Letter Sequence Request |
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EPID:L-2019-LLL-0015, Request for Approval of a Certified Fuel Handler Training and Retraining Program (Open) |
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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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Text
Entergy Nuclear Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213 Tel 601-368-5573 Mandy K. Halter Director, Nuclear Licensing 10 CFR 50.2 NL-19-012 April 15, 2019 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
Request for Approval of a Certified Fuel Handler Training and Retraining Program Indian Point Nuclear Generating Units 2 and 3 NRC Docket Nos. 50-247, 50-286, and 72-51 Renewed Facility Operating License Nos. DPR-26 and DPR-64
References:
- 1) Entergy Nuclear Operations, Inc., (Entergy) letter to U.S. Nuclear Regulatory Commission (NRC), "Notification of Permanent Cessation of Power Operations," dated February 8, 2017 (NL-17-021) (ADAMS Accession No. ML17044A004)
- 2) Entergy letter to NRC, "Request for Approval of a Certified Fuel Handler Training and Retraining Program," dated February 2, 2017 (Pilgrim Letter No. 2.17.001) (ADAMS Accession No. ML17045A467)
- 3) NRC letter to Entergy "Pilgrim Nuclear Power Plant - Approval of the Certified Fuel Handler Training and Retraining Program," dated April 12, 2017 (ADAMS Accession No. ML17058A325)
On February 8, 2017 Entergy Nuclear Operations, Inc. (Entergy) notified the U.S. Nuclear Regulatory Commission (NRC) that it intends to permanently cease power operations of Indian Point Nuclear Generating Units 2 and 3 (IP2 and IP3) no later than April 30, 2020 and April 30, 2021 respectively (Reference 1).
In accordance with 10 CFR 50.2, Entergy requests NRC approval of the Certified Fuel Handler (CFH) Training and Retraining Program for IP2 and IP3. In 10 CFR 50.2, the definition of CFH is described as "a non-licensed operator who has qualified in accordance with a fuel handler training program approved by the Commission."
NL-19-012 Page 2 of 3 After Entergy submits certifications of permanent cessation of power operations and permanent removal of fuel from the reactor vessel in accordance with 10 CFR 50.82(a)(1)(i) and (ii), the 10 CFR Part 50 license will no longer authorize reactor operation or emplacement or retention of fuel in the reactor vessels in accordance with 10 CFR 50.82(a)(2). As a result, licensed reactor operators will no longer be required to support plant operating activities. Instead, approval of a CFH Training and Retraining Program is needed to facilitate activities associated with decommissioning and irradiated fuel handling and management.
A copy of the proposed CFH Training and Retraining Program is provided in the Enclosure to this letter. The IP2 and IP3 proposed program is patterned after the Pilgrim Nuclear Power Plant CFH Training and Retraining Program, which was previously submitted (Reference 2) and approved by the NRC (Reference 3). The CFH Training and Retraining Program will ensure that the qualifications of personnel are commensurate with the tasks to be performed and the conditions requiring response.
10 CFR 50.120, "Training and Qualification of Nuclear Power Plant Personnel," requires training programs to be established, implemented, maintained, and derived using a systematic approach to training (SAT) as defined in 10 CFR 55.4. The requirements of 10 CFR 50.120 apply to holders of operating licenses issued under 10 CFR Part 50. After permanent cessation of operation and certification of fuel removal, the license will no longer authorize operation. The CFH Training and Retraining Program will nonetheless align with the provisions of 10 CFR 50.120. The CFH Training and Retraining Program provides adequate confidence that appropriate SAT based training of personnel who will perform CFH duties is conducted to ensure the facility is maintained in a safe and stable condition.
Entergy requests approval of this CFH Training Program by March 31, 2020 in order to support preparations for and the timely transition of IP2 and IP3 to a permanently shutdown and defueled condition.
If you have any questions regarding the content of this submittal, please contact Robert W.
Walpole at 914-254-6710.
There are no regulatory commitments contained in this letter.
Respectfully, Mandy K. Halter MKH/rww/aye
Enclosure:
Indian Point Nuclear Generating Units 2 and 3 - Certified Fuel Handler Training and Retraining Program cc: Next Page
NL-19-012 Page 3 of 3 cc: Regional Administrator, NRC Region I NRC Senior Resident Inspector, Indian Point Nuclear Generating Units 2 and 3 NRC Senior Project Manager, NRC/NRR/DORL President and CEO, NYSERDA New York State Public Service Commission NYS Department of Health - Radiation Control Program NYS Emergency Management Agency
Enclosure NL-19-012 Certified Fuel Handler Training and Retraining Program Indian Point Nuclear Generating Units 2 and 3 NRC Docket Nos. 50-247, 50-286, 72-51 Renewed Facility Operating License Nos. DPR-26 & DPR-64 (10 Pages)
NL-19-012 Enclosure Page 1 of 10
- 1. Introduction The Certified Fuel Handler Training and Retraining Program contained herein describes the training program to be implemented at Indian Point Nuclear Generating Unit Nos. 2 and 3 (IP2 and IP3, collectively referred to as IPEC) to ensure the monitoring, handling, storage and cooling of nuclear fuel is performed in a manner consistent with ensuring the public health and safety.
The program describes the personnel to whom the program applies, the areas in which training is provided, what constitutes certification, how certification is maintained, and required qualifications (e.g., medical). The program shall comply with the IPEC Technical Specifications (TS) and be consistent with the level of hazard at the facility to ensure the facility is maintained in a safe and stable condition. Certified Fuel Handlers will not be trained as licensed operators; however, candidates in the training program shall meet minimum applicable operator experience requirements of the facility TS.
Changes to this program may be made without prior U. S. Nuclear Regulatory Commission (NRC) approval provided the program continues to comply with the TS.
The Certified Fuel Handler Training and Retraining Program will become effective upon:
(1) Approval of the Certified Fuel Handler Training and Retraining Program by the NRC; and (2) Amendment of each respective IP2 and IP3 Facility Operating Licenses to eliminate the requirements for the NRC licensed Senior Reactor Operators and Reactor Operators, and the requirement for the associated Title 10 Code of Federal Regulations (CFR) Part 55 Training Program.
Training of personnel can be conducted prior to the Certified Fuel Handler Training and Retraining Program being approved by the NRC or prior to the training program effective date.
The Certified Fuel Handler Training and Retraining Program is not accredited with the National Academy for Nuclear Training in accordance with ACAD 02-002, "The Process for Accreditation of Training in the Nuclear Power Industry." Although the program is not accredited, the Certified Fuel Handler Training and Retraining Program will adhere to the guidelines of Revision 1 of NUREG-1220, "Training Review Criteria and Procedures,"
that are applicable to a permanently defueled facility and will be based on a systematic approach to training (SAT) process.
The SAT process contains the following elements:
(1) Systematic analysis of the jobs to be performed.
(2) Learning objectives derived from the analysis which describe desired performance after training.
(3) Training design and implementation based on the learning objectives.
(4) Evaluation of trainee mastery of the objectives during training.
(5) Evaluation and revision of the training based on the performance of trained personnel in the job setting.
NL-19-012 Enclosure Page 2 of 10 The Site Vice President (or designee) may exempt an individual from a specific training requirement based upon the individual's depth of experience and previous training.
Such exemptions, including the basis, shall be documented.
The Certified Fuel Handler Training and Retraining Program consists of an initial training program and a requalification training program (or retraining program) as described below.
1.1 Initial Training Program 1.1.1 Eligibility Requirements Candidates for enrollment in the Certified Fuel Handler initial training program shall meet the applicable requirements of the facility TS.
For the purposes of the Certified Fuel Handler Training Program, the definition of nuclear power plant experience listed in American National Standards Institute (ANSI) 3.1-1978 as amended to include nuclear power plant experience acquired at a defueled reactor site which has spent nuclear fuel stored in its spent fuel pool.
1.1.2 Fundamentals Training The fundamental training phase of the Certified Fuel Handler Training Program consists of lecture, and/or self-study of topics appropriate to the monitoring, handling, storage, and cooling of nuclear fuel. The lecture method of instruction is the training of individual topics by classroom presentation. Self-study is training accomplished by the student through the independent study of texts, handouts, and other materials. Selection of topics will be based on a job analysis for the Certified Fuel Handler tasks and functions.
The job analysis will be performed by an individual holding a Senior Reactor Operator license at the facility. A Difficulty, Importance and Frequency (DIF) rating will be assigned to each Certified Fuel Handler task by a holder of a Senior Reactor Operator license who is familiar with the expected plant conditions during decommissioning.
A review of the DIF ratings for each task will be performed by Operations and Training personnel and management. Learning objectives will be derived from the analysis to describe the desired performance after training. Training materials will be designed based on the learning objectives. Depending on an analysis of the candidate's background, self-study may be used for up to 100% of the course material.
A comprehensive exam at the end of the course will provide assurance of mastery of the skills, knowledge, and abilities required for successful performance of Certified Fuel Handler job and associated tasks.
Typically the fundamental topics include thermodynamics, heat transfer, fluid mechanics, radiological safety principles and monitoring, electrical theory, mechanical components operation, facility/system design and function, and facility administrative and safety procedures, as appropriate for the current facility status.
The training plan will adhere to the guidelines of Revision 1 of NUREG-1220, "Training Review Criteria and Procedures," that are applicable to a permanently defueled facility and be developed utilizing the SAT process.
NL-19-012 Enclosure Page 3 of 10 The following procedures provide specific guidance on training design and implementation, such as guidance on training program oversight, administration, analysis of training needs, development of lesson objectives and lesson plans, design and development of training materials, conduct of training, evaluation of training effectiveness, and record keeping:
EN-TQ-201, Systematic Approach to Training Process EN-TQ-201-01, SAT - Analysis Phase EN-TQ-201-02, SAT - Design Phase EN-TQ-201-03, SAT - Development Phase EN-TQ-201-04, SAT - Implementation Phase EN-TQ-201-05, SAT - Evaluation Phase 1.1.3 On-the-Job Training (OJT)
The on-the-job training phase of the Certified Fuel Handler Training Program includes hands-on training of shift operations such as shift turnover, shift record keeping, removal and return of equipment to service, and specified watch-standing activities. Watch-standing activities include on-the-job training in operation of systems/components used to provide handling, storage, cooling, and monitoring of the fuel; normal, abnormal, and emergency procedures; accident analysis; Emergency Plan; facility license; and the content, bases, and importance of TS. A minimum of 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of on-shift watches under the instruction of a Certified Fuel Handler must be completed as part of the qualification process.
1.1.4 Candidate Evaluation Examination A comprehensive final examination shall be administered at the end of the initial training program. The comprehensive examination shall include a written examination and an operating examination. Areas examined are described in Appendices A and B for the written and operating examinations, respectively. The written examination requires a minimum score of 80 percent to pass. The operating examination will consist of Job Performance Measures (JPMs). Passing criteria for an individual JPM is that the examinee successfully completes the assigned task in accordance with the governing procedure without missing any critical steps. Missed or incorrectly performed critical steps are the bases for JPM failure. Critical steps for a JPM will be pre-identified as defined in Revision 11 of NUREG-1021, "Operator Licensing Examination Standards for Power Reactors" or later. Each JPM will be scored on a pass/fail basis. The candidate must pass at least 80 percent of the administered JPMs to successfully pass the operating examination.
NL-19-012 Enclosure Page 4 of 10 Examination Failures An individual who fails to pass either the written or operating examination shall not perform Certified Fuel Handler duties until he/she has completed a remedial training program and passes an appropriate re-examination. Only those portions of the original examination that were failed need to be re-examined (i.e., written or operating exam).
Exemption of Training Requirements The Site Vice President (or designee) may exempt an individual from specific training requirements based upon the individual's depth of experience and previous training.
Any exemptions granted shall be based on an evaluation of the candidate's training and/or work history to ensure that the intent of the exempted training objectives is satisfied. Such exemptions, including the basis, shall be documented. The requirement for a medical examination shall not be exempted.
Training of current IPEC Licensed Operators (i.e., individuals who hold a current NRC issued Reactor Operator or Senior Reactor Operator License) may be evaluated to determine if they satisfy all of the requirements of this training program, or if they only need to complete portions of this program to qualify as a Certified Fuel Handler. This evaluation will focus on the differences between the requirements of a Certified Fuel Handler and a Licensed Operator to identify any additional training required to become a Certified Fuel Handler. Examples may include an examination on TS, fuel handling, and administrative controls required to perform the Certified Fuel Handler function. The Certified Fuel Handler Training Program allows for the evaluation of other facility personnel to determine if portions of the required training have already been completed and therefore may be exempted. The evaluation will concentrate on required areas to determine if the level of previous training and examination were the same as that required for a Certified Fuel Handler.
In general the training of holders of NRC Senior Reactor Operator licenses who are also qualified as Fuel Handling Supervisors will meet the qualification requirements for Certified Fuel Handler. However, it is expected that some additional training requirements may arise as the plant transitions to a permanently shutdown and defueled configuration. These additional training requirements may arise from changes to plant systems or procedures associated with Spent Fuel Pool operations. Therefore the training requirements for Certified Fuel Handler will be specifically identified and enumerated using the SAT process prior to permanent defueling. The training history of each currently licensed Senior Reactor Operator who is identified as a candidate for Certified Fuel Handler qualification will be separately evaluated to ensure that all the specific training requirements of the Certified Fuel Handler Training Program are met.
Training to address any identified gaps between the individual's training history and the Certified Fuel Handler Training Program requirements will be completed prior to certification as Certified Fuel Handler.
The Site Vice President (or designee) shall approve the basis for evaluations qualifying an individual as a Certified Fuel Handler.
NL-19-012 Enclosure Page 5 of 10 1.1.5 Qualifications All candidates shall satisfy the following requirements:
(1) Complete the Certified Fuel Handler Training Program or have the requirement exempted; (2) Score at least 80 percent on a written examination; (3) Pass at least 80 percent of the administered JPMs on the operating examination; and (4) Pass a medical examination by a physician to determine that the candidate's medical condition is not such that it might cause operational errors that could endanger other plant personnel or the public health and safety 1.2 Retraining Program 1.2.1 Eligibility Requirement Candidates for enrollment in the Certified Fuel Handler Retraining program (also known as the requalification training program) shall have successfully completed the initial Certified Fuel Handler Training Program.
1.2.2 Retraining All Certified Fuel Handlers will participate in the retraining program. The Certified Fuel Handler Retraining Program consists of lecture and/or self-study of topics appropriate to the monitoring, handling, storage, and cooling of nuclear fuel. The content of the retraining program will be based upon the tasks selected during program development for the retraining cycle. A retraining plan will be developed and will be approved by the Site Vice President (or designee). The training plan adheres to the guidelines of Revision 1 of NUREG-1220 that are applicable to a permanently defueled facility and be developed utilizing the SAT process. Retraining will typically include a review of changes associated with the facility and procedures, as well as problem areas associated with the monitoring, handling, storage, and cooling of nuclear fuel, and selected topics from the initial training program.
1.2.3 Schedule Course Schedule The Certified Fuel Handler Retraining Program shall be administered in a biennial training cycle. This cycle includes annual operating examinations and biennial written examination. Biennial and annual are as defined in Revision 11 of NUREG-1021 or later.
NL-19-012 Enclosure Page 6 of 10 Missed Training Any missed training or examination must be made up within 90 days of the missed training activity. If required training or evaluation is not completed within the specified makeup period, the Certified Fuel Handler shall be suspended from Certified Fuel Handler duties, pending successful completion of the missed training or evaluation.
1.2.4 Evaluation of Retraining Examinations Participants in the Certified Fuel Handler Retraining Program must pass a biennial written examination and an annual operating examination to maintain their qualification.
Areas examined are described in Appendices A and B for the written and operating examinations, respectively. The written examination requires a minimum score of 80 percent to pass. The operating examination will consist of JPMs and each JPM will be scored on a pass/fail basis. Passing criteria for an individual JPM is that the examinee successfully completes the assigned task in accordance with the governing procedure without missing any critical steps. Missed or incorrectly performed critical steps are the bases for JPM failure. Critical tasks for a JPM will be pre-identified as defined in Revision 11 of NUREG-1021 or later. Each JPM will be scored on a pass/fail basis. The candidate must pass at least 80 percent of the administered JPMs to successfully pass the operating examination.
Periodic written and/or operating exams may be administered during the retraining cycle to assess student knowledge and training effectiveness.
Examination Failures An individual who fails to pass either the comprehensive biennial written or annual operating examination shall not perform Certified Fuel Handler duties until a remedial training program is completed and an appropriate re-examination is passed. Only those portions that were originally failed need to be successfully re-examined prior to restoring qualifications.
1.2.5 Maintenance of Certified Fuel Handler Qualifications Requirements to Maintain Qualification To maintain the Certified Fuel Handler qualification, the following requirements must be satisfied or they may be exempted:
(1) Complete all required Certified Fuel Handler Retraining; (2) Score at least 80 percent on the biennial written examination; (3) Pass at least 80 percent of the administered JPMs on the annual operating examination;
NL-19-012 Enclosure Page 7 of 10 (4) Pass a biennial medical examination by a physician to determine that the Certified Fuel Handler's medical condition is not such that it might cause operational errors that could endanger other plant personnel or the public health and safety; and (5) Stand the designated Certified Fuel Handler watch for a minimum of eight (8) hours per calendar quarter. A Certified Fuel Handler who fails to meet this time requirement can regain qualified status by serving eight (8) hours of watch under the instruction of a qualified Certified Fuel Handler. The time under instruction should include a review of the spent fuel pool cooling system and shift turnover procedures.
An individual who fails to meet any of the requirements for maintaining the Certified Fuel Handler qualification shall be removed from all duties associated with that position until such time as the discrepancies can be resolved. The Operating Shifts shall be notified of the individual's removal and subsequent status.
Exemption of Maintenance of Qualification Requirements The Site Vice President (or designee) may exempt an individual from a specific retraining requirement. Such exemptions, including the basis, shall be documented.
The requirement for a biennial medical examination shall not be exempted. An individual shall not be exempted from the annual operating or biennial written examinations unless that individual prepared the examination. No individual may be exempted from any two consecutive annual operating exams. No individual may be exempted from any two consecutive biennial written examinations.
1.3 Program Evaluation As part of the training process, routine assessments of the effectiveness and accuracy of training are conducted by appropriate management personnel during and at the end of each two (2) year training cycle. These routine assessments ensure that the IPEC Certified Fuel Handler Training and Retraining Program:
(1) Contains the guidance necessary to ensure compliance with the requirements of the SAT process defined in 10 CFR 50.120(b)(3); and (2) Is revised to incorporate changes to the program, as appropriate, to reflect industry experience, changes to the facility, procedures, regulations, and quality assurance requirements.
Evaluation results shall be reviewed by a station oversight board as defined in site procedures. The station oversight board will verify the resolution of any discrepancies identified by the evaluation. Any required changes to the program determined by the station oversight board, shall be incorporated into the program.
NL-19-012 Enclosure Page 8 of 10 1.4 Records Retention Records associated with the Certified Fuel Handler Training and Retraining Program will be retained in retrievable format until there is no longer a need for the Certified Fuel Handler position at the facility (i.e., all fuel permanently transferred to a dry fuel storage facility).
1.5 Evaluating Changes to the CFH Training and Retraining Program Because the program is based on SAT, changes may be made to program elements without NRC approval as long as the following are applicable: (1) suitable proficiency in the performance of the program's activities is maintained; and (2) changes are documented in an accessible manner that will allow the NRC to verify the adequacy of the program in accordance with 10 CFR 50.120.
Specifically, the NRC-approved Certified Fuel Handler Training and Retraining Program will be revised to incorporate changes to the program, as appropriate, to reflect industry experience, changes to the facility, procedures, regulations, and quality assurance requirements.
NL-19-012 Enclosure Page 9 of 10 Appendix A Written Examination Areas The written examination shall include a sample of the following aspects of the Certified Fuel Handler position:
(1) Design, function, and operation of systems used in handling, storage, cooling, monitoring of nuclear fuel, and auxiliary support systems.
(2) Purpose and operation of the radiation monitoring systems.
(3) Radiological safety principles and procedures including radiation hazards that may arise during normal, maintenance, and abnormal activities.
(4) Principles of heat transfer, thermodynamics, and fluid mechanics as they apply to fuel handling, storage, cooling, and monitoring.
(5) Conditions and limitations of facility license, including content, basis and importance of Technical Specifications.
(6) Assessment of facility condition and selection of appropriate procedures during normal, abnormal and emergency situations.
(7) Fuel handling facilities and procedures.
NL-19-012 Enclosure Page 10 of 10 Appendix B Operating Examination Areas The operating examination will consist of Job Performance Measures and shall include a sample of the following aspects of the Certified Fuel Handler duties and tasks:
(1) Evaluate annunciators; valve, pump, and breaker status indicators; and instrument readings as necessary to determine/perform appropriate remedial actions.
(2) Evaluate the ability to manipulate the controls required to obtain desired operating results during normal, abnormal, and emergency conditions. This includes the spent fuel pool cooling system and those auxiliary and emergency systems that could affect the release of radioactive material to the environment.
(3) Evaluate radiation monitoring system readings, including alarm conditions, to determine appropriate actions. Such actions may include setting an alarm setpoint to monitor a release or determine appropriate remedial actions for an alarm condition.
(4) Evaluate abnormal or emergency conditions to determine if the emergency plan for the facility should be implemented and, if implemented, evaluate performance of duties as required by the emergency plan.