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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: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:Bases Change
MONTHYEARML20259A2162020-09-14014 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 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 ML14287A3002014-09-17017 September 2014 Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Specification Bases List of Effective Sections 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 ML14268A3532014-09-15015 September 2014 Proposed License Amendment Re an Exigent Change to Technical Specification 3.8.6, Station Battery Surveillance 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 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 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 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 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 ML0702903522007-01-19019 January 2007 Revision 0 to IPEC Site Management Manual, IP-SMM-AD-103, IP3 Its/Bases ML0631905242006-04-19019 April 2006 Technical Specification Bases Manual, IP-SMM-AD-103 ML0620003692006-04-19019 April 2006 Update to IP3 Technical Specifications Bases ML0532004452005-10-28028 October 2005 Technical Specification Bases Changes ML0523702312005-08-0808 August 2005 Technical Specification Bases ML0510903802005-03-31031 March 2005 Technical Specification Bases ML0507500422005-02-0303 February 2005 Technical Specification Bases ML0506705222005-02-0303 February 2005 Technical Specification Bases ML0503303642005-01-19019 January 2005 Transmittal of Indian Point, Unit 3 Technical Specifications Bases ML0436303732004-12-10010 December 2004 Technical Specification Bases ML0318205862003-06-18018 June 2003 Transmittal of Indian Point 3 Technical Specification Bases ML0311204822003-03-28028 March 2003 Transmittal of Technical Specification Bases ML0311403632003-03-18018 March 2003 Transmittal of Technical Specification Amendment 215 ML0311403592003-03-18018 March 2003 Controlled Document Transmittal Form No. 27784 ML0218401362002-06-0505 June 2002 Proposed Changes to Technical Specifications: Selective Adoption of Alternate Source Term and Incorporation of Generic Changes; TSTF-51, TSTF-68; & TSTF-312 NL-02-037, Technical Specification Bases Changes2002-03-28028 March 2002 Technical Specification Bases Changes NL-02-024, Submittal of Technical Specifications Bases Changes for Indian Point Unit 22002-03-0101 March 2002 Submittal of Technical Specifications Bases Changes for Indian Point Unit 2 2020-09-14
[Table view] Category:Updated Final Safety Analysis Report (UFSAR)
MONTHYEARML22257A1272022-09-14014 September 2022 Biennial Defueled Safety Analysis Report Update, and Regulatory Commitment Change Summary - September 2020 to September 2022 ML20259A2022020-09-14014 September 2020 Defueled Safety Analysis Report, Chapter 1, Introduction and Summary ML20259A2072020-09-14014 September 2020 Defueled Safety Analysis Report, Chapter 6, Safety Analysis ML20259A2152020-09-14014 September 2020 Defueled Safety Analysis Report, Table of Contents ML20259A2122020-09-14014 September 2020 Defueled Safety Analysis Report, Appendix a, License Renewal ML20259A2112020-09-14014 September 2020 Updated Final Safety Analysis Report, Chapter 11, Figures ML20259A2032020-09-14014 September 2020 Defueled Safety Analysis Report, Chapter 2, Site and Environment ML20259A2012020-09-14014 September 2020 Summary Report of Indian Point Unit 2 Updated Final Safety Analysis Report, Revision 27 to Defueled Safety Analysis Report, Revision 0, Changes ML20259A2142020-09-14014 September 2020 Defueled Safety Analysis Report, Instructions and Key to Unit 2 DSAR Revision 0 ML20259A2062020-09-14014 September 2020 Defueled Safety Analysis Report, Chapter 5, Conduct of Facility Activities ML20259A2102020-09-14014 September 2020 Updated Final Safety Analysis Report, Chapters 3 Through 5, Figures ML20259A2092020-09-14014 September 2020 Updated Final Safety Analysis Report, Chapter 2, Figures ML20259A2132020-09-14014 September 2020 Defueled Safety Analysis Report, Appendix B, Technical Requirements Manual (TRM) ML20259A2082020-09-14014 September 2020 Updated Final Safety Analysis Report, Chapter 1, Figures ML20259A2052020-09-14014 September 2020 Defueled Safety Analysis Report, Chapter 4, Waste Disposal and Radiation Protection System ML20259A2042020-09-14014 September 2020 Defueled Safety Analysis Report, Chapter 3, Facility Design and Operation ML20259A2162020-09-14014 September 2020 Defueled Safety Analysis Report, Appendix a, Permanently Defueled Technical Specifications Bases NL-18-069, Submittal of Revision 27 to Updated Final Safety Analysis Report2018-09-17017 September 2018 Submittal of Revision 27 to Updated Final Safety Analysis Report ML17354A0152017-11-28028 November 2017 Enclosure 2 - NET-28091-003-01NP, Rev. 0, Criticality Safety Analysis for the Indian Point Unit 2 Spent Fuel Pool with No Absorber Panel Credit IR 05000247/20160092016-11-21021 November 2016 Davis-Besse Nuclear Power Station, Unit 1, Revision 31 to Updated Final Safety Analysis Report, Drawing E-0058B, Rev 12, Sheet 0015A ML16280A2082016-09-19019 September 2016 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 9, Auxiliary and Emergency Systems, Drawing No. 9321-F-2736-130 to Drawing No. 138248-9 ML16280A1652016-09-19019 September 2016 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26 - Chapter 3, Reactor, Figures ML16280A2072016-09-19019 September 2016 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 9, Auxiliary and Emergency Systems, Figures 9.2-1 to 9.9-1 NL-16-109, Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 16, Instructions and Key2016-09-19019 September 2016 Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 16, Instructions and Key NL-16-109, Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 14, Safety Analysis, Figures 14.0-1 to 14.1-672016-09-19019 September 2016 Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 14, Safety Analysis, Figures 14.0-1 to 14.1-67 ML16280A1952016-09-19019 September 2016 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26 - Chapter 7, Instrumentation and Control, Drawings NL-16-109, Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 17, Table of Contents2016-09-19019 September 2016 Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 17, Table of Contents NL-16-109, Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 11, Waste Disposal and Radiation Protection System, Drawing No. 9321-F-2719-136 to Drawing No. 9321-F-2730-752016-09-19019 September 2016 Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 11, Waste Disposal and Radiation Protection System, Drawing No. 9321-F-2719-136 to Drawing No. 9321-F-2730-75 NL-16-109, Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 12, Conduct of Operations2016-09-19019 September 2016 Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 12, Conduct of Operations NL-16-109, Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 11, Waste Disposal and Radiation Protection System2016-09-19019 September 2016 Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 11, Waste Disposal and Radiation Protection System NL-16-109, Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 10, Steam and Power Conversion System, Figure 10.1-1, Revision 21 to Figure 10.2-92016-09-19019 September 2016 Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 10, Steam and Power Conversion System, Figure 10.1-1, Revision 21 to Figure 10.2-9 NL-16-109, Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 10, Steam and Power Conversion System, Figures 10.2-1 to 10.2-72016-09-19019 September 2016 Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 10, Steam and Power Conversion System, Figures 10.2-1 to 10.2-7 NL-16-109, Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 11, Waste Disposal and Radiation Protection System, Figure 11.1-1 to Figure 11B-52016-09-19019 September 2016 Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 11, Waste Disposal and Radiation Protection System, Figure 11.1-1 to Figure 11B-5 NL-16-109, Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 13, Tests and Operations2016-09-19019 September 2016 Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 13, Tests and Operations NL-16-109, Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 14, Safety Analysis2016-09-19019 September 2016 Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 14, Safety Analysis ML16280A2202016-09-19019 September 2016 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 14, Safety Analysis, Figures 14.2-0 to 14.2-18 ML16280A2242016-09-19019 September 2016 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 17, Table of Contents ML16280A2232016-09-19019 September 2016 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 16, Instructions and Key ML16280A1962016-09-19019 September 2016 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26 - 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I Indian Point Energy Center 450 Broadway, GSB En y P.O. Box 249 Buchanan, N.Y. 10511-0249 Tel (914) 734-6700 J. Pollock.
Site Vice President Administrat~on October 20, 2008 Re: Indian Point Unit No. 2 Docket No. 50-247 NL-08-163 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station O-Pl-17 Washington, D.C. 20555-0001
Subject:
Indian Point 2 (IP2) Nuclear Power Plant Amendment Update to the Final Safety Analysis Report (FSAR), Revision 21
References:
- 1. NEI 98-03, "Guidelines for Updating Final Safety Analysis Reports," Revision 1, June 1999
- 2. NEI 99-04, "Guidelines for Managing NRC Commitments,"
Revision 2, December 1995
Dear Sir or Madam:
Entergy Nuclear Operations, Inc. (Entergy), in accordance with 10 CFR 50.71(e), hereby transmits the most recent update to the Updated Final Safety Analysis Report (UFSAR) for Indian Point Unit 2 (IP2). This submittal incorporates applicable changes made to the IP2 facility since the last UFSAR update in November 15, 2006, through the information available as of April 20, 2008, the completion of the last IP2 refueling outage. This submittal constitutes the twenty first (21) revision to the IP2 UFSAR.
As was done with previous versions of the IP2 UFSAR, this revision is being submitted on CD-ROM, and contains the entire IP2 UFSAR in Adobe Acrobat PDF format. The CD-ROM was prepared in accordance with the guidance contained in the NRC Electronic Submissions Final Rule issued October 10, 2003.
UFSAR changes to the text and tables since the last revision are indicated by gray highlighted background rather than a revision bar next to the line containing the change.
Any UFSAR figures that have been revised since the last revision contain "Rev. 21" in the figure title block.
This update to the FSAR also contains information that has been classified as "Historical" information according to the NEI 98-03 definition (Reference 1), and is no longer subject to updating. Material designated as "Historical" information in the UFSAR is indicated by a green highlighted background.
Docket No. 50-247 NL-08-163 Page 2 of 3 IP2 Technical Specification 5.5.12.d, "Technical Specification Bases Control Program,"
requires that changes to the Bases implemented without prior NRC approval be provided to the NRC on a frequency consistent with 10 CFR 50.71(e). The required information is provided in Attachment 1, "Summary of Revisions to the IP2 Technical Specification Bases". , "Revisions to IP2 Docketed Commitments," submits a summary update of all changes made to the Unit 2 docketed commitments using the NEI 99-04 guidance (Reference 2) for determination of commitments which do not have either a safety or regulatory significance, which may be changed without prior interaction with the NRC staff and which require periodic NRC staff, notification either annually or along with the FSAR updates as required by 10 CFR 50.71(e).
As specified in NEI 98-03 (Reference 1), the Technical Requirements Manual (TRM) is controlled in a manner consistent with procedures fully or partially described in the UFSAR. Under this approach, the TRM document is subject to the change control requirements of 10 CFR 50.59 and the update/reporting requirements of 10CFR50.71(e). Attachment 3 of this letter, "Summary of Revisions to the IP2 Technical Requirements Manual (TRM)," submits the summary of changes to the IP2 TRM for the same time period as the IP2 FSAR update. of this letter, "Summary Report to the NRC of Revision 21 UFSAR Changes," contains a summary with a brief description of the information changed in this revision to the IP2 UFSAR.
Entergy is making no new commitments in this letter.
Should you or your staff have any questions regarding this submittal, please contact Mr.
Robert Walpole, Manager, Licensing, Indian Point Energy Center (IPEC) at (914) 734-6710.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on O\ zt\o 9D Date Sincerely, Pollock Site Vice President Indian Point Energy Center
Docket No. 50-247 NL-08-163 Page 3 of 3
Attachment:
- 1. Summary of Revisions to the IP2 Technical Specification Bases
- 2. Revisions to IP2 Docketed Commitments
- 3. Summary of Revisions to the IP2 Technical Requirements Manual (TRM)
- 4. Summary Report of IP2 Revision 21 UFSAR Changes
Enclosure:
CD-ROM containing the IP2 UFSAR (Rev. 21) files cc w/o enclosure:
Mr. John P. Boska, Senior Project Manager, NRC NRR DORL NRC Resident Inspector's Office, Indian Point Energy Center Mr. Paul Eddy, NYS Department of Public Service
ATTACHMENT 1 TO NL-08-163
SUMMARY
OF REVISIONS TO THE IP2 TECHNICAL SPECIFICATION BASES ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 DOCKET NO. 50-247
NL-08-163 Attachment 1 Page 1 of 7 CHANGES TO INDIAN POINT 2 TECHNICAL SPECIFICATION BASES (for period November 2007 through October 14, 2008)
AFFECTED EFFECTIVE SECTIONS REV DATE DESCRIPTION Initial issue of Bases derived from NUREG-1431, in ALL 0 11/3/2003 conjunction with Technical Specification Amendment 238 for conversion of 'Current Technical Specifications' to
'Improved Technical Specifications'.
BASES UPDATE PACKAGE 01-12102003 B 3.1.6 1 12/10/2003 Various wording clarifications based on Licensed Operator B 3.3.1 feedback during trial run of ITS.
B 3.3.2 B 3.3.4 B 3.4.15 B 3.4.16 B 3.5.2 B 3.6.3 B 3.6.6 B 3.6.10 B 3.7.7
'BASES UPDATE PACKAGE 02-03042004..
B 3.8.9 1 03/04/2004 Remove 'MCC 210' from Table B 3.8.9-1, per 50.59 screen BASES UPDATE PACKAGE 03-08092004 B 3.3.1 2 08/09/2004 Clarification of testing in bypass, per 50.59 screen.
B 3.3.5 1 08/09/2004 Clarify requirements for performing a Trip Actuating Device Operational Test (TADOT) on the 480Volt SBO, degraded grid and undervoltage relays, per 50.59 screen.
B 3.7.10 1 08/09/2004 CRVS Fan terminology correction, per 50.59 screen.
B 3.8.7 1 08/09/2004 Clarification of inverter operability with frequency out-of-range, per 50.59 screen.
B 3.8.9 2 08/09/2004 Update Table 3.8.9-1 for safeguards MCC's, per 50.59 screen.
B 3.9.4 1 08/09/2004 Installation of a roll-up door on the Containment Equipment Hatch, per 50.59 Evaluation 04-0732-MD B 3.9.5 1 08/09/2004 RE.
NL-08-163 Attachment 1 Page 2 of 7 AFFECTED EFFECTIVE SECTIONS REV DATE DESCRIPTION BASES UPDATE PACKAGE 04-10222004 B 3.4.7 1 10/22/2004 Clarification on SG coupled to remove residual heat to provide additional operating flexibility while remaining consistent with the guidance of IN 95-35, per 50.59 screen.
BASES UPDATE PACKAGE 05-11222004 B 3.3.2 2 11/22/2004 Stretch Power Uprate (3.26%) from 3114.4 MWth to B 3.4.1321611/22/2004 MWth.
B 3.4.1 1 B 3.4.9 B 3.5.4
'BASES UPDATE PACKAGE 06-12132004 B 3.1.1 1 12/13/2004 Stretch Power Uprate (3.26%) from 3114.4 MWth to B 3.2.2 3216 MWth.
B 3.3.1 3 B 3.3.2 B 3.3.6 B 3.3.7 1 B 3.4.13 B 3.4.16 2 B 3.6.1 1 B 3.6.2 B 3.6.3 2 B 3.6.4 B 3.6.7 B 3.7.3 1 B 3.7.4 B 3.7.5 B 3.7.7 2 B 3.7.8 1 Continued from previous page
NL-08-163 Attachment 1 Page 3 of 7 AFFECTED EFFECTIVE SECTIONS REV DATE DESCRIPTION B 3.7.10 12/13/2004 Stretch Power Uprate (3.26%) from 3114.4 MWth to 3216 MWth.
2 B 3.7.11 B 3.7.14 B 3.8.2 B 3.8.5 B 3.8.8 B 3.8.10 B 3.9.6 BASES UPDATE PACKAGE 07-02252005 B 3.3.1 4 02/25/2005 Clarification on the frequency of Surveillance Requirement 3.3.1.8 to perform a Channel Operational Test (COT) (CR-IP2-2004-04344).
B 3.7.5 2 Clarification on Surveillance Requirement 3.7.5.3 as it relates to plant condition/frequency of performance of Auxiliary Feedwater Pump full flow testing.
BASES UPDATE PACKAGE 08-06102005 B 3.5.2 .2 06/10/2005 Change the Hot Leg Switchover time from 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to 6.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> (as per the latest Westinghouse Power Uprate analyses).
BASES UPDATE PACKAGE 09-08102005 TOC 1 08/10/2005 TOC, B 3.3.3, B 3.6.8 - Removal of Hydrogen B 3.3.3 Recombiners from the bases as per Technical 1 Specification Amendment 243.
B 3.3.4 2 B 3.3.4 - add the circuit breaker and transfer switch B 3.4.13 2 designators to the 21 and 22 RHR pump sections.
B 3.6.8 1 B 3.4.13 - Reference correction - editorial.
B 3.7.10 - Add reference that if the primary coolant B 3.7.10 3 source of containment is in question, refer to ITS 5.5.2.
BASES UPDATE PACKAGE 10-09162005 B 3.6.2 1 09/16/2005 Clarification to reflect the approved TS 5.5.14 which states that the testing program shall be in accordance with RG 1.163.
NL-08-163 Attachment 1 Page 4 of 7 AFFECTED EFFECTIVE SECTIONS REV DATE DESCRIPTION Continued from previous page B 3.6.10 1 09/16/2005 Update LCO and Condition B to clarify required actions consistent with FSAR.
BASES UPDATE PACKAGEI1-11042005, B 3.8.1 1 11/04/2005 Include operability criteria for 138 kV and 13.8 kV offsite circuits.
'BASES UPDATE PACKAGE 12-11102005 B 3.7.3 2 11/10/2005 Assess low flow FBVs and low flow FIVs being opened while at power and the single failure of either valve for MSLB (as per 50.59 Evaluation IP2-05-026384). This supplements the SPU analysis.
BASES UPDATE PACKAGE 13-12212005 B 3.8.1 2 12/21/2005 B 3.8.1 - Allow for the performance of offsite power verifications up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to a planned equipment B 3.9.3 1 outage. Clarify the 22 EDG starting air motor redundancy limitations. Provide for establishing EDG operability on one air start motor when one of the redundant air start motors is inoperable and to provide for a staggered surveillance of operable air start motors.
B 3.9.3 - Reflect the revised fuel decay time assumption used in the updated fuel handling accident analysis performed for the IP2 Stretch Power Uprate Project.
BASES UPDATE PACKAGE 14-02272006 B 3.7.3 3 02/27/2006 Reflect the current design of main FW isolation based on cited documents and made to provide operations with clarification (EVL-IP2-05-026384, Analysis CN-CRA 20 (SPU MSLB)
NL-08-163 Attachment 1 Page 5 of 7 AFFECTED EFFECTIVE SECTIONS REV DATE DESCRIPTION BASES UPDATE PACKAGE 15-04132006 B 3.4.9 2 04/13/2006 B 3.4.9 - Relaxation of the pressurizer water level limit in 4Mode 3.
B 3.7.3 B 3.7.3 - Clarification on electronic valve closure delay assumptions, per 50.59 Evaluation EVL-IP2-05-26384, Rev. 1 BASES UPDATE PACKAGE 16-07062006 B 3.9.1 1 07/06/2006 B 3.9.1 - Clarification on effective method for ensuring 1shutdown margin.
B 3.9.2 B 3.9.2 - Editorial change to make the bases consistent with TS 3.3.1.
BASES UPDATE PACKAGE 17-08152006 B 3.3.3 2 08/15/2006 B 3.3.3 - Reflect deletion of LT-940 from the TS LCO B 3.4.15 2 3.3.3 (Amendment 249).
B 3.4.15 - Remove LT-3303 (Sump Mod - 2R17)
BASES UPDATE PACKAGE 18-11072006 B 3.0 1 11/07/2006 B 3.0 - Reflect allowing a delay time for entering a supported system TS whenifthe inoperability is due solely B 3.3.4 3 to an inoperable snubber, risk is assessed and managed. Limiting Condition of Operation 3.0.8 is added B 3.6.10 3 to provide this allowance and define the requirements and limitations of its use. (Amendment 245)
B 3.3.4 - Addition of indicators LI-459A and LI-459B to provide additional Remote Shutdown Instrumentation flexibility.
B 3.6.10 - Revise editorial error on B 3.6.10-2 to make consistent with page B 3.6.10-9.
NL-08-163 Attachment 1 Page 6 of 7 BASES UPDATE PACKAGE 19-02162007 B 3.7.12 1 02/16/2007 B 3.7.12 & B 3.7.13 - Reflect that the validity of the criticality and boron dilution analysis can be extended B. 3.7.13 1 through end of current license based upon Badger Testing in 2003 and 2006 and Racklife code projections.
B 3.8.5 2 B 3.8.5 - Clarify LCO bases regarding allowance to cross-connect DC subsystems with the plant in Modes 5 and 6 (CR-IP2-2006-02339).
BASES UPDATE PACKAGE 20-04112007 TOC 2 04/11/07 TOC, B 3.4.4, B 3.4.5, B 3.4.6, B 3.4.7, B 3.4.13, and B 3.4.17 - Implement TS Amendment 251 related to B 3.4.4 1 steam generator tube integrity.
B 3.4.5 1 B 3.7.5 - Clarify the relationship between the AFW B 3.4.6 1 system and a design basis SBLOCA.
B 3.8.3 - Revise the wording regarding EDG operating B 3.4.7 2 time capability, associated loading and unusable fuel B 3.4.13 3 volume to be consistent with UFSAR Section 8.2.3.2 B 3.4.17 0 B 3.7.5 3 B 3.8.3 1 BASES UPDATE PACKAGE 21-05162007 B 3.9.4 2 05/16/2007 Remove use of the roll-up door as a Containment closure B 3.9.5 2 device subsequent to loss of RHR cooling in Mode 6.
BASES UPDATE PACKAGE 22-08082007 B 3.3.3 3 08/08/2007 Identify the TS for functions 5 and 6 as non-conservative and to send the reader to TRM 3.3.K.
NL-08-163 Attachment 1 Page 7 of 7 BASES UPDATE PACKAGE 23-10052007 B 3.3.1 5 10/05/2007 B 3.3.1 - The TS and bases currently allow a normal B 3.8.2 shutdown without the SR testing by reducing power 2 below the modes of applicability for SR 3.3.1.8. Clarify that testing is not required if such testing was done within the prior 184 days, even if a mode of applicability was still met.
B 3.8.2 - Clarify LCO with regard to the required power sources for modes 5 and 6.
BASES UPDATE PACKAGE 24-12142007 B 3.7.10 4 12/14/2007 List CCRA1 supplying Train B and CCRA2 supplying Train A.
BASES UPDATE PACKAGE 25-04112008 B 3.6.6 2 04/11/2008 B 3.6.6 and B 3.6.7 - Replacement of the trisodium phosphate buffer by sodium tetraborate (Amendment 253)
B 3.6.7 2 BASES UPDATE PACKAGE 26-07012008 B 3.4.16 3 07/31/2008 Implement the Bases pages of TSTF 490 for dose equivalent iodine (Amendment 254)
BASES UPDATE PACKAGE 27-09162008 B 3.8.1 3 09/16/2008 Reflect installation of Appendix R Diesel and GT B 3.8.3 2 removal.
ATTACHMENT 2 TO NL-08-163 REVISIONS TO IP2 DOCKETED COMMITMENTS ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 DOCKET NO. 50-247
NL-08-163 Attachment 2 Page 1 of 1 Revisions to IP2 Docketed Commitments May 2006 throuqh ADril 2008 COMMITMENT CURRENT CHANGED DESCRIPTION NUMBER STATUS DATE Revised text:
NOTE: There were no commitments changed over the time frame that require a report to the NRC per the NEI 99-04 guidance.
ATTACHMENT 3 TO NL-08-163
SUMMARY
OF REVISIONS TO THE IP2 TECHNICAL REQUIREMENTS MANUAL (TRM)
ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 DOCKET NO. 50-247
NL-08-163 Attachment 3 Page 1 of 3 Unit 2 TECHNICAL REQUIREMENTS MANUAL (TRM)
REVISION HISTORY AFFECTED NEW EFFECTIVE DESCRIPTION SECTIONS REV # DATE 3.7.F 2 03/31/2004 To extend the testing frequency of the Post Accident containment venting system from 24 months to 60 months.
3.9.C 2 Revise TRO 3.9.C from "Spent fuel pit water level shall be maintained
> 23 ft above the top of irradiated fuel" to say, 'The Spent Fuel Pit water level shall be >23 ft over the top of irradiated fuel assemblies seated in the storage racks."
5.3.B 2 Revise the to be more generic in referencing the procedures(s) used for Procedure Preparation, Review, and Approval and to state that changes shall be reviewed and approved in accordance with the approved process that meets the requirements in the Quality Assurance Program Manual.
3.3.C 2 08/19/2004 Changes to Service Water Inlet 3.3.K 3 Temperature Monitoring and B3.3.K 3 Instrumentation for references to correct conditions, actions and time. Section 3.3.K changes to:
"Flowmeter (LEFM) check 2000 system" to "Flowmeters (LEFMs)".
5.0 4 08/24/2004 Change responsibility to read the Shift Manager shall be responsible for ensuring plant operations are in accordance with the TRM.
B 3.9.6 2 10/28/2004 Add clarification to TRM for the use of the roll-up door as a containment closure device.
B3.0 2 01/20/2005 Place the word NOT in paragraph on B3.0-3.
5.0 5 Replace Steam Generator procedure reference with a new I
NL-08-163 Attachment 3 Page 2 of 3 joint EN-DC-317 reference.
3.2.A 2 01/24/2005 Revise to say, "Both Quadrant B 3.2.A 2 power tilt monitors" instead of "One Quadrant power tilt monitor, and "Verify QPTR is within limit by calculation" instead of "Perform Tech Spec SR 3.2.4.1."
TOC 2 04/20/2005 Deletions due to Stretch Power 3.3.K 3 Uprate 2% uncertainty.
B.3.3.K 3 5.0 6 05/04/2005 Update of the Inservice Testing Program procedures list.
5.0 7 05/24/2005 Add requirement to provide to the NRC using an industry database (INPO's) the operating data for each calendar month that is described in GL 97-02 by the last day of the month following the end of each calendar quarter.
Complete 05/23/2005 Provide to the NRC the complete TRM to NRC TRM as of 05/23/2005 and the revision history.
5.0 8 11/30/2005 Update the procedures listed in 5.5.B "Primary Coolant Sources Outside Containment" and 5.5.F "Inservice Testing Program". The procedure list is contained in procedures ENN-DC-197 & 332.
3.9.A 2 02/02/2006 Revise the TRM to reflect the fuel B3.9.A 2 decay time assumption used in the updated fuel handling accident analysis performed for the IP2 Stretch Power Uprate project.
3.0 3 02/02/2006 Update the rules of usage sections B3.0 of TRO and TRS to reflect the 3.3.G adoption of TSTF-359; "Increased 3.9.A Flexibility in MODE Restraints".
B3.9.A B3.0 4 02/07/2006 Typo correction for TRS in place of Surveillances 3.3.G 4 03/14/2006 Correction to Rev. 2 of this section deleted step 6 from Table 3.3.G-1 PAM, however, the master copy still showed Rev. 1. Rev. 3 was made from Rev. 1 and step 6 was still included.
TOC 4 07/25/2006 Removal of subheading in section 5.4 to create Units 2 & 3 TOC the same.
2
NL-08-163 Attachment 3 Page 3 of 3 7- F 3.7.A 2 Addition of new type of snubber, LISEGA to section that may be inspected remotely.
5.0 9 Removal of required annual submittal of an Occupational Radiation Exposure Report from Tech Specs under adoption of TSTF-369 an adds a new reporting requirement to the TRM for an annual occupational exposure information.
Complete 11/17/2006 Provide to the NRC the complete TRM to NRC TRM as of 11/17/2006 and the revision history.
3.3.B 2 03/06/2007 Change to provide a TRM B.3.3.B clarification such that it is understood that there are 5 transmitters applicable to section 3.3.B RHR Flow Monitoring Instrumentation.
3.3.K 0 Containment / Recirculation Sump Level Indication addition to TRM.
3.3.L 0 09/04/2007 Containment / Recirculation Sump Level Indication addition to TRM section changed from 3.3.K to 3.3.L.
3.3.K 0 09/04/2007 Toxic Gas Monitoring Instrumentation added to TRM from UFSAR. Was previously Containment / Recir section, moved to 3.3.L.
3.3.B 0 10/05/2007 Gas Turbines section added to TRM.
3.8.C 2 10/05/2007 Provide additional detailed information on the surveillances routinely performed for the IP2 TSC diesel.
TOC 8 03/03/2008 Typo on page numbering for section 3.3.L Report of 10/20/2008 Provide to the NRC the completed TRM Changes TRM revision history changes as of to NRC 10/20/2008.
3
ATTACHMENT 4 TO NL-08-163
SUMMARY
REPORT OF IP2 REVISION 21 UFSAR CHANGES ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 DOCKET NO. 50-247
NL-08-163 Attachment 4 Page 1 of 7 2008 Summary Report of IP2 Revision 21 UFSAR Changes May 2006 throuah October 2008 FSAR AFFECTED SOURCE of INITIATOR'S INFORMATION CHAPTER PAGES, CHANGE, NAME DESC. OF1 CHANGE I
& TABLE, or 50.59 or SCREEN PROBLEM PACKAGE FIGURES NUMBER U208 CH. 1 01-01-001 Pg. 1 NRC SER for LAR for J. Quirk Revise the UFSAR to reflect Stretch Power Uprate the correct Megawatt Thermal output of 3216 MWt and approximate electric output of 1078 MWe from the SPU changes.
01-01-002 Pg. 33 Editorial A. Stewart Update the UFSAR supplements to include Rev.
21.
01-09-001 Ch. 1 Pg. 33 EC 5000034131 M. Driscoll Reactor Core Information for Ch. 3 2R18.
CH. 2 02-02-001 Pg. 3 PAD A. Stewart Correction to the Algonquin gas pipeline information.
CH.3 CH. 4 04-02-001 T4-2-1 50.59 screen W. Wittich Revise table and appendix to App. 4C reflect actual materials of construction as documented in WCAP-15151 and 1968 Material Certification reports.
04-02-002 Pg. 40 TS Amend. #231 & F. Gumble Correct discrepancies in the T4.2-7 & 241 reported copper and nickel Ch. 14 CR-IP2-2006-06522 content of 3 Rx. Vessel base Pg.63 WCAP-15629, Rev. 1 plates. -&-
T1 4.3-52 CR-IP2-2006-06530 Tank Rupture 04-03-001 T4.3-2 NL-07-039 Error in W. Wittich Revise the table to reflect technical data from Cumulative Usage Factors vendor found during with optimized Reactor Vessel License Renewal. stud tensioning procedures as documented in Stress Report R-4147-00-1.
NL-08-163 Attachment 4 Page 2 of 7 2008 Summary Report of IP2 Revision 21 UFSAR Changes May 2006 throuah October 2008 FSAR AFFECTED SOURCE of INITIATOR'S INFORMATION CHAPTER PAGES, CHANGE, NAME DESC. OF CHANGE I
& TABLE, or 50.59 or SCREEN PROBLEM PACKAGE FIGURES NUMBER U208 CH.5 05-01-001 Pg. 42 PAD & 50.59 screen F. Gumble Remove use of the rollup door as a Containment closure device subsequent to loss of RHR cooling in MODE 6.
05-02-001 T5.2-1 CR-IP2-08-02231 K. Curley Change the normal position of PAD Containment Isolation Valves 791, 798, 796 &793 from normally open to normally closed.
CH.6 06-01-001 6.1.1 NL-07-077, F. Bauer To implement GSI-191 6.3.2 NRC SER 2/7/08 potential debris & chemical App 6A, 6C EC-5000034233 clogging of sump screens to 7.1.4 change the pH buffer from 9.2.2 STB to TSP.
14.3.6 06-02-001 6.2.3.9.2 PAD L. Cerra Clarification of the term "run-Pg. 35 LO-IP3LO-2006- out" relative to 20% margin.
00335 CA 12 & 13 06-02-002 6.2.2 Pg. 16 PAD & 50.59 screen J. Bencivenga Add note about operation of 2 EOP ES-1.3 & ES- IR pumps restriction to low 1.4 head recirculation conditions.
If high head recir exist, operator action will be taken to preclude operating 2 pumps in parallel.
06-02-003 6.2.2 Pg. 12 PAD & 50.59 screen L. Cerra Completion of sump T6.2-2 for sump mod modifications. Also includes 6.7.1 Pg. package U208 06-07-001 117 below.
Ch. 7 Pg. 2, 88
NL-08-163 Attachment 4 Page 3 of 7 2008 Summary Report of IP2 Revision 21 UFSAR Changes May 2006 through October 2008 FSAR AFFECTED SOURCE of INITIATOR'S INFORMATION CHAPTER PAGES, CHANGE, NAME DESC. OF CHANGE I
& TABLE, or 50.59 or SCREEN PROBLEM PACKAGE FIGURES NUMBER U208 06-04-001 Pg. 81 Original Typo NRC Identified Cooling coils in org. plant design are listed as tubes 0.0625" diameter & tube thickness of 0.035" both are incorrect.
06-06-001 6.6.2 Pg. 97 PAD J. Bencivenga Retire in place WC&PPS EC 7121 supply to penetration MP-O-O.
06-07-001 Pg. 117 & PAD & 50.59 Screen R. Sergi Removal of containment sump PART of Ch. 7 Pg 2, ERCN-IP2-06-28155 level transmitter LT-940.
PKG. 06- 88 ER 04-02-234 02-003 06-08-001 Pg. 138 NRC SER's for LAR's K. Kingsley Was Pkg. IP2-06 01-01-002 228 & 243 but information was missed in RA-05-022 2006 update.
CH.7 07-02-001 7.2.1.1 Pg. NRC SER G. Dahl Relocation of Toxic Gas 14 monitor LCO information from Ch. 7 & Ch. 9 into TRM.
07-02-002 F7.2-3 EC-5000034060 (ER- A. King Stator Cooling Water 10.2.3 05-2-137) PAD Reliability Upgrade.
07-02-003 7.2 pg.35 Editorial for W. Mahlmeister Cable tests rated at 600 volts clarification of IEEE for IEEE.
NL-08-163 Attachment 4 Page 4 of 7 2008 Summary Report of IP2 Revision 21 UFSAR Changes May 2006 through October 2008 FSAR AFFECTED SOURCE of INITIATOR'S INFORMATION CHAPTER PAGES, CHANGE, NAME DESC. OF CHANGE I
& TABLE, or 50.59 or SCREEN PROBLEM PACKAGE FIGURES NUMBER U208 CH. 8 08-01-001 Section 8.1 PAD &50.59 screen J. Herrera Statement that the station Pg. 7 & 8.5 1P2-2008 08-01 -001 batteries are subjected to an Pg. 29 CR-IP2-2007-00404 equalize charge on a periodic basis is not a vendor recommended practice and should be changed to an equalize charge based on voltage and specific gravity readings.
08-01-002 8.1 Pg. 3, 6 EC SBO/App R S. Prussman Revise UFSAR for placement 8.2 Pg. 9, diesel of Gas Turbine with SBO/App 10,19,22 R diesel.
8.3 Pg. 28, 29 8.5 Pg. 29, 30 Ch. 9 Pg.
17,46 08-02-001 8.2.3 Pg. 19 PAD & 50.59 screen J. Bencivenga EDG air receivers UFSAR information needs to be corrected for one automatic start during any particular power failure. This was identified during the NRC CDBI inspection, LOCR-IP2LO-06-335.
08-02-002 8.2.1 Pg. 10 CR-IP2-2006-04722 G. Dahl LCO & Surv. Req.s for Gas 8.5 Pg. 29 CA-2 Turbines removed and relocated into the TRM.
08-05-001 8.5 Pg. 29 Editorial Change A. Stewart Correction that changes to the Only Maint. Program are controlled by 10 CFR 50.64 and not CH. 9 50.59 CH.9 ____________________
NL-08-163 Attachment 4 Page 5 of 7 2008 Summary Report of IP2 Revision 21 UFSAR Changes May 2006 through October 2008 FSAR AFFECTED SOURCE of INITIATOR'S INFORMATION CHAPTER PAGES, CHANGE, NAME DESC. OF1 CHANGE I
& TABLE, or 50.59 or SCREEN PROBLEM PACKAGE FIGURES NUMBER U208 09-02-001 9.2 p. 17 E. Anderson App. R diesel 9.3 p. 45 09-03-001 46, 50 Editorial Change S. Wilkie Add Westinghouse reference Only to references for section 9.3 CR-IP2-2007-00452 and correct typo on pg. 46.
Westinghouse Calc.
CN-SEE-03-5, Rev. 0 WCAP 12312, Rev.0 09-05-001 New section 50.59 screen R. Evers Addition of the new Unit 2 Fuel 9.5.7 ER-05-2-014 Storage Building Dry Cask ER-05-2-015 Operations and crane to the UFSAR.
09-06-001 87, 88 NRC SER's for Fire S. Wilkie Removal of detail per NE198-Protection Program 03 and adding in the NRC listing of approved FP SER's.
09-06-002 85 PAD & 50.59 screen G. Bhalla Butterfly valve SWN-840 removal and the 7500 GPM flow orifice as the material upgrade to the FCU tubes.
NL-08-163 Attachment 4 Page 6 of 7 2008 Summary Report of IP2 Revision 21 UFSAR Changes May 2006 through October 2008 FSAR AFFECTED SOURCE of INITIATOR'S INFORMATION CHAPTER PAGES, CHANGE, NAME DESC. OF: CHANGE /
& TABLE, or 50.59 or SCREEN PROBLEM PACKAGE FIGURES NUMBER U208 CH. 10 10-01-001 10 PAD & 50.59 screen Y. Nembo Correct turbine differential ER-06-2-141 expansion instrumentation which does not properly correlate to the actual axial clearance.
10-01-002 F10.1-1 NRC SER for LAR# J. Bubniak SPU increased thermal and 241 electric power, this change is to correct information missed in the 2006 update for Figure 10.1-1.
CH. 11 11-02-001 40 PAD & 50.59 screen R. Deschamps Removal of detail per NEI 98-IP2-2008 11-02-001 03. Limits for removal of contamination in the controlled area should be removed and controlled through Rad Pro procedures.
CH. 12 12-01-001 Pg. 1 & 2 QAPM F. Bloise Facility staff qualifications PAD changed to reflect in the requirements ANSI N18.1-1971 to ANSI/ANS-3.1-1978.
12-06-001 Pg. 5 PAD S. Prussman Changes to the UFSAR to NRC approval of the update and correctly reflect Security Plan new NRC approved Security changes Plan changes.
CH. 13 CH. 14
NL-08-163 Attachment 4 Page 7 of 7 2008 Summary Report of IP2 Revision 21 UFSAR Changes May 2006 throunh October 2008 FSAR AFFECTED SOURCE of INITIATOR'S INFORMATION CHAPTER PAGES, CHANGE, NAME DESC. OF: CHANGE I
& TABLE, or 50.59 or SCREEN PROBLEM PACKAGE FIGURES NUMBER U208 14-02-001 69 & 70 PAD & 50.59 screen C. Tippin Based on Badger testing the IP2-2008 14-02-001 validity of the criticality and W.O. IP2-06-31214 boron dilution analysis can be extended through the end of the current license 09/30/2013.
14-02-002 Pg. 94-96, PAD & 50.59 screen A. Irani This change is to correct an 110 -112, IP2-2008 14-02-002 error in the analysis of the F1 4-2-12 RCCA ejection accident.
F14.2-15 F1 4.2-16 F1 4.2-18 CH. 15