Technical Specification Section 5.6.5, Core Operating Limits Report.
2.0 PROPOSED CHANGE
S Technical Specification Section 5.6.5 (Core Operating Limits Report); three references in line item b.6 are replaced by a new reference, WCAP-16009-P-A. Refer to Attachment 2 for markup page.
3.0 BACKGROUND
The current methodology used for analysis of LBLOCA at IP2 is based on Westinghouse Topical Report WCAP-12945 and the plant-specific application of the methodology to IP2 as approved by NRC in 1997 (Reference 2). Since that time, the analyses have been updated to account for various plant change evaluations and model correction items in accordance with 10 CFR 50.46(a)(3). The most recent analysis update was performed as part of a stretch power uprate project in 2004 (Reference 3).
Entergy committed, in Reference 4, to perform a reanalysis of LBLOCA using the ASTRUM methodology. NRC subsequently approved (Reference 5) Westinghouse Topical Report WCAP-16009-P, which describes the ASTRUM methodology and Entergy performed the LBLOCA reanalysis as committed. Entergy reported the results of that analysis in Reference 6 and stated the intent to submit a license amendment request to formally adopt the ASTRUM methodology.
NL-05-1 07 Docket No. 50-247 Attachment I Page 2 of 11
4.0 TECHNICAL ANALYSIS
The original application of the Westinghouse Best Estimate Methodology to Indian Point Unit 2 Nuclear Plant, approved by the NRC in 1997, employed the NRC approved 1996 Evaluation Model (Reference 2). Westinghouse recently underwent a program to revise the statistical app roach used to develop the Peak Cladding Temperature (PCT) and oxidation results at the 95 percentile. This method is still based on the Code Qualification Document (CQD) methodology (Reference 7) and follows the steps in the Code Scaling, Applicability, and Uncertainty (CSAU) evaluation methodology. However, the uncertainty analysis (Element 3 in CSAU) is replaced by a technique based on order statistics. The ASTRUM methodology replaces the response surface technique with a statistical sampling method where the uncertainty parameters are simultaneously sampled for each case. The ASTRUM evaluation model is documented in WCAP-16009-P-A (Reference 1).
This section summarizes the application of the Westinghouse ASTRUM Best Estimate Loss of Coolant Accident (BELOCA) evaluation model to the Indian Point Unit 2 Nuclear Plant for analysis of the large break LOCAs (LBLOCA). The analysis was performed in compliance with all the NRC conditions and limitations as identified in WCAP-16009-P-A.
The current WCOBRA/TRAC model for Indian Point Unit 2 is based on the methodology of WCAP-1 2945 and uses the current uprated power level of 3216 MWth. Use of the best estimate LBLOCA methodology for Indian Point 2 was initially approved by NRC in 1997 (Reference 2). The WCOBRAITRAC noding that was developed at that time remains unchanged for the best estimate LBLOCA ASTRUM analysis. The ASTRUM best estimate LBLOCA analysis was performed for a full core of upgraded fuel. Table 1 lists the major plant parameter assumptions used in the analysis for Indian Point Unit 2. The axial power distribution envelope assumption is shown in Figure 1. Table 2 summarizes the results of the ASTRUM best estimate LBLOCA analysis, as previously reported in Reference 6. Table 3 contains a sequence of events for the limiting PCT transient. Based on these results, Indian Point Unit 2 continues to maintain a margin of safety to the limits prescribed by 10 CFR 50.46.
The ASTRUM methodology requires the execution of 124 transients to determine a bounding estimate of the 95th percentile of the Peak Clad Temperature (PCT), Local Maximum Oxidation (LMO), and Core Wide Oxidation (CWO) with 95% confidence level. These parameters are needed to satisfy the 10 CFR 50.46 criteria with regard to PCT, LMO, and CWO. From these 124 calculations, Run 76 proved to be the limiting PCT transient and the limiting IMO transient, and Run 11 the limiting CWO transient.
The scatter plot presented on Figure 2 shows the effect of the effective break area on the final PCT. The effective break area is calculated by multiplying the discharge coefficient (CD) with the sample value of the break area, normalized to the cold-leg cross sectional area. Figure 2 is provided because the break area is a significant contributor to the variation in PCT.
Figures 3 and 4 are presented to show the limiting cladding transient for each criterion. Figure 3 shows the predicted clad temperature transient at the PCT and LMO limiting elevation for Run 76 and Figure 4 presents the PCT trace for the CWO limiting transient from Run 11.
NL-05-107 Docket No. 50-247 Attachment I Page 3 of 11 Table 1: Major Plant Parameter Assumptions Used in the Best Estimate Large Break LOCA Analysis for Indian Point Unit 2 Parameter Value Documentation Plant Physical Description
- SG Tube Plugging l 10% ** UFSAR 14.3 Plant Initial Operating Conditions
- Reactor Power 5102% of 3216 MWt UFSAR 14.3
- Peaking Factors Fas 2.5 UFSAR 14.3
_ __ __ __ __ _ _ _ _ _ _ _ _ _ _ _ FAH~s 1.7_ _ _ _ _ _
- Axial Power Distribution See Figure 1 UFSAR 14.3 Fluid Conditions
- TAVG 549 - 3.3 0F 5 TAVO < 572 + 3.3 °F ()* UFSAR 14.3
- Pressurizer Pressure 2250 - 25 psia s PRCS s 2250 + 25 psia (2) UFSAR 14.3
- Accumulator Water Volume 723 ft3 s VAcc s 875 ft3 UFSAR 14.3 Accident Boundary Conditions
- Single Failure Assumptions Loss of one ECCS train UFSAR 14.3
- Safety Injection Flow Minimum UFSAR 14.3
- Safety Injection Temperature 35 0F STs1 s 110 OF UFSAR 14.3
- Safety Injection Initiation s 38 seconds (with offsite power) AR Delay Time s 45 seconds (without offsite power) UFS 14.3
- Containment Pressure Bounded (minimum) UFSAR 14.3 (1) Include -3 (bias)*
(2) Include -3, +12 (bias)*
- Bias sign convention: u+emeans indicated value is higher than actual and "-. means indicated value is lower than actual.
- The current version of the UFSAR does not contain this value, or range. However, this value or range will be updated in a subsequent UFSAR revision.
NL-05-107 Docket No. 50-247 Attachment 1 Page 4 of 11 Table 2: Indian Point Unit 2 Best Estimate Large Break LOCA Results 10 CFR 50.46 Requirement Value Criteria 95/95 PCT (0F) 1962 < 2200 95/95 LMO 1(%) 2.39 < 17 95/95 CWO (%) 0.35 <1 Core remains Core remains C abGe ercoolable coolable Core remains cool Long Term Cooling Core term cool in long term in longremains 1 Local Maximum Oxidation 2 Core Wide Oxidation Table 3: Indian Point Unit 2 Best Estimate Large Break LOCA Sequence of Events for Limiting PCT Transient Event Time (sec)
Start of Transient 0.0 Safety Injection Signal 6.0 Accumulator Injection Begins 10.0 End of Blowdown 28.0 Accumulator Empty 39.0 Bottom of Core Recovery 40.0 Safety Injection Begins 51.0 PCT Occurs 123.0 PCT Elevation Quench 330.0 End of Transient 500.0
NL-05-107 Docket No. 50-247 Attachment I Page 5 of 11 Figure 1: Indian Point Unit 2 Best Estimate Large Break LOCA Analysis Axial Power Shape Operating Space Envelope PBOT: integrated power fraction in the lower third of the core PMID: integrated power fraction in the middle third of the core
NL-05-107 Docket No. 50-247 Attachment I Page 6 of 11 Figure 2: Indian Point Unit 2 Best Estimate Large Break LOCA Analysis HOTSPOT PCT vs. Effective Break Area Scatter Plot 2000 aU .
1800 -
mE.
N a
- U 1600-
Q mu ONU
" 1400 -
I-Cl- * * * . U C) -
1200 -
U M
a
1000 -
M
_0 600 -I II I I I I I I I I I I I I I I I I I I I 0 i 15 2.5 3 CdsAbreak/ACL
NL-05-1 07 Docket No. 50-247 Attachment 1 Page 7 of 11 Figure 3: Indian Point Unit 2 Best Estimate Large Break LOCA Analysis HOTSPOT Clad Temperature Transient at the Limiting Elevation for the PCT and LMO Limiting Case Cladding Temperature at Limiting PCT and LMO Elevation 2000 1500-D 1000 so-0
NL-05-1 07 Docket No. 50-247 Attachment 1 Page 8 of 11 Figure 4: Indian Point Unit 2 Best Estimate Large Break LOCA Analysis WCOBRAITRAC PCT Transient for the CWO Limiting Case Peck Cladding Temperature 2000 1500 -
31000 E
500 0
Time After Break (s)
NL-05-1 07 Docket No. 50-247 Attachment 1 Page 9 of 11
5.0 REGULATORY ANALYSIS
5.1 No Significant Hazards Consideration Entergy Nuclear Operations, Inc. (Entergy) has evaluated the safety significance of the proposed changes regarding use of the ASTRUM methodology in the analysis of the Large Break Loss of Coolant Accident (LBLOCA) for Indian Point 2 (IP2) according to the criteria of 10 CFR 50.92, "Issuance of Amendment". Entergy has determined that the subject changes do not involve a Significant Hazards Consideration as discussed below:
- 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No The proposed change modifies the analysis methodology used to account for the variation in parameters that are used for the safety analysis of the LBLOCA. This proposed change has no effect on the design or operation of plant equipment.
Use of the new methodology will revise the results of the current analysis, but there will be no change in initiating events for this accident scenario or the ability of the plant equipment or plant operators to respond.
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated
- 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No The proposed change does not involve modifications to existing plant equipment or the installation of any new equipment. The proposed change only affects the analysis methodology that is used to evaluate the response of existing plant equipment to the LBLOCA scenario. Plant operating and emergency procedures that are in place for the LBLOCA scenario are also not being changed by this proposed amendment. This proposed change does not create new failure modes or malfunctions of plant equipment nor is there a new credible failure mechanism.
Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.
- 3. Does the proposed change involve a significant reduction in a margin of safety?
Response: No
NL-05-1 07 Docket No. 50-247 Attachment I Page 10 of 11 The proposed license amendment revises the analysis methodology which is used to assess the impact of the LBLOCA scenario with respect to established acceptance criteria. Margins of safety for LBLOCA include quantitative limits for fuel performance established in 10 CFR 50.46. These acceptance criteria and the associated margins of safety are not being changed. The evaluation of the LBLOCA scenario, using the proposed new methodology must still meet the existing established acceptance criteria.
Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Based on the above, Entergy Nuclear Operations, Inc. concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92 (c), and, accordingly, a finding of uno significant hazards consideration' is justified.
5.2 Applicable Requlatorv Requirements / Criteria The applicable regulatory requirement for this license amendment request is 10 CFR 50.46, which includes requirements and acceptance criteria pertaining to the evaluation of emergency core cooling system (ECCS) performance.
This regulation includes the requirement that "... uncertainties in the analysis method and inputs must be identified and assessed so that the uncertainty in the calculated results can be estimated. This uncertainty must be accounted for, so that, when the calculated ECCS cooling performance is compared to the criteria ... there is a high level of probability that the criteria would not be exceeded."
The proposed license amendment requests approval to use the ASTRUM methodology (WCAP-16009) for the treatment of uncertainties in the inputs used for the LBLOCA analysis. There is no change being proposed to the analysis acceptance criteria specified in the regulations. NRC has reviewed WCAP-16009 and found it acceptable for referencing in licensing applications for Westinghouse and Combustion Engineering designed pressurized water reactors. WCAP-16009 is applicable to Indian Point 2 and the plant-specific application of the ASTRUM methodology to the IP2 LBLOCA analysis has been performed in accordance with the conditions and limitations of the topical report and the associated NRC Safety Evaluation.
5.3 Environmental Considerations The proposed change to the IP2 Technical Specifications do not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51 .22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
NL-05-1 07 Docket No. 50-247 Attachment 1 Page 11 of 11 6.0 PRECEDENCE NRC has reviewed and accepted the Westinghouse topical report (WCAP-16009) which describes the ASTRUM methodology and NRC is in the process of reviewing a plant-specific application (Docket 50-244; April 29, 2005) which includes use of ASTRUM.
7.0 REFERENCES
- 1. Nissley, M. E., et.al, "Realistic Large-Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty (ASTRUM)," WCAP-16009-P-A, January 2005.
- 2. NRC letter to Consolidated Edison; Issuance of Amendment [188] for Indian Point Nuclear Generating Unit No. 2", dated March 31, 1997.
- 3. NRC letter to Entergy; "Issuance of Amendment [241] Re: 3.26 Percent Power Uprate (TAC MC1865)0, dated October 27, 2004.
- 4. Entergy letter (NL-04-081) to NRC; "Proposed Schedule for Reanalysis of Large Break Loss of Coolant Accident", July 2, 2004.
- 5. NRC letter to Westinghouse; "Final Safety Evaluation for WCAP-1 6009-P, Revision 0, Realistic Large-Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty (ASTRUM)," November 5, 2004.
- 6. Entergy letter (NL-05-058) to NRC; "Reanalysis of Large Break Loss of Coolant Accident Using ASTRUM", April 22, 2005.
- 7. Bajorek, S. M., et. al., 1998, "Code Qualification Document for Best Estimate LOCA Analysis,' WCAP-1 2945-P-A, Volume 1, Revision 2 and Volumes 2 through 5, Revision 1, and WCAP-14747 (Non-Proprietary).
ATTACHMENT 2 TO NL-05-107 MARKUP OF TECHNICAL SPECIFICATION PAGES FOR PROPOSED CHANGES REGARDING USE OF ASTRUM FOR LBLOCA ANALYSIS AFFECTED PAGE 5.6-3 ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 DOCKET NO. 50-247
Reporting Requirements 5.6 5.6 Reporting Requirements NO CHANGES THIS PAGE - INFORMATION ONLY 5.6.3 Radioactive Effluent Release ReDort
-NOTE -
A single submittal may be made for a multiple unit station. The submittal shall combine sections common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.
The Radioactive Effluent Release Report covering the operation of the unit in the previous year shall be submitted prior to May 1 of each year in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR Part 50, Appendix I, Section IV.B.1.
5.6.4 Not Used 5.6.5 CORE OPERATING LIMITS REPORT (COLR)
- a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:
- 1. Technical Specification 2.1, Safety Limits (SL);
- 2. Technical Specification 3.1.1, SHUTDOWN MARGIN (SDM);
- 3. Technical Specification 3.1.3, Moderator Temperature Coefficient (MTC);
- 4. Technical Specification 3.1.5, Shutdown Bank Insertion Limits;
- 5. Technical Specification 3.1.6, Control Bank Insertion Limits;
- 6. Technical Specification 3.2.1, Heat Flux Hot Channel Factor (FO(Z));
- 7. Technical Specification 3.2.2, Nuclear Enthalpy Rise Hot Channel Factor, INDIAN POINT 2 5.6- 2 Amendment No. 241
INSERT REFERENCE 6 FOR SECTION 5.6.5.b:
WCAP-16009-P-A, uRealistic Large Break LOCA Evaluation Methodology Using Automated Statistical Treatment of Uncertainty Method (ASTRUM)," M. E. Nissley, et al., January 2005.
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)
- 8. Technical Specification 3.2.3, Axial Flux Difference (AFD);
- 9. Technical Specification 3.3.1, Reactor Protection System Instrumentation;
- 10. Technical Specification 3.4.1, RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits; and
- 11. Technical Specification 3.9.1, Boron Concentration.
- b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
- 1. WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985;
- 2. WCAP-8385, nPower Distribution Control and Load Following Procedures - Topical Report", September 1974;
- 3. T.M. Anderson to K. Kniel (NRC) January 31, 1980 -
Attachment:
Operation and Safety Analysis Aspects of an Improved Load Follow Package;
- 4. NUREG-0800, Standard Review Plan, US Nuclear Regulatory Commission, Section 4.3, Nuclear Design, July 1981, including Branch Technical Position CPB 4.3-1,Westinghouse Constant Axial Offset Control (CAOC), Rev. 2, July 1981;
- 5. WCAP-1 1397-P-A, "Revised Thermal Design Procedure', April 1989; Replace with 6. Y P12945-P, "Code Qualification Document for Best Es mte new Ref 6, /LOCA Analysis", June 1993, as supplemented up to June 13, 1996 as see insert at / follows:
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\ l Westinghouse letter (N. J. Liparulo) to USNRC, "Re-Analysis Work Plans Using Final Best Estimate Methodology", NSD-NRC-96-4746,
\ June 13, 1996, and
- USNRC letter (J. Harold) to Consolidated Edison Company (S.
Quinn), "Issuance of Amendment [188] for Indian Point Nuclea
\ Generating Unit No. 2 (TAC No. M96370)", March 1997.
- 7. WCAP-8745-P-A, Design Bases for the Thermal Overpower Delta-T and Thermal Overtemperature Delta-T Trip Functions", September 1986; INDIAN POINT 2 5.6- 3 Amendment No. 241