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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 450 Broadway, GSB P.O. Box 249 Ete Buchanan, NY 10511-0249 Tel 914 734 6700 Fred Dacimo Site Vice President Administration October 3, 2005 Indian Point Unit 3 Docket No. 50-286 NL-05-105 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-PI-17 Washington, D.C. 20555-0001
Subject:
Proposed Change to Technical Specifications Regarding Emergency Core Cooling System Throttle Valve Surveillance Requirements
Dear Sir:
Pursuant to 10 CFR 50.90, Entergy Nuclear Operations, Inc. (Entergy) hereby requests an amendment to the Operating License and the Technical Specifications (TS) contained in Appendix A for Indian Point Unit 3. The proposed amendment revises Surveillance Requirement 3.5.2.6 to reflect the changes to the Emergency Core Cooling System throttle valves. A modification added seven throttle valves (valves SI-2165, 2166, 2168, 2169, 2170, 2171, and 2172) which the proposed amendment will add to the surveillance. The proposed amendment will remove existing throttle valves SI-856A and 856F from the surveillance since they are now locked closed. The proposed amendment will add SI-856B and 856G to the surveillance since these valves are used in a throttle position when opened.
The proposed changes have been evaluated in accordance with 10 CFR 50.91(a)(1) using the criteria of 10 CFR 50.92(c) and Entergy has determined that these proposed changes involve no significant hazards considerations (Attachment I). The proposed changes to the TS are provided in Attachment II. Planned Bases changes are in Attachment IlIl for information.
In accordance with 10 CFR 50.91, a copy of this application and the associated attachments are being submitted to the designated New York State official.
There are no new commitments identified in this submittal. If you have any questions or require additional information, please contact Mr. Patric W. Conroy at (914) 734-6668.
NL-05-105 Docket Nos. 50-286 Page 2 of 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on October
> 2005.
Sincerely, Fred R. Dacimo Site Vice President Indian Point Energy Center cc:
Mr. Boska, Senior Project Manager Mr. Samuel J. Collins Project Directorate I, Regional Administrator, Region I Division of Reactor Projects I/li U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Resident Inspector's Office Mr. Paul Eddy Indian Point Unit 3 New York State Dept. of Public Service U.S. Nuclear Regulatory Commission Mr. Peter R. Smith President, NYSERDA
ATTACHMENT I TO NL-05-105 ANALYSIS OF PROPOSED LICENSE AMENDMENT REQUEST AND TECHNICAL SPECIFICATION CHANGE REGARDING EMERGENCY CORE COOLING SYSTEM THROTTLE VALVES ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT 3 NUCLEAR POWER PLANT DOCKET NO. 50-286 DPR-64
Attachment I Docket No. 50-286 NL-05-105 Page 1 of 5
1.0 DESCRIPTION
This is a request to amend Operating License DPR-64, Docket 286, for Indian Point Unit 3 (IP3). The proposed amendment revises Technical Specification (TS) Surveillance Requirement (SR) 3.5.2.6 to reflect the changes to the Emergency Core Cooling System throttle valves. A modification added seven throttle valves (valves SI-2165, 2166, 2168, 2169, 2170, 2171, and 2172) which the proposed amendment will add to the surveillance. The proposed amendment will remove existing throttle valves Sl-856A and 856F from the surveillance since they are now locked closed. The proposed amendment will add SI-856B and 856G to the surveillance since they are used in a throttle position when opened.
2.0 PROPOSED CHANGE
S Revise TS 3.5.2, SR 3.5.2.6 from:
'Verify, for each ECCS throttle valve listed below, each position stop is in the correct position.
Valve Numbers Sl-856A Sl-856F SI-856C SI-856H Sl-856D Sl-856J Sl-856E SI-856K" To say:
"Verify, for each ECCS throttle valve listed below, each position stop is in the correct position.
Valve Numbers Sl-856B Sl-856H SI-2168 SI-856C Sl-856J SI-2169 SI-856D SI-856K SI-2170 Sl-856E SI-2165 SI-2171 SI-856G SI-2166 SI-2172"
3.0 TECHNICAL ANALYSIS
This License Amendment request is intended to correct a non-conservative TS surveillance requirement.
The current SR 3.5.2.6 does not include throttle valves SI-2165, 2166, 2168, 2169, 2170, 2171, 2172, 856B, and 856G. The amendment is also intended to remove valves Sl-856A and 856F since these are
Attachment I Docket No. 50-286 NL-05-105 Page 2 of 5 now locked closed such that throttle positions no longer require verification. Administrative controls assure that these valves are verified in the proper position required by flow balancing.
The High Head Safety Injection (HHSI) system utilizes three pumps discharging to two headers for safety injection. One header contains the Boron Injection Tank (BIT) that is no longer utilized and it is called the BIT header. Prior to the stretch power uprate (SPU), the BIT header discharged to four cold legs through motor operated valves 856E and 856C and manual valves 856D and 856F and discharged to one hot leg through motor operated valve 856G. The non BIT header discharged to four cold legs through motor operated valves 856H and 856J and manual valves 856A and 856K and discharged to one hot leg through motor operated valve 856B. The eight cold leg valves were used to throttle flow and the two hot leg valves were closed and de-energized until hot leg recirculation was initiated. For hot leg injection, these two hot leg valves were then opened to a preset throttled position.
The HHSI System was modified as part of the SPU to provide increased cold leg and hot leg flow capabilities, to support hot leg switchover as early as 6.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> following a postulated LOCA, to eliminate the potential for debris accumulation during recirculation, and to reduce or eliminate the potential for cavitation damage to throttle valves. The modification included the addition of six cold leg throttle valves (valves SI-2165, 2166, 2169, 2170, 2171, and 2172) and one hot leg throttle valve (SI-2168). These are manual valves which are designed to be set in a locked throttled position after adjustment during flow balance testing. The locked position will provide the required HHSI flow while also limiting pump run out flow. The SPU submittal regarded these valves as similar to orifices and based on the guidance of WCAP 1431, Rev 3 (surveillance 3.5.2.7 is not required for flow limiting orifices) concluded that no Technical Specification change was required. A recent review concluded that it is more appropriate to include these valves in the surveillance requirement since these valves can change position when being set. The SPU change also locked closed valves SI-856A and Sl-856F. Since these valves no longer perform a throttle function, they can be removed from SR 3.5.2.6.
Since the SPU modification allows valves SI-856C, 856D, 856E, 856H, 856J, or 856K to be used for trimming system resistance based on system flow balance testing, these valves could be used to perform throttling and they are therefore being left in SR 3.5.2.6. During this cycle these valves have their limit switches adjusted so that they do not perform a throttle function. The TS bases will clarify the option to flow balance with these valves.
The hot leg valves SI-856B and 856G are used to throttle flow during hot leg recirculation. The throttle position is achieved by adjusting the limit switch so that when a valve is opened for hot leg recirculation it will open to the proper position to throttle flow. Valve Sl-856G continues to function in this manner and has been added to SR 3.5.2.6. The SPU modification allows valve Sl-856B to be used for trimming system resistance based on system flow balance testing. Since valve SI-856B could be used to perform throttling, it is being added to SR 3.5.2.6.
The SR requires verification, for each ECCS throttle valve listed, that Oeach position stop is in the correct position.' No change to this wording is requested since the throttle positions of the motor operated valves are set by adjusting limit switches to stop them in position and the manually operated valves are set by locking valves in the position where they are stopped for flow testing. The TS Bases will clarify this.
The SPU application (Reference 1) stated, in Section 4.1.4, that the power uprate required higher HHSI cold leg and hot leg flows. The application described the HHSI system modification that permanently closed two cold leg branch valves and throttled the HHSI system to provide higher cold leg and hot leg flows. System changes were also made to enhance spilling line performance. These changes addressed recirculation sump particle criteria and throttle valve cavitation issues.
Attachment I Docket No. 50-286 NL-05-105 Page 3 of 5 Further clarification was provided in response to Question RSA-12 (Reference 2). This response advised that the revised HHSI system cold and hot leg performance was calculated with the 856A and 856F valves closed. This HHSI flow performance data was then used in the various accident analyses performed in support of the Indian Point 3 SPU program. The appropriate limiting single failure assumptions were also applied in calculating the HHSI system flow performance data. The driving reason for permanently closing the 856A line (to cold leg loop 1) and 856F line (to cold leg loop 3) was identified as the achievement of higher hot leg recirculation flow performance, required to support the SPU program, while maintaining the maximum allowable HHSI pump flow limits. The response also indicated that 856A and 856F valves are administratively controlled by changing the normal position to lock closed.
The SPU submittal discussed above did not request a change to SR 3.5.2.6 because the throttle valves were regarded as similar to orifices due to their design. Based on the guidance of WCAP-1431, Rev 3 (surveillance 3.5.2.7 is not required for flow limiting orifices), a conclusion was reached that no Technical Specification change was required. A recent review concluded that it is more appropriate to include these valves in the surveillance requirement since these valves can change position when being set.
4.0 REGULATORY ANALYSIS
4.1 No Significant Hazards Consideration Determination Entergy has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by assessing the change using the three criteria of 10 CFR 50.92 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 to Surveillance Requirement (SR) 3.5.2.6 adds nine valves and removes two valves in the High Head Safety Injection (HHSI) system discharge lines. The SR requires verification that identified ECCS throttle valves position stops are in the correct position. The change reflects a stretch power uprate (SPU) modification that added throttle valves SI-2165, 2166, 2168, 2169, 2170, 2171, and 2172, and locked closed valves Sl-856A and 856F. This amendment is adding to the SR those throttle valves which are now under administrative control and deletes the valves which no longer perform a throttle function. The amendment also adds hot leg valves Sl-856B and 856G which are used as throttle valves but never included in the SR. Valve Sl-856G still performs a throttle function and valve SI-856B can still be considered a throttle valve when used to trim system resistance.
Verification of valve position has no effect on the probability of an accident previously evaluated since the HHSI system is not associated with the initiation of any accident.
The verification of valve positions that will be required by the revised SR provides additional assurance that the HHSI throttle valves are in the position that is established by flow testing. Providing assurance of required valve positions does not increase the consequences of an accident previously evaluated. Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
Attachment I Docket No. 50-286 NL-05-105 Page 4 of 5
- 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 to Surveillance Requirement 3.5.2.6 adds nine valves and removes two valves in the High Head Safety Injection (HHSI) system discharge lines. The SR requires verification that identified ECCS throttle valves position stops are in the correct position. The change corrects a deficient surveillance and does not affect the function of the valves or otherwise affect the design and operation of plant systems and components and therefore no new accident scenarios would be created. Therefore, no new failure modes are being introduced that could lead to different accidents.
- 3. Does the proposed change involve a significant reduction in a margin of safety?
Response - No The proposed change to Surveillance Requirement 3.5.2.6 adds nine valves and removes two valves in the High Head Safety Injection (HHSI) system discharge lines. The SR requires verification that identified ECCS throttle valves position stops are in the correct position. The change reflects a stretch power uprate (SPU) modification that added throttle valves SI-2165, 2166, 2168, 2169, 2170, 2171, and 2172, and locked closed valves Sl-856A and 856F. The proposed amendment also adds valves SI-856B and 856G which are used as throttle valves but never included in the SR. Valve Sl-856G still performs a throttle function and valve Sl-856B can still be considered a throttle valve when used to trim system resistance. The frequency for verification of throttle valve stop positions is not altered by this amendment so this has no effect on the margin of safety. The valves for which verification of positions stops is required reflect the manner in which the system is currently analyzed and configured so the proposed change serves to maintain the required margin of safety by adding to the Technical Specifications the surveillances presently being administratively controlled. Therefore, the proposed change does not involve a significant reduction in the margin of safety.
4.2 Applicable Regulatory Requirements I Criteria The proposed changes have been evaluated to determine compliance with applicable regulatory requirements.
10 CFR 50.46 establishes acceptance criteria for emergency core cooling system. The HHSI system was evaluated for SPU in a modified condition. That modification included seven new throttle valves (valves SI-2165, 2166, 2168, 2169, 2170, 2171, and 2172),
added the potential use of valves Sl-856B, 856C, 856D, 856E, 856H, 856J, or 856K as throttle valves to trim system resistance during system flow balance testing, and locked closed throttle valves SI-856A and 856F eliminating them as throttle valves. Valve 856G is used as a throttle valve but was never included in the surveillance requirement. These changes were made to enhance system operation. The proposed amendment will revise
Attachment I Docket No. 50-286 NL-05-105 Page 5 of 5 the surveillance requirements to reflect this configuration. Surveillances, now performed under administrative controls, provide assurance that the HHSI system can perform as necessary to maintain compliance with 10 CFR 50.46.
4.3 Environmental Considerations The proposed changes in this license amendment to the plant 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.
5.0 PRECEDENCE NUREG 1431, Revision 3, 'Standard Technical Specifications Westinghouse Plants" requires verification, for each ECCS throttle valve, that the position stop is in the correct position.
This assures that realigned valves are In the correct position. The proposed revision is consistent with that requirement.
6.0 REFERENCES
- 1. Entergy Letter NL-04-069 to NRC, NProposed Changes to Technical Specifications: Stretch Power Uprate (4.85%) and Adoption of TSTF 339," June 3, 2004.
- 2. Entergy Letter NL-04-156 to NRC, "Reply to RAI Regarding Indian Point 3 Stretch Power Uprate dated November 5, 2004 (TAC MC 3352)," dated December 15, 2004.
.4 . I ATTACHMENT II TO IPN-05-105 MARK UP OF EXISTING TECHNICAL SPECIFICATION PAGES TO SHOW THE PROPOSED CHANGE Note - Deleted items have been lined through and new items underlined ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT 3 NUCLEAR POWER PLANTS DOCKET NO. 50-286 DPR-64
ECCS - Operating 3.5.2 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.5.2.2 verify that each ECCS manual, power 31 days operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.
SR 3.5.2.3 verify each ECCS pump's developed head In accordance at the test flow point is greater than with the or equal to the required developed Inservice head. Testing Program SR 3.5.2.4 verify each ECCS automatic valve in the 24 months flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.
SR 3.5.2.5 verify each ECCS pump starts 24 months automatically on an actual or simulated actuation signal.
SR 3.5.2.6 verify, for each ECCS throttle valve 24 months listed below, each position stop is in the correct position.
valve Numbers SI 856A 'I 856F SI-856C SI-856H SI-856D SI-856J SI-856E SI-856K SI-856B SI-2168 SI-856G SI-2169 SI-2170 SI-2165 SI-2171 SI-2166 SI-2172 (continued)
INDIAN POINT 3 3.5.2-3 Amendment 205&
ATTACHMENT III TO IPN-05-105 MARK UP OF EXISTING TECHNICAL SPECIFICATION BASES PAGES TO SHOW THE PROPOSED CHANGE (FOR INFORMATION ONLY)
Note - Deleted items have been lined through and new items underlined ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT 3 NUCLEAR POWER PLANT DOCKET NO. 50-286 DPR- 64
ECCS- Operating B 3.5.2 BASES SURVEILLANCE REQUIREMENTS (continued)
SR 3.5.2.4 and SR 3.5.2.5 These surveillances demonstrate that each automatic ECCS valve actuates to the required position on an actual or simulated SI signal and that each ECCS pump starts on receipt of an actual or simulated SI signal.
Note that the containment Recirculation system is a manually initiated system and is not included as part of this SR. Additionally, this Surveillance is not required for valves that are locked, sealed, or otherwise secured in the required position under administrative controls. The 24 month Frequency is based on the need to perform these surveillances under the conditions that apply during a plant outage and the potential for unplanned plant transients if the Surveillances were performed with the reactor at power. The 24 month Frequency is also acceptable based on consideration of the design reliability (and confirming operating experience) of the equipment.
The actuation logic is tested as part of ESF Actuation System testing, and equipment performance is monitored as part of the Inservice Testing Program.
SR 3.5.2.6 f-eaAlignment of valves in the HHSI flow path on an SI sickes. is necessary for proper ECCS performance.
These valves have stops to allow proper positioning and/or locking manual valves in the flow Dath for restricted flow to a ruptured cold leg, ensuring that the other cold legs receive at least the required minimum flow, and to allow Droper Dositioning for restricting hot lea flow. Therefore, an improperly positioned valve could result in the inoperability of more than one injection flow path. The stops and/or the locked manual valves are set based on the results of the most recent ECCS operational flow test. valves SI-856B, 856C. 856D. 856E. E856H, 856). and 856K are not necessarily used for flow balancing but can be used to trim svstem resistance durinc flow balance testing. The stop positions are set to reflect their usage. The 24 month Frequency is based on the reasons stated in SR 3.5.2.4 and SR 3.5.2.5.
SR 3.5.2.7 Periodic inspections of each containment and recirculation sump suction inlet ensure that each is unrestricted and stays in INDIAN POINT 3 B 3.5.2 - 9 Revision 0