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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:Miscellaneous
MONTHYEARML22013A7062022-01-13013 January 2022 Investigation Report of LLRW Shipment Pursuant to 10 CFR 20, Appendix G 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 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 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 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 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 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-15-013, 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 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 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 ML14141A5402014-05-0909 May 2014 Supplemental Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendations 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML14071A1832014-04-0101 April 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident NL-14-042, Entergy Seismic Hazard and Screening 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 Fukushima Dai-ichi.2014-03-31031 March 2014 Entergy Seismic Hazard and Screening 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 Fukushima Dai-ichi. NL-14-043, Entergy Seismic Hazard and Screening 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 the Fukushima.2014-03-31031 March 2014 Entergy Seismic Hazard and Screening 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 the Fukushima. ML14071A1982014-03-20020 March 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML14015A4172014-01-30030 January 2014 Staff Summary of the Steam Generator Tube Inservice Inspections for the Spring 2013 Refueling Outage ML14304A7512013-12-13013 December 2013 Unit 3 Coastal Zone Management Act Consistency Certification, Vol. II of III, Supplemental Information Regarding NYSDEC Record, Part 8 of 9 NL-13-133, 10 CFR 71.95 Report on Failure to Observe Certificate of Compliance Conditions for Radwaste Model 8-120B Cask Vent Port Leak Test Hold Time2013-10-0202 October 2013 10 CFR 71.95 Report on Failure to Observe Certificate of Compliance Conditions for Radwaste Model 8-120B Cask Vent Port Leak Test Hold Time ML13221A4172013-07-26026 July 2013 LTR-13-0662 - Susan Lerner, Common Cause New York Ltr Provides a Copy of Generating Influence, Entergy'S Political Spending and the Battle Over the Indian Point Nuclear Power Plant. ML14304A7522012-12-31031 December 2012 Unit 3 Coastal Zone Management Act Consistency Certification, Vol. II of III, Supplemental Information Regarding NYSDEC Record, Part 9 of 9 ML12346A3432012-11-20020 November 2012 Enclosure to NL-12-167 Seismic Walkdown Report - Page D-69 of 203 Through End ML12346A3422012-11-20020 November 2012 Enclosure to NL-12-167 Seismic Walkdown Report - Cover Through Page C-288 of 434 NL-12-167, Indian Point, Unit 2, Enclosure to NL-12-167 Seismic Walkdown Report - Cover Through Page C-288 of 4342012-11-20020 November 2012 Indian Point, Unit 2, Enclosure to NL-12-167 Seismic Walkdown Report - Cover Through Page C-288 of 434 NL-12-167, Indian Point, Unit 2, Enclosure to NL-12-167 Seismic Walkdown Report - Page D-69 of 203 Through End2012-11-20020 November 2012 Indian Point, Unit 2, Enclosure to NL-12-167 Seismic Walkdown Report - Page D-69 of 203 Through End NL-12-136, 10 CFR 72.48(d)(2) Report, Listing and Summary of Changes, Tests and Experiments2012-10-0101 October 2012 10 CFR 72.48(d)(2) Report, Listing and Summary of Changes, Tests and Experiments NL-14-002, Enclosure - NL-14-002, SAMA Engineering Project Cost Estimates Prepared by RCM Technologies2012-09-20020 September 2012 Enclosure - NL-14-002, SAMA Engineering Project Cost Estimates Prepared by RCM Technologies NL-12-009, Enclosure 1 to NL-12-009, Holtec International Licensing Report HI-2094289, Revision 52012-01-11011 January 2012 Enclosure 1 to NL-12-009, Holtec International Licensing Report HI-2094289, Revision 5 ML12040A3102012-01-11011 January 2012 Enclosure 1 to NL-12-009, Holtec International Licensing Report HI-2094289, Revision 5 ML11280A1212011-09-28028 September 2011 License Renewal Application - Completion of Commitment #30 Re Reactor Vessel Internals Inspection Plan NL-11-094, Request for Relief Request 14 - Code Case N-770-1 Weld Inspection Frequency Extension2011-08-0303 August 2011 Request for Relief Request 14 - Code Case N-770-1 Weld Inspection Frequency Extension NL-10-109, CFR 50.59(d) Report Listing and Summary Report of the Changes, Tests and Experiments Implemented Between 04/20/2008 and 04/12/20102010-10-12012 October 2010 CFR 50.59(d) Report Listing and Summary Report of the Changes, Tests and Experiments Implemented Between 04/20/2008 and 04/12/2010 ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants ML11299A1752010-02-0808 February 2010 Lr Hearing - Indian Point Task I Report - Deliverable (Redacted Version) ML0936410942009-12-30030 December 2009 Preliminary Power Authority of the State of New York, Indian Point No. 3, Nuclear Power Plant, Systems Interaction Study. Volume II ML0926401772009-08-28028 August 2009 Environmental Science and Engineering NL-09-095, Annual 10 CFR 50.46 Report for Calendar Year 2008 Emergency Core Cooling System Evaluation Changes2009-07-21021 July 2009 Annual 10 CFR 50.46 Report for Calendar Year 2008 Emergency Core Cooling System Evaluation Changes ML0905407042009-01-0909 January 2009 American Radiation Services, Inc. Laboratory Analysis Report No. ARS1-08-02367, Revised 01/09/2009 2022-01-13
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Entergy Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB SEntergy P.O. Box 249 Buchanan, NY 10511-0249 Tel 914 734 6700 Fred Dacimo Site Vice President Administration July 24, 2006 Re: Indian Point Unit No. 3 Docket No. 50-286 NL-06-078 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Request for Revision of Existing Exemptions from 10 CFR 50, Appendix R: One-Hour Hemyc Electrical Raceway Fire Barrier System, Fire Areas ETN-4 and PAB-2
References:
- 1) NRC Information Notice 2005-07, "Results of HEMYC Electrical Raceway Fire Barrier System Full Scale Fire Testing," April 1, 2005
- 2) NYPA Letter, J. C. Brons to S. A. Varga (NRC), "Appendix R Fire Protection Program," August 16, 1984
- 3) NYPA Letter, J. C. Brons to S. A. Varga (NRC), "Information to Support the Evaluation of IP3 to 10 CFR 50.48 and Appendix R to 10 CFR 50," September 19, 1985
- 4) NRC Letter and SER, S. A. Varga to J. C. Brons (NYPA), "Indian Point 3 Nuclear Power Plant - Exemption From Certain Requirements of Section III.G and III.J of Appendix R to 10 CFR Part 50," January 7, 1987
- 5) IPEC Letter NL-06-060, F. Dacimo to Document Control Desk, "Response to Generic Letter 2006-03 (Potentially Nonconforming Hemyc and MT Fire Barrier Configurations)," June 8, 2006
Dear Sir or Madam:
NRC Information Notice (IN)2005-07 (Reference 1) notified licensees of potential performance concerns associated with the one-hour rated Hemyc electrical raceway fire barrier system (ERFBS), indicating that the system may be incapable of fulfilling the stated one-hour fire resistance rating when tested in accordance with Generic Letter 86-10, Supplement 1 criteria. Indian Point Unit No. 3 (IP3) utilizes the one-hour rated Hemyc
NL-06-078 Docket No. 50-286 Page 2 of 3 ERFBS that is the subject of IN 2005-07 in two areas of the plant. In a Safety Evaluation Report (SER) dated January 7, 1987 (Reference 4) , the Staff granted a number of exemptions from specific requirements of 10 CFR 50, Appendix R, which included these two plant areas. Entergy has reviewed the Hemyc fire test results provided by the NRC in IN 2005-07 and has determined that it is necessary to revise the fire resistance rating of the Hemyc ERFBS configurations credited in two of the exemptions. The two affected exemptions are those applicable to Fire Area PAB-2 in the Primary Auxiliary Building, and Fire Area ETN-4 in the Electrical Tunnels and Electrical Penetration Areas.
In accordance with 10 CFR 50.12, the purpose of this letter is to request revision of the January 7, 1987 SER to reflect that the installed Hemyc ERFBS configurations provide a 30-minute fire resistance rating, in lieu of the previously stated one-hour fire resistance rating. The requests for the exemptions granted by the January 7, 1987 SER were docketed in NYPA Letters dated August 16, 1984 (Reference 2) and September 19, 1985 (Reference 3). Based on a review of these letters and of the NRC test results, it is Entergy's position that a Hemyc ERFBS fire resistance rating of 30 minutes will provide sufficient protection for the affected raceways, with adequate margin, to continue to meet the intent of the original requests for exemption and the conclusions presented in the January 7, 1987 SER. This evaluation is summarized in Attachment 1.
As documented in Attachment 1, it is Entergy's conclusion that the revised fire resistance rating of the Hemyc ERFBS does not reflect a reduction in overall fire safety, and presents no added challenge to the credited post-fire safe-shutdown capability. The remainder of the credited fire protection features, the fire hazards and ignition sources, fire brigade and operator response to fire events, and the credited post-fire safe-shutdown capability remain materially unchanged from the configuration as originally described in the NYPA letters and as credited in the January 7, 1987 SER.
Entergy has reviewed the as-built configurations of the Hemyc ERFBS installed at IP3 against the results of the NRC Hemyc fire test program as referenced by IN2005-07.
This review has determined that the installed ERFBS can be expected to afford a thermal protection rating of at least 30 minutes, contingent upon the installation of a modification to augment raceway support protection and to install over-banding of certain enclosures.
A commitment to install these modifications is contained in our response to Generic Letter 2006-03 (Reference 5). The conclusions from the engineering evaluation are also summarized in Attachment 1.
There are no new commitments contained in this letter. Ifyou have any questions or require additional information, please contact Mr. Patric W. Conroy at 914-734-6668.
NL-06-078 Docket No. 50-286 Page 3 of 3 SereIrel
ý...* '4 -- Fed R . D a c im o
-YV'V - Site Vice President Indian Point Energy Center : Request for Revision of Existing Exemptions from 10 CFR 50, Appendix R:
One-Hour Hemyc Electrical Raceway Fire Barrier System, Fire Areas ETN-4 and PAB-2 cc: Mr. Samuel J. Collins, Regional Administrator, NRC Region I Mr. John P. Boska, Senior Project Manager, NRC NRR DORL NRC Resident Inspectors Office, Indian Point Energy Center Mr. Paul Eddy, New York State Department of Public Service Mr. Peter R. Smith, NYSERDA
ATTACHMENT 1 to NL-06-078 Request for Revision of Existing Exemptions from 10 CFR 50, Appendix R: One-Hour Hemyc Electrical Raceway Fire Barrier System, Fire Areas ETN-4 and PAB-2 Entergy Nuclear Operations, Inc.
Indian Point Nuclear Generating Unit No. 3 Docket No. 50-286
NL-06-078 Docket No. 50-286 Attachment 1 Page 1 of 14 Request for Revision of Existing Exemptions from 10 CFR 50, Appendix R: One-Hour Hemyc Electrical Raceway Fire Barrier System, Fire Areas ETN-4 and PAB-2
1.0 INTRODUCTION
The Indian Point Unit No. 3 (IP3) electrical raceways provided with Hemyc ERFBS protection consist of several conduits, cable trays, and a box-type enclosure. The locations of the Hemyc ERFBS installations are illustrated by Figures 1 through 4.
To support the request for revision to the two exemptions applicable to Fire Areas ETN-4 (Electrical Tunnels and Electrical Penetration Areas) and PAB-2 (Component Cooling Pump Area) contained in the January 7, 1987 SER (Reference 8.1), this attachment:
- Discusses the licensing basis for the one-hour Hemyc electrical raceway fire barrier system (ERFBS) (Section 2.0);
- Discusses the fire hazards, combustible controls, and fire protection features of the areas (Section 3.0);
0 Evaluates the acceptability of a 30-minute rating considering the current fire hazards and fire protection features in the areas (Section 4.0);
- Presents a summary description of the installed one-hour Hemyc ERFBS configurations, and of the evaluation of the results of the NRC Hemyc fire test program (Reference 8.11) (Section 5.0).
As documented in Reference 8.11, the NRC Hemyc test specimens provided acceptable thermal performance for a period of at least 30 minutes, or the results provided insight into the observed failure mechanisms. Further, each of the installed IP3 Hemyc configurations is bounded by one or more of the NRC test specimens, or is subject to a planned modification based on the insights learned from the NRC test program. As determined in Reference 8.11, the Hemyc ERFBS at IP3 can be expected to provide a fire resistance rating of a minimum of 30 minutes, consistent with ASTM E 119 temperature rise acceptance criteria. A fire resistance rating of 30 minutes will provide adequate protection for the affected IP3 safe-shutdown raceways, in consideration of the additional mitigating factors of low fire loading and active and passive fire protection features installed in each of the two affected plant areas.
NL-06-078 Docket No. 50-286 Attachment 1 Page 2 of 14 2.0 EXISTING LICENSING BASIS FOR ONE-HOUR ERFBS IN AFFECTED PLANT AREAS 2.1 Electrical Tunnels and Penetration Areas: Fire Area ETN-4: Upper and Lower Electrical Tunnels (Fire Zones 7A and 60A, respectively) and Upper Penetration Area (Fire Zone 73A)
By SER dated February 2, 1984 (Reference 8.4), the Staff approved an exemption from the Appendix R Section Il.G separation requirements, to the extent that redundant safe-shutdown systems are not separated by more than 20 feet free of intervening combustibles or fire hazards, and that redundant safe-shutdown systems are not separated by a one-hour rated fire barrier in an area which is protected by automatic fire detection and suppression systems. The bases for this exemption included the existing separation between redundant safe-shutdown trains, minimal fire hazards, flame-retardant characteristics of cable insulation, and the installed active and passive fire protection features.
Following a comprehensive reassessment of the IP3 Appendix R compliance basis, by letters dated August 16, 1984 and September 19, 1985 (References 8.3 and 8.2, respectively), NYPA informed the NRC of the need for additional separation measures to be installed in Fire Area ETN-4. These measures included the installation of one-hour rated fire wrap on several safe-shutdown raceways. By SER dated January 7, 1987 (Reference 8.1), the Staff acknowledged this clarification and the addition of one-hour rated fire wrap, and confirmed the continued validity of the exemption granted by the February 2, 1984 SER (Reference 8.4).
2.2 Primary Auxiliary Buildinq, Fire Area PAB-2: Fire Zone 1, 41' Elevation CCW Pump Area In the SER dated January 7, 1987 (Reference 8.1), the Staff approved an exemption from the Section III.G separation requirements for this fire zone, to the extent that an automatic suppression system has not been provided, and redundant safe-shutdown systems are not separated by more than 20 feet free of intervening combustibles. The bases for this exemption included the existing separation between redundant safe-shutdown trains, low fire loading, a fire detection system, manual hose stations and portable extinguishers, a partial height noncombustible barrier designed to protect the CCW pump against radiant heat from a fire, and a one-hour fire rated cable wrap around the normal power feed conduit to the 33 CCW pump.
NL-06-078 Docket No. 50-286 Attachment I Page 3 of 14 3.0 FIRE HAZARDS, COMBUSTIBLE CONTROLS, AND FIRE PROTECTION FEATURES IN FIRE AREAS ETN-4 AND PAB-2 3.1 Evaluation of Hazards/Ignition Sources and Combustible Controls The fire hazards and ignition sources in Fire Areas ETN-4 and PAB-2 remain materially unchanged from the characteristics of these areas as described in the SERs dated February 2, 1984 (Reference 8.4) and January 7, 1987 (Reference 8.1), and the NYPA correspondence referenced therein, as applicable to the specific fire zone.
Transient combustible and hot work controls have been enhanced since the transition from NYPA to Entergy operation of IP3, with the issuance of procedures EN-DC-127, "Control of Hot Work and Ignition Sources" (Reference 8.8) and ENN-DC-161, "Transient Combustible Program" (Reference 8.9). Notably, per Transient Combustible Program procedure ENN-DC-161, Fire Areas ETN-4 and PAB-2 are designated as "Level 2" combustible control areas, which constrains transient combustibles to moderate quantities. Any planned introduction of more than the allowable quantities of combustibles into these areas requires a prior review by Fire Protection Engineering, which will include the definition of additional protective/compensatory measures as determined to be applicable. In addition, per procedure EN-DC-127, any planned hot work in IP3 Fire Areas ETN-4 or PAB-2 requires the prior review and approval of Fire Protection Engineering. This constraint provides assurance that hazards and potential effects consistently receive proper prior evaluation, and that compensatory measures, as applicable, are adequately defined in advance of the hot work activity.
The administrative controls imposed by ENN-DC-161 and the structured Fire Protection Engineering review of planned hot work activities per EN-DC-127 provide additional assurance that the potential for, and potential effects of, significant floor-based transient combustible fires is sharply limited.
3.2 Active Protection: Fire Detection and Suppression Features The installed fire detection systems and automatic and manual fire suppression features in the affected zones of Fire Areas ETN-4 and PAB-2 remain functionally unchanged from those described in SERs dated February 2, 1984 (Reference 8.4) and January 7, 1987 (Reference 8.1), and the NYPA correspondence referenced therein, as applicable. Preaction automatic water spray suppression is provided in ETN-4 for protection of cable trays; manual suppression capabilities are provided in both Fire Areas ETN-4 and PAB-2, in the form of accessible fire hose stations and portable fire extinguishers.
NL-06-078 Docket No. 50-286 Attachment 1 Page 4 of 14 3.3 Passive Fire Protection Features The installed passive fire protection features (fire barriers and penetration seal systems) in Fire Areas ETN-4 and PAB-2 remain functionally unchanged from those described in SERs dated February 2, 1984 (Reference 8.4) and January 7, 1987 (Reference 8.1), and the NYPA correspondence referenced therein, as applicable.
3.4 Transient Combustible Control and FP Equipment Operating History A review of IP3 condition reports for the period beginning with Entergy ownership through the present indicated that no significant fire protection related deficiencies applicable to Fire Zones 1, 7A, 60A, or 73A were identified during this time period.
Topics searched included fire barriers, ERFBS, fire suppression, fire detection, and housekeeping/combustible loading. Hence, there is reasonable assurance that the design and operational controls (as described above) in place since the transition to Entergy operation of IP3 have maintained the fire protection defense-in-depth measures consistent with the IP3 fire protection licensing basis.
4.0 ADEQUACY OF A 30-MINUTE ERFBS TO PROTECT SAFE-SHUTDOWN CABLES 4.1 Fire Area ETN-4, Fire Zones 7A, 60A, and 73A As described in the SER dated February 2, 1984 (Reference 8.4), the fire hazards in the affected zones of this area are small. As given by Reference 8.7, the calculated fire severity in Fire Area ETN-4 is less than 60 minutes, of which less than one minute of fire severity is attributable to the expected transient fire loading.
The balance of the combustible inventory is predominantly asbestos-jacketed, flame-retardant electrical cable insulation. The flame-retardant characteristics of the principal combustible ensure that fire will not propagate along the cables to any significant degree, thereby limiting the rate of development and damage incurred by credible fires. As the credible fire scenarios involve floor-based transient combustibles, the impact of such a fire, at any location within the area, is expected to be slight, and insufficient to involve substantial quantities of the predominant fixed combustibles (the flame-retardant cables in trays). In addition, the fire detection, automatic cable tray fire suppression system, and manual fire suppression features provide further assurance that fire damage will be limited in scope and severity. Therefore, based on the current Fire Hazards Analysis, an ERFBS with a 30-minute fire resistance rating is adequate to protect the safe-shutdown cables in this area.
NL-06-078 Docket No. 50-286 Attachment 1 Page 5 of 14 Based on a review of the fire zones in this area using the guidance and tools of NUREG-1 805 (Reference 8.10), it was found that the credible fire challenge would be less severe than that imposed by an ASTM E 119 fire exposure. Further, with the installed smoke detection system and the preaction water spray system for the cable trays in the area, the credible fire challenge in the affected zones of Fire Area ETN-4 can be expected to result in a temperature profile that is substantially less severe than that of the ASTM E 119 time-temperature curve. Therefore, based on the insights using NUREG-1805 guidance and tools, the expected fire effects in this Fire Area will not challenge a Hemyc ERFBS installation that has a fire resistance rating of 30 minutes.
4.2 Fire Area PAB-2, Fire Zone 1 As described in the SER dated January 7, 1987 (Reference 8.1), the fire load in this area is low. As given by Reference 8.7, the calculated fire severity in Fire Area PAB-2, Fire Zone 1 is less than 10 minutes. The small quantity of combustible materials (e.g., CCW pump lubricating oil or transient materials) would be expected to result in a credible fire which is localized, with a low aggregate heat release, and no challenge to redundant safe-shutdown cables or components caused by radiant or convective energy. The installed fire detection system would ensure timely detection, enable prompt manual suppression of the fire, and provide assurance that any fire damage will be limited in scope and severity.
Therefore, the credible fire challenge can be expected to result in a temperature profile less severe than that of the ASTM E 119 time-temperature curve.
Hence, an ERFBS capable of providing at least 30 minutes of protection for the enclosed cables when tested in accordance with ASTM E 119 will provide adequate protection for the safe-shutdown cables in this area, given the hazards in the area and the active fire protection features.
5.0 EVALUATION OF 1P3-SPECIFIC HEMYC ERFBS VERSUS NRC-TESTED CONFIGURATIONS The installed IP3 Hemyc ERFBS is summarized as follows:
- Two 4" rigid steel conduits, each with a cable percent fill of approximately 30%.
The two 4" rigid steel conduits are protected with direct-attached 2" thick Hemyc blanket wrap.
- Seven 18" cable tray sections, with a cable percent fill in these trays ranging from approximately 10% to 25%. Also wrapped are two 24" cable tray sections, each with a cable percent fill of approximately 50%. All cable trays
NL-06-078 Docket No. 50-286 Attachment I Page 6 of 14 are wrapped using 1-1/2" thick Hemyc blanket with a 2" air gap between the blanket and the protected raceway.
- Box-type enclosure at containment electrical penetrations H19/1H20, consisting of 2" thick Hemyc blanket directly attached to the enclosure.
The IP3 Hemyc ERFBS configurations have been compared to the size, orientation, materials, methods of construction, and thermal performance of the test specimens of References 8.5 and 8.6 in an engineering evaluation (Reference 8.11). The detailed thermal performance results of the NRC Hemyc fire tests indicated that several of the tested configurations provided at least 30 minutes of protection for the enclosed safe-shutdown cables, or provided insights into the failure mechanisms that occurred during testing. The engineering evaluation compares the details of these tested configurations with the details of the IP3 Hemyc ERFBS configurations. This evaluation establishes that the IP3 Hemyc ERFBS configurations are sufficiently comparable to the NRC-tested configurations, with minor enhancements to several IP3 configurations, which include the need to augment the ERFBS on raceway supports and to install additional over-banding on certain enclosures. Pending implementation of those modifications to the affected configurations, all of the IP3 Hemyc ERFBS configurations can be expected to provide a fire resistance capability of at least 30 minutes for the enclosed safe-shutdown cables.
6.0 REGULATORY ANALYSIS
10 CFR 50.12(a) states that the Commission may grant exemptions from the requirements of the regulations contained in 10 CFR 50 which are:
(1) Authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security; and, (2) If special circumstances are present.
This request for revision of existing exemptions meets the criteria set forth in 10 CFR 50.12, as discussed herein.
6.1 The requested exemption is authorized by law 10 CFR 50.12(a) authorizes the NRC to grant exemptions from its regulations, and no law is known that precludes the NRC from granting the requested revision to the existing exemptions.
NL-06-078 Docket No. 50-286 Attachment 1 Page 7 of 14 6.2 The requested exemption does not present an undue risk to the public health and safety.
The Hemyc ERFBS configurations installed in IP3 Fire Areas ETN-4 and PAB-2 will provide a fire resistance capability of at least 30 minutes, as discussed in Section 5.0. The minimal fire hazards and ignition sources, combined with the nature of the fire hazards in the areas, the active and passive fire protection features, and the controls on transient combustibles and ignition sources, as discussed in Section 3.0, provide assurance that the credible fire challenge to the IP3 Hemyc ERFBS will be substantially less than that of an equivalent ASTM E 119 30-minute fire exposure. Therefore, as discussed in Section 4.0, the installed ERFBS can be expected to provide adequate protection for the affected safe-shutdown raceways and enclosed cables.
Therefore, given the existing level of fire protection defense in depth, combined with the minimal fire challenge presented by the credible fire scenarios in these areas, and the favorable FP equipment operating history, the change in credited ERFBS fire resistance rating from one hour to 30-minutes will not degrade the effectiveness of the IP3 fire protection program, nor will it challenge the credited post-fire safe-shutdown capability. Based on the determination that safe shutdown in the event of a fire can be achieved and maintained with less than a one-hour fire resistance rating, the requested revision to the existing exemptions does not present an undue risk to the public health and safety.
6.3 The requested exemption is consistent with the common defense and security The requested revision to the existing exemptions is not directly related to and should not adversely impact the common defense and security.
6.4 Special circumstances are present - underlyinq purpose of the rule 10 CFR 50.12(a) requires that special circumstance be present in order for the Commission to consider granting an exemption. Per 10 CFR 50.12(a)(2)(ii), one special circumstance is that application of the regulation in the particular circumstances would not serve the underlying purpose of the rule or is not necessary to achieve the underlying purpose of the rule.
The underlying purpose of 10 CFR 50, Appendix R, Section IIL.G is to provide reasonable assurance that at least one means of achieving and maintaining safe shutdown conditions will remain available during and after any postulated fire. For the areas containing the Hemyc ERFBS installations, the credible fire challenge to the IP3 Hemyc ERFBS due to any postulated fire will be substantially less than that of an equivalent ASTM E 119 30-minute fire exposure. Therefore, a fire
NL-06-078 Docket No. 50-286 Attachment 1 Page 8 of 14 resistance capability of at least 30 minutes provides protection of the components required for achieving and maintaining safe shutdown. Therefore, the underlying purpose of the rule is satisfied and the application of the regulation in these particular circumstances is not necessary to achieve the underlying purpose of the rule.
7.0 CONCLUSION
The defense-in-depth objectives of the Fire Protection Program are to
- 1) Prevent fires from occurring;
- 2) Detect, control, and extinguish promptly those fires that do occur; and,
- 3) Provide protection from the effects of a fire for structures, systems, and components needed to achieve and maintain safe shutdown.
The fire hazards analysis of the fire zones containing the Hemyc ERFBS installations and the existing protection (after completion of modifications discussed in Section 5.0) of the electrical raceways show that these objectives are met. The first objective is supported by the fact that there are few significant ignition sources 1 in the areas, and transient combustibles are controlled.
Supporting the second objective are the active fire detection and suppression features in each area. The third objective is supported by the Hemyc ERFBS configurations which provide protection from credible fire exposures, which have an expected duration less than that of the proposed 30 minute rating.
This request for revision of existing exemptions is warranted under the provisions of 10 CFR 50.12, in that it is authorized by law, does not present an undue risk to the public health and safety, and is consistent with the common defense and security. Further, it meets the requirement for a special circumstance in that it satisfies the underlying purpose of 10 CFR 50 Appendix R by providing an ERFBS that will provide protection for the duration of any postulated fire such that safe shutdown can be achieved and maintained.
Ignition sources in the affected fire zones consist of limited transient combustibles (all zones),
several equipment cabinets and (3kVA) 480/120V instrument power transformer BH8 (Fire Zone 73A), and a CCW pump motor (Fire Zone 1)
NL-06-078 Docket No. 50-286 Attachment 1 Page 9 of 14
8.0 REFERENCES
8.1 NRC Letter and SER, S. A. Varga to J. C. Brons (NYPA); Indian Point 3 Nuclear Power Plant - Exemption From Certain Requirements of Section III.G and III.J of Appendix R to 10 CFR Part 50, January 7, 1987 8.2 NYPA Letter, J. C. Brons to S. A. Varga (NRC); Information to Support the Evaluation of IP3 to 10 CFR 50.48 and Appendix R to 10 CFR 50, September 19, 1985 8.3 NYPA Letter, J. C. Brons to S. A. Varga (NRC); Appendix R Fire Protection Program, August 16,1984 8.4 NRC Letter and SER, S. A. Varga to J. C. Brons (NYPA); Exemptions From the Requirements of 10 CFR 50, Appendix R, for the Indian Point Nuclear Generating Plant, Unit No. 3 (IP-3), February 2, 1984 8.5 Hemyc (One-Hour) Electrical Raceway Fire Barrier Systems Performance Testing; Conduit and Junction Box Raceways (Omega Point Laboratories Fire Test Report, Project 14790-123263, dated April 11, 2005) 8.6 Hemyc (One-Hour) Electrical Raceway Fire Barrier Systems Performance Testing; Cable Tray, Cable Air Drop and Junction Box Raceways (Omega Point Laboratories Fire Test Report, Project 14790-123264, dated April 18, 2005) 8.7 IP3-ANAL-FP-02143, Indian Point 3 Fire Hazards Analysis, Revision 4 8.8 EN-DC-127, Control of Hot Work and Ignition Sources, Revision 2 8.9 ENN-DC-161, Transient Combustible Program, Revision 1 8.10 NUREG-1805, "Fire Dynamics Tools (FDTs) Quantitative Fire Hazard Analysis Methods for the U.S. NRC Fire Protection Inspection Program," December 2004.
8.11 Entergy Engineering Report IP-RPT-06-00062, Revision 0; "Comparison of IP3 Hemyc Electrical Raceway Fire Barrier System to NRC Hemyc Fire Test Results."
NL-06-078 Docket No. 50-286 Attachment 1 Page 10 of 14 9.0 FIGURES 9.1 Hemyc ERFBS in Fire Zone 1 9.2 Hemyc ERFBS in Fire Zone 7A 9.3 Hemyc ERFBS in Fire Zone 60A 9.4 Hemyc ERFBS in Fire Zone 73A
NL-06-078 Docket No. 50-286 Attachment 1 Page 11 of 14 Unit 3 Primary Aux. Bldg.-Component Cooling Pumps Elev. 41'-0" 37' -Condensate Receiver and Pumps To El. 55 111L I Partial Heih IE T N L Appendix R WTUNNEL Coponent _
CoolingPumrps
'*..,*Alternate PoSwe Transfer Switch CORRIDOR IPEC Hemyc ERFBS In IP3 Fine Zone I (Component Cooling Pump Area)
PFP-306A Figure 9.1: Hemyc ERFBS In Fire Zone 1
NL-06-078 Docket No. 50-286 Attachment 1 Page 12 of 14 Figure 9.2: Hemyc ERFBS In Fire Zone 7A
NL-06-078 Docket No. 50-286 Attachment I Page 13 of 14 Unit 3 Upper Electrical Tunnel UPPER ELECT. Elev. 43'-O" PENETRATION AREA MINI CONTAINMENT AREA Floor EL 35' PAB PIPE TUNNEL Floor EL. 32'-6*
SAFETY INJ.
PUMP ROOM MAIN TRANSFORMER YARD AREA PAB CORRIDOR DEMINERALIZERS Gendull:
Cable Trays Floor to Ceiling Elect. Tunnel 3-h*r R ted 138 KV Exhoust Fan Vent Dampers SWITCHYARD Control Panel (Typ) Under Grating in Floor ot EL. 33" ROOM CABLE SPREADING ROOM
- Entergy IPEC Floor EL 34' Hemyc ERFBS In IP3 Fire Zone 60A (Upper Electrical Tunnel)
PFP-357 Figure 9.3: Hemyc ERFBS In Fire Zone 60A
NL-06-078 Docket No. 50-286 Attachment 1 Page 14 of 14 Figure 9.4: Hemyc ERFBS In Fire Zone 73A