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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:Report
MONTHYEARML22013A7062022-01-13013 January 2022 Investigation Report of LLRW Shipment Pursuant to 10 CFR 20, Appendix G ML21056A0782021-04-0707 April 2021 Final Environmental Assessment and Finding of No Significant Impact for Initial and Updated Decommissioning Funding Plans for Indian Point ISFSI (Docket: 72-51) 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 ML20259A2172020-09-14014 September 2020 Commitment Change Summary Report ML20260H0722020-06-18018 June 2020 IP-RPT-14-00013, Revision 3, Indian Point Nuclear Generating Units 2 and 3, Consequences of a Postulated Fire and Explosion Following the Release of Natural Gas from the New Aim 42 Pipeline Near Ipec ML20122A1052020-05-27027 May 2020 Letter from Margaret M. Doane to John B. Rhodes, Chair and Executive Officer, Ny State Public Service Commission: Response to Ny State Public Service Commission Regarding Natural Gas Transmission Pipelines Near Indian Point Nuclear Power Pl ML20100F6352020-04-0808 April 2020 Expert Team Final Report 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) ML19252A3182019-09-0909 September 2019 Entergy to NRC, IPEC Weekly Sturgeon Monitoring Report for Week of Sept 2, 2019 NL-19-061, Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements2019-06-13013 June 2019 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements ML19114A0742019-04-22022 April 2019 Entergy to NRC, IPEC Weekly Sturgeon Monitoring Report for Week of April 15, 2019 NL-19-012, Request for Approval of a Certified Fuel Handler Training and Retraining Program2019-04-15015 April 2019 Request for Approval of a Certified Fuel Handler Training and Retraining Program ML18098A0882018-04-0606 April 2018 Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability NL-18-021, Indian Point, Unit 2, Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability2018-04-0606 April 2018 Indian Point, Unit 2, Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability NL-20-066, Engineering Report IP-RPT-11-00032, Revision 5, Licensing Report on the Inter-Unit Transfer of Spent Nuclear Fuel at the Indian Point Energy Center2017-12-19019 December 2017 Engineering Report IP-RPT-11-00032, Revision 5, Licensing Report on the Inter-Unit Transfer of Spent Nuclear Fuel at the Indian Point Energy Center ML17349A1562017-12-0808 December 2017 Risk Impact of One-Time Extending the ILRT Interval Associated with the Proposed Technical Specification Changes ML17279A2472017-10-0606 October 2017 2017 Annual Assessment Meeting Written Comments Compilation ML17222A2392017-10-0404 October 2017 NRC Response to Request for Deferral of Actions Related to Beyond-Design-Basis Seismic and Flooding Hazard Reevaluations ML17289A6552017-10-0202 October 2017 Attachment 6 to NL-17-115, Revised HI-2094289, Licensing Report on the Inter-Unit Transfer of Spent Fuel at the Energy Center, Revision 9 NL-17-122, Transmittal of 10 CFR 50.59(d)(2) Summary Report, March 26, 2015 to May 18,20172017-09-28028 September 2017 Transmittal of 10 CFR 50.59(d)(2) Summary Report, March 26, 2015 to May 18,2017 ML17096A2122017-03-23023 March 2017 Entergy Engineering Report No. IP-RPT-16-00078, Indian Point RAI CLI-16-07 SAMA Cost-Benefit Sensitivities Rev. 1 (March 23, 2017) NL-17-020, License Renewal Application - Revisions to Reactor Vessel Internals Aging Management Program and Inspection Plan2017-02-0606 February 2017 License Renewal Application - Revisions to Reactor Vessel Internals Aging Management Program and Inspection Plan ML17096A2112017-01-0404 January 2017 Entergy Engineering Report No. IP-RPT-16-00077, Indian Point RAI CLI-16-07 MACCS2 Sensitivities, Rev. 0 (Jan 4, 2017) ML16280A2282016-09-19019 September 2016 Indian Point 2 Technical Requirements Manual NL-16-109, Indian Point 2 Technical Requirements Manual2016-09-19019 September 2016 Indian Point 2 Technical Requirements Manual NL-16-109, HI-2094289, Licensing Report on the Inter-Unit Transfer of Spent Fuel at the Indian Point Energy Center.2016-09-19019 September 2016 HI-2094289, Licensing Report on the Inter-Unit Transfer of Spent Fuel at the Indian Point Energy Center. ML16250A2762016-09-13013 September 2016 Evaluation of Impacts to Proposed Critical Habitat for the Atlantic Sturgeon for Indian Point Nuclear Generating Units 2 and 3 Proposed License Renewal NL-16-083, Post Accident Monitoring (PAM) Report for an Inoperable Containment Area Radiation Monitor (R-26) High Range, Indian Point Unit Number 32016-08-0101 August 2016 Post Accident Monitoring (PAM) Report for an Inoperable Containment Area Radiation Monitor (R-26) High Range, Indian Point Unit Number 3 ML18115A0592016-06-28028 June 2016 After Action Report/Improvement Plan, Drill Date June 28, 2016 ML17052A2662015-10-0202 October 2015 Sturgeon Mobile Tracking for the New Ny Bridge at Tappan Zee NL-15-128, Submittal of 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments Implemented Between 04/01/2013 and 03/25/2015, And/Or Utilized in Support of the UFSAR Update2015-09-28028 September 2015 Submittal of 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments Implemented Between 04/01/2013 and 03/25/2015, And/Or Utilized in Support of the UFSAR Update 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 NL-15-099, Submittal of 2014 Annual 10 CFR 50.46 Emergency Core Cooling System Evaluation Changes Report2015-07-30030 July 2015 Submittal of 2014 Annual 10 CFR 50.46 Emergency Core Cooling System Evaluation Changes Report NL-15-072, 2015 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements2015-06-18018 June 2015 2015 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements NL-15-030, Revised 10 C.F.R. 50.59 Safety Evaluation and Supporting Analyses Prepared in Response to the Algonquin Incremental Market Natural Gas Project2015-04-0808 April 2015 Revised 10 C.F.R. 50.59 Safety Evaluation and Supporting Analyses Prepared in Response to the Algonquin Incremental Market Natural Gas Project NL-15-029, Summary of Analysis Results Based on Corrected Format 2 Data Files Dated March 20152015-04-0606 April 2015 Summary of Analysis Results Based on Corrected Format 2 Data Files Dated March 2015 ML15062A2002015-02-19019 February 2015 NET-300067-01, Revision 1, Criticality Safety Analysis of the Indian Point, Unit 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels. (Non-Proprietary) NL-15-013, Re-Submittal of Netco Report NET-300067-01, Criticality Safety Analysis of the Indian Point Unit 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels, for NRC Review and Approval2015-01-28028 January 2015 Re-Submittal of Netco Report NET-300067-01, Criticality Safety Analysis of the Indian Point Unit 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels, for NRC Review and Approval ML15061A2772014-12-31031 December 2014 WCAP-17954-NP, Revision 0, Indian Point Unit 3 Heatup and Cooldown Limit Curves for Normal Operation. NL-14-152, Entergy'S Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights From...2014-12-22022 December 2014 Entergy'S Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights From... ML14329A1952014-11-0404 November 2014 NET-300067-01, Rev. 0, Criticality Safety Analysis of the Indian Point Unit 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels NL-14-115, 10 CFR 50.59(d)(2) Summary Report for Indian Point, Units 1 and 2 April 1, 2012 to March 19, 20142014-09-18018 September 2014 10 CFR 50.59(d)(2) Summary Report for Indian Point, Units 1 and 2 April 1, 2012 to March 19, 2014 ML14304A7012014-09-16016 September 2014 Reliability Needs Assessment ML15166A0702014-08-31031 August 2014 Algonquin Incremental Market (Aim) Project, Phase 2 Acoustic Survey for Indiana Bats (Myotis Sodalis) and Northern Long-Eared Bats (Myotis Septentrionalis), August 2014 NL-14-110, Third Six-Month Status Report for the Implementation of Order EA-12-049 Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2014-08-27027 August 2014 Third Six-Month Status Report for the Implementation of Order EA-12-049 Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events NL-14-071, Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 3 of 52014-06-0505 June 2014 Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 3 of 5 NL-14-071, Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 2 of 52014-06-0505 June 2014 Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 2 of 5 ML14168A0592014-06-0505 June 2014 Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 1 of 5 ML14168A0602014-06-0505 June 2014 Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 2 of 5 ML14168A0612014-06-0505 June 2014 Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 3 of 5 2022-01-13
[Table view] Category:Technical
MONTHYEARNL-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 ML20259A2172020-09-14014 September 2020 Commitment Change Summary Report ML20100F6352020-04-0808 April 2020 Expert Team Final Report ML18098A0882018-04-0606 April 2018 Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability NL-18-021, Indian Point, Unit 2, Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability2018-04-0606 April 2018 Indian Point, Unit 2, Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability NL-20-066, Engineering Report IP-RPT-11-00032, Revision 5, Licensing Report on the Inter-Unit Transfer of Spent Nuclear Fuel at the Indian Point Energy Center2017-12-19019 December 2017 Engineering Report IP-RPT-11-00032, Revision 5, Licensing Report on the Inter-Unit Transfer of Spent Nuclear Fuel at the Indian Point Energy Center ML17349A1562017-12-0808 December 2017 Risk Impact of One-Time Extending the ILRT Interval Associated with the Proposed Technical Specification Changes ML17289A6552017-10-0202 October 2017 Attachment 6 to NL-17-115, Revised HI-2094289, Licensing Report on the Inter-Unit Transfer of Spent Fuel at the Energy Center, Revision 9 NL-17-122, Transmittal of 10 CFR 50.59(d)(2) Summary Report, March 26, 2015 to May 18,20172017-09-28028 September 2017 Transmittal of 10 CFR 50.59(d)(2) Summary Report, March 26, 2015 to May 18,2017 ML17096A2122017-03-23023 March 2017 Entergy Engineering Report No. IP-RPT-16-00078, Indian Point RAI CLI-16-07 SAMA Cost-Benefit Sensitivities Rev. 1 (March 23, 2017) ML17096A2112017-01-0404 January 2017 Entergy Engineering Report No. IP-RPT-16-00077, Indian Point RAI CLI-16-07 MACCS2 Sensitivities, Rev. 0 (Jan 4, 2017) NL-16-109, Indian Point 2 Technical Requirements Manual2016-09-19019 September 2016 Indian Point 2 Technical Requirements Manual ML16280A2282016-09-19019 September 2016 Indian Point 2 Technical Requirements Manual NL-16-109, HI-2094289, Licensing Report on the Inter-Unit Transfer of Spent Fuel at the Indian Point Energy Center.2016-09-19019 September 2016 HI-2094289, Licensing Report on the Inter-Unit Transfer of Spent Fuel at the Indian Point Energy Center. ML16250A2762016-09-13013 September 2016 Evaluation of Impacts to Proposed Critical Habitat for the Atlantic Sturgeon for Indian Point Nuclear Generating Units 2 and 3 Proposed License Renewal ML17052A2662015-10-0202 October 2015 Sturgeon Mobile Tracking for the New Ny Bridge at Tappan Zee NL-15-029, Summary of Analysis Results Based on Corrected Format 2 Data Files Dated March 20152015-04-0606 April 2015 Summary of Analysis Results Based on Corrected Format 2 Data Files Dated March 2015 ML15062A2002015-02-19019 February 2015 NET-300067-01, Revision 1, Criticality Safety Analysis of the Indian Point, Unit 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels. (Non-Proprietary) ML15061A2772014-12-31031 December 2014 WCAP-17954-NP, Revision 0, Indian Point Unit 3 Heatup and Cooldown Limit Curves for Normal Operation. ML14304A7012014-09-16016 September 2014 Reliability Needs Assessment NL-14-071, Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 2 of 52014-06-0505 June 2014 Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 2 of 5 NL-14-071, Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 1 of 52014-06-0505 June 2014 Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 1 of 5 NL-14-071, Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 4 of 52014-06-0505 June 2014 Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 4 of 5 NL-14-071, Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 3 of 52014-06-0505 June 2014 Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 3 of 5 ML14168A0592014-06-0505 June 2014 Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 1 of 5 ML14168A0602014-06-0505 June 2014 Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 2 of 5 ML14168A0632014-06-0505 June 2014 Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 5 of 5 NL-14-071, Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 4 of 52014-06-0505 June 2014 Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 4 of 5 ML14168A0612014-06-0505 June 2014 Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 3 of 5 ML14107A0432014-03-31031 March 2014 Enclosure 2 to NL-14-045 - Acceptable Value of the Location of the Bottom of the Expansion Transition (Bet) for Implementation of H* at Indian Point Unit 2 ML13337A5942014-01-24024 January 2014 Interim Staff Evaluation and Audit Report Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14027A5152014-01-16016 January 2014 WCAP-17828-NP, Revision 0, Indian Point Unit 2 H* Alternate Repair Criteria for the Tubesheet Hydraulic Expansion Region (Model 44F - 4-Loop) ML14010A3312014-01-14014 January 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Indian Point Energy Center, Units 2 and 3, TAC Nos.: MF0744 and MF0745 NL-14-027, LTR-PAFM-13-115-NP, Rev. 0, Technical Justification to Support Extended Volumetric Examination Interval for Indian Point Generating Station Unit 3 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds.2013-11-30030 November 2013 LTR-PAFM-13-115-NP, Rev. 0, Technical Justification to Support Extended Volumetric Examination Interval for Indian Point Generating Station Unit 3 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds. 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AM Entergy Nuclear Northeast mEn tergy" Entergy Nuclear Operations, Inc Indian Point Energy Center 295 Broadway, Suite 1 PO Box 249 Buchanan, NY 10511-0249 December 19, 2002 Re: Indian Point Unit No. 2 Docket No. 50-247 NL-02-161 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-P1-17 Washington, DC 20555-0001
Subject:
Steam Generator Inservice Examination Program Results 2002 Refueling Outage (2R15)
Reference:
ENO letter to NRC, "Proposed Steam Generator Examination Program - 2002 Refueling Outage (2R 15)," dated August 21, 2002
Dear Sir:
Enclosed is a report of the Steam Generator Examination Program Results conducted at Indian Point Unit 2 during the 2002 refueling outage (2R15), submitted pursuant to Technical Specification 4.13.C.2.
No new regulatory commitments are being made by ENO in this correspondence.
Should you or your staff have any questions regarding this matter, please contact Mr. John McCann, Manager, Licensing at (914) 734-5074.
Sincerely, Fred Dacimo Vice President - Operations Indian Point 2 Attachment A:EV0
cc: Mr. Hubert J. Miller Regional Administrator - Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. Patrick D. Milano, Senior Project Manager Project Directorate I Division of Licensing Project Management U.S. Nuclear Regulatory Commission Mail Stop O-8-C2 Washington, DC 20555 Senior Resident Inspector U.S. Nuclear Regulatory Commission PO Box 38 Buchanan, NY 10511
ATTACHMENT 1 TO NL-02-161 Steam Generator Examination Program Results 2002 Refueling Outage (2R15)
Entergy Nuclear Operations, Inc.
Indian Point Unit No. 2 Docket No. 50-247
NL-02-161 Attachment 1 Page 2 of 10 Indian Point Unit 2 Steam Generator Examination Program Results 2002 Refueling Outage (2R15) 1.0 Examination Program Description Details of the Indian Point Unit 2 steam generator tube inservice examination program to be conducted during the fifteenth refueling outage were submitted to the NRC via ENO letter dated August 21, 2002. The original examination scope is described in Section 2 below. This original scope was subsequently expanded during the outage, to include all periphery tubes in the cold leg inspection. This change was primarily due to finding two (2) confirmed loose parts with Rotating Pancake Coil (RPC) at the top of tubesheet (TTS) hot leg. The results and conclusions of the full examination scope are provided in Sections 3 and 4 respectively.
2.0 Examination Scope
- a. Steam Generator Tube Eddy Current Examination The Indian Point Unit 2 Fall 2002 steam generator eddy current inspection was the first inservice inspection for the replacement steam generators, which were installed in December of 2000. All bobbin full length tests, TTS RPC, low row U-bend RPC, and hot leg special interest tests were collected on the hot legs first, and then the robots were moved to the cold legs to finish the straight section bobbin and special interest tests on the cold legs.
The original planned inspection programs consisted of the following:
0 Full-length bobbin coil test of 100% of the open tubes in all four steam generators, except for the U-bend sections of rows 1 and 2, which were tested with the rotating plus point coil.
0 3-Coil Rotating Probe inspection of approximately 26-27% (20% random plus all peripheral tubes) of the Top of Tubesheet (TTS) intersections in the Hot Leg of each SG. The extent of each TTS exam was -3" to +3" as a minimum.
0 100% row 1, and 2 U-bends were inspected with a mid-range +Point coil. Both primary and secondary analysts monitored noise values at the apex of each U-bend and were reviewed by lead analyst.
0 100% of dings and dents > 5.0 volts from bobbin were inspected with +Pt RPC. This accounted for a total of 23 tests.
Additionally, a series of special interest +Point MRPC exams were planned, which included all "I" codes, and other codes of interest from the bobbin exam.
NL-02-161 Attachment 1 Page 3 of 10 Additional testing (scope expansion) included the following:
" There were a total of 991 RPC special interest tests of bobbin signals. The actual number of bobbin "I" codes tested was 1074 (some tests covered multiple "I" code signals). An "I" code from bobbin was reported when either the signal was not present in the baseline or had changed from baseline history. The large number of signals that changed from history was due to the fact that this was the first operating cycle of the generators; therefore, the first time heat was applied to the tubes. Steam generators with thermal treated 1600 tubing throughout the industry are well known to contain many benign signals which change rapidly after the first cycle and not as much in subsequent cycles, so the large number of RPC tests which needed to be performed, was not unexpected.
"* A total of 51 tubes were RPC tested at the top of tube sheet to bound all tubes with Possible Loose Parts.
"* Due to finding two (2) confirmed loose parts with RPC at the top of tubesheet hot leg, ENO added all peripheral tubes on the cold leg side to the RPC top of tube sheet inspection program. This was a total of 1080 tubes.
- b. Secondary Side Examination The steam generator secondary side examination plan assesses steam generator internals, both in-bundle and steam drum, and top of tubesheet regions. Visual inspection is utilized to assess the presence of loose parts or other steam generator secondary side component conditions that could affect the structural integrity of the primary boundary and leak tightness.
The secondary side inspection incorporated sludge lancing and foreign object search and retrieval (FOSAR). In-bundle inspection was performed in approximately every fifth column. The upper bundle inspection was performed by looking up from the bottom on all four steam generators. Also for one steam generator, the inspection port located above the top support plate was removed, and an inspection looking downward was performed.
- c. Steam Generator Sludge The sludge removed from the steam generator tubesheets during 2R15 by lancing operations is being analyzed.
NL-02-161 Attachment 1 Page 4 of 10 3.0 2002 Examination Results
- a. Steam Generator Tube Eddy Current Examination Inspection Results- Overall Summary Anti vibration bar (AVB) wear was reported during the 2R15 inspection. Thirteen tubes contained AVB wear indications > 9% with the highest percentage wear measured at 20% in 3 locations over 2 tubes.
3 Volumetric (VOL) indications were found in the free span of the tubes and measured using the EPRI qualified sizing technique #21998.1 for the Plus Point Probe. None measured >19%.
Steam generator inspections were performed in accordance with the EPRI PWR Steam Generator Examination Guidelines, Rev. 5, and all applicable requirements of Station Administrative Order (SAO)-180, "Administrative Steam Generator Program Plan," Rev. 4.
Table 1 summarizes the overall inspection results.
Inspection Results - Possible Loose Parts Indications No wear was found on any tubes due to Possible Loose Parts (PLP). All PLP reported during the 2R15 inspections were detected by the +PT RPC and all were reported on top of the tube sheets. It is sometimes difficult to distinguish sludge from a loose part with eddy current, therefore reporting a PLP with eddy current indicates only the possibility of a loose part present and does not indicate that a loose part is present for certain.
In SG 24, four adjacent tubes were reported originally by RPC on the top of the tubesheet hot leg. The tubes were R37 C22, R38 C22, R37 C23, and R38 C24. As a result of these reported PLP calls, a 2.5" long piece of metal bracket was removed from that area. When the tubes were retested with +PT after the removal of the part, the indications were no longer present from eddy current.
All other PLP calls reported from eddy current were visually checked on the secondary side. As a result, one other loose part was found wedged between tubes in SG 21 on the hot leg Top of Tubesheet and in the periphery of the steam generator, however could not be removed. Westinghouse performed an evaluation to leave the tubes with PLP indications in service. None of the PLP locations showed any sign of tube wear from +PT testing. All tubes adjacent to PLP calls were tested with +PT RPC to bound all PLP indications.
Table 2 summarizes all PLP calls remaining in the database.
NL-02-161 Attachment 1 Page 5 of 10 Inspection Results - Tubes Plugged A total of 16 tubes were administratively plugged during the 2R15 inspection with Westinghouse (W) mechanical plugs fabricated from Alloy 690. A total 13 tubes were plugged due to AVB wear and 3 tubes were plugged due to volumetric indications. None of the tubes plugged met EPRI Rev. 5 criteria for requiring repair.
No crack-like indications were reported.
The qualified bobbin sizing standard contains only single sided wear. All three 20%
bobbin indications at AVB locations were tested with +Pt RPC and confirmed as double sided wear. Therefore, the qualified bobbin sizing technique that was used overestimated the 20% calls. In addition, 2 other < 20% bobbin calls at the AVB's were tested with +Pt and confirmed as wear (single sided).
Table 3 summarizes the plugged tubes.
- b. Secondary Side Examination Results Foreign Object Search and Retrieval (FOSAR) procedures were conducted in the steam generators around the annulus and within the tube bundle during 2R15.
Various loose objects were observed during FOSAR and eddy current of the tubesheet region of the steam generators. Some of these objects were removed; however, some were not removed due to the small size of the objects and the time and personnel exposure required to do so. Secondary side inspections after sludge lancing included a visual (by camera) inspection of the peripheral and tube lanes on the tubesheet. Objects found were removed in this area. Additionally a visual inspection was performed at every fifth column. This was where the remaining loose parts were located. The remaining items were evaluated for wear rates on adjacent tubes. The evaluation concluded that the Indian Point Unit 2 steam generators may be returned to service with the identified items, and that operation during Cycles 16 and 17 with these foreign objects would not involve a change to any Technical Specification, and would not represent an unreviewed safety question in accordance with 10CFR 50.59
- c. Steam Generator Sludge Sludge was removed from each of the steam generators by lancing. The sludge is being analyzed. The quantities are listed in Table 5.
NL-02-161 Attachment 1 Page 6 of 10 4.0 Conclusions This report provides a summary of the Indian Point Unit 2 steam generator tube integrity condition as determined during the 2R15 refueling outage by NDE inspection and a projection by analysis of the tube integrity until the next planned steam generator inspection. The next inspection is planned for 2R17, which is following the completion of two fuel cycles. All of the activities reported in this report have been conducted in accordance with NEI 97-06 Revision 1 and associated guidelines.
The 2R15 represents the end of the first fuel cycle after steam generator replacement, consequently all four steam generators were inspected. A Condition Monitoring assessment was performed, on a defect specific basis, to demonstrate compliance with integrity criteria by the comparison of 2R15 NDE measurements with calculated burst and leakage integrity limits. Calculated integrity limits, including consideration for appropriate uncertainties, burst and leak analytical correlations, material properties, and NDE technique and analyst uncertainties were provided in the degradation assessment report. All indications in this inspection were below the calculated integrity limits and therefore met integrity requirements without further testing. Based upon the inspection results, all four steam generators were found in compliance with Condition Monitoring requirements.
A preliminary Operational Assessment for assumed operation duration of 4.0 EFPY for Cycle 16 and 17 confirms that the steam generator tube structural and leakage integrity will be maintained until the next planned steam generator inspection.
The 2R15 steam generator tube inservice examination demonstrates that the Indian Point Unit 2 steam generators are acceptable for continued service at full power. A Conditioning Monitoring Assessment performed for Indian Point Unit 2 has established the end of cycle structural and leakage integrity of the steam generator tubing.
NL-02-161 Attachment 1 Page 7 of 10 Table 1 Inspection Results- Overall Summary Bobbin Coil Results Indication SG-21 SG-22 SG-23 SG-24 Total 1-19% 11 1 4 7 23 20-39% 2 0 1 0 3
>=40% 0 0 0 0 0 NQI 2 0 1 0 3 PID 6 1 2 4 13 DNS 10 12 11 5 38 DSS 3 0 1 1 5 NQS 287 335 153 246 1021 Total "S" Codes,: 300, 347 165, 252 1064 BLG 1 1 1 0 3 DNG < 2.00 Volts 1 9 1 2 13 DNG 2.00 - 4.99 Volts 100 57 58 51 266 DNG >= 5.00 Volts 2 4 3 1 10
'TotalDNG. ,103 70', 62 fl 154 289 DNT < 2.00 Volts 0 0 0 0 0 DNT 2.00 - 4.99 Volts 75 8 65 13 161 DNT >= 5.00 Volts 3 1 15 2 21 TotalDNT 78 9 80A 15 182 FSA 31 44 30 49 154 FSD 288 250 225 245 1008 DNR 0 6 2 1 9 INR 155 60 120 81 416 INF 2 6 2 7 17 PVN 7 5 1 5 18 Total Bobbin Results 986 800 696 720 3202
+Point Inspection Results Indication SG-21 SG-22 SG-23 SG-24 Total 1-19% 2 0 1 0 3 VOL 10 0 4 0 14 PID 2 0 1 0 3 PLP 6 1 1 0 8 PVN 4 0 1 0 5 DNT 0 1 0 0 1 TRA 2 1 0 0 3 NDF 310 371 188 262 1131 Total +Point Results 336 374 196 262 1168 All Probes 1322 1174 892 982 4370
NL-02-161 Attachment 1 Page 8 of 10 Table 2 Summary of Possible Loose Part (PLP)
SG ROW COL CODE Location Result of Visual Search 21 44 43 PLP TSH +0.42" No Part Visible 21 45 43 PLP TSH +0.21" No Part Visible 21 44 44 PLP TSH +0.04" No Part Visible 21 1 47 PLP TSH +0.04" No Part Visible, possible sludge deposits Part wedged between tubes. Removal not 21 42 59 PLP TSH +0.07" possible.
Part wedged between tubes. Removal not 21 42 60 PLP TSH +0.27" possible.
22 1 47 PLP TSC +0.12" No Part Visible, possible sludge deposits 23 1 46 PLP TSC +0.20" No Part Visible, possible sludge deposits
NL-02-161 Attachment 1 Page 9 of 10 Table 3 Locations of Indications Plugged SG ROW COL Location Reason for Plugging 21 16 28 5H + 5.63" 18% Volumetric Indication (sized by +Pt) 21 44 43 AV3, AV4 WEAR 9% AV3, 10% AV4 21 45 45 AV1, AV2, AV3, AV4 WEAR 17% AV1, 20% AV2, 20% AV3, 14% AV4 21 38 47 AV2, AV3 WEAR 13% AV2, 16% AV3 21 45 47 AV1, AV2 WEAR 14% AV1, 18% AV2 21 28 50 AV3, AV4 WEAR 10% AV3, 14% AV4 21 21 56 TSH + 18.39" 18% Volumetric Indication (sized by +Pt) 21 28 79 AV3 WEAR 12% AV3 22 39 37 AV3 WEAR 10% AV3 23 27 33 5H + 37.98" 19% Volumetric Indication (sized by +Pt) 23 41 46 AV1, AV2, AV3, AV4 WEAR 12% AV1, 17% AV2,20% AV3,17% AV4 23 41 61 AV3 WEAR 13% AV3 24 41 41 AV2, AV3, AV4 WEAR 14% AV2, 15% AV3, 16% AV4 24 34 51 AV2 WEAR 12% AV2 24 36 64 AV3, AV4 WEAR 11% AV3, 12% AV4 24 36 66 AVI WEAR 11% AV1 Table 4 Summary of Tubes Plugged SG Plugged in Previously Total Percent 2002 Plugged Plugged Plugged 21 8 0 8 0.25%
22 1 0 1 0.03%
23 3 0 3 0.09%
24 4 2 6 0.19%
Total 16 2 18 0.14%
Notes:
All tubes were plugged on both the hot and cold legs.
All tubes plugged in 2002 used Westinghouse (W) mechanical plug fabricated from Alloy 690.
All tubes previously plugged used (W) welded plug fabricated from Alloy 690.
NL-02-161 Attachment 1 Page 10 of 10 Table 5 Sludge Removed (November 2002)
SG 2002 21 13 lbs 22 8 lbs 23 10 lbs 24 11 lbs Total 42 lbs Table 6 Eddy Current Data Acronyms 3-Letter Code Description BLG Bulge DNG Ding DNR Ding With Rotation DNS Ding Signal DNT Dent DSS Distorted Support Signal FSA Freespan Absolute Signal FSD Freespan Differential Signal INF Indication Not Found INR Indication Not Reportable NDF No Degradation Found NQI Non Quantifiable Indication NQS Non Quantifiable Signal PID Positive Identification PLP Possible Loose Part PVN Permeability Variation TRA Trackable Anomaly VOL Volumetric Signal