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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 Specifications
MONTHYEARML23339A0442023-12-0505 December 2023 Issuance of Amendment No. 68, 301 and 277 Regarding Changes to Implement the Independent Spent Fuel Storage Installation Physical Security Plan ML22307A0452023-11-17017 November 2023 Enclosure 1 - Amendment No. 297 to Rfl No. DPR-26 for Indian Point Unit 2 License Amendment Request to Modify Tech Specs for Staffing Requirements with Spent Fuel Transfer to Dry Storage ML23100A1172023-11-17017 November 2023 NRC Response - Indian Point Energy Center Generating Units 1, 2, and 3 Letter with Enclosures Regarding Changes to Remove the Cyber Security Plan License Condition ML20297A3262020-11-23023 November 2020 Enclosure 2, Draft Conforming Amendments for Transfer of Facility Operating Licenses to Holtec International, Owner, and Holtec Decommissioning International, LLC, Operator ML20100H9922020-06-0202 June 2020 Issuance of Amendment No. 269 Proposed Technical Specification Changes to City Water Surveillance Requirement and Condensate Storage Tank Required Action A.1 ML20081J4022020-04-28028 April 2020 Issuance of Amendment No. 294 Permanently Defueled Technical Specifications ML20110A0052020-04-27027 April 2020 Correction to Amendment No. 267 Issued April 10, 2020, Changes to Technical Specifications for a Permanently Defueled Condition ML20071Q7172020-04-10010 April 2020 Issuance of Amendment Nos. 292 and No. 267 Changes to Technical Specification Sections 1.1, 4.0, and 5.0 for a Permanently Defueled Condition ML19175A0422019-09-11011 September 2019 Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules ML19072A1342019-03-15015 March 2019 Amended Provisional Operating License DPR-5, 3-22-2019 ML18212A1902018-09-17017 September 2018 Renewed Facility Operating License DPR-64, Technical Specifications, Appendix a ML18212A1852018-09-17017 September 2018 Renewed Facility Operating License DPR-26, Technical Specifications, Appendix B ML18212A1942018-09-17017 September 2018 Renewed Facility Operating License DPR-64, Technical Specifications, Appendix B ML18212A1952018-09-17017 September 2018 Renewed Facility Operating License DPR-64, Technical Specifications, Appendix C ML16064A2152016-04-12012 April 2016 Issuance of Amendments Cyber Security Plan Implementation Schedule NL-16-027, Response to Request for Additional Information Related to License Amendment Request Regarding Conditional Exemption from End-of-Life (Eol) Moderator Temperature Coefficient (Mtc) Measurement2016-03-0202 March 2016 Response to Request for Additional Information Related to License Amendment Request Regarding Conditional Exemption from End-of-Life (Eol) Moderator Temperature Coefficient (Mtc) Measurement ML15349A7942016-02-23023 February 2016 Generation, Unit No. 2 - Issuance of Amendment Extension of the Containment Integrated Leak Rate Test to 15 Years 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-15-118, Post Accident Monitoring (PAM) Report for an Inoperable Reactor Vessel Level Indication System (RVLIS) Train B, Indian Point Unit 32015-09-0303 September 2015 Post Accident Monitoring (PAM) Report for an Inoperable Reactor Vessel Level Indication System (RVLIS) Train B, Indian Point Unit 3 ML15226A1592015-09-0303 September 2015 Issuance of Amendment Changes to Reactor Vessel Heatup and Cooldown Curves and Low Temperature Overpressure Protection System Requirements ML15110A0092015-05-26026 May 2015 Issuance of Amendment Re Implementation of Technical Specification Task Force Traveler 510, Revision 2, Revision to Steam Generator Program Inspection Frequencies & Tube Sample Selection(Tac Nos. MF3752 & MF3753) ML15083A4902015-04-0202 April 2015 Issuance of Amendment Proposed License Amendment Regarding a Change to Technical Specification 3.1.4 Reactivity Control Systems ML15028A3082015-03-13013 March 2015 Issuance of Amendment Extension of the Type a Containment Integrated Leak Rate Test Frequency from 10 to 15 Years 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 ML14265A3292014-09-24024 September 2014 Issuance of Amendment Temporary Change to Technical Specification 3.8.6 Battery 22 Surveillance Requirement (Exigent Circumstances) ML14287A2942014-09-17017 September 2014 Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Requirements Manual NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Requirements Manual2014-09-17017 September 2014 Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Requirements Manual ML14198A1612014-09-0505 September 2014 Issuance of Amendment H* Alternate Repair Criteria for Steam Generator Tube Inspection and Repair (Tac No. MF3369) ML14169A5832014-07-17017 July 2014 Issuance of Amendment Revised Containment Integrity Analysis (Tac No. MF0591) NL-14-053, Response to Request for Additional Information Regarding Emergency Diesel Generator Fuel Oil Storage Supplies2014-04-14014 April 2014 Response to Request for Additional Information Regarding Emergency Diesel Generator Fuel Oil Storage Supplies 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 ML14045A2482014-03-0505 March 2014 Issuance of Amendment Pressure-Temperature Limit Curves and Low Temperature Over Pressure Requirements NL-14-032, Supplemental Information to Proposed Changes to Indian Point 2 Technical Specifications Regarding Reactor Vessel Heatup and Cooldown Curves and Low Temperature Over Pressure Requirements Indian Point Unit Number 22014-02-24024 February 2014 Supplemental Information to Proposed Changes to Indian Point 2 Technical Specifications Regarding Reactor Vessel Heatup and Cooldown Curves and Low Temperature Over Pressure Requirements Indian Point Unit Number 2 NL-14-001, Indian Point, Unit 2 - Proposed License Amendment for Alternate Repair Criteria for Steam Generator Tube Inspection and Repair2014-01-16016 January 2014 Indian Point, Unit 2 - Proposed License Amendment for Alternate Repair Criteria for Steam Generator Tube Inspection and Repair NL-14-001, Proposed License Amendment for Alternate Repair Criteria for Steam Generator Tube Inspection and Repair2014-01-16016 January 2014 Proposed License Amendment for Alternate Repair Criteria for Steam Generator Tube Inspection and Repair CNRO-2012-00009, Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications2012-11-20020 November 2012 Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications NL-12-039, Proposed License Amendment Regarding Atmospheric Dump Valves2012-05-23023 May 2012 Proposed License Amendment Regarding Atmospheric Dump Valves NL-12-002, Proposed Change to Containment Purge System and Pressure Relief Line Isolation Instrumentation Technical Specifications2012-01-11011 January 2012 Proposed Change to Containment Purge System and Pressure Relief Line Isolation Instrumentation Technical Specifications 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-10-072, Proposed Technical Specification Change Regarding RWST Surveillance Requirement2010-10-0606 October 2010 Proposed Technical Specification Change Regarding RWST Surveillance Requirement NL-09-167, Proposed Exigent License Amendment Re One Time Extension of the Auxiliary Boiler Feedwater Pump Allowed Outage Time2009-12-15015 December 2009 Proposed Exigent License Amendment Re One Time Extension of the Auxiliary Boiler Feedwater Pump Allowed Outage Time NL-09-129, Indian Point, Unit 3, Proposed License Amendment to Change Technical Specifications Regarding Surveillance Requirements for AC and DC Sources2009-11-19019 November 2009 Indian Point, Unit 3, Proposed License Amendment to Change Technical Specifications Regarding Surveillance Requirements for AC and DC Sources NL-09-129, Proposed License Amendment to Change Technical Specifications Regarding Surveillance Requirements for AC and DC Sources2009-11-19019 November 2009 Proposed License Amendment to Change Technical Specifications Regarding Surveillance Requirements for AC and DC Sources NL-09-119, Proposed License Amendment Regarding Diesel Generator Air Start Receiver Pressure, Indian Point Units 2 & 32009-11-17017 November 2009 Proposed License Amendment Regarding Diesel Generator Air Start Receiver Pressure, Indian Point Units 2 & 3 ML0834304242009-05-29029 May 2009 License Amendment, Technical Specifications Regarding Removal of Spent Fuel from Unit 1 and Drain Down of the Spent Fuel Pool NL-08-137, Reply to Request for Additional Information Regarding Amendment Application on Control Room Envelope Habitability2008-09-18018 September 2008 Reply to Request for Additional Information Regarding Amendment Application on Control Room Envelope Habitability ML0811401772008-06-0909 June 2008 Tec Specs to Amedment 236, License No. DPR-64 for Indian Point, Unit 3 ML0727805822007-10-0404 October 2007 Technical Specifications, Change of Pressure-temperature and Low Temperature Protection System Limits ML0722901282007-08-16016 August 2007 Technical Specifications 2023-12-05
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SEnQtergy Enteray Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Tel 914 734 6700 Joseph Pollack Site Vice President Administration December 15, 2009 NL-09-167 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Proposed Exigent License Amendment Regarding One Time Extension of the Auxiliary Boiler Feedwater Pump Allowed Outage Time Indian Point Unit Number 3 Docket No. 50-286 License No. DPR-64
Dear Sir or Madam:
Pursuant to 10 CFR 50.90, Entergy Nuclear Operations, Inc, (Entergy) hereby requests a License Amendment to Operating License DPR-64, Docket No. 50-286 for Indian Point Nuclear Generating Unit No. 3 (IP3). The proposed amendment will allow a one time extension of the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> completion time of TS 3.7.5, Condition B, Action B.1 "Restore AFW train to OPERABLE status" by 34 hours3.935185e-4 days <br />0.00944 hours <br />5.621693e-5 weeks <br />1.2937e-5 months <br />.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 consideration, as described in Attachment
- 1. The marked-up page showing the proposed change is provided in Attachment
- 2. A copy of this application and the associated attachments are being submitted to the designated New York State official in accordance with 10 CFR 50.91.Entergy requests approval of the proposed amendment on an exigent basis by January 5, 2010 with basis explained in Attachment
- 1. The commitments being made in this submittal are in Attachment
- 3. If you have any questions or require additional information, please contact Mr.Robert Walpole, Manager, Licensing at (914) 734-6710.Aloo!
NL-09-167 Docket No. 50-286 Page 2 6f 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on December 15, 2009.Sincerely, V JEP/sp Attachments:
- 1. Analysis of Proposed Technical Specification Change Regarding One Time Extension of the Auxiliary Boiler Feedwater Pump Allowed Outage Time 2. Markup of Technical Specifications Page for Proposed Change Regarding One Time Extension of the Auxiliary Boiler Feedwater Pump Allowed Outage Time 3. Commitments cc: Mr. John P. Boska, Senior Project Manager, NRC NRR DORL Mr. Samuel J. Collins, Regional Administrator, NRC Region 1 NRC Resident Inspectors Mr. Francis J. Murray, Jr., President and CEO, NYSERDA Mr. Paul Eddy, New York State Dept. of Public Service ATTACHMENT 1 TO NL-09-167 ANALYSIS OF PROPOSED TECHNICAL SPECIFICATION CHANGE REGARDING ONE TIME EXTENSION OF THE AUXILIARY BOILER FEEDWATER PUMP ALLOWED OUTAGE TIME ENTERGY NUCLEAR OPERATIONS, INC.INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 DOCKET NO. 50-286 NL-09-167 Docket No. 50-286 Attachment 1 Page 1 of 8
1.0 DESCRIPTION
Entergy Nuclear Operations, Inc (Entergy) is requesting an amendment to Operating License Operating License DPR-64, Docket No. 50-286 for Indian Point Nuclear Generating Unit No. 3 (IP3). The proposed change will allow a one time extension of the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> completion time of TS 3.7.5, Condition B, Action B.1 "Restore AFW train to OPERABLE status." The specific proposed changes are listed in the following section.2.0 PROPOSED CHANGES The proposed TS change is as follows: Change that portion of the TS 3.7.5, Condition B Completion Time from"72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> To"72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (1)(1) A one time extension to 106 hours0.00123 days <br />0.0294 hours <br />1.752645e-4 weeks <br />4.0333e-5 months <br /> during the first 45 days after amendment approval for repairs to AFW pump 32." The marked up Technical Specification page showing this change is in Attachment
2.3.0 BACKGROUND
The Auxiliary Feedwater System (AFWS) is used for plant startup. It also supplies high pressure feedwater to the steam generators.
This feedwater supply is needed to maintain sufficient water inventory in the steam generators to allow removal of decay heat from the Reactor Coolant System by secondary steam releases in the event that the Main Feedwater System is unavailable.
The AFWS loop utilizes a steam turbine driven auxiliary boiler feedwater pump (ABFP) and two motor driven ABFPs. The design ensures that at least two of the four steam generators will not boil dry and that the Primary Coolant System will not relieve water through the pressurizer relief/safety valves following a loss of main feedwater flow.After a start signal, steam flow to the turbine for the steam driven pump must be throttled manually in order to bring the turbine up to speed. In addition, the steam driven pump discharge flow control valves are manually opened as necessary to provide adequate auxiliary feedwater flow. The steam turbine driven pump was designed to supply 800 gpm of feedwater flow to the steam generators, conservatively assumed to be 596 gpm in the relevant Chapter 14 analyses.
These analyses evaluate the feedwater supply needed to maintain sufficient water inventory in the steam generators to allow removal of decay heat from the Reactor Coolant System by secondary steam releases in the event that the Main Feedwater System is unavailable.
NL-09-167 Docket No. 50-286 Attachment 1 Page 2 of 8 Redundancy and diversity of auxiliary feedwater supply is provided by utilizing two different types of motive power to the pumps. One supply utilizes the steam turbine driven pump and the other utilizes two redundant motor driven pumps. The steam turbine driven pump is capable of delivering auxiliary feedwater to all four steam generators.
Each motor driven pump is capable of providing auxiliary feedwater to two steam generators.
The design ensures that at least two of the four steam generators will not boil dry and that the Primary Coolant System will not relieve water through the pressurizer relief/safety valves following a loss of main feedwater flow. One motor driven pump has sufficient capacity to maintain a sufficient water inventory in the steam generators to which it is connected, preventing relief through the primary coolant system pressurizer relief valve following a reactor/turbine trip. Thus, in the event of a loss of the steam driven pump, a single motor driven pump is adequate to ensure safety of the public.The purpose of the current TS request is to allow online assessment and repair of the steam driven 32 ABFP. On November 23, 2009 the 32 ABFP was found to have high axial vibrations.
Previously, the 32 ABFW pump had been running with a 0.3 inches per second axial vibration.
Assessment of the high vibrations included replacement of the oil and inspection of the coupling.The coupling proved not to be the issue and the oil sample showed high levels of tin and iron indicating wear of the turbine journal thrust bearings and leaching of iron from the turbine bearing housing. Both were known conditions.
The bearing housing requires a coating to prevent leaching and this is being evaluated but there are no unacceptable consequences.
The bearing oil high tin content was determined to be higher during the last refuel outage. This was prior to the replacement of the turbine outboard journal bearing during that outage. The 32 ABFW pump was tested after the November work and the vibrations steadied out at 0.6 inches per second which is acceptable for operability but places the pump in the alert range. This testing was done using a digital vibration monitor which has a higher frequency response than the analog meter used during quarterly testing. An operability evaluation concluded the potential cause of the increased vibration was pump to turbine misalignment which was insufficient to affect the safety mission of the pump.An exigent TS change is being requested in order to further evaluate the cause of the high vibrations, to inspect / replace the bearing and to perform other corrective actions as needed to increase the reliability of the pump. The exigent TS is being sought in order to avoid the potential for the 32 ABFP to degrade. Since the mission time of the turbine pump is fairly short, the 32 ABFP pump is credited for 29 hours3.356481e-4 days <br />0.00806 hours <br />4.794974e-5 weeks <br />1.10345e-5 months <br /> prior to transfer to the residual heat removal system, there is no reason to believe the pump would not perform as required.
The vibrations have been steady at 0.6 inch per second during the last test and it is expected they would remain there. Performing further assessment
/ repairs would provide greater assurance that the pump will not see an unexpected increase in vibrations in future testing. In order to allow the assessments and potential bearing replacement the exigent TS change is being requested.
The preferred timing is to allow the pump to be fixed prior to testing to avoid any potential for increased vibration due to more frequent testing. In the alert stage, the pump is tested at half the normal interval which would require testing by January 9, 2010.The planned work tasks, schedule and potential concerns with the schedule are as follows:* Check cold alignment using optiline (to verify alignment)
-5 hours* Check footprint adequacy using optiline -6 hours* Loosen steam inlet pipe and check effect on alignment using optiline -7 hours" Remove bearing covers and assess -9 hours* Replace journal and thrust bearings as required (fit up, align, etc) -43 hours NL-09-167 Docket No. 50-286 Attachment 1 Page 3 of 8" Clear tag out, perform 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> run, reapply tag out -4 hours" Perform hot alignment and adjustments
-11.25 hour2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />s* Uncouple pump / turbine and perform overspeed test -3 hours* Recouple turbine and perform quarterly run -4 hours The request includes 13.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> for contingency should some step of the planned work go wrong.For example, inspection results requiring further engineering evaluation such as tolerance deviation on mating surfaces / piping strain that may increase the work scope.4.0 TECHNICAL ANALYSIS The one time extension of an allowed outage time is requested based on compensatory measures that will be taken to reduce the risk that the AFWP will be required and an evaluation of the risk associated with the extension.
The request is to allow a 34 hour3.935185e-4 days <br />0.00944 hours <br />5.621693e-5 weeks <br />1.2937e-5 months <br /> extension of the AOT within 45 days of the TS change which will allow the repairs to be performed before the next surveillance test or shortly thereafter.
Feed and bleed of the primary system is the only alternative to the use of the auxiliary feed water system so the extension to the allowed outage is based on compensatory actions. Compensatory measures will be taken to reduce the risk associated with the extension; these are based on both event mitigation and initiating event likelihood.
In order to minimize risk during the period of noncompliance, IP3 proposes the following actions when the 32 ABFWP is out of service: 1. No equipment directly associated with motor driven auxiliary feedwater pumps 31 and 33 will be removed from service.2. No equipment associated with the AC power system will be removed from service or worked on for the duration of the 32 ABFP allowed completion time. This includes work on the offsite circuit and EDGs 31, 32, and 33. The offsite circuit, emergency diesel generators 31, 32, and 33, and motor driven auxiliary feedwater pumps 31 and 33 will be protected with physical barriers and administrative controls (posting of protected train signage), preventing work on this equipment.
- 3. Access will be limited to the following areas important for maintaining the plant in a stable condition:
auxiliary feedwater pump room, diesel generators 31, 32, and 33 rooms, control building-15 foot switchgear room and 125 volt dc battery charger and station battery rooms.Access will be controlled by posted signs requiring approval by the operations shift manager prior to entry.4. The following equipment will be protected by critical plant equipment sign(s) during the time the 32 ABFP is out of service:* Motor Driven Auxiliary Feedwater Pumps 31 and 33* Emergency Diesel Generators 31, 32, and 33* 125V DC Power Panels 32 and 33 and 125V DC Batteries 32 and 33* Safety Injection Pumps 31, 32 and 33* Component Cooling Water Pumps 31, 32 and 33* Service Water Pumps 31, 32, 33, 34, 35 and 36* Residual Heat Removal Pumps 31 and 32* EDG Room 31, 32 and 33 Ventilation System NL-09-167 Docket No. 50-286 Attachment 1 Page 4 of 8* PORVs (PCV-455C
& 456) and associated block valve (535 & 536, respectively)
- 5. The physical barriers referenced above will be verified shiftly for the duration of the inoperability of the 32 ABFP and logged in the Operations log.6. No switchyard work will be allowed.7. The C02 suppression in the Switchgear Room and Cable Spreading Room will be ensured to remain available 8. Hot work will be prohibited in Control Building Switchgear Rooms, Batteries and Chargers, Cable Spreading Room, Electric Tunnels, EDG Rooms 31, 32, and 33, and Auxiliary Feedwater Pump Room. Transient combustible loading in these rooms will be minimized as well.9. IP3 will discuss with the grid operator the IP3 condition and the need for heightened sensitivity and continual monitoring of grid conditions to anticipate challenges to offsite power availability.
- 10. Operators will be briefed on sensitivity to safety bus electrical power supply issues to recognize and respond expeditiously to a station black out or loss of offsite power event.11. A continuous fire / flood watch will be implemented in Auxiliary Feedwater Pump Room, Cable Spreading Room, 31 EDG Room and Control Building Switchgear Room until 32 ABFP is declared operable.
The 10 inch fire header pipe going through the switchgear room will be isolated during the allowed outage time.12. Trip risks which could lead to Main Turbine trips or impact main condenser will be identified and avoided.13. If an equipment failure occurs that could affect the margin to safety on the remaining auxiliary feedwater pump 31 or 33 secondary cooling function, the operations manager will be contacted to notify the NRC and convene an onsite safety review committee meeting to evaluate plant status, and determine if the basis for the license amendment is affected.14. The plant operations crew will be briefed on these risk management measures.15. Prior to initiating any work on 32 ABFP the weather will be assessed to assure there are no severe weather conditions forecasted for the proposed period of work that would require entry into the severe weather procedure.
This is to assure no plant vulnerabilities related to weather conditions exist.It can be concluded that the proposed change does not involve a significant increase in the probability of an accident previously evaluated or create the possibility of a new or different kind of accident from any accident previously evaluated.
The extension of the allowed outage time does not increase the probability of an accident since the availability of the pump does not affect accident probability.
The extension of the allowed outage time does not alter any plant equipment, change the manner in which the plant is operated or revise any operating procedure so no new or different kind of accident is possible.
It can be concluded that the proposed change does not involve a significant increase in the consequences of an accident previously evaluated or result in a significant reduction in a margin of safety. The unavailability of the 32 AFWP does not significantly increase the consequences of an accident since a single failure of this pump is already NL-09-167 Docket No. 50-286 Attachment 1 Page 5 of 8 evaluated in accidents.
This assumption is still applicable since there is no significant decrease in the margin of safety. The margin of safety of continued IP3 operation with ABFP 32 out of service during a 34 hour3.935185e-4 days <br />0.00944 hours <br />5.621693e-5 weeks <br />1.2937e-5 months <br /> extension of the allowed outage time is acceptable.
The increase in core damage frequency (CDF) associated with continued IP3 operation with ABFP 32 out of service for a duration of 106 hours0.00123 days <br />0.0294 hours <br />1.752645e-4 weeks <br />4.0333e-5 months <br /> (which represents a 34 hour3.935185e-4 days <br />0.00944 hours <br />5.621693e-5 weeks <br />1.2937e-5 months <br /> period beyond the current allowed outage time)is 3.9E-5 per reactor year (ry). This results in an incremental conditional core damage probability (ICCDP) of 4.8E-07, which is below the ICCDP guidance threshold of 5E-07 identified in NRC Inspection Manual Part 9900. The ICCDP includes risk for external events such as seismic, fire, and flood. The increase in large early release frequency (LERF) was estimated as 4.2E-7/ry (including external events), which results in an incremental conditional large early release probability (ICLERP) of 5.1 E-9. The CDF and LERF results were generated using the baseline model which includes nominal maintenance unavailabilities for PSA-modeled components.
For determining the impact on CDF associated with having 32 ABFP out of service, credit was taken for the following compensatory measures: 1. The fire non-suppression probabilities for the Switchgear Room, Cable Spreading Room, 31 EDG Room and ABFP Room were reduced by a factor of 10 to credit the continuous fire watch that will be implemented while 32ABFP is out of service.2. The frequency of an event associated with the rupture of the 10-inch fire protection deluge line in the switchgear room was reduced by a factor of 10 to reflect that this line will be isolated while 32ABFP is out of service. This is conservative since with the line isolated, a rupture of the fire protection piping will not result in failure of the switchgear due to flooding.3. Credit was taken for the fact that no maintenance will be allowed which could adversely impact availability of any EDG, remaining motor-driven ABFP or safety injection pump.4. Credit was taken for operator action to recover a fast transfer failure should a loss of 125VDC Power Panel 32 occur, assuming a non-recovery failure probability of 0.1.Because this action is proceduralized but is not credited in the baseline model, the baseline risk was adjusted (decreased) to take credit for this recovery action. This is conservative compared with the nominal baseline risk since it results in a higher increase in risk due to a lower baseline value.While additional compensatory measures are also being implemented to further reduce risk and provide additional defense-in-depth, no quantitative credit was taken for compensatory measures other than the ones listed directly above.5.0 REGULATORY ANALYSIS 5.1 No Significant Hazards Consideration Entergy Nuclear Operations, Inc. (Entergy) has evaluated the safety significance of the proposed change to the Indian Point 3 Technical Specification which revise the allowed outage time for the 32 Auxiliary Boiler Feedwater pump by 34 hours3.935185e-4 days <br />0.00944 hours <br />5.621693e-5 weeks <br />1.2937e-5 months <br /> for one time repair work. The proposed changes have been evaluated 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:
NL-09-167 Docket No. 50-286 Attachment 1 Page 6 of 8 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
No. The proposed change revises the allowed outage time (AOT) for the steam driven Auxiliary Boiler Feedwater Pump (ABFP) on a one time basis. Revising the AOT is not an accident initiator since an ABFP is a mitigating system. Therefore the proposed changes do not increase the probability of an accident occurring.
The proposed AOT change is a one time increase that will allow repairs without the transient of shutdown.
The plant is designed for single failure and recognizes that inoperability for short periods does not cause a significant increase in the consequences of an accident.
The one time increase in this outage time is compensate*d with measures to reduce the potential need for the ABFP and the effects of events that could require the pump. Therefore the increase does not significantly increase the consequences of an accident.
Therefore the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the change create the possibility of a new or different kind of accident from any accident previously evaluated?
No. The proposed change revises the allowed outage time for the ABFP on a one time basis. The proposed change does not involve installation of new equipment or modification of existing equipment, so no new equipment failure modes are introduced.
The proposed revision is not a change to the way that the equipment or facility is operated or analyzed and no new accident initiators are created. Therefore the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does the proposed change involve a significant reduction in a margin of safety?No. The reduction in the margin of safety associated with continued IP3 operation with Auxiliary Boiler Feedwater (ABF) pump 32 out of service during a 34 hour3.935185e-4 days <br />0.00944 hours <br />5.621693e-5 weeks <br />1.2937e-5 months <br /> period beyond current allowed outage time is represented by an increase of approximately 50 percent in the allowed outage time. This change in the margin of safety has been compensated for by specific compensatory measures to reduce the potential need for the pump and to address postulated events that could require the pump. The increase in core damage frequency (CDF) associated with continued IP3 operation with ABFP 32 out of service for a duration of 106 hours0.00123 days <br />0.0294 hours <br />1.752645e-4 weeks <br />4.0333e-5 months <br /> which represents a 34 hour3.935185e-4 days <br />0.00944 hours <br />5.621693e-5 weeks <br />1.2937e-5 months <br /> period beyond the current allowed outage time) is 3.9E-5 per reactor year (ry) This results in an incremental conditional core damage probability (ICCDP) of 4.8E-07, which is below the ICCDP guidance threshold of 5E-07 identified in NRC Inspection Manual Part 9900. The ICCDP includes risk due to external events due to seismic, fire, and flood. The increase in large early release frequency (LERF)was estimated as 4.2E-7/ry (including external events), which results in an incremental conditional large early release probability (ICLERP) of 5.1 E-9. Therefore the proposed change does not involve a significant reduction in a margin of safety.Based on the above, Entergy concludes that the proposed amendment to the Indian Point 3 Technical Specification presents no significant hazards consideration under the standards set forth in 10 CFR 50.92 (c), and, accordingly, a finding of "no significant hazards consideration" is justified.
NL-09-167 Docket No. 50-286 Attachment 1 Page 7 of 8 5.2 Applicable Regulatory Requirements
/ Criteria The proposed extension of the allowed outage time does not affect design and therefore does not affect compliance with: 1. GDC 2 requirements since there is no effect related to structures housing the system and the system itself being capable of withstanding the effects of earthquakes, tornados and floods.2. GDC 4 requirements since there is no effect on the capability of structures housing the system and the system itself being capable of withstanding the effects of external missiles and internally generated missiles, pipe whip, and jet impingement forces associated with pipe breaks.3. GDC 5 requirements since there are no required shared systems and components important to safety to perform required safety functions.
- 4. GDC 19 requirements since there is no effect on the design capability of system instrumentation and controls for prompt hot shutdown of the reactor and potential capability for subsequent cold shutdown.5. GDC 45 requirements since there is no effect on the provisions made to permit periodic in service inspection of system components and equipment.
- 6. GDC 46 requirements to permit appropriate functional testing of the system and components to assure structural integrity and leak-tightness, operability and performance of active components, and capability of the integrated system to function as intended during normal, shutdown, and accident conditions since none of these are affected.7. 10 CFR 50.62 requirements for automatic initiation of the AFWS.The extension of the allowed outage time for the ABFP can affect the capability to comply with the following criteria: 1. GDC 34 and 44 requirements to assure redundancy of components for performance of the safety function under accident conditions, assuming a single active component failure (perhaps coincident with the loss of offsite power for certain events) would be slightly affected but within the acceptable margins of safety.2. 10 CFR 50.63 requirements for withstanding and recovering from a station blackout, including an acceptable degree of independence from the ac power system and the capability for removal of decay heat at an appropriate rate for an appropriate duration would be slightly affected but within the acceptable margins of safety.3. 10 CFR 50.48 requirements for fire protection including shutdown and decay heat removal would be slightly affected but within the acceptable margins of safety.In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and NL-09-167 Docket No. 50-286 Attachment 1 Page 8 of 8 (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.5.3 Environmental Considerations The proposed change to the IP3 Technical Specifications does 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.
6.0 PRECEDENCE
No specific approvals for an extension to the allowed outage time for the auxiliary boiler feedwater pump were identified.
A notice of enforcement discretion was granted to South Texas Project, Unit 1, by letter dated December 20, 2006.
ATTACHMENT 2 TO NL-09-167 MARKUP OF TECHNICAL SPECIFICATION PAGE FOR PROPOSED CHANGE REGARDING ONE TIME EXTENSION OF THE AUXILIARY BOILER FEEDPUMP ALLOWED OUTAGE TIME Changes indicated by lineout for deletion and Bold/Italics for additions ENTERGY NUCLEAR OPERATIONS, INC.INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 DOCKET NO. 50-286 AFW System 3.7.5 3.7 PLANT SYSTEMS 3.7.5 Auxiliary Feedwater (AFW) System LCO 3.7.5 Three AFW trains shall be OPERABLE.--------------------------------
NOTE -------------------------
Only one AFW train, which includes a motor driven pump capable of supporting the credited steam generator(s), is required to be OPERABLE in MODE 4.APPLICABILITY:
MODES 1, 2, and 3, MODE 4 when steam generator is relied upon for heat removal.ACTIONS-----------
NOTE------------
LCO 3.0.4.b is not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. One steam supply to A.1 Restore steam supply 7 days turbine driven AFW to OPERABLE status.pump inoperable.
AND 10 days from discovery of failure to meet the LCO B. One AFW train B.1 Restore AFW train to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (1)inoperable in MODE 1, 2 OPERABLE status.or 3 for reasons other AND than Condition A.10 days from discovery of failure to meet the LCO (1) A one time extension to 106 hours0.00123 days <br />0.0294 hours <br />1.752645e-4 weeks <br />4.0333e-5 months <br /> during the first 45 days after amendment approval for repairs to AFW pump 32.(continued INDIAN POINT 3 3.7.5-1 Amendment L2-24 ATTACHMENT 3 TO NL-09-167 COMMITMENTS ENTERGY NUCLEAR OPERATIONS, INC.INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 DOCKET NO. 50-286 NL-09-167 Docket No. 50-286 Attachment 3 Page 1 of 3 List of Commitments Commitment Commitment Due Number NL-09-167-01 In order to minimize risk during the period of noncompliance, At time of IP3 has identified additional controls to increase operator entry into awareness of critical equipment, provide assurance that 32 ABFP assumptions in the risk model are maintained, and minimize the AOT with likelihood of a plant transient.
IP3 proposes the following one time actions for the extended completion time to manage risk: extension 1. No equipment directly associated with motor driven auxiliary feedwater pumps 31 and 33 will be removed from service.2. No equipment associated with the AC power system will be removed from service or worked on for the duration of the 32 ABFP allowed completion time. This includes work on the offsite circuit and EDGs 31, 32, and 33. The offsite circuit, emergency diesel generators 31, 32, and 33, and motor driven auxiliary feedwater pumps 31 and 33 will be protected with physical barriers and administrative controls (posting of protected train signage), preventing work on this equipment.
- 3. Access will be limited to the following areas important for maintaining the plant in a stable condition:
auxiliary feedwater pump room, diesel generators 31, 32, and 33 rooms, control building-15 foot switchgear room and 125 volt dc battery charger and station battery rooms. Access will be controlled by posted signs requiring approval by the operations shift manager prior to entry.4. The following equipment will be protected by critical plant equipment sign(s) during the time the 32 ABFP is out of service:* Motor Driven Auxiliary Feedwater Pumps 31 and 33* Emergency Diesel Generators 31, 32, and 33* 125V DC Power Panels 32 and 33 and 125V DC Batteries 32 and 33" Safety Injection Pumps 31, 32 and 33* Component Cooling Water Pumps 31, 32 and 33* Service Water Pumps 31, 32, 33, 34, 35 and 36" Residual Heat Removal Pumps 31 and 32* EDG Room 31, 32 and 33 Ventilation System NL-09-167 Docket No. 50-286 Attachment 3 Page 2 of 3 PORVs (PCV-455C
& 456) and associated block valve (535 & 536, respectively)
- 5. The physical barriers referenced above will be verified shiftly for the duration of the inoperability of the 32 ABFP and logged in the Operations log.6. No switchyard work will be allowed.7. The C02 suppression in the Switchgear Room and Cable Spreading Room will be ensured to remain available 8. Hot work will be prohibited in Control Building Switchgear Rooms, Batteries and Chargers, Cable Spreading Room, Electric Tunnels, EDG Rooms 31, 32, and 33, and Auxiliary Feedwater Pump Room. Transient combustible loading in these rooms will be minimized as well.9. IP3 will discuss with the grid operator the IP3 condition and the need for heightened sensitivity and continual monitoring of grid conditions to anticipate challenges to offsite power availability.
- 10. Operators will be briefed on sensitivity to safety bus electrical power supply issues to recognize and respond expeditiously to a station black out or loss of offsite power event.11. A continuous fire / flood watch will be implemented in Auxiliary Feedwater Pump Room, Cable Spreading Room, 31 EDG Room and Control Building Switchgear Room until 32 ABFP is declared operable.
The 10 inch fire header pipe going through the switchgear room will be isolated during the allowed outage time.12. Trip risks which could lead to Main Turbine trips or impact main condenser will be identified and avoided.13. If an equipment failure occurs that could affect the margin to safety on the remaining auxiliary feedwater pump 31 or 33 secondary cooling function, the operations manager will be contacted to notify the NRC and convene an onsite safety review committee meeting to evaluate plant status, and determine if the basis for the license amendment is affected.14. The plant operations crew will be briefed on these risk.manaaement measures.
NL-09-167 Docket No. 50-286 Attachment 3 Page 3 of 3 15. Prior to initiating any work on 32 ABFP the weather will be assessed to assure there are no severe weather conditions forecasted for the proposed period of work that would require entry into the severe weather procedure.
This is to assure no plant vulnerabilities related to weather conditions exist.